LIC-15-0147 U.S. Nuclear Regulatory Commission Attn ...indicated by condition monitoring tasks and...

27
LIC-15-0147 January 11, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Fort Calhoun Station (FCS), Unit 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285 Subject: Response to NRC Request for Additional Information RE: Fifth lnservice Testing Interval Relief Requests P-1 and P-2 (CAC Nos. MF6651 and MF6652) References: 1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk}, "Submittal of Relief Requests Associated with the Fifth lnservice Testing Interval," dated August 27, 2015 (LIC-15- 0089) (ML 152398214) 2. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortopassi), "Fort Calhoun Station, Unit No. 1 - Request for Additional Information RE: Fifth lnservice Testing Interval Relief Requests P-1 and P-2 (CAC Nos. MF6651 and MF6652)," (NRC-15-0097) (ML 15323A036) In Reference 1, the Omaha Public Power District (OPPD) requested approval of proposed relief requests submitted in accordance with 10 CFR 50.55a, "Codes and standards." The relief requests are associated with the Fifth 10 -Year lnservice Testing (IST) Program Interval for Fort Calhoun Station (FCS), Unit No. 1. The Fifth 10 -Year Interval begins on June 7, 2016 and is required by 10 CFR 50.55a(f)(4) to comply with the requirements of the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code (2004 Edition through Addenda OMb-2006). In Reference 2, the NRC requested additional information to complete its review and OPPD's response is attached. No commitments to the NRC are contained in this submittal. If you should have any questions or require additional information, please contact Mr. Bill R. Hansher at 402-533-6894. Respec11u11yu Chief Nuclear Officer (CNO) LPC/JDR/mle Attachments: 1. RAI Response 2. Sl-3A Vibration Data 3. Performance and NPSH Curves 4. Waterfall Plots c: M. L. Dapas, NRC Regional Administrator, Region IV C. F. Lyon, NRC Senior Project Manager S. M. Schneider, NRC Senior Resident Inspector 444 SOUTH 16TH STREET MALL• OMAHA, NE 68102-2247

Transcript of LIC-15-0147 U.S. Nuclear Regulatory Commission Attn ...indicated by condition monitoring tasks and...

Page 1: LIC-15-0147 U.S. Nuclear Regulatory Commission Attn ...indicated by condition monitoring tasks and not driven on a regular schedule. The other pumps were rebuilt because conditions

LIC-15-0147 January 11, 2016

U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Fort Calhoun Station (FCS), Unit 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285

Subject: Response to NRC Request for Additional Information RE: Fifth lnservice Testing Interval Relief Requests P-1 and P-2 (CAC Nos. MF6651 and MF6652)

References: 1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk}, "Submittal of Relief Requests Associated with the Fifth lnservice Testing Interval," dated August 27, 2015 (LIC-15-0089) (ML 152398214)

2. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortopassi) , "Fort Calhoun Station, Unit No. 1 -Request for Additional Information RE: Fifth lnservice Testing Interval Relief Requests P-1 and P-2 (CAC Nos. MF6651 and MF6652)," (NRC-15-0097) (ML 15323A036)

In Reference 1, the Omaha Public Power District (OPPD) requested approval of proposed relief requests submitted in accordance with 10 CFR 50.55a, "Codes and standards." The relief requests are associated with the Fifth 10 -Year lnservice Testing (IST) Program Interval for Fort Calhoun Station (FCS), Unit No. 1. The Fifth 10 -Year Interval begins on June 7, 2016 and is required by 10 CFR 50.55a(f)(4) to comply with the requirements of the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code (2004 Edition through Addenda OMb-2006). In Reference 2, the NRC requested additional information to complete its review and OPPD's response is attached.

No commitments to the NRC are contained in this submittal. If you should have any questions or require additional information, please contact Mr. Bill R. Hansher at 402-533-6894.

Respec11u11yu

L~passi Chief Nuclear Officer (CNO)

LPC/JDR/mle

Attachments: 1. RAI Response 2. Sl-3A Vibration Data 3. Performance and NPSH Curves 4. Waterfall Plots

c: M. L. Dapas, NRC Regional Administrator, Region IV C. F. Lyon, NRC Senior Project Manager S. M. Schneider, NRC Senior Resident Inspector

444 SOUTH 16TH STREET MALL• OMAHA, NE 68102-2247

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LIC-15-0147 Attachment 1 Page 1

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUESTS P-1 AND P-2

OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT NO. 1

DOCKET NO. 50-285

By letter dated August 27, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 152398214 ), Omaha Public Power District submitted relief requests for the fifth 10-year inservice testing (IST) program interval at Fort Calhoun Station, Unit No. 1 (FCS). The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that the following additional information is required in order to complete its formal review of relief requests P-1 and P-2.

NRC RAI P-1-1 Please provide the units of measure for the minimum flow and shutoff head values given in the table in Section 4.

OPPD Response Minimum flow units of measure are in gallons per minute (gpm). Shutoff head units of measure are in feet (ft.).

NRC RAI P-1-2 In section 4, it states that while in an extended refueling outage, internal inspections and pump refurbishment were performed on pumps Sl-1A, Sl-18, Sl-38, and Sl-3C. Please explain why pump Sl-3A was not inspected internally and not refurbished, and what has been done to conclude that pump Sl-3A does not have degradation due to operating on mini-flow conditions during Group A testing. Also, provide the IST vibration data for the past 10 years for pump Sl-3A.

OPPD Response • Safety injection and containment spray pump maintenance strategy incorporates the Electric

Power Research lnstitute's (EPRI) Preventive Maintenance Template for horizontal pumps. This template specifies that pump refurbishment is driven by the need for corrective maintenance as indicated by condition monitoring tasks and not driven on a regular schedule. The other pumps were rebuilt because conditions requiring such maintenance were discovered as discussed below:

o Pump Sl-1A - disassembled due to condition monitoring of the pump {i.e., vibration and oil analysis results (Condition Report {CR) 2009-6169)).

o Pump Sl-1 B - pump shaft was difficult to rotate and motion felt rough {CR 2011-3892). During maintenance, it was identified that the bearing housing flange for Pump Sl-1 B contained cracks {CR 2011-4139).

o Pump Sl-3B - disassembled and inspected due to unexpected oil analysis results {CR 2012-3348, 2012-3885).

o Pump Sl-3C - disassembled to support the repair of Pump Sl-1 B {i.e., exchange the bearing housing for each pump). {Work Order 00412469)

As a result of the above maintenance activates, no generic condition existed which warranted the disassembly and inspection of Pump Sl-3A.

• Pump Sl-3A continues to be monitored via the quarterly Group A pump test as well as during a Biennial Comprehensive test. When these tests are performed, vibration and oil analysis data are

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LIC-15-0147 Attachment 1 Page 2

collected for analysis by the station's Component Maintenance Optimization (CMO) group using the preventive maintenance (PM) process.

• IST vibration data for Pump Sl-3A is attached. Date ranges for the Group A test data are from October 28, 2005 to September 18, 2015. Date ranges for the Comprehensive Pump Test (CPT) data are from April 7, 2005 to May 23, 2015.

NRC RAI P-1-3 Please provide performance curves and net positive suction head curves for the pumps.

OPPD Response Pump curves for the low pressure safety injection (LPSI) and containment spray (CS) pumps are attached. This includes both the performance and net positive suction head curves. Please note that due to the poor quality of the original curves, a vendor recreation of the original curves is provided. These curves are documented in Calculation FC 07076, Rev. 3, "Safety Injection and Containment Spray System Proto-Flo Model Development," Attachment D.

NRC RAI P-1-4 Please provide minimum continuous stable flow for each pump.

OPPD Response Calculation FC06644, Rev. 3, "LPSI Pump Sl-1A and Sl-1 B Performance, IST Acceptance and Hot Leg Injection (HLI)," EOP/AOP Attachment 11, contains Flowserve letter ER-1186 "Engineering Report - Minimum Flow Calculations on Low Pressure Safety Injection Pumps (6-UCL)," which states that the minimum flow rate for continuous unrestricted operation is 584 gpm. This value was requested of the vendor to support the 2010 Hot Leg Injection Modification as the LPSI pumps have a 30 day operation requirement.

Note that this flowrate is for the LPSI pumps only. OPPD does not currently have a vendor defined limiting value for continuous unrestricted operation the CS pumps as they are not credited for extended operation at low flow rates.

Although both pumping systems are the same model, their curves vary slightly and therefore presumably so would their continuous unrestricted operation flow value.

NRC RAI P-1-5 Please describe the purpose of the minimum flow recirculation lines and to where they discharge.

OPPD Response The minimum flow line recirculation lines are installed to ensure that the pump does not experience a no flow condition, which would lead to pump damage.

The minimum recirculation lines discharge back to the Safety Injection and Refueling Water Tank (Equipment Tag No. Sl-5), reference FCS Drawing E-23866-210-130 Sh. 1 "Safety Injection and Containment Spray System Flow Diagram," P & ID Rev. 118 (File No. 10479).

NRC RAI P-1-6 Please explain why these pumps are operated in a mini-flow for Group A testing.

OPPD Response The LPSI pump minimum recirculation line must be used when conducting the quarterly test during

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LI C-1 5-014 7 Attachment 1 Page 3

power operations, because the only other flow path is to the reactor coolant system (RCS) using shutdown cooling alignment. That flow path cannot be utilized because the pump discharge pressure cannot overcome RCS pressure.

The CS pump minimum flow recirculation line must be used when conducting the quarterly test during power operations, because the other flow paths would either result in water damage to equipment in containment or are not permitted by Technical Specifications.

NRC RAI P-1-7 Section 4 states, in part, that The absolute limits for vibration of 0.325 in/sec for Alert and 0.70 in/sec for Required Action are too restrictive for the Ft. Calhoun Low Pressure Safety Injection (LPSI) and Containment Spray (CS) pumps during Group A testing as they are normally about those limits when tested. Later in Section 4 it states, in part, that:

A review of lnservice Test (IST) history to date has determined these pumps have never exceeded the Required Action limits of ISTB-5131-1 during Group A or Comprehensive Tests (CPTs). Please explain this apparent contradiction.

OPPD Response Upon further review, OPPD recognizes the contradiction. Please note that the NRC RAI mistakenly states that OPPD referenced ISTB-5131-1 in its request. OPPD actually referenced ISTB-5121-1.

Please disregard the sentence concerning the review of lnservice Test history contained in Section 4 of OPPD's August 27 , 2015 Relief Request. A more accurate way of stating that information is that a review of Forth Interval lnservice Test (IST) history to date has determined these pumps have never exceeded the modified Required Action limits during Group A tests and the ISTB-5121-1 Required Action limits during Comprehensive Pump Tests (CPTs).

As discussed in Section 4 of the August 27, 2015 Relief Request and also mentioned in the NRC RAI above, the absolute limits are too restrictive for the subject pumps during Group A testing only. No relief is requested for the Comprehensive Pump Test (CPT) Table ISTB-5121-1 vibration limits since vibration levels subside at these higher flow conditions.

NRC RAl-P-1-8 If spectral analysis is performed on the pumps, please provide the results for the past 1 O years and discuss the results.

OPPD Response Spectral analysis performed on these pumps is completed by the station's CMO organization following the collection of data under the PM program concurrent with the execution of the scheduled Surveillance Test.

Waterfall plots of each of the monitored points for the last 1 O years, dated December 1, 2005 to December 1, 2015 are attached, which were generated from the vibration collection database for each of the five pumps. The results of the spectrum analysis data have not shown any discrete fault frequencies. Each of the pumps exhibit low frequency noise. The presence of this noise has been consistent over the reviewed 10 year time period.

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LIC-15-0147 Attachment 1 Page 4

NRC RAI P-2-1 Please discuss if plant operators will try to achieve the exact flow or differential pressure (or discharge pressure) reference values during testing, or if they will only try to achieve a value in the reference band.

OPPD Response The plant operators will continue to try to achieve the exact flow or differential pressure (or discharge pressure) reference values during testing. This will be completed to limit any deviation of trends as a result in fluctuation of reference value set points.

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LIC-15-0147 Attachment 2 Page 1

Sl-3A Vibration Data

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0.900

0.800

0.700

0.600

0.500

0.400

0.300

0.200

0.100

0.000 01/14/04 05/28/05

Sl-3A IST Vibration Data - RAI P-1-2 - Group A

~

10/10/06 02/22/08 07/06/09

~ IB Vertical , IB Horiz

11/18/10

' I\ I

04/01/12 08/14/13

08 Vertical -&-- OB Horiz ~OB Axial

\/

12/27/14 05/10/16

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0.400

0.350

0.300

0.250

0.200

0.150

0.100

0.050

0.000 1/14/2004 5/28/2005

Sl-3A IST Vibration Data - RAJ P-1-2 - CPT

10/10/2006 2/22/2008 7/6/2009 11/18/2010 4/1/2012 8/14/2013 12/27/2014 5/10/2016

--- !B Vertical - IB Horiz OB Vertical ~OB Horiz _._ OB Axial

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LI C-15-014 7 Attachment 3 Page 1

Performance and NPSH Curves

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~

FLOWSERVE ~

Curve Number N-1730 Liquid Water S.p_eed (RPM) :3560 - .. ~l!~h_, ~ilpaclty (gpm) . I - ····--· rlimP9ratur1i <"FL - fo:.SOo Max Customer OPPD-Ft Calhoun Pump type ,6UCL D_lsch. Head (ft)

Service LPSI Viscosity (Cp) 1 Pump Serial No. i 0669-058/9 Efficiency irate ___ 9124/2013

-Specific Gravity 1 NPSHR(ft)

Curves are appraldmala. Pump Is guaranleed for one set of condlHons. Capacity. head, and elllciency guarantees am based on shop test and when handling el9ar. cold. freon water at a temperature Rev. A of not over 85 d<lg""'s. --

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LIC-15-0147 Attachment 4 Page 1

Waterfall Plots

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Sl-lA- Spectrum Vibration Data -10 Years

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51-lA- Spectrum Vibration Data - 10 Years

W111rfall

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51-lA - Spectrum Vibration Data - 10 Years

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Sl-lB - Spectrum Vibration Data -10 Years

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Sl-18 - Spectrum Vibration Data - 10 Years

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Sl-lB - Spectrum Vibration Data - 10 Years

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Sl-3A- Spectrum Vibration Data - 10 Years

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Sl-3A - Spectrum Vibration Data - 10 Years

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Sl-3A- Spectrum Vibration Data - 10 Years

Wa1•rf~lj

CONT SPP.AY PUMP A\ S1-3APMP 06 ~. ChtrWl,l X"

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ftt~cy · HZ

t2'1l2005

Page 22: LIC-15-0147 U.S. Nuclear Regulatory Commission Attn ...indicated by condition monitoring tasks and not driven on a regular schedule. The other pumps were rebuilt because conditions

Sl-3B - Spectrum Vibration Data - 10 Years

Wartrl~I

CONT SPRAY f'JJMP ff\ S1-3B Pt-IP AN. Chi:ine! X COh.i' SPR.AV PIJli'P B\S1-3B PM~ EV. Amp {l00.77'6, FF11q SO, Crit.r 08368, Dal.tr.,. 10l'U20t5 -, 1156PM

OlS. OJ

025 ~ .t 02

~001~ oos

······· ······-· ·-·····---· ········-·· ····-·-·· · ······-····· ··· ······· ··········· ············ ········································ ··· ·1

.m ll'O:l Fr~·H:z

Pump - Inboard Vertical

'Hll ... 111 CQitSPAA\' P.i.NPB \ Sl -.38PMI' llh c.,......1 ir

CONT SPAA'Y PIJhF f \St .)8 PMP !OH ~ Ommt- f1•~ S>, 0tfl'1' 0 83tt. 01ttlirN lfYllX)iSl.13 PM

0;!; ...

02 _..0.175 : 0.15 ~o 125

io~~ 0.05

0.02S 0

!""''''''------··-·· - ----- ·· ···········--·- ···· ·-·-· ·- - ---····· ...... ..................................... !

l !1 ' J .. ~~~~:t,;;;;,~~~~~~~~~==~~~~-';'-j

,~ ...... E ... ...- ... -----·- ~---... -· . ___ .. ~ .. --~~""f';..; .. :..,..;;l .. ~-:...~- -

• ~~tlfliif~f/1~:{J~~~;:~~0.~5~~j.~~{~~~~~;;~~~;.~,,m,5 ~ ~ .m ~ ~ ~ ~ ~ ~ ~

f~Cf,llfttf · Hz

Pump - Inboard Horizontal

Page 23: LIC-15-0147 U.S. Nuclear Regulatory Commission Attn ...indicated by condition monitoring tasks and not driven on a regular schedule. The other pumps were rebuilt because conditions

Sl-3B - Spectrum Vibration Data - 10 Years

Wattff~

CONT SPRAY Pl.MP B \ S1 ·3B PM.P OB'V, Ct:11?111l x CONT SPRA.Y PUhF 8\ 81·38 PMF OBV', Amp Dms57. Fu1Q !il. 01d11 Ore&3. D•1tn""1tn1 10/'2l2015 2 1339 PM

02,.

016 ... ou ~012 . 01

J;OOO ·-o.oo

0:)1 0.111

0

Pump - Outboard Vertical

f11quencr · Hz

W•JatWI CONT SPAAY PUi.11' e \ S1·3B PMP OOH. Chtr>HIX

CotlT SPAAY PUMP 6\ S'1-3BPMP Oatt ~ 0 03)34 , F1eq so. Oidt· Oa:B. D1111Titnt : 1DJ2/2015 2 14 5J PM

0.16. Du 012

! 0.1 °:·ore ?oos

OD<

D.01

Pump - Outboard Horizontal

1211/2005

.;.t'

t211/2005

Page 24: LIC-15-0147 U.S. Nuclear Regulatory Commission Attn ...indicated by condition monitoring tasks and not driven on a regular schedule. The other pumps were rebuilt because conditions

Sl-3B - Spectrum Vibration Data - 10 Years

wa1-.1 CONT SPAA'f PUMP B \ Sl-38 PMP oe AA. Ch;rm11I x

CONT SPRAY PUMP B \ Si 38 PMP 08 ii.>.'., A.'Tlfl 0{[fa)j, Frn 50 Orit.J Oft:JXI. D11.,-T'irne 11li'21X1152 1602 PM

0 i75

....................................... ......................... .. ...................................... ..... .. ... .................... !

1ii 0.15 l,0125 .:. 0.1 lD.0'5

0.05 0025

0

100

Pump - Outboard Axial

100J

I I

/

Page 25: LIC-15-0147 U.S. Nuclear Regulatory Commission Attn ...indicated by condition monitoring tasks and not driven on a regular schedule. The other pumps were rebuilt because conditions

Sl-3C - Spectrum Vibration Data - 10 Years

Wioiltlfd CONT SPAA.Y Pt.JM? C \ Sl-3C PMP JBV, Chiftlnfl i(

CONT SPRAY PIJ!tr1P C \ SJ.3C PMP JEN. At»p D OOU34. Freq 00, Ordtir {I P36EI. O-i•f'ftllll ;'/21/201210 :?4 39 AM

Pump - Inboard Vertica l

W.-1.iflll CONT SPP.J..¥' PllMP C \ 'SI-JC PMP 181'1, t •11t111'1 ~

COhTSPR.AV POMP C \Shlt' PMP. 91., An1fl' 001J11 ' '•" 5l 0.iL.- ObSe, D.il.,,."'"' 1mr..o,, 10 )5. ~ AM

o.a.., 0 2!.

01

O.IS

0 I

DO!

100 300

Pump- Inboard Horizontal

120/2005

/

/

11Xll

Page 26: LIC-15-0147 U.S. Nuclear Regulatory Commission Attn ...indicated by condition monitoring tasks and not driven on a regular schedule. The other pumps were rebuilt because conditions

Sl-3C - Spectrum Vibration Data -10 Years

W;.!t"rfd CONT SPR:A.Y PUMP C \ Sf.3C PMP OfJV, ChinMI X

CONT SPRAY Pl.IMP C \S~JC PMP OBV, Am;i OC&U( Fu1q 50, Ordlr D836E, -0,;IK!'l'rmt 7n7!.20121025 XIAM

Pump - Outboard Vertical

W11er1'1W CONT SPRAY PVfi'P C \ Sl-3C PMP UBH, Ch•Mtl ~

CONT 9PAAV PUhF C\S~JC PMP DE'IH. Atnp· 0 O!«i. "''"· 50, Ouhilr. 0.9'.'"S. D:.1.trime. 1m.00121o~ · u .AM

os. O'.IS

% D2

~a 15

i 0.1

ODS

Pump - Outboard Horizontal

Page 27: LIC-15-0147 U.S. Nuclear Regulatory Commission Attn ...indicated by condition monitoring tasks and not driven on a regular schedule. The other pumps were rebuilt because conditions

Sl-3C - Spectrum Vibration Data - 10 Years

Watarfall CONT SPRAY PUMP C\Si.3C PMP OBAA, ChlilnrttlX

CONT SPRAY J:.UM? c \S\.JC l'lwiP OB~. A.'nfl 0 ([6f54, Fu111 50 . O.'TJ1t1 0 8368, D;ita/Tim1 7ml"ll1210 25 (},I AM

~ 0.2

<to.ts .i 0.1

""'

Pump - Outboard Axial

ftltQiMnt"J · tb

12/ln<ll:6

/