REGULATORY FORMATION DISTRIBUTION SY M (RIDS)

ACCE'SSION NBR;8305020388 DOC ~ DATE: 83/04/27 NOTARIZED: YESFACIL:50-275 Diablo Canyon Nuclear 'Power Plantr Unit ii Pacific Ga

50-323 Diablo Canyan Nuclear Power P'lant'nit 2g Pacific GaAUTH,NAME AUTHOR AFF ILIATION

SCHUYLERiJ.O, Pacific Gas 8 Electric Co0RECIP ~ NAME RECIPIENT AFFILIATION

EISENHUTgD ~ G ~ Divisian of Licensing

SUBJECT: Responds to 830322 request for addi info on instrumentationsys for detection af inadequate core cooling (Generic Ltr82 28),Installation completed 8 sys currently being tested,Status of conformance w/NUREG-0737 Item IFFY 2 encl.

DISTRIBUTION CODE: B001S COPIES RECEIVED:LTR,. ENCL SIZEtTITLE: Licensing Submittal: PSAR/FSAR Amdts 8, Related Correspondence

NOTES:J Hanchett icy PDR Documents'Hanchett icy PDR Documents.

DOCKET0500027505000323

0500027505000303

REC IP IENTID CODF/NAME

NRR/DL/ADLNRR LB3 LA

INTERNAL~ ELD/HDS2IE/DEPER/EPB 36IE/DEQA/QAB 21NRR/DE/CEB iiNRR/DE/EQB 13NRR/DE/HGEB 30NRR/DE/MTEB 17NRR/DE/SGEB 25NRR/DHFS/LQB 3?NRR/DS I/AEB 26NRR/DSI/CPB 10NRR/DSI/ICSB 16NRR/DSI/PSB 19NRR/DSI/RS8 "23RGN5

EXTERNAL: ACRS 41DMB/DSS (AMDTS)LPDR 03NSIC 05

NOTES!

COPIESLTTR ENCL

1 0

1 0

1 03 3

1

? 21 1

1 1

2 21

1 1

1

1 1

1 1

1 1

3 3

6 61 1

2 21 1

1 1

RECIPIENTID CODE/NAME

NRR LB3 BCBUCKLEYrB~ 01

IE F ILEIE/DEPER/IRB 35NRR/DE/AEABNRR/DE/EHEBNRR/DE/GB 28NRR/DE/MEB 18NRR/DE/SAB 24NRR/DHFS/HFEB40NRR/DL/SSPBNRR/DS I/ASBNRR/DS I/CSB 09NRR/DS I/METB 12NR RAB 22

G FIL 04RM/DDAMI/MI8

BNL(AMDTS ONLY)FEMA REP DIY 39NRC PDR 02NTIS

COPIESLTTR ENCL

1 0,1 1

1 1

1 1

1 01 1

'2 21 1

1 «11 1

1 01 1

1

1 1

1 1

1 1

1 0

1 1

1 1

1 1

1

TOTAL NUMBER OF COPIES REQUIRED0 LTTR 56 ENCL 49

II $ IM

'S»

4»»'t 'a»'''»»'I44

g (-I g Q4 ) fit lt I'-» f(,'44(( I( ((» il t

a It » t(( SC!»Cl "A

(ft»»»(' 'Ir ii't(tt') if 41

1 i ) 'P(I" (

,»»(( f I

i

f Ji,(( Ilt

I I Q lj'l I Ifi'i 'if

ii4t i '» '|I i(i1'(i" CI

)cl~ g I

t',I

I'')4(

'$Qt

—,tff f'l~t, i 'lil f l i( I( I lf tl "it 'I»

f ~)

t,t tt

i ',!»',

, 'l ', ' » (,(r-~(I

I I

0 if 4I

I 4

(

I'(

T'1NI'I f

I'I

~ t rt»)4'

Ctf

((( jf

(t I

l'4

F(

t(

It

,( T(

J II »ift I il

4t )f tt

J'i

(if I( hi

44

PA.C IP IC 0-LS AND ELECTRIC C OMPA.NT77 BEALE STREET, SAN FRANCISCO, CALIFORNIA 94106 TELEPHONE (415) 781 ~ 4211

P. O. BOX 7442, SAN FRANCISCO, CALIFORNIA 94120 TELECOPIER (415) 543 ~ 7813ROBERT OHLBACH

VICE CRILID5RY ARD OKRCCAL AIIDRRCY

CHAR LCS T. VAN DC V 8C N

PHI I IP A. C RAN Ce JR ~

HCNRY J. LOPLANTCJOHN S O ISSON

ARTHUR L HILLMAN.JR,CHARLCS W. THISSCL L

OANICL C. SISSONJ AC K IT. PA L L I N» J R,

JOSEPH I. KCLLYHOWAR 0 V. OOLV5SL C NN WC ST» LIR ~

AEIIITACToca Iaal CDUEIIL

OILCE1T L H411IOEDAN OAAT~ ON LUSSOCEJANET 0 LOOSDONROOEAT L SOAOOHPETC1W HAN~ CNENRlswaao T, lootsDAVIDL lUDVIDCONWILLIANH, COW41DOJ HISNACL REIOEHSACNIVOA C SAHSON~ NIALEY*,WOO~aTHCE 0, OOLOENRl~ NA1D H Ho ~ SLONI~ C VINCENT

CDW410 J HCOANHEVstaelaao J DELLASANTAJOSHUA ~ A~ 'LEVJo ~ tar ~ CHOLE1T JaROSCAT L HAAAI~DDUCLA~ A DDLc~ CYJ PETE A ~ AUNOAATIIE1JOHN H TAVERostat R RlcccecDaVID J WILLI*NEON~ ANCE R,WDATIIINOTONRICNaao L Htl~ OJACEW SNUCK

April 27, 1983

DAVIDW ANDCASONCaela H, ~ UCH ~ OAUIILCION O 04 ~ SIDTAaoatvA DarltsDONALDD CAICE~ OND4VIO 0, OILSEATsetvtr p. DacclewaLoRlcraao C. Jo«t ~HAAATW LONO J ~JOHN R. lsrRO ~ t ~ I S HCLCI NANRoots J ~ ETEA ~JD ANN ~ Nae ~ Ea

IATNANT, ANNAND~ TtvEII P, SUAEEPa e cia CNAAAELLE041Y P, CNCINA~DAVIDH TLEI~ IDSall A. DacclvJUAN H JATOHEAEE C LI~ SONJtcseca Los INCA KIAE HCKENEIEKENleter D OLC ~ OleSalaetYA, SANOE1 ~ OHKCNNETN YAHD

ATTOANEY~

Mr. D. G. Eisenhut, DirectorDivision of LicensingOffice of Nuclear Reactor RegulationUS Nuclear Regulatory CommissionWashington DC 20555

Re: Docket No. 50-275, OL-DPR-76Docket iVo. 50-323Diablo Canyon Units 1 and 2Inadequate Core Cooling Instrumentation System(Generic Letter No. 82-28)

Dear Mr. Eisenhut:

The information provided in this submittal is in response toMr. George W. Knighton's letter dated March 22, 1983 requestingadditional information on the instrumentation system for detectionof inadequate core cooling (ICC).

PGandE has completed the installation of the ICC instrumenta-tion system and is currently conducting system testing. Informa-tion on the ICC system has been provided to the Staff in previoussubmittals and, as suggested in Mr. Knighton's letter, where thisinformation remains valid, reference is made to those earliersubmittals. We have reviewed those earlier submittals, andEnclosure 1 gives updates needed to make those submittals current.This submittal also provides (in Enclosure 2) the status ofconformance of all components of the ICC instrumentation systemwith NUREG-0737, Item II.F.2.

We believe that this response provides all the informationnecessary for the NRC Staff to complete their review and thereforeno further submittals on this subject are anticipated.

@DO

(

8305020388 830427PDR ADOCK 05000275P PDR

tC

- ~

~ ~

Mr. D. G. Eisenhut April 27, 1983Page 2

Kindly acknowledge receipt of this material on the enclosedcopy of this letter and return it, in the enclosed addressedenvelope.

Subscribed to in San Francisco, California, this 27th dayof April, 1983.

Respectfully submitted,

Pacific Gas and Electric Company

J es 0. Schuylerce President

uclear Power Generation

Robert OhlbachPhilip A. Crane, Jr.Richard F. LockeAttorneys for PacificGas and Electric Company

Subscribed and sworn to before methis 27th day o Apr'983

N c J. m ter, ry Public inan for the City and County of San

ncisco, State of Californiay Commission expires April 14, 1986.

SEAL

Phili A. Cra e, Jr.

Enclosures

cc: Mr. John B. Martin, NRC Region V

',> {) '/»{AD,g'ee{,{ee{NNee(e '{l{X»s»{~e {e- "ZC

NANCY J. LEMASTERNOTARY PUBLIC.CALIFORNIA g

$g'04ft CITY AND COUNTY OF

SAr FRANCiSCO X

My Commission Expires April 14, 1986~ 4p tee»»pe(t tt upgee(t eepge{»{» »»pete)e{EQ»(» ee ' /egg»{)

bet

Service List

0 ~ g

E

gy ~

~r~/i e h"

l L

EKXOStJRH 1

Supplenentary Information forPlant Specific Review of

Inad uate Core Cooling (ICC) Instrumentation System

On February 6, 1981, PGandE responded to Item II.F.2 of NURKl-0737, "Instrumentation for Detection of Inadequate Core Cooling". Thisresponse was supplenented by a letter on March 19, 1981.

The information provided in these submittals included the designof the ICC instrumentation system selected for Diablo Canyon Unit 1 and 2and schedules for installation of systen canponents. Although these submittalsrefer to "a typical plant", PGandH design exactly complies with the Westinghouseguidance for a "typical plant". The information provided in those responsesremains valid except as supplanented below:

1. February 6, 1981 Submittal

Page 46, Iten 6 SCHEDULE FOR INSZALLATION

Currently, all systems described in the submittal ofFebruary 6, 1981 are installed. They are now undergoingtest and cleanup work. Final testing and calibrationwill be canpleted prior to fuel load. The environmentalqualifications of the systems are not complete, butwill be completed by the first refueling outage.

2. March 19, 1981 Submittal

Item 4 CRITERION 1

We have noted that the term "redundant analog recorder"used in the response to Criterion 1 needs a clarification.The single failure criterion for the readout is met byone indicator on the main control board and one analogstrip chart recorder on the post accident monitoringpanel in the control room. The strip chart recordersupplies subcooling information redundant to that shownon the main display. There are not two redundantanalog recorders, but rather an analog recorder whichserves as a backup to the indicator on the min controlboard.

~ ' I

N

II g gg1 ~

\

~ ~ ENCLOSURE 2

CheckLtetfor 'tlant Specific kevin of

inadequate Core Cooling Q.CC) Iastruzaentatfon Spat»a

d'or Diablo Can on Units 1 and 250-275~~t Io. 50-323

Operated by: Pacific Gas and Electric Company

77 Beale Street

San Francisco California 94106

\

The follovfng items for revfev are taken tron KJEE~737, pp II.F.2-3 ~ and 4. Reiponics should be made to full requirements fn XURE~737,sot abbreviated forms belov. hpplfc»ntI should provfde reference toeither the applfcant' submfttal or the generic deacriptfon ender thecolumn Xabled "Reference." These items are requfred to be tcvfeved on aplant specific beefs by NUREM737 for »D plants. differences from thegeneric deacrfptfons provide& by Veatfnghouse, the Veathghouae Oem'sCroup, Ccnnbustfon Kngfneerfng, or Combuitfon lhffneertag Cheer's Croup«uet be indicated by "ye! or no" Cn the column 'laMed deviations end«uet ~q guetffied. Under the Column labeled schedule, either indicatethat your documentatfon of the ft»e fs coeplet» or Irovfde a proposedschedule for your submittal.

kaference 0 Oevfatfonek'0'chedule

04»crfption of the proposed finalsya tc20 including:~ . I ffnal deafen deacriptfoa of

addi tfona1 inatruaentatfon anddisplays;

b. detailed description of esLstCagfnetrMmentatfce systeas.

e. description ot ccepleted IryZanned aod iffcstfons.

2, k.design analysis Nad evaZuatfon IfInventory trend hutrnaentatfon> Nndtest data to support Aefga Cattea l.description f tests planned Iadresults of tests cNapleted forevaluatfon, ~aliffcatfon, adcalibration of sddftfonal fnstte«entatfce,.

Paragraph No.(Page No.)

.A 7-24

I.B 24-25

I.C (25) See item 1 of Enclosure 1

25-34

3 (35-39)

kApplies to PGandE letter datedFebruary 6, 1981 unless specificallystated.

HPGandE design exactly complieswith the ttestinghouse guidancefor a "typical plant".

~ y ) 4

~~

0

4o

5.

6.

70

8.

9.

Provide a Cable or dsscrtpttcecovsrtag the evaluation o! con-formaacs vtth RJRXQ-0737! ZI.P.2,Attachment l, and kppsadhc 5 (toba revieved on i plant spectficSuts)*Describe computer, software enddisplay functions associated vtthICC monitoring in the

plant'rovidea proposed schedule fortastallatton, testiag and cali-bration and implementation of anyproposed ncv tnstrumentattoa orinformation displays.

. Describe guidelines for use ofreactor coolant inventory trackingSystemy aad analyses Used to developprocedures-Operator instructions in emergencyoperettas procedures for ICC andho+ these procedures villbemodified vhea ftaal moaitortagsystem ts tmplemented.Provide a schedule for additioaal~"bmtttals required*<

Paragraph .No.(Page No.)

4 40-46 and attachment to PGandE

letter dated March 19, 1981.

5 46

ee item of Enclosure 1

*IX.P.2 kttachment 1 (for Core Erit Thermocouples)

Xa response to item 4 tn the above chcckltst, the folloMXag materialsshould be included Co ahov Chat Che proposed system meets the design andqualtftcattoa criteria for the core exit thermocouple system.

l20

30

4.

Provide dtagram of core exit thermocouple locations or reference thegeneric description tf appropriate.Provtde a description of the primary operator displays including:a. k diagram of the display panel layout for the core map and descrip-

tion of hens it ts implemented, «.g., hardvare or CRT display.%. Provide the range of the readoata.c. Descrtbe the alarm system.d Describe hew the XCC tastrumeatatton rasdouts are arranged youth

respect to «acb otherdescribe the fmplemeatattoa of the backup display(s) including theeubcooliag margin monitors), hov the thermocouples are selected ~

they are checked for operabtltty, aad the range of the dtsplay.Describe the use of the primary aad backup displays. Shat tr ngvill the operators have in ustag the core «xtt thermocouple instru-%encactoaf Rov vill the operacor knov vixen to use che core «xtcthermocouples and vhea not to use theat Reference approprtate«mergency operating guidelines vhere appltcable.

o

~ ~

K

S. Confirm completion of control room design task analysis applicable toICC fnstpanentatfon. Confirm that the core «xft thermocouples meet the

= crfterfa of NUMN-0737, Attadaneat l and hppendix 5, or identify and/ustify 4eviations.

6. Describe what parts of .the systems are povered from the lK poser sourcesused, and how fsolatfon from non-XE equipment is prcnrided. Describe the~r supply for the primary display. Clearly delfneata in tm categoriesvhfch hardvare is fncluded up to the isolation devfc» and vhich is not.

7. Conffrm the environmental qualification of the core exft thermocouplefnstrumentatfon up to the isolation device.

Appendix 5 (of NUREtM737, ZI.P.2)

Conffrm explicitly the conformance to the Appendix 5 items listed belov forthe ICC fnetrumentatfon, f.e. ~ the QS, the reactor coolant inventorytracking system, the core exft thermocouples and the dfsplay systems.

Reference ¹

X. Environmental qualiffcation2. Single failure analysfs3. <~ass IX pover source

4. kvaflabflfty prior to an accident

S. alf ty hasurance

6. Continuous indicatfons

7. Recording of instrument outputs

8. Identification of instruments

9. Isolation

4.A.5.14.A.5.24.A.5.34.A.5.44.A.5.54.A.5.6

4.A.5.84.A.5.9

4.B. 1

4.B.2

4.8.34B44.B.54.B.6

4.B.84.B.9

Criterion 1

Criterion 2

Criterion 3

CriterionCriterion 5

Criterion 6

i e iCriterion 8

Criterion 9

Thermocouples(p42) ~

RVLIS(pp44-45)

SUNPlease see theattachment toPGandE letterdated March 19.1981.

¹Applies to PGandE letter da'ted February 6,1981 unless specifically stated.

o ~

. ~

~ ~

0

+*for the users of either Combuition Rag&earing'Seated Rection tbezaocoupla(MTC) System or Vastinihous» Differential treasure (dp) Iyatem I detailedxosponol to 'thE plant Specific items Ntatad %@1m Ihould ba presided.

Reference 0 Deviations

Meetinghouse dp System Paragraph No.

1. Describe the effect of instrument (Pa e No.

uncertainties on the measurementof level. 2.2 2.3 32-34 +

2. kre the differential pressuretransduccio located outsidecontainmentt 1.A.2.1.2 (10)

3. hre hydraulic iaolatoro andaensors included in the impulselincs2 1.A.2.1.2 10 +

B. CZ HJTC Syotem

1. Discuss the apacing of theaensoro from the core aliga-aent plate to the top of thereactor vessel head. Eov moldthe decrease in resolution dueto the 1oss oi a aingle sensoraffect thc ability of the systemto detect an approach to ICC2 Not A licable

/Applies to PGandE letter datedFebruary 6, 1981 unless specificallystated.

+Information addressing the requestedinformation is provided by thesereferences but is not specificallyidentified.

> ~

~ ~