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LICIM885 CONTACT POR TMas Lin H31

NAME TELEPweOht NUM64R

'"'^ c *L. W. MCFFATT, NUCLEAR SAFETY SUPERVISOR904 795yi6 i 4;8 61 i i i i_

LWLETE ONS LIN8 FOR EACM CCesPOasgNT F AILumE DESCRIBde IN TM88 AGPORT list

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On April 20, 1987, while operating.at 93'4 RTp and gelierating 828MWe, Crystal River Unit 3. failed to comply with STS 4.3.3.6. Amonthly channel check was not being performed on post-accidentmonitor recorders and a' quarterly channel calibration was notbeing performed on the power range nuclear flux recorder.

A channel check was not beino performed because of a. deficiencyin handling administrative procedures. A corrective actionassignment was prematurely closed when a procedure change wasinitiated versus waiting for the change to be issued.

< A quarterly charusel calibration was not being performed on* NI-5-NIR, nuclear power range flux recorder, because the

different frequency for that recorder was overlooked whenreviewing Amendment 60 to STS.

Surveillance procedure 5p-300, Daily Operation Surveillance Log,was revised to include a channel check on the post-accidentmonitoring recorders.

Sp-113, Power range Nuclear Instrumentation Calibration, has beenrevised to include a quarterly calibration of NI-5-NIR and was

pperformed on June 12, 1987,

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EXPIRES 8/31/85

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EVENT DESCRIPTION

On April 20, 1987, while operating at 93% RTP and generating 828 MWe.the NRC Resident ~ Inspector notified Crystal River Unit 3 of aviolation of Technical Specification 4.3.3.6. Technical Specification4.3.3.6. requires that the post-accident monitoring instrumentation,including recorders, be demonstrated operable by the performance of. monthly channel checks and quarterly or refueling interval channelcalibrations.

Contrary to the above, as of April 2, 1987, monthly channel checks onthe recorders for the following post accident monitoring instrumenta-tion were not performed: power range nuclear flux (JR), source rangenuclear flux (JR), reactor coolant outlet temperature (TR), andborated water. storage tank level (LR). In addition, quarterly channelcalibrations for the power range nuclear flux recorder and refuelinginterval calibration of the reactor coolant total flow rate recorderwere not performed.

This event is being reported under 10 CFR 50.73 a (2) (i) (B), whichstates that the licensee shall report any operation or condition pro-hibited by the plant's Technical Specifications.

On December 8, 1983, a post-accident monitoring recorder, (pR) BS-65-PR (a multipoint recorder) was determined to be inoperable because ofdiscrepancies in electrical drawings for a plant modification (LER83-62). Part of the corrective actions for this event was to reviseSP-300, Daily Operating Surveillance Log, to ensure that the recordersidentified in Technical Specification 3.3.3.6 were checked for oper-ability each shift. For reasons unknown, this revision to SP-300 wasnot approved and issued. The corrective action assignment was prema-turely closed when the proposed revision was submitted for approval.Investigation of this earlier event by the NRC Resident Inspector ledto this citation for violation of Technical Specification 4.3.3.6.

On May 18, 1987 Florida power Corporation determined that a LicenseeEvent Report (LER) would not be filed on this event because a viola-tion response was being submitted. Later, on May 27, 1987, it wasdetermined that the violation response would not satisfy the require- 1

ment to file a LER. Therefore, this report is being filed late.

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EXPIAES 8/3145

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CAUSE

Amendment 60 to Technical Specification 4.3.3.6. added the requirementfor channel checks and channel calibrations to be performed on post-accident monitoring instrumentation recorders. LER 83-62 identified

| several channel checks that were not being performed. AppropriateT. procedure changes were - initiated at that time to correct this defi-

ciency. However, the corrective action assignment to implement thechannel checks was prematurely closed when the proposed revision wassubmitted for approval. The procedure change was never issued.

As a result of the issuance of Amendment 60, all post-accidentmonitoring recorders except NI-5-NIR were required to be calibratedevery refueling. The calibration frequency for NI-5-NIR was specifiedas quarterly, During the review of Amendment 60, the difference incalibration frequency was not noticed.

CORRECTIVE ACTIONS:

1. Surveillance procedure SP-3OO, Daily Operating Surveillance Log,has been revised to include a channel check for the power RangeNuclear Flux Recorders (NI-5-NIR), Source Range Nuclear FluxRecorder (NI-9-NIR), Reactor Coolant Outlet Temperature Recorder(RC-4-TR), and BWST Level and RB pressure Recorder (BS-65-pR).

2. FpC no longer accepts the initiation of the procedure change to )satisfy a corrective action assignment. The procedure changemust be approved by the plant Review Committee and issued byDocument Control.

3. Upon notification of the violation, the NI-5-NIR post accidentmonitoring channel was declared inoperable, and the applicableaction statement was entered. The recorder was bench calibrated '

and the action statement was exited.

Technical Specification 4.3.3.6 was interpreted by Florida powerCorporation to apply to the power range flux post-accidentrecorder (NI-5-NIR) as a separate entity. It was FpC positionthat due to difficulty. of calibrating this equipment while inmodes 1 or 2, the portions of the string that do not supportReactor Protection System functions would still require calibra-tion once a refueling. This was based upon concern that the onlyapparent method for achieving a full calibration involved placingseveral ICS stations in " hand" simultaneously and concurrententry into two reactor protective cabinets. Following discus-sions with the NRC on May 26, 1987, it was agreed that the properinterpretation of the technical specification included allcomponents of the instrumentation string. The original NCOR wasreevaluated as reportable and the action statement was re-enteredon May 27, 1987.

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NSC Face 384A U.S NUCLEAR REGULATORY COMMIS$40N' " ' 'LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Aaeaovuo oMe No siso -oio4

EXPIRE $ 8/31/85

#ACILITY NAMS (16 DOCKET NUMetA (2) LER NUMBER tel PAGE 43)

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4. Surveillance procedure Sp-113, power Range Nuclear Instrumenta-tion Calibration, has been revised to include quarterly calibra-tion of the nuclear power range flux recorder, NI-5-NIR, and theactive components between the WI power Range Detectors and theRecorder. This calibration was performed on June 12, 1987.

|

S. In addition, due to the relative difficulty of performing - thecalibration.of NI-5-NIR during power operation, and due to thefact that there is no technical reason that the power rangenuclear flux post-accident recorder should require more frequentcalibrations than any of the other post-accident recorders, atechnical specification change will be initiated to change thecalibration frequency of the power range nuclear flux post-accident recorder to once per 18 months.

SAFETY CONCERNS:

The function of'the recorders associated with the post-accident moni-toring instrumentation is to provide historical data. No accidentmitigation functions are automatically initiated by these instruments,therefore the health and safety of the public was not compromised.

SIMILAR EVENTS:

No previous events reported due to inadequate review of an amendmentto technical specifications or premature closure of a correctiveassignment.

Na sonu 3een

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FloridaPower-C OH POR ATIO N

June'25, 19873F0687-15

U. S. Nuclear Regulatory CommissionAttn: Document control DeskWashington, D. C. 20555

Subject: Crystal | River Unit 3Docket No. 50-302Operating License No. DPR-72Licensee Event Report No. 87-008-00

Dear Sir:.

1

Enclosed is Licensee Event Report (LER) No. 87-008-00 whichis submitted in accordance with 10 CFR 50.73.

Should there be any questions, please contact this office.

Sincerely,.

E. C. SimpsonDirector, Nuclear

Operations Site Support

WLR: mag

Enclosure

xc: Dr. J. Nelson GraceRegional Administrator, Region II

Mr. T. F. Stetk'aSenior Resident Inspector

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I* A Florida Progress Company