ML17251A987

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Ro:On 880314,radiation Process Monitor R-15 Alarmed, Indicating Possible Steam Generator Tube Leak.Leak Confirmed by Analysis of Steam Generator Blowdown & Air Injector Sys Grab Samples.Reactor Shut Down
ML17251A987
Person / Time
Site: Ginna Constellation icon.png
Issue date: 03/15/1988
From: Snow B
ROCHESTER GAS & ELECTRIC CORP.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8803240270
Download: ML17251A987 (4)


Text

ACCELERATED DISIBUTION DEMONSTRlON

'SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8803240270 DOC.DATE: 88/03/15 NOTARIZED: NO DOCKET g

FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION SNOW,B.A.

Rochester Gas

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

RO:on 880314,radiation process monitor R-15, alarmed indicating possible steam generator tube leak.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:

,TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 S

RECIPIENT ID CODE/NAME PDl-3 LA STAHLE, C INTERNAL: ACRS MICHELSON AEOD/DOA AEOD/DSP/ROAB ARM/DCTS/DAB NRR/DEST/ADS7E4 NRR/DEST/ESB 8D NRR/DEST/MEB9H3 NRR/DEST/PSB8D1 NRR/DEST/SGB 8D NRR/DLPQ/QAB10A NRR/DREP/RABlOA NRR/DRISJSIB9A1 02 RES/DE/EI B RGNl FILE 01 EXTERNAL: EGGG GROH,M H ST LOBBY WARD NRC PDR "NSIC MAYS,G COPIES LTTR ENCL 1

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1 RECIPIENT ID CODE/NAME PD1-3 PD ACRS MOELLER AEOD/DSP/NAS AEOD/DSP/TPAB DEDRO NRR/DEST/CEB8H7 NRR/DEST/ICSB7A NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB10D NRR/DOEA/EAB11E NRR/DREP/RPB10A NRR/PMAS/ILRB12 RES TELFORD,J RES/DRPS DIR FORD BLDG HOY,A LPDR NSIC HARRIS,J COPIES LTTR ENCL 1

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TOTAL NUMBER OF COPIES REQUIRED:

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)

ROCHESTER GAS AND ELECTRIC CORPORATION

~ 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 1Cl.C>eel II ARCA CO>>C 1IC 546-27C<

March 15, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Sub) ect:

Follow-up Summary of Close-out of March. 14, 1988 Unusual Event R.E.

Ginna Nuclear Power Plant Docket No. 50-244 In accordance with NUREG 0654 reporting requirements which requires a written summary of "close-out or class reduction conditions," the attached close-out summary for the March 14, 1988 Unusual Event is hereby submitted.

This event has in no way affected the public's health and safety.

Very truly yours, Bruce A. Snow Superintendent of Nuclear Production Attachment XCA U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Resident Inspector SS03240270 SS0315 PDR ADOCK 05000244

'CD pgss 773< I~

Attachment to Close-out of March 1

1988 Unusual Event R E.

Gonna Nuclear Power Plant Docket No. 50-244 On March 14, 1988 at approximately 1409 EST Radiation Process Monitor R-15 (Condenser Air Ejector) alarmed indicating a possible primary to secondary Steam Generator Tube Leak.

At this time radiation process monitor R-19 (Steam Generator Blowdown) was out of service for maintenance so confirming indication from this monitor could not be obtained.

At approximately 1500 EST R-19 (Steam Generator Blowdown) monitor was returned to service thus adding additional monitoring of the Steam Generator Tube Leak.

At 1515 EST air ejector and Steam Generator Blowdown grab samples were taken and analyzed confirming a primary to secondary Steam Generator Tube Leak of approximately 60 cc/min (i.e.

.016 gpm) and that the tube leak was in the "B" Steam Generator; At 1600 EST a meeting was held between the Plant Superintendent and department managers to plan for a forced outage to investigate and repair the "B" Steam Generator Tube Leak.

At approximately 1830 EST a "B" Steam Generator sample iodine calculation indicated that the primary to secondary leak rate was approximately 0.11 gallons per minute although air ejector calculations still indicated 0.016 gpm.

Based on the above leakage determination, at 1845 EST the Plant Superintendent ordered the plant shutdown to investigate and repair the leak.

Also at this time the Technical Specification limit of no more than.1 gpm tube leakage in one steam generator when averaged over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was addressed and it was decided since the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> average was not exceeded, to wait for a more accurate leak rate calculation from a Steam Generator Blowdown sample.

At 2116 EST the Turbine Generator was taken off the line.

At '2117 EST the "B" Steam Generator was isolated from the secondary steam system to limit releases to the environment and to limit contamination of the secondary system.

At 2127 the reactor was shutdown with all control rods inserted and plant cooldown commenced.

At 2130 EST a "B" Steam Generator Blowdown sample calculation indicated the primary to secondary tube leak was greater than

.1 gpm (i.e.

approximately

.14 gpm).

At this time the Operations Shift Supervisor declared an Unusual Event in accordance with SC-100, "Ginna Station Event Evaluation and Classification,"

EAL:

Reactor Coolant Leakage; Steam Generator Tube Leakage

>.1 gpm as identified by sampling.

All offsite notifications were made per SC-601, "Unusual Event Notifications."

At 0159 EST March 15, 1988 the plant reached less than 350 F

reactor coolant temperature.

This completed the Technical Specification action statement for a Steam Generator Tube Leak of

.1 gpm.

The action statement states to be in hot shutdown within six hours and at an RCS temperature of less than 350 F

within the following six hours.

Pith the RCS temperature less than'50 F and all Technical Specification action statements met, the Operations Shift Super-visor, with approval of the Superintendent

- Ginna Station, declared the Unusual Event terminated at 0213 EST in accordance with SC-110, "Ginna Station Event Evaluation For Reducing The Classification."

At 0346 EST the Residual Heat Removal system was placed in service and cooldown to cold shutdown continued.

At 0700 EST the plant entered the cold shutdown mode of operation.

An estimated release to the environment was calculated assuming a

0.14 gpm tube leak during the entire event.

Total noble gas release calculated was.062 curies or approximately 0.00154 of the Technical Specification limit.