ML20072J964

Forwards Interim Surveillance & Limiting Conditions for Operations,Transmitted by ,In Response to IE Bulletin 83-02.Plans for Insp or Mod of Recirculation Sys & Other RCPB Sys,For Next Refueling Outage,Will Be Submitted

ML20072J964
Person / Time
Site:	Peach Bottom
Issue date:	06/27/1983
From:	Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
REF-SSINS-6820, REF-SSINS-SSINS-6 IEB-83-02, IEB-83-2, NUDOCS 8307010106
Download: ML20072J964 (6)

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PHILADELPHIA ELECTRIC COMPANY

' 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 SHIELDS L DALTROFF sincfn5c rYo$"c som June 27, 1983 Docket Nos. 50-277 50-278 Mr. Darrell G. Eisenhut Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

References:

1) Letter, S. L. Daltroff (PECo) to D.

G. Eisenhut (NRC), dated May 23, 1983

2) Telephone conversation between G.

Gears (NRC) and W. M. Alden (PEco) on June 20, 1983

Dear Mr. Eisenhut:

In the referenced letter, Philadelphia Electric company proposed certain interim surveillance and limiting conditions for operation regarding coolant leakage relative to IE Bulletin 83-02 for Peach Botton Unit 2 operation until its refueling outage in October, 1983. In the referenced telephone conversation with a member of your staff, we agreed to transmit a letter which would document our commitment to implement these interim conditions for operation for both Unit 2 and for Unit 3 in lieu of Technical Specifications until such time as the Technical Specification is amended. Attached is a copy of the interim surveillance and limiting conditions for operation that were transmited with our

.May 23, 1983, letter.

f In addition, we commit to submit our plans for inspection and/or modification of the recirculation system and other reactor coolant pressure boundary piping systems for the next refueling outage. These plans will be submitted to the NRC for review at least one month before the start of the next refueling outage.

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Mr. Darrell G. Eisenhut Page 2 We trust that this information is satisfactory; however, should you have any questions, please contact us.

Very truly yours,

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c Attachment cc: A. R. Blough, Site Inspector i Mr. T. T. Martin, USNRC, Region 1 i

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May 23, 1993 i

Docket No. 50-277 ATTACHMFNT V INTEDTM SURVETLLMTCE AND LIMTTTMG CONDITTON OF OPERATTON FOR DEACH BOTTOM ATOMTC POWER STATTOM, UNTT 2 THROUGH OCTOBER 1993 Attached are the interim proponed surveillance and limiting conditionn for operation regarding coolant leakage to be incorporated into the Peach Bottom technical specifications to support Peach Bottom Uni t 2 operation through October 1493.

These interim measures are required to suoport continued power operation of Unit 2 with a crack at weld No. 10-0-6 on the non-isolable 70" RHR shutdown cooling suction line.

The interim limiting conditions for operation reflect those contained in the Standard Technical Specifications (NUREG 0123, 'Rev. 3) with the following exception. The rate of change of 2 gpm per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance period i s applicable only when the reactor mode switch is in the RUN position. Standard  ;

m echnical Specifications apply this LCO to-reactor operations in the 904, STARTUP or HOT SHUTnOuN mode. During reactor operations in the startun mode, large variations in primary coolant system nressure result in changes of measured leakage not indicative of system degradation. This rate of change criteria, if applied during STARTUP operations, could preclude reactor power operation since the LCO for the rate of change of unidentified leakage would most likely be exceeded, resulting in unit shutdown. The maximum leak rate of 9 gallons per minuto during the limited duration of the startup phase will assure primary coolant system integrity during this time ~ period.

F To monitor and alarm pressure boundary leakage, a I

moisture detection. system, consisting of water sensitive tape,

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has been applied to. ten susceptihte welds in the RHR shutdown

. cooling suction line .and vertical recirculation system risers.

To be consistent with the Standard Technical Specifications (NUREG 0123, Fev. 3) if leakage is known and located to be pressure boundary leakage, the reactor will be shutdown to-allow 1further investigation and corrective action. This system will remain in service as an 'interin- additional leak detection system

'through October 1993.

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To determine coolant leakage monitoring nyntamn operable, the currant Peach Bottom Technical Snecificationn (see Table 4.2.E of PBApS Tech 9pecs) will remain in effect. Thin 4

include 9 the Enuipmant Drain Rumn Flow Rate Monitor, Floor Drain Sump Fl ow Rate Moni tor , and Primary Containment Air Samnlinq System. Thone mystems are all demonstrated onerable in the following manner at the stated frequancy:

functional tent once per month

- inntrument check once ner day calibration once per 3 monthn I

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SUDVETLLANCE AMD LTMTTTNG CONDT'r TON OF OPERATIO'T POn DEAC9 ROTTOM ATO*fTC POWED STAT T O'7, M *1T P 2 & 3 T,TMTTTFG CONOTTION9 POD OPP P AT IO'T SUDVETLT,ANCE REOUTPEMENTS 3.6.C. Coolant Teakane 4.6.C Coolant Leakaqe

1. Any time irradiated fuel is 1. neactor coolant system leakage in the reactor vessal and reactor shall be determined by the coolant temperature in above nung or air namnlina nvntem 212 degrees F, the rate of and recorded every 4 hourn reactor coolant leakage to the or less.

primary containment from unidenti-fled nources shall not exceed 9 qall ons ner minute. The rate of channe of unidentifed leakage nhall not exceed 2 qallons ner ninute ner ?4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> aurveillance I period when the reactor in operated in the " Pun" node. In addition, tha total reactor coolant syctem leakane into the primary contain-ment shall not exceed 25 qnn 9urvei l l ance per i od .

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2. Upon receint of valid alarn from 7. The function of the the mointure monitoring nv9 tem, moisture monitoring synten the unit shall be placed in HOT display and control unit

, shutdown within 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> and be will be checked once in COT.D nhutdown within the next per shift.

74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />.

3. If the nointure monitoring synton is found to be inoperable, an houriv monitoring of the Drywell sump operation to detect an increase in pump-out rate and an hour 1.y innpection of the Drywell radiation monitor recordern to detect an increase in Drywell airborne activity will be initiated until the nointure Monitoring synten can he returned to service. The NRC will be notified promotiv in accordance with Technical Specification 6.0.2 (Promnt

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T.TMTTING CO'7DTTTONS FO" OPERATTON SURVETIJAMCE REOUTREMENTS Noti #ication with Written Follow-up) from and after the date that the moisture monitoring system is made or found to be inonerable for any reason, reactor power operation is permissible only during the succeeding seven days unless the nystem is made operabl e sooner.

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4. Both the sump and air sampling systems shall be operable during reactor power operation. From and after the date that one of the9e systems is made or found to be inoperable for any reason, reactor power operation is permissibl e only during the succeeding seven days unlese the system is made onerable sooner.

5. If the conditions in 1, 3, or 4 cannot be met, an order 1v shutdown shall be initiated and the reactor shall be in Cold Shutdown Condition within 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />.

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