ML20076J242
| ML20076J242 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/15/1983 |
| From: | Murphy W VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| REF-SSINS-6820 FVY-83-57, IEB-83-02, IEB-83-2, NUDOCS 8306200388 | |
| Download: ML20076J242 (3) | |
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T VERMONT YANKEE NUCLEAR POWER CORPORATION 2.C.2.11 FVY 83-57 RD 5. Box 169, Ferry Road, Brattleboro, VT 05301 y
ENGINEERING OFFICE 1671 WORCESTER ROAD FRAMINGHAM. M ASSACHUSETTS 01701 i
June 15, 1983 memose sn..n...
U.. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Office of Nuclear Reactor Regulation Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing Reference.
a)
License No. DPR-28 (Docket No. 50-271) b)
Letter, USNRC to VYNPC, dated 3/4/83; IE Bulletin 83-02 c)
Letter, VYNPC to USNRC (FVY 83-50), dated 6/3/83 Dear Sir
Subject:
IE Bulletin 83-02, Commitments During a telecon with members of your staff on June 14, 1983, we agreed to prepare and transmit a letter which would document our commitment to conduct certain actions relative to IE Bulletin 83-02, Reference (b). Accordingly, we commit to implement the revised leakage monitoring provisions provided in Enclosure A.
In cases where these limits, frequencies or corrective actions conflict with the current Technical Specification 3.6.c/4.6.c, it is our intent to follow these revised provisions in lieu of Technical Specifications until such time as the Technical Specification is amended.
In addition, we commit to submit our plans for inspection and/or modifica-tion of the recirculation 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 three (3) months before the start of the next refueling outage.
We trust that this information is satisfactory; however, should you have I
any questions, please contact us.
Very truly yours, l
VERMONT YANKEE NUCLEAR POWER CORPORATION
//
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Warren P.
urphy Vice Pres dent and Manager of Operatio s WPM /dm cc: USNRC, Region I 631 Park Avenue King of Prussia, PA 19406 i
Attn: Mr. T.T. Martin 8306200308 830615 PDR ADOCK 05000271 h
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I ENCLOSURE A s
1 C.
COOLANT LEAKAGE C.
COOLANT LEAKAGE (Surveillance) 1 1.
During power operation, reactor coolant system leakage into Reactor Coolant system Leakage shall be j
the primary containment shall be limited to:
demonstrated to be within the limits of J
Specification 3.6.C.1 & 2 by checking i
a.
5 GPM unidentified leakage when averaged over the and logging the leakage collected in previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period; the primary containment floor and equip-ment sumps at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
j b.
20 GPM identified leakage when averaged over the In addition, the primary containment previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period; atmosphere activity shall be checked and logged at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
j 2.
Any time the reactor is in the run mode, reactor coolant 1
system leakage into the primary containment from un-identified sources shall be limited to:
a.
2 GPM increase in unidentified leakage within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period (see Note 1).
i 3.
If the requirements of specification 3.6.C.1 cannot be i
met, initiate action as follows:
i a.
With any reactor coolant system leakage greater than j
any one of the limits specificed in 3.6.C.1 a or b, j
reduce the leakage rate to within the limits or be in at least hot shutdown in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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i NOTE 1 - During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the run mode following startup, the i
limits of specification 3.6.C.2 may be waived provided the require-i ments of 3.6.C.1 are met.
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4.
If the requirements of specification 3.6.C.2 cannot be met, initiate action as follows:
a.
With any increase in unidentified leakage of >2 GPM, averaged over the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, identify the source of j
leakage or be in at least hot shutdown in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.
Both the drywell sump and air sampling systems shall be operable during power operation.
From and after tiie date that one of these systems is made or found inoperable for any reason, reactor operation is permissible only during the succeeding 7 days.
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6.
If the requirements of specification 3.6.C.5 cannot be met, an orderly shutdown shall be initiated and the reactor brought to a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i
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