ML20141B979
| ML20141B979 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/13/1997 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20141B977 | List: |
| References | |
| NUDOCS 9706240247 | |
| Download: ML20141B979 (9) | |
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~s REACTOR COOLANT SYSTEM JAN 31 1986 HOT SHUTDOWN SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The required reactor coolant pump (s), if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.
4.4.1.3.2 The required steam generator (s) shall be determined OPERABLE by j
verifying secondary side water level to be greater than or equal to 17% at l
1 east once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, g
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4.4.1.3.3 (,^t leert ene reacter coelent er RMR le % shall be verified in I
l operation and chduT&t-Q riastoIco6126t~it feiiIonce per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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9706240247 970613 PDR ADOCK 05000423 PDR p
MILLSTONE - UNIT 3 3/4 4-4
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Docket No. 50-423 B16530 Millstone Nuclear Power Station Unit No. 3 Proposed Revision to Technical Specification Reactor Coolant System - Hot Shutdown (PTSCR 3-28-97)
Retvoed Paae June 1997
U.S. Nuclear Reguletory Commission B16530\\ Attachment 3\\Page 1 RETYPE OF PROPOSED REVISION Refer to the attached retype of the proposed revision to the Technical Specifications.
The attached retype reflects the currently issued version of the Technical Specifications. Pending Technical Specification revisions or Technical Specification revisions issued subsequent to this submittal are not reflected in the enclosed retype.
j The enclosed retype should 'oe checked for continuity with Technical Specifications prior to issuance.
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REACTOR COOLANT SYSTEN HOT SHUTDOWN SURVEILLANCE REQUIRENENTS J
4.4.1.3.1 The required reactor coolant pump (s), if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.
4.4.1.3.2 The required steam generator (s) shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to 17% at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.1.3.3 The required loops shall be verified in operation and circulating l reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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d NILLSTONE - UNIT 3 3/4 4-4 Amendment No.
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Docket No. 50-423 B16530 l
l Millstone Nuclear Power Station Unit No. 3 Proposed Revision to Technical Specification Reactor Coolant System - Hot Shutdown (PTSCR 3-28-97)
Backaround and Safety Assessment June 1997 l-i
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I U.S Nuclecr Regulatory Commission B16530\\ Attachment 4\\Page 1 i
i Backaround The current wording of Technical Specification Surveillance 4.4.1.3.3 does not adequately ensure compliance with Technical Specification 3.4.1.3.
Safety Assessment Technical Specification Surveillance 4.4.1.3.3 currently requires "At least one reactor coolant or RHR loop shall be verified in operation and circulating reactor l
coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."
l Technical Specification 3.4.1.3 was changed in Amendment No. 7 to address the closure of the Reactor Trip System breakers in Mode 4. The amended specification
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required that one of the following two conditions is satisfied during MODE 4-l
' At least two reactor coolant loops are OPERABLE with at least two reactor coolant e
l loops in operation when the Reactor Trip System (RTS) breakers are closed, or 1
At least two of the listed loops (4 Reactor Coolant and 2 Residual Heat Removal l
(RHR) loops) are OPERABLE with at least one of these loops in operation when the i
RTS breakers are open.
As written, Technical Specification Surveillance 4.4.1.3.3 does not adequately ensure compliance with Technical Specification 3.4.1.3. This proposed change is necessary to bring Surveillance 4.4.1.3.3 in agreement with Technical Specification 3.4.1.3 as it was amended.
Technical Specification Surveillance 4.4.1.3.3 is being revised to read as follows:
"The required loops shall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."
This proposed change will require verification of at least two reactor coolant system loops OPERABLE with at least two reactor coolant system loops in operation when the Reactor Trip System breakers are closed, and at least two of the listed loops are OPERABLE and one in operation when the Reactor Trip System breakers are open.
i This proposed change will not alter the operation of the reactor coolant system as currently required by Technical Specification 3.4.1.3.
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Docket No. 50-423 B16530
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Millstone Nuclear Power Station Unit No. 3 Proposed Revision to Technical Specification Reactor Coolant System - Hot Shutdown (PTSCR 3-28-97)
Sionificant Hazards Consideration and Environmental Considerations 1
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U.S Nuclerr Rngulttory Commission B16530\\ Attachment 5\\Page 1 Slanificant Hazards Consideration NNECO has reviewed the proposed revision in accordance with 10CFR50.92 and has concluded that the revision does not involve a significant hazards consideration (SHC).
The basis for this conclusion is that the three criteria of 10CFR50.92(c) are not i
satisfied. The proposed revision does not involve a SHC because the revision would not:
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Involve a significant increase in the probability or consequence of an accident previously evaluated.
The proposed change to Technical Specification Surveillance 4.4.1.3.3 is being made to bring Technical Specification Surveillance 4.4.1.3.3 into agreement with Technical Specification 3.4.1.3 that requires at least two reactor coolant system loops to be operable and in operation when the reactor trip system breakers are closed during Mode 4.
This requirement was incorporated -into Technical Specification 3.4.1.3 in Amendment 7. This change to the surveillance does not alter the design, operation, maintenance or testing of the associated systems as previously analyzed.
Therefore, the proposed revision does not involve a significant increase in the probability or consequence of an accident previously evaluated.
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Create the possibility of a new or different kind of accident from any accident previously evaluated.
This proposed change does not introduce any new failure modes or malfunctions, since the changes only bring Surveillance 4.4.1.3.3 in agreement with Technical Specification 3.4.1.3.
Additionally, the proposed change does not alter the operation of the reactor coolant system during normal or accident conditions.
Therefore, the proposed revision does not create the possibility of a new or different kind of accident from any accident previously evaluated.
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5 U.S Nuclear Regul tory Commission B16530%ttachment 5\\Page 2 3.
Involve a significant reduction in a margin of safety.
The proposed change to Technical Specification Surveillance 4.4.1.3.3 will reword the surveillance to ensure compliance with Technical Specification 3.4.1.3. Technical Specification 3.4.1.3 was changed in Amendment No. 7 to address the closure of the Reactor Trip System breakers in Mode 4. As written, Technical Specification Surveillance 4.4.1.3.3 does not adequately ensure compliance with Technical Specification 3.4.1.3.
This proposed change is necessary to bring Surveillance 4.4.1.3.3 in agreement with Technical l
Specification 3.4.1.3 as it was amended.
l Therefore, the proposed revision does not involve a significant reduction in a margin of safety.
In conclusion, based on the information provided, it is determined that the proposed revision does not involve an SHC.
L Environmental Considerations l
NNECO has reviewed the proposed license amendment against_ the criteria of 10CFR51.22 for environmental considerations. The proposed revision does not involve l
an SHC, does not significantly increase the type and amounts of effluents that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, NNECO concludes that the proposed revision meets the criteria delineated in 10CFR51.22(c)(9) for categorical exclusion from the requirements of environmental considerations.
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