ML17037B645

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Nine Mile Point Unit 1 - Letter Regarding an Evaluation of Two Submittals Regarding Compliance with Appendix J, 10 CFR Part 50 and a Request to Amend and Resubmit Your Request for Exemption
ML17037B645
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 12/30/1976
From: Lear G
Office of Nuclear Reactor Regulation
To: Rhode G K
Niagara Mohawk Power Corp
References
Download: ML17037B645 (4)


Text

Docket No.50-220~Niagara Mohawk Power Corporation ATTN: Mr.Gerald K.Rhode Vice President-Engineering 300 Erie Boulevard liest Syracuse, Hew York 13202 Gentlemen:

l<e have completed our evaluation of your two submittals dated October 28, 1975 and October 31, 1975 regarding compliance with Appendix J.10 CFR Part gp.The above cited letters were submitted in response to our letter dated August 7, 1975, in which you were requested to determine if.you were conducting containment leakage testing at Nine Nile Point Unit No.1 in full compliance with Appendix J.If you were not in full compliance with Appendix J, you were requested to identify your planned actions and the associated schedule for attaining conformance.

In your October 28, 1975 and October 31, 1975 responses to our August 7, 1975 letter, you requested a number of exemptions from the containment leak testing requirements of Appendix J.The Safety Analysis provided in Attachment 8 to your October 28, 1975 and October 31.1975 submittals do not provide adequate information to support your contention that,"Though the facility does not fully comply with the specifics of the containment"design criteria", it does meet the general intent of those criteria".

Please amend and resubmit your request for exemption, to include identifica-tion of: (1)specific exemptions and (2)the specific areas of non-compliance from the requirements of Appendix J.With regard to the latter, please provide your planned actions and the associated schedule for achieving compliance.

For each exemption requested, identify the design features that do not permit testing in accordance v>ith Appendix J and provide specific justification to support the proposed exemption.

In addition, provide the following additional information regarding the application of the Appendix J requirements:.

T.,~TTT T T Table 3.2.7 and 3.3.4 of the Technical Specifications list the reactor.coolant isolation valves-and the primary containmen~isolation val ves.SURNAMC~nATC+FOrm hEC.318 (Rer.9 55)hECM 0240 4 U S 4OVCRNMCNT rRINTINO OrrlcCI 1174 SCS ISS 4 V II Sr>>f I h rm"I>>I 4 r~'4 4 4 II 4'~>>4~4 hlI I t, ih tr<<V f>>I>>~t m I"'4~I I<<mt,>>1~t<<t I$I 4>>t<>*~>>~t hl 4'\I~'<<hr-<>>><<t~<<it S tt<<*4 4, 4<<~4~4 I'4 t tl 1 2 which requires Type C testing by applying Section II.H of Appendix J and considering potential single active failures which may result in a valve becoming a containment leakage barrier.2.~TBlYour submittals indicate that Type B testing should not be required for the TIP system, drywell vent and purge lines, suppression chamber vent and purge lines, drywell nitrogen makeup lines,, suppression chamber nitrogen makeup, vacuum relief lines, and spare penetrations.

It is not clear in what context Type B testing has been considered for these systems.Therefore', identify all penetrations which require Type B testing by applying Section II.G of Appendix J.3.Containment Airlocks Your submittals did not include any requests for exemptions associated with the containment airlock testing requirements.

However, your existing Technical Specifications are not in full compliance with.Appendix J.In your submittal to the Commission, describe the planned actions and the associated schedule for achieving compliance.

To assist you in preparing this submittal, a clarification of the airlock testing requirements is provided in Attachment A.Your response to these requirements should be provided within 60 days from receipt of this letter.'f you have any questions concerning this matter, please feel free to contact me.

Enclosure:

Attachment A George Lear, Chief Operating Reactors Branch¹3 Division of Operating Reactors FI1 e orrIcc~5URNAMKW OAT5%ORB¹3.$.Nut.i.c, c.r....12/>g/76 ORB¹3 GLe.ar..12/$~/76 DISTRI BUT ION: Docket CParri sh NRC PDR SNowicki Local PDR OELD ORB¹3 Rdg OI8IE (3)VStel 1 o DEi senhut KRGoller TBAbernathy TJCarter JRBuchanan GLear ACRS (16)DOR llButl e 12/2P/7 ORB(4)44.>+...MFai rti].e...........

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