ML17037B645
ML17037B645 | |
Person / Time | |
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Site: | Nine Mile Point |
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) | |
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Category:Letter
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RITSTF Initiative 4b, Revision 2 RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 NMP2L2742, Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components2020-08-28028 August 2020 Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information NMP2L2713, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates2019-11-21021 November 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants NMP1L3264, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Contain2019-02-25025 February 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Containm JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. NMP1L3248, Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pre2018-11-0202 November 2018 Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pres NMP1L3238, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ...2018-10-0101 October 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ... NMP1L3233, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039)2018-08-17017 August 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039) NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017 Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2658, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water2017-11-0303 November 2017 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water NMP1L3180, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)2017-09-18018 September 2017 Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702) RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP1L3146, Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J2017-04-0606 April 2017 Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-027, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-10010 March 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML17037A2652017-02-0606 February 2017 Response to Request for Information Concerning Regional Meteorological Conditions Characterizing Atmospheric Transport Processes within 50 Miles of the Plant RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure ML16131A6542016-05-0404 May 2016 Response to a Question Raised During the Audit ML16131A6552016-05-0404 May 2016 White Paper Prepared in Response to a Question Raised During the Audit 2024-09-12 |
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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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