Letter Sequence Other |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement
Results
Other: A06539, Ack Receipt of Encl NRC Invoices for Costs Incurred in Review of Util Submittals for Plants.Fee Will Be Sent to J Rodriquez,Per 10CFR50,55 & 170, B11549, Proposed Tech Spec Revs to Sections 5 & 3/4.9,expanding Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks in Two Region Arrangement, B11827, Forwards Addl Info Requested in Oct 1985 Re Util Request to Modify Tech Specs Concerning Spent Fuel Storage Capacity, ML20129A151, ML20133F264, ML20138R217, ML20141B826, ML20141F878, ML20141N037, ML20151M062, ML20154E988, ML20195G527
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MONTHYEARB11271, Application for Amend to License DPR-65,revising Tech Specs Re Fire Protection Sys,Including Fire Detectors,Fire Water Pump Diesels,Spray/Sprinkler Sys,Hose Station & Penetration Fire Barriers.Fee Paid1985-05-28028 May 1985 Application for Amend to License DPR-65,revising Tech Specs Re Fire Protection Sys,Including Fire Detectors,Fire Water Pump Diesels,Spray/Sprinkler Sys,Hose Station & Penetration Fire Barriers.Fee Paid Project stage: Request A04668, Forwards Responses to Open Items Re Exceptions from Guidelines of Rev 2 to Reg Guide 1.97 (Contained in Suppl 1 to NUREG-0737) Discussed in 850416 Meeting.Responses Should Resolve NRC Concerns Re Open Items1985-05-28028 May 1985 Forwards Responses to Open Items Re Exceptions from Guidelines of Rev 2 to Reg Guide 1.97 (Contained in Suppl 1 to NUREG-0737) Discussed in 850416 Meeting.Responses Should Resolve NRC Concerns Re Open Items Project stage: Request ML20129A1511985-05-31031 May 1985 Proposed Tech Specs Re Fire Protection Sys,Including Fire Detectors,Fire Water Pump Diesels,Spray/Sprinkler Sys,Hose Station & Penetration Fire Barriers Project stage: Other B11598, Forwards Millstone Nuclear Power Station Unit 2 Inservice Insp & Testing Program, for Second 10-yr Insp Interval to Commence on 851226.Response Re Acceptability Requested by 8512261985-06-27027 June 1985 Forwards Millstone Nuclear Power Station Unit 2 Inservice Insp & Testing Program, for Second 10-yr Insp Interval to Commence on 851226.Response Re Acceptability Requested by 851226 Project stage: Request ML20126M2981985-07-24024 July 1985 Application for Amend to License DPR-65,revising Tech Specs to Expand Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks.Fee Paid Project stage: Request B11549, Proposed Tech Spec Revs to Sections 5 & 3/4.9,expanding Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks in Two Region Arrangement1985-07-24024 July 1985 Proposed Tech Spec Revs to Sections 5 & 3/4.9,expanding Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks in Two Region Arrangement Project stage: Other ML20134N6051985-08-26026 August 1985 Forwards Auxiliary Sys Branch Request for Addl Info Re Util 850724 Request to Modify Tech Spec Concerning Expansion of Spent Fuel Storage Capacity.Response Requested within 15 Days Project stage: RAI ML20135G1691985-09-0505 September 1985 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion,To Complete Review of 850724 Request to Modify Tech Specs.Info Requested within 15 Days of Ltr Receipt Project stage: RAI B11712, Forwards Response to 850826 Request for Addl Info Re Util 850724 Proposed Change to Tech Spec Mods for Spent Fuel Storage Pool Capacity1985-09-16016 September 1985 Forwards Response to 850826 Request for Addl Info Re Util 850724 Proposed Change to Tech Spec Mods for Spent Fuel Storage Pool Capacity Project stage: Request B11733, Rev to 850528 Application to Amend License DPR-65,adding Continuous or Hourly Fire Watch Patrol Until Temporary or Inoperable Fire Barrier Permanently Repaired.Determinations Re 10CFR50,App R Still Applicable1985-10-0101 October 1985 Rev to 850528 Application to Amend License DPR-65,adding Continuous or Hourly Fire Watch Patrol Until Temporary or Inoperable Fire Barrier Permanently Repaired.Determinations Re 10CFR50,App R Still Applicable Project stage: Request ML20133F2641985-10-0101 October 1985 Proposed Rev to Tech Spec 3/4.7.10,adding Continuous or Hourly Fire Watch Patrol Until Temporary or Inoperable Fire Barrier Permanently Repaired Project stage: Other B11672, Forwards Revised Response to SER (NUREG-1031) Question 480.37 Re Asymmetric Pressure Loadings on Structures & Components Due to Postulated Pipe Ruptures,Including Results of Evaluation of Asymmetric Loadings on Pressurizer1985-10-0101 October 1985 Forwards Revised Response to SER (NUREG-1031) Question 480.37 Re Asymmetric Pressure Loadings on Structures & Components Due to Postulated Pipe Ruptures,Including Results of Evaluation of Asymmetric Loadings on Pressurizer Project stage: Request ML20133E7071985-10-0303 October 1985 Forwards Structural & Geotechnical Engineering Branch Request for Addl Info to Complete Review of 850724 Application to Modify Tech Specs Re Spent Fuel Storage Capacity Expansion Project stage: RAI B11827, Forwards Addl Info Requested in Oct 1985 Re Util Request to Modify Tech Specs Concerning Spent Fuel Storage Capacity1985-10-28028 October 1985 Forwards Addl Info Requested in Oct 1985 Re Util Request to Modify Tech Specs Concerning Spent Fuel Storage Capacity Project stage: Other B11889, Forwards Confirmation of Resolution to Request for Addl Info Re Application for Increased Spent Fuel Storage Capacity Based on Series of Telcons1985-11-25025 November 1985 Forwards Confirmation of Resolution to Request for Addl Info Re Application for Increased Spent Fuel Storage Capacity Based on Series of Telcons Project stage: Request B11766, Submits Isap Topic 1.11, Post-Accident Hydrogen Monitor Per 850517 Commitment.Installation of Redundant Containment Hydrogen Monitor Unnecessary.Addl Info Will Be Provided by 8601311985-11-25025 November 1985 Submits Isap Topic 1.11, Post-Accident Hydrogen Monitor Per 850517 Commitment.Installation of Redundant Containment Hydrogen Monitor Unnecessary.Addl Info Will Be Provided by 860131 Project stage: Request B11910, Responds to Request for Addl Info Re Spent Fuel Storage Capacity.Analysis Showing That Adjacent Modules Do Not Contact During Seismic Event Inadvertently Omitted from1985-12-0303 December 1985 Responds to Request for Addl Info Re Spent Fuel Storage Capacity.Analysis Showing That Adjacent Modules Do Not Contact During Seismic Event Inadvertently Omitted from Project stage: Request B11916, Provides Supplemental Relief Request Info Re Inservice Insp & Testing Program.Main Feed Sys Check Valves 2-FW-5A & 2-FW-5B Cannot Be Tested Per ASME Boiler & Pressure Vessel Code.Periodic Valve Disassembly Suggested1985-12-16016 December 1985 Provides Supplemental Relief Request Info Re Inservice Insp & Testing Program.Main Feed Sys Check Valves 2-FW-5A & 2-FW-5B Cannot Be Tested Per ASME Boiler & Pressure Vessel Code.Periodic Valve Disassembly Suggested Project stage: Supplement ML20141B8261985-12-17017 December 1985 Evaluation of Spent Fuel Racks Structural Analysis, Millstone Nuclear Power Station Unit 2, Technical Evaluation Rept Project stage: Other ML20138R2191985-12-24024 December 1985 Safety Evaluation Supporting Amend 108 to License DPR-65 Project stage: Approval ML20138R2171985-12-24024 December 1985 Amend 108 to License DPR-65,eliminating 18-month Battery Svc Test During Every 60th Month,Since More Stringent Performance Discharge Test Performed Project stage: Other ML20141F8781986-01-0303 January 1986 Advises That Review Underway of Proposed Inservice Insp & Testing Program,Submitted on 850627.Proposal Would Increase Program Beyond Current Tech Spec Requirements.Final Approval of Submission Will Be Granted Upon Completion of Review Project stage: Other ML20141N0411986-02-0404 February 1986 Safety Evaluation Supporting Amend 110 to License DPR-65 Project stage: Approval ML20141N0371986-02-0404 February 1986 Amend 110 to License DPR-65 Changing Tech Specs to Add Fire Detector,Sprinkler Sys & Fire Hose Stations Recently Installed & Changing Wording of diesel-driven Fire Pump Surveillance Requirements Project stage: Other ML20214N7971987-05-27027 May 1987 Forwards Request for Addl Info for Review of 850627 Submittal Re Inservice Testing at Facility.Addl Info Should Be Submitted within 60 Days of Ltr Receipt Project stage: RAI A06539, Ack Receipt of Encl NRC Invoices for Costs Incurred in Review of Util Submittals for Plants.Fee Will Be Sent to J Rodriquez,Per 10CFR50,55 & 1701987-05-29029 May 1987 Ack Receipt of Encl NRC Invoices for Costs Incurred in Review of Util Submittals for Plants.Fee Will Be Sent to J Rodriquez,Per 10CFR50,55 & 170 Project stage: Other ML20195G5271987-10-0202 October 1987 Technical Evaluation Rept:Millstone Nuclear Power Station, Unit 1,Post-Fire Shutdown Evaluation,App R Project stage: Other A06958, Confirms 880515 Revised Due Date for Util Response to NRC Request for Addl Info Re Inservice Insp Program,Per Telcons W/Facility Project Manager1988-01-0808 January 1988 Confirms 880515 Revised Due Date for Util Response to NRC Request for Addl Info Re Inservice Insp Program,Per Telcons W/Facility Project Manager Project stage: Request ML20151M0621988-04-14014 April 1988 Advises That Revised post-fire Safe Shutdown Methodology Conforms W/Requirements of Sections III.G.3. & Iii.L of App R,10CFR50 & Acceptable,Per .Technical Evaluation Rept SAIC-87/3084 Encl Project stage: Other ML20154E9881988-05-12012 May 1988 Fowards Addl Info Re Inservice Insp Program,Per 880212 Request.Attachment 1 Consists of Util Response to Questions Posed in NRC & Attachment 2 Consists of Revised Program Sections Project stage: Other ML20150C7151988-06-28028 June 1988 Forwards Request for Addl Info Re Pump & Valve Inservice Testing Program.Response Requested within 60 Days of Receipt of Ltr Project stage: RAI 1985-07-24
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Text
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April 14,1988 Docket No. 50-245 DISTRIBUTION EDechet: File OGC-WF l
0 NRC & Lecal PDRs EJordan-SVarga JPartlow j
Mr. Edward J. Mroczka BBoger ACRS(10)
Senior Vice President SNorris
- Gray File Nuclear Engineering and Orcrations MBoyle Northeast Nuclear Energy Company i
P. O. Box 270 i
Hartford, Connecticut 06141-0270
Dear Mr. Mroczka:
SUBJECT:
SAFETY EVALUATION OF THE POST-FIRE SAFE SHUTDOWN METH000 LOGY - MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 (TACNO,60188)
By letter dated December 10, 1986 NNEC0 submitted a revised description of the post-fire safe shutdown capability at Millstone Unit No.1.
This submittal superseded previous submittals and was intended to address issues raised in l
NRC Gener'c Letter 86-10 lmplementation of Fire Protecticn Requirements".
The staff ceviewed ;.his information and developed a request for additional information. The licensee responded to this request during a meeting at the Millstone site during the week of August 17, 1987. On that occasion, the l
licensee provided Revision P to the Appendix R Compliance Review.
1 t
The ttaff and its contractor, Science Applications International Corporation (sal"), has reviewed this informatien. Enclosed with this letter is a j
Techn cal Evaluation Report by SAIC, concurred on by the staff, which concludes that the revised post-fire safe shutdown methodology conforms with I
the requirements of Sections III.G.3 and III.L of Appendix R, 10 CFR Part 50 and is therefore, acceptable.
i Sincerely,
+
original signed by i
Michael L. Boyle, Project Manager Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation 1
Enclosure:
]
As stated cc w/ enclosure:
See next page
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.O Mr. Edward J. Mroczka Millstone Nuclear Power Station
' Northeast Nuclear Energy Company Unit No. I cc:
Gerald Garfield, Esquire R. M. Kacich, Manager Day, Berry and Howard Generation Facilities Licensing Counselors at Law Northeast Utilities Service Ccmpany City Place Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 W. D. Romberg, Vice President D. O. Nordquist Nuclear Operations Manager of Quality Assurance Northeast Utilities Service Company Northeast Nuclear Energy Company Post Office Box 270 Post Office Box 270 Hartford, Connecticut 06141-0270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Regional Administrator Radiation Control Unit Region I Department of Environmental Protection U. S. Nuclear Regulatory Comission State Office Building 475 Allendale Road Hertford, Connecticut 06106 King of Prussia, Pennsylvania 19406 Bradford S. Chase, Under Secretary First Selectmen Energy Division Town of Waterford Office of Policy and Management Hall of Records 80 Washington Street 200 Boston Post Road Hartford, Connecticut 06106 Waterford, Connecticut 06385 S. E. Scace, Station Superintendent W. J. Raymond, Resident inspector Millstone Nuclear Power Station Millstone Nuclear Power Statien Northeast Nuclear Energy Company c/o U. S. Nuclear Regulatory Comission Post Office Box 128 Post Office Box 811 Waterford, Connecticut 06385 Niantic, Connecticut 06357 J. P. Stetz, Unit Superintendent Millstone -it No.1 Northeast Nuclear Energy Company Post Office Box 128 Waterford, Connecticut 06385 i
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