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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January 3,1986 Docket No. 50-336 Mr. John F. Opeka, Senior Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
MILLSTONE UNIT 2 - INSERVICE INSPECTION AND TESTING PROGRAM - SECOND 10 YEAR INTERVAL By letter dated June 27, 1985 and supplemented on August 30, 1985 and December 16, 1985, you submitted a proposed inservice inspection and testing program description and requests for relief from selected ASME Code requirements pursuant to 10 CFR 50.55a(g). Although we have not completed our detailed j
review of your submittal, our prelininary review makes clear to us that your l
proposed program to implement those ASME Code requirements that you have found to be practical would increase the scope of inservice inspection and testing for your facility beyond that currently required by your Technical Specifications.
We have concluded that this upgrading of your inservice inspection and testing program will further enhance safety.
Based on our preliminary review, we agree with the determination that it is impractical within the limitations of design, geometry and materials of construction of components, for you to meet certain of the specified ASME l
Code requirements and that imposition of those requirements would result in hardships or unusual difficulties without a compensating increase in the level of quality or safety. Therefore, pursuant to 10 CFR 50.55a(g)(6)(1),
we hereby grant relief until the staff has completed its detailed review or until October 1,1986, whichever comes first, from those inservice inspection and testing requirements of the ASME Code that you have requested. There exists some ambiguity in the alternate testing inspection period proposed in your December 16, 1985 letter. Our interim relief is granted on the basis that one Main Feed System check valve (i.e., 2-FW-5A or 2-FW-58) is disassembled during each refueling outage to verify obturator freedom of movement. Should this inspection reveal that the disassembled valve's full-stroke capability is in question, then the remaining check valve is also to be disassembled and verified to operate properly prior to startup. Moreover, since the scope of the inservice inspection and testing will be increased by your proposed program, and the granting of this relief is based only on the I
impracticality of selected ASME Code requirements, we have determined that t
the relief granted neither increases the probability or consequences of accidents previously.onsidered nor decreases safety margins and that, therefore, it does not involve a significant hazards consideration. Therefore, you are authorized to, and should proceed to, implement your proposed program (except where your current Technical Specifications are more restrictive).
During the period between now and the date we complete our detailed review of your submittal, you must comply with both your existing Technical Specifications and your proposed inservice inspection-and testing program.
8601090576 860103 PDR ADOCK 05000336 O
PDR
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Mr. John F. Opeka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 cc:
Gerald Garfield, Esq.
Mr. Wayne D. Romberg Day, Berry & Howard
-Superintendent Counselors at Law Millstone Nuclear Power Station City Place P. O. Box 128 Hartford, Connecticut 06103-3499 Waterford, Connecticut 06385 Regional Administrator, Region I Mr. Edward J. Mroczke U.S. Nuclear Regulatory Commission Vice President, Nuclear Operations Office of Executive Director for Northeast Nuclear Energy Company Opera tions P. O. Box 270 631 Park Avenue Hartford, Connecticut 06141-0270 King of Prussia, Pennsylvania 19406 Mr. Charles Brinkman, Manager Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.
7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. Lawrence Bettencourt, First Selectman Town of Waterford Hall of Records - 200 Boston Post Road Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. Richard R. Laudenat, Manager Generation Facilities Licensing Post Office Box 270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Radittion Control Unit Department of Environmental Protection State Office Building
-Hartford, Connecticut 06106 Mr. John Shediosky Resident Inspector / Millstone Box 811 Niantic, Connecticut 06357 Office of Policy & Management ATTN: Under Secretary Energy Division-80 Washington Street Hartford, Connecticut 06106
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s Mr. John F. Opeka In the event conflicting requirements arise for some components, you must comply with the more restrictive requirements (e.g)., shorter inspection intervals, increased number of parameters measured.
In other words, the granting of this relief from ASME Code requirements should not be interpreted to give you relief from any of the requirements in your existing Technical Specifications.
When our detailed review of your submittals is complete we will:
(1) issue final approval of your program (which may contain modifications resulting from the staff's review; and (2) grant relief from any ASME Code requirements that are determined to be impractical for your facility for the duration of the inspection interval. These reviews are being conducted under our TAC number 59265.
Sincerely,
/S/
Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B cc: See next page DISTRIBUTION:
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