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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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(203) 66s-s000 July 24,1985 Docket No. 50-336 Bl1549 Director of Nuclear Reactor Regulation Attn:
Edward J. Butcher, Chief Operating Reactors Branch //3 U. 5. Nuclear Regulatory Commission Washington, D. C. 20555 l
References:
(1)
W. G. Counsil !ctter to 3. R. Miller, dated March 30, 1934.
(2)
D. B. Osborne letter to W. G. Counsil, dated June 4,1984.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Proposed Change to Technical Specifications Modifications to Spent Fuel Storage Pool In Reference (1), Northeast Nuclear Energy Company (NNECO), licensee for Millstone Unit No. 2, provided information to the NRC Staff regarding our plans for interim onsite storage of Millstone Unit No. 2 spent fuel. An integral two-step program was described which would increase the storage capacity of the Millstone Unit No. 2 spent fuel pool, first by a reracking project, and later by a fuel co solidation project.
In subsequent meetings between the NRC and NNECO specific questions were raised by the Staff and identified in Reference (2). Attachment 4 to this submittal addresses each of these previously identified questions.
Pursuant to 10CFR50.90, Northeast Nuclear Energy Company hereby proposes to amend its operating license, No. DPR-65, by incorporating the attached proposed changes into the Millstone Unit No. 2 Technical Specifications.
The proposed revisions to Sections 5 and 3/4.9 are provided as Attachment I and concern expansion of the storage capacity of the Millstone Unit No. 2 spent fuel pool from 667 to 1112 storage locations.
The proposed expansion is to be achieved by reracking the spent fuel pool with a combination of poison acks and non-poison racks in a two region arrangement. Detailed descriptions of the two types of spent fuel storage racks as well as a discussion of the safety and environmentalimplications of the reracking are found in Attachment 2.
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, The smaller pitch values for fuel stored in the spent fuel pool as a result of the pr posed reracking results in an increase in the number of fuel assemblies per unit area of the pool, in analyzing the consequences of a cask drop accident for this increased storage density, it was determined that the site boundary two hour whole body doses would rise from 140 millirem to 240 millirem, an increase of 100 millirem. However, this increase is well within the requirements established in 10CFR100.
NNECO has determined that the increase in consequences of the cask drop accident constitutes an unreviewed safety question pursuant to 10C FR 50.59(a)(2)(i), llowever, the limiting criterion given in 10CFR 100 for this accident is not exceeded. The actual increase in consequences is acceptable from a safety standpoint.
Thus, the attached analyses support the changes proposed and demonstrates continued conformance with applicable requirements with ample margin.
NNECO has reviewed the proposed changes,in accordance with 10CFR50.92, and has concluded that they do not involve a significant hazards consideration. In accordance with 10CFR50.91(a), Attachment 3 is an analysis of the proposed action in light of the standards, contained in 50.92(b) regarding the issue of no significant hazards consideration.
The Millstone Unit No. 2 Nuclear Review Board has reviewed and approved the attached proposed revision and concurs with the above determinations.
In accordance with 10CFR50.91(b), NNECO is providing the State of Connecticut a copy of this proposed amendment.
Pursuant to the requirements of 10CFR170.12(c), enclosed with this amendment request is the application fee of $150.00.
We trust you will find this information satisfactory and remain available to assist you in the expedited review of this matter. To support current plant schedules, NNECO respectfully requests issuance of this amendment by October 25, 1985.
We remain available to promptly respond to staf f questions or to participate in meetings in your offices to support this requested schedule.
Very truly yours, NORTilEAST NUCLEAR ENERGY COMPANY F Guf~
J. F. Opeka V
Senior Vice President cc:
Mr. Kevin McCarthy Director, Radiation Control Unit Department of Environmental Protection liartford, CT 06116
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o STATE OF CONNECTICUT )
) ss. Berlin COUNTY OF HARTFORD )
Then personally appeared before me 3. F. Opeka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, a 1.icensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein and that the statements contained in said information are true and correct to the best of his knowledge and belief, n:LAk 6 t%tary Public
,% Commission Empires March 31,1988
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