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Results
Other: 05000280/LER-1980-046, Forwards LER 80-046/03L-0, A01085, Forwards Nonproprietary Response to Questions on Cycle 4 Basic Safety Rept, A01151, Advises of Minor Adjustments to Evaluation Program Re Resolution of Cycle 3 Startup Commitments.Adjustments Are to Optimize Timetable for Critical Path Refueling Activities, B10005, Discusses Small Break LOCA ECCS Performance Results. Primarily Effect Function of Sys Characteristics Such as ECCS Flow Rates,Safety Injection Tank Actuation Pressures & Core Power Level.Supporting Info Encl, B10009, Forwards Reload Safety Analysis, Demonstrating That Cycle 4 Reload Assures Continued Conformance to Design & Safety Limits of Facility, B10015, Forwards Large Break Loca/Eccs Performance Results. Analysis Showed double-ended Cold Leg Guillotine Break at Pump Discharge to Be Limiting Large Break.Review of Results Determined That Applicable Fee Was Submitted 800509, B10028, Forwards Addl Info Re Fuel Design & Physics Calculations Per RA Clark 800620 Request.Response to Question 10 Withheld (Ref 10CFR2.790), B10060, Forwards Addl Info Requested by NRC Re Design Mod to Cycle 4 Fuel Assemblies & QA Program in Effect During Design of Cycle 4 Reload Fuel, B10068, Advises That C-E Owners Group 800215,0630 & 0731 Ltrs Re Asymmetric LOCA Loads Are Applicable to Millstone Unit 2 & Should Be Regarded as Util Response to NRC 780125 Request, B10076, Forwards Nonproprietary & Proprietary Repts, Guide Thimble Inset Design. Withholding Application & Affidavit Encl. Proprietary Version Withheld (Ref 10CFR2.790), B10080, Corrects Typographical Error in Tech Spec Table 3.9-1 of Amend 60 to License DPR-65.Doors 292 & 297,listed as Servicing Solidification Sys Area,Should Be 292 & 207, B10084, Submits Addl Info Re Fuel Misload Analysis Performed in Support of Cycle 4 Reload.Procedures Utilized During Fuel Movement Provide Adequate Assurance That Probability of Fuel Misloading Event Is Sufficiently Low to Preclude Analysis, ML19210C634, ML19210C638, ML19253B386, ML19257A505, ML19296B295, ML19296B298, ML19305E096, ML19309B532, ML19309C217, ML19309G003, ML19312E209, ML19312E212, ML19318A345, ML19323C588, ML19323C595, ML19323D864, ML19323H680, ML19330B446, ML19332A343, ML19337A776, ML19338C766, ML19338E936, ML19344D183, ML20076A987, ML20125A706
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MONTHYEARML19256A1121978-10-27027 October 1978 Application for Amend to License DPR-35,changing Tech Specs to Accomodate New Steamline Break Protection Sys Scheduled for Installation in Spring of 1979.Fee Paid Project stage: Request ML20037A2061979-03-21021 March 1979 Forwards Proprietary Info Presented to NRC at 790126 Meeting Re Reload Application.Info Withheld (Ref 10CFR2.790) Project stage: Meeting ML20076A9871979-04-27027 April 1979 Forwards Proposed Revision to Tech Specs to Allow Unlimited Containment Purges.Revisions Deal W/Containment Isolation Valves Project stage: Other ML19274G1021979-07-31031 July 1979 Forwards Request for Addl Info to Util Proposed Steam Break Protection Sys & N-1 Loop Operation Project stage: RAI ML19207B9461979-08-28028 August 1979 Forwards Addl Info Supporting Tech Specs Change 35 Re Proposed New Steamline Break Protection Sys,In Response to 790731 Request Project stage: Other ML20125A7061979-08-31031 August 1979 Proposed Revisions to Tech Specs to Add Leak Rate Surveillance Requirements to ECCS & Containment Sys Project stage: Other ML19253B3861979-10-0909 October 1979 Discusses Method for Mitigating Control Element Assembly Guide Tube Wear in Fuel Supplied by Westinghouse for Cycle 4.Util Will Use Westinghouse Sleeve Design Project stage: Other ML19256E2921979-10-22022 October 1979 Fowards Generic Request for Addl Info & Requirements for Auxiliary Feedwater Sys Project stage: RAI ML19210C6341979-11-0909 November 1979 Responds to Re Resolution of Cycle 3 Startup Commitments.Forwards Rept, Evaluation of Neutron Shield Effectiveness Project stage: Other ML19210E6701979-11-28028 November 1979 Responds to NRC 791018,22 & 1121 Requests Re short- & long- Term Recommendations for Auxiliary Feedwater Sys Requirements Project stage: Other ML19253C5871979-11-30030 November 1979 Forwards Calculations Re Automatic Initiation of Auxiliary Feedwater & Supporting Statement That Longer Time Is Available for Haddem Neck Steam Generator Dryout than for Millstone-2 Project stage: Other ML19210C6381979-11-30030 November 1979 Evaluation of Neutron Shield Effectiveness Project stage: Other ML19260B5111979-12-0606 December 1979 Forwards Proposed Automatic Initiation Scheme for Auxiliary Feedwater Sys, in Response to NRC Request for Specific Design Details & Demonstration of Compliance W/Hr Denton Project stage: Request ML19211A9001979-12-17017 December 1979 Forwards Design Drawings Re Automatic Initiation of Auxiliary Feedwater,In Response to NRC Request.W/O Encl. List of Drawings Encl Project stage: Other ML19211C1601979-12-21021 December 1979 Requests Tech Specs for Auxiliary Feedwater Sys Mods & Revision of Normal & Emergency Operating Procedures. Sample Tech Spec Pages Encl Project stage: Other ML20125D0981979-12-27027 December 1979 Responds to to Hendrie Re Concerns About Requirement for Automatically Initiated Auxiliary Feedwater Sys at Facilities.Requests Analysis of Effect of Failure to Isolate Feedwater Flow to Affected Steam Generator Project stage: Other ML19260B5171979-12-31031 December 1979 Proposed Automatic Initiation Scheme for Auxiliary Feedwater Sys Project stage: Other ML19257A5051979-12-31031 December 1979 Responds to NRC 790913 TMI Lessons Learned Task Force short- Term Requirements.All short-term Requirements Will Be Implemented by 800101.Implementation Rept Encl Project stage: Other ML19257C0811980-01-0303 January 1980 Forwards Summary of Bulletins & Orders Task Force 791218-19 Audit of Small Break LOCA Emergency Procedure & Operator Retraining.List of Exit Interview Attendees & List of Instrument Power Supplies Encl Project stage: Other ML19257C2881980-01-17017 January 1980 Submits Results of Review of Operating Records of 48-h Endurance Test on Auxiliary Feedwater Pumps,In Response to short-term Recommendations of NRC 791011 & 22 Ltrs.Intent of Recommendation Fulfilled Project stage: Other ML19257D5491980-01-25025 January 1980 Forwards Info Re Automatic Initiation of Auxiliary Feedwater.No Conclusion Reached Re Acceptability of Implementation Project stage: Other ML19296B2951980-02-0808 February 1980 Discusses Fuel Cladding Strain & Fuel Assembly Flow Blockage Models for Facility.Analysis Was Performed for Operating Plants W/Ce Fuel.Forwards Analysis Verifying Compliance W/Eccs Acceptance Criteria Project stage: Other ML19273D1251980-02-14014 February 1980 Forwards Licensee Accident Analysis Re Main Steam Line Break Inside Containment.Requests Safety Evaluation.Licensee Plans to Submit Auxiliary Feedwater Sys auto-initiation Sys Which Delays Auxiliary Feedwater Flow for Three Minutes Project stage: Approval ML19344D1831980-02-29029 February 1980 Discusses Slightly Diminished Capacity of Charging Pumps to Inject Concentrated Boric Acid Into RCS Under Test Conditions.Change in Peak Clad Temp Due to Smaller Charging Pump Flow Is Not Significant Enough to Be Reportable Project stage: Other ML19296B2981980-02-29029 February 1980 Verification of Compliance W/Eccs Acceptance Criteria of Code Utilizing Conservative Cladding Rupture Strain & Assembly Flow Blockage Models Project stage: Other ML19322E3811980-03-0505 March 1980 Responds to IE Bulletin 80-04 Re Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition.Details of Control Grade Automatic Initiation of Auxiliary Feedwater Scheme Are Being Finalized.Necessity of Installation Is Questionable Project stage: Other ML19290E3391980-03-0606 March 1980 Forwards Basic Safety Rept, in Support of Cycle 4 Reload. Affidavit Encl.Rept Withheld (Ref 10CFR2.790) & Available in Central Files Only Project stage: Other ML19305A9721980-03-10010 March 1980 Advises That Util Response to NRC 791022 Request Re Auxiliary Feedwater Sys Flow Design Info Is Scheduled for Submittal on or About 800616 Project stage: Other ML19309B5321980-03-26026 March 1980 Forwards Basic Safety Rept. Proprietary Version Withheld (Ref 10CFR2.790).Affidavit Previously Submitted on 800229 & 760727 Project stage: Other ML19309B1741980-03-31031 March 1980 Application to Amend License DPR-65,in Response to Concerns Expressed in NRC .Revisions Add Surveillance Requirement for Auxiliary Feedwater Flow Test After Cold Shutdown Exceeding One Month.Affidavit Encl Project stage: Request ML19309B2231980-03-31031 March 1980 Proposed Revisions to Tech Specs 3.7.1.2 & 4.7.1.2,adding Surveillance Requirement for Auxiliary Feedwater Flow Test After Cold Shutdown Exceeding One Month Project stage: Other ML19309C2171980-03-31031 March 1980 Outlines Plans for Cycle 4 Reload Outage Steam Generator Insp Per Amend 52 to License DPR-65.Resolution of Cycle 3 Startup Commitments Encl Project stage: Other ML19305D9561980-04-11011 April 1980 Discusses Problems W/Implementation of Lessons Learned Task Force Recommendation Re Automatic Initiation of Auxiliary Feedwaters Sys.Requests NRC Concurrence W/Plan for Implementing Requirement During 1980 Refueling Outage Project stage: Other ML19305E0961980-04-15015 April 1980 Submits Info in Support of Continued Operation W/Sleeved Guide Tubes in Cycle 4.Anticipates That Negligible Guide Tube Sleeve Wear Will Be Measured Project stage: Other ML19309G0031980-04-24024 April 1980 Responds to IE Bulletin 79-13, Cracking in Feedwater Sys Piping. Util Conducted Insp During Aug 1979 Outage.Several Crack Indications in nozzle-to-pipe Welds of Both Steam Generators Were Found.All Repairs Completed Project stage: Other ML19323C5881980-05-0707 May 1980 Forwards Revised Steam Generator Insp. Includes Final Dent Progression Statistics Re Mar 1979 Steam Generator Tube eddy-current Insp.Biases Identified in Testing Procedures Have Been Corrected Project stage: Other ML19275E7271980-05-0909 May 1980 Suppl to Safety Evaluation Supporting Licensee 800125 Response.Peak Containment Pressure Will Remain Below Design Pressure Even W/Addition of Auxiliary Feedwater at run-out Flow Project stage: Approval ML19275E7241980-05-0909 May 1980 Forwards Supplemental Safety Evaluation Supporting Licensee 800125 Response.Peak Containment Pressure Will Remain Below Design Pressure Even W/Addition of Auxiliary Feedwater at Run Out Flow Project stage: Approval ML19323D8641980-05-13013 May 1980 Submits Info Re Proposal for Permanent Type Repair of Containment Electrical Penetrations.Penetration Modules Which Have Experienced Insulation Resistance Degradation, Will Be Replaced Project stage: Other ML19323F2551980-05-20020 May 1980 Tech Spec Change Request for Tables 3.3-3,3.3-4,3.3-5 & 4.3-2,for Engineered Safety Features Actuation Sys Instrumentation,Trip Values,Response Times & Surveillance Requirements Project stage: Request A00803, Application to Amend License DPR-65,submitted as Proposed Revision to Tech Specs,In Response to NRC . Summarizes Status of Implementation of Automatic Initiation of Auxiliary Feedwater.One Pump Sufficient1980-05-20020 May 1980 Application to Amend License DPR-65,submitted as Proposed Revision to Tech Specs,In Response to NRC . Summarizes Status of Implementation of Automatic Initiation of Auxiliary Feedwater.One Pump Sufficient Project stage: Request B10002, Forwards Proprietary Version of Basic Safety Rept Addendum, Nuclear Uncertainties, Supplementing Rept Section 4.0. Describes Power Peaking Factor Uncertainty Analysis Used in Reload Fuel Design.Rept Withheld (Ref 10CFR2.790)1980-05-28028 May 1980 Forwards Proprietary Version of Basic Safety Rept Addendum, Nuclear Uncertainties, Supplementing Rept Section 4.0. Describes Power Peaking Factor Uncertainty Analysis Used in Reload Fuel Design.Rept Withheld (Ref 10CFR2.790) Project stage: Supplement ML19312E2091980-05-30030 May 1980 Forwards Addendum to Basic Safety Rept Re Nuclear Uncertainties,Nonproprietary Version Project stage: Other ML19312E2121980-05-31031 May 1980 Addendum to Basic Safety Rept Re Nuclear Uncertainties, Nonproprietary Version Project stage: Other ML19323C5951980-05-31031 May 1980 Steam Generator Insp Project stage: Other B10005, Discusses Small Break LOCA ECCS Performance Results. Primarily Effect Function of Sys Characteristics Such as ECCS Flow Rates,Safety Injection Tank Actuation Pressures & Core Power Level.Supporting Info Encl1980-06-0202 June 1980 Discusses Small Break LOCA ECCS Performance Results. Primarily Effect Function of Sys Characteristics Such as ECCS Flow Rates,Safety Injection Tank Actuation Pressures & Core Power Level.Supporting Info Encl Project stage: Other B10009, Forwards Reload Safety Analysis, Demonstrating That Cycle 4 Reload Assures Continued Conformance to Design & Safety Limits of Facility1980-06-0303 June 1980 Forwards Reload Safety Analysis, Demonstrating That Cycle 4 Reload Assures Continued Conformance to Design & Safety Limits of Facility Project stage: Other B10015, Forwards Large Break Loca/Eccs Performance Results. Analysis Showed double-ended Cold Leg Guillotine Break at Pump Discharge to Be Limiting Large Break.Review of Results Determined That Applicable Fee Was Submitted 8005091980-06-11011 June 1980 Forwards Large Break Loca/Eccs Performance Results. Analysis Showed double-ended Cold Leg Guillotine Break at Pump Discharge to Be Limiting Large Break.Review of Results Determined That Applicable Fee Was Submitted 800509 Project stage: Other A01061, Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.41980-06-16016 June 1980 Forwards Info Re Design Basis Transient & Accident Conditions Providing Basis for Auxiliary Feedwater Sys Flow Requirements,In Response to NRC 791022 Request.Based on Analyses,Auxiliary Feedwater Sys Complies W/Section 1.4 Project stage: Other ML20244B0591980-06-16016 June 1980 Summary of 800604 Meeting W/Util in Bethesda,Md Re Cycle 4 Reload at Facility W/Westinghouse Fuel.List of Attendees & Agenda Encl Project stage: Meeting 1980-02-29
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Text
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"": '. :,",":," "7l0l August 29, 1980 Docket No. 50-336 B10061 Director of Nuclear Reactor Regulation Attn: Mr. Robert A. Clark, Chief Operating Reactors Branch #3 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
References:
(1)W.G.CounsillettertoR.A.ClarkdatedMay9,1980.
(2) W. G. Counsil letter to R. A. Clark dated June 26, 1980.
(3) W. G. Counsil letter to R. A. Clark dated July 10, 1980.
(4) W. G. Counsil letter to R. A. Clark dated July 14, 1980.
(5) W. G. Counsil letter to R. A. Clark dated August 7, 1980.
(6) W. G. Counsil letter to R. Reid dated March 6, 1980.
(7) W. G. Counsil letter to R. A. Clark dated May 28, 1980.
(8) W. G. Counsil letter to R. A. Clark dated June 3, 1980.
(9) W. G. Counsil letter to R. A. Clark dated June 2, 1980.
(10) W. G. Counsil letter to R. A. Clark dated June 11, 1980.
(11) J. F. Opeka letter to B. H. Grier dated March 21, 1980.
(12) W. G. Counsil letter to R. Reid dated March 2,1979.
(13) W. G. Counsil letter to R. Reid dated March 23, 1979.
(14) W. G. Counsil letter to R. Reid dated February 14, 1980.
(15) W. G. Counsil letter to H. Denton dated December 6, 1979.
(16) W. G. Counsil letter to R. A. Clark dated May 20, 1980.
i Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Proposed Revisions to Technical Specifications Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNEC0) hereby proposes to amend its operating license, DPR-65, by incorporating the revisions identified in Attachment 1 into the Millstone Unit No. 2 Technical Specifications. These proposed revisions together with the proposed revisions idantified in References (1) through (5) are those changes to the Millstone Unit No. 2 Technical Specifications required to 1
support plant operation during Cycle 4.
As identified in previous correspondence between our respective Staffs, this reload will be the first instance in which Westinghouse will supply the fuel and safet.y analyses for a non-Westinghouse NSSS.
The non-LOCA accident analyses supporting Cycle 4 operation of Millstone Unit No. 2 have been :,ubmitted in References (6) through (8).
In addition, the Large and Small break LOCA ECCS performance analyses have been submitted in References (9) and (10), respectively.
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A discussion of each of the proposed changes outlined in Attachment 1 is provided in Attachment 2 to facilitate the NRC Staff review of the Technical Specification package.
It should be noted that, as was dis-cussed at a meeting in your Bethesda Offices on June 4, 1980, no changes to the Technical Specifications will be required due to power distribution control or setpoints.
NNECO has reviewed the attached changes pursuant to the requirements of 10CFR50.59 and has determined that they do not constitute an unreviewed safety question.
The Millstone Unit No. 2 Nuclear Review Board t s reviewed and approved the attached proposed changes and has concurred in the above determination.
NNEC0 has reviewed the proposed license amendment pursuant to the require-ments of 10CFR170 and has determined that these prcposed changes constitute a Class IV license amendment.
NNEC0 has previously forwarded the approp-riate Class IV license amendment fee in conjunction with the Cycle 4 reload review in Reference (1).
We trust this information is sufficient for the Staff to concur in the changes identified, and NNECO remains available to expedite Staff review and issuance of the attached proposed license amendment.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY (did1 W. G. Counsil Senior Vice President Attachment 4
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.o-STATE OF CCNNECTICUT )
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Berlin g9 j 9 p)d COUtiTY OF HARTFORD
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Then personally appeared before me W. G. Counsil, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, a Licensee 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 j
and correct to the best of his knowledge and belief.
AX n. ck Notary Public
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My Commission Expres March 31,1981 4
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