Letter Sequence Other |
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MONTHYEARML20078D2971983-09-22022 September 1983
Proposed Tech Specs Increasing Upper Limit for Containment Lower Compartment to 125 F for Up to 90 Cumulative Days Per Calendar Yr Provided Lower Compartment Temp Overaged Over Previous 365 Days Less than 120 F
Project stage: Other
ML20078D2621983-09-22022 September 1983
Application to Amend Licenses NPF-9 & NPF-17,changing Tech Specs to Increase Upper Limit for Containment Lower Compartment to 125 F for Up to 90 Cumulative Days Provided Lower Compartment Temp Less than 120 F
Project stage: Request
ML20081D6831983-10-26026 October 1983
Forwards Justification for Raising Lower Containment Temp from 120 F to 125 F,Per 830922 Application for Amend to Licenses NPF-9 & NPF-17 Changing Tech Specs
Project stage: Request
ML20082D6571983-11-14014 November 1983
Safety Evaluation for McGuire Units 1 & 2 Transition to Westinghouse 17x17 Optimized Fuel Assemblies
Project stage: Other
ML20082D6391983-11-14014 November 1983
Forwards Safety Evaluation for McGuire Units 1 & 2 Transition to Westinghouse 17x17 Optimized Fuel Assemblies. License Amend Requests,Including Tech Spec Changes & cycle- Specific Reload Safety Evaluations,Will Be Submitted
Project stage: Other
ML20082V1181983-12-0202 December 1983
Notice of Issuance & Availability of Amends 27 & 8 to Licenses NPF-9 & NPF-17,respectively & Final NSHC Determination
Project stage: Other
ML20082V1071983-12-0202 December 1983
Amends 27 & 8 to Licenses NPF-9 & NPF-17,respectively, Changing Tech Specs Re Containment Lower Compartment Temp
Project stage: Other
ML20082U2401983-12-12012 December 1983
Application for Amend to License NPF-17,revising Tech Specs Affected by Use of Optimized Fuel Assembly Design for Cycle 2 to Ensure Proper Plant Operation
Project stage: Request
ML20086P4771984-02-20020 February 1984
Proposed Tech Spec Pages 2-9 & B 2-4 Re Reactor Trip Sys Instrumentation Trip Setpoints & Limiting Safety Sys Settings,Respectively.Fuel Assembly Design Parameters Encl
Project stage: Other
ML20086P4631984-02-20020 February 1984
Revs to 831212 Application for Amend to Licenses NPF-9 & NPF-17,changing Tech Specs Re Plant Operating Limitations. Rev Corrects Time Constants Utilized in lead-lag Controller for Unit 1/Cycle 2
Project stage: Request
ML20084D0071984-04-20020 April 1984
Safety Evaluation Supporting Amends 32 & 13 to Licenses NPF-9 & NPF-17,respectively
Project stage: Approval
ML20084C9891984-04-20020 April 1984
Amends 32 & 13 to Licenses NPF-9 & NPF-17,respectively, Revising Tech Specs Re Operating Limits for Transition to Use of Optimized Fuel Assemblies,Boron Injection Sys & Control Rod Insertion Limits
Project stage: Other
ML20099G7481984-11-16016 November 1984
Application for Amends to Licenses NPF-9 & NPF-17,revising Tech Specs Re Plant Operating Limitations Affected by Use of Optimized Fuel Assembly Designs.Fee paid.Marked-up Tech Specs Encl
Project stage: Request
ML20101E3661984-12-14014 December 1984
Forwards Peaking Factor Limit Rept for Cycle 2 to Support 841116 Proposed Amends to Licenses NPF-9 & NPF-17 Re Plant Operating Limitations Affected by Use of Optimized Fuel Assembly Design
Project stage: Other
NRC-85-2995, Requests Review of WCAP-9561,Addendum 1, Addendum to Bart A1:Computer Code for Best Estimate Analysis of Reflood Transients, in Support of Anticipated Startup in Late Mar 19851985-01-0909 January 1985
Requests Review of WCAP-9561,Addendum 1, Addendum to Bart A1:Computer Code for Best Estimate Analysis of Reflood Transients, in Support of Anticipated Startup in Late Mar 1985
Project stage: Other
NRC-85-3011, Forwards Supplementary Info to WCAP-9561,Addendum 1, Addendum to Bart A1:Computer Code for Best Estimate Analysis of Reflood Transients. Timely Completion of Review Needed to Support Anticipated Mar 1985 Startup1985-02-26026 February 1985
Forwards Supplementary Info to WCAP-9561,Addendum 1, Addendum to Bart A1:Computer Code for Best Estimate Analysis of Reflood Transients. Timely Completion of Review Needed to Support Anticipated Mar 1985 Startup
Project stage: Supplement
ML20108B6681985-02-26026 February 1985
Supplementary Info to Addendum 1 to, Addendum to Bart A1: Computer Code for Best Estimate Analysis of Reflood Transients
Project stage: Supplement
ML20100D2731985-03-22022 March 1985
Amends 42 & 23 to Licenses NPF-9 & NPF-17,respectively, Changing Tech Specs to Reflect Transition to Use of Optimized Fuel Assemblies
Project stage: Other
ML20100D2801985-03-22022 March 1985
SER Supporting Amends 42 & 23 to Licenses NPF-9 & NPF-17, Respectively
Project stage: Other
1984-11-16
[Table View] |
Forwards Safety Evaluation for McGuire Units 1 & 2 Transition to Westinghouse 17x17 Optimized Fuel Assemblies. License Amend Requests,Including Tech Spec Changes & cycle- Specific Reload Safety Evaluations,Will Be Submitted| ML20082D639 |
| Person / Time |
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| Site: |
McGuire, Mcguire  |
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| Issue date: |
11/14/1983 |
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| From: |
Tucker H
DUKE POWER CO. |
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| To: |
Adensam E, Harold Denton
Office of Nuclear Reactor Regulation |
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| Shared Package |
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| ML20082D641 |
List: |
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| References |
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| TAC-52390, TAC-52391, TAC-53319, TAC-53320, TAC-56336, TAC-56337, NUDOCS 8311220490 |
| Download: ML20082D639 (2) |
|
Text
o e
DUKE POWER GOMPANY l'.o. nox 33180 CitAMLOTTE, N.G. 28242 IIALltTUCKER TELEPHONE (704) 373-4531 TM41 PERSWENT Dr0015A5 PEODUCT90W November 14, 1983 Mr. Harold R. Denton, Direc*or Office of Nuclear Reactor, Regtd stion U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Ms.
E.'G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station
-Docket Nos. 50-369, 50-370
Dear Mr. Denton:
The purpose of this letter is to describe planned changes in the fuel design for McGuire Nuclear Station, Units 1 and 2.
Commencing with the first refueling of each of the units,.the standard fuel assemblies (STD) currently in use will be replaced over the next four; refuelings with optimized fuel assemblies (OFA).
The attached reference safety evaluation (RSE) describes the safety impact of operation with a transition core (1/3 0FA - 2/3 STD and 2/3 0FA - 1/3 STD) and an all 0FA core.
Since the transition to 0FA involves changes in operating limits, license amendments will be required for operation of both Units 1 and 2 beyond the first cycle. Specific license amendment requests including proposed changes to Technical Specifications and a cycle-specific RSE will be submitted four to six months prior to the first refueling of each unit.
It is anticipated that for subsequent cycles, no changes to Technical Specifications will be required and future reload design would be accomplished under 10 CFR 50.59 using standard reload design methods.
The Unit Cycle 2 RSE and proposed Technical Specification changes will be submitted within the next ten days. Unit 1 first refueling shutdown is currently l
planned for mid-February with return to service planned for late March.
Please advise if there are any questions concerning this matter.
l Very truly yours, b
l C
y Hal B. Tucker GAC/php
\\
9 8311220490 831114 1
1 PDR ADOCK 05000396 P
PDR
l l
Mr. Harold'R. Denton, Director November 11, 1983 Page 2 s
t cc:
Mr. James P. O'Reilly,-Regional Administrator U. S. Nuclear Regulatory Cotamission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station
,