ML20072T037
| ML20072T037 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/30/1983 |
| From: | Head G GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20072T041 | List: |
| References | |
| NED-83-216, TAC-49989, TAC-51054, NUDOCS 8304070419 | |
| Download: ML20072T037 (4) | |
Text
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Geoga Pcver Cer pany 333 Picar"unt Aa rue Acada Geyma 303C8 TewNne 404 526 763 f/ W g A n ess Pt:M OF.ce Bc = 4545 e#1a Gmrc a 30302 G.F. Head E.[. M $ 7 "
March 30, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.
20555 NRC DOCKET 50-366 OPERATING LICENSE FFF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSAL FOR TECHNICAL SPECIFICATION CHANGES CYCLE 4 MAPLHGR AND MCPR Gentlemen:
In accordance with the provisions of 10 CFR 50.90 as required by 10 CFR 50.59(c)(1), Georgia Power Company (GPC) hereby proposes an amendment to the Edwin I. Hatch Nuclear Plant Unit 2 Technical Specifications (Appendix A to the Operating License).
This application reflects the changes to the reactor core design for Cycle 4.
The major change is in Specification 3/4.2.1, Maximum Average Planar Linear Heat Generation Rate (MAPLHGR).
The MAPLHGR curve for the new fuel type is added, as well as MAPLHGR curves for Unit 1 initial core and Reload 2 fuel types which may be used in Unit 2.
The documents which support these MAPLHGR curves are attached:
Y1003J01A57, " Supplemental Reload Licensing Submittal for Edwin I.
Hatch Nuclear Plant Unit 2, Reload 3 (Cycle 4)" dated January 1983, and General Electric (GE) letter # LMQ: 83-018, " Hatch 2 ECCS MAPLHGR Calculations for Hatch 1 Initial Core and Reconstituted Hatch 1 Reload 2 Fuel" dated February 22, 1983.
The MAPLHGR curves reflect burnup extensions in accordance with the guidance of NRC Generic letter 82-03 dated March 31, 1982.
Other changes include addition of a MCPR curve for 7x7 fuel based on a generic Rod Withdrawal Error Analysis, addition of the Linear Heat Generation Rate for 7x7 fuel, and several editorial changes.
Please refer to Attachment 3 for a page-by-page description of changes.
The MCPR limits currently in the Unit 2 Technical Specification are not being changed at this time even though the limits based on the Reload g
document, Y1003J01A57, would allow a lowering of the limits.
The attached GE letter # LMQ: 83-022, Hatch 2 Cycle 4 OLMCPR, dated February 24, 1983 states that the OLMCPR's in the Reload document, Y1003J01A57, (and, t
' therefore, the current OLMCPR's) are "sufficiently conservative to bound operation in Cycle 4 before nominal end-of-cycle at increased core flow (up to 105% of rated) and/or final feedwater temperature reduction (up to 630 FAT, on or below the 100% power /100% flow load line) conditions..."
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8304070419 830330 PDR ADOCK 05000366 O
rg.m
Georgia PowerA Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 March 30, 1983 Page Two The Plant Review Board and Safety Review Board have reviewed these proposed changes and have determined that these changes do not constitute an unreviewed safety question.
Because the values in these proposed changes were established by NRC approved core reload methodology, the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety are not increased above those analyzed in the FSAR nor is the margin of safety as defined in the Technical Specifications reduced due to these changes.
Since these changes introduce no new mode of operation, the possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result.
Enclosed is the determination of amendment class.
The proposed changes have been determined to be Amendment Class III types.
The appropriate payment is enclosed.
Implementation of this change is requested prior to unit startup, planned for May 29, 1983.
If you require any additional information or have any questions, please contact this office.
G. F. Head states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.
GEORGIA POWER COWANY By:
$. 7. /Lc b G. F. Head Sworn to a ubscribed before me th 30th day of March, 1983.
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Notary Pubuc, Georgia, state et Large ffffjfg)
@j My Commiaion Expires July 28,1984
'Notar9fubl DLT/nb Enclosure xc:
H. C. Nix, Jr.
Senior Resident Inspector J. P. O'Reilly, (NRC-Region II)
ATTACHENT 1 NRC DOCKET 50-366 OPERATING LICENSE tFF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 DETERMINATION OF AENDENT CLASS Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the attached proposed amendment to Operating License PPF-5 and has determined that:-
a)
The proposed amendment does not require the evaluation of a new Saf:tf f.aalysis Report or rewrite of the facility license; b)
The proposed amendment does not contain several complex issues, does not involve ACRS review, and does not require an environmental impact statement; c)
.The. proposed amendment does not involve a complex issue or more
- than one. environmental or safety issue; d)
The proposed amendment does involve a single safety issue, namely, changes to Cycle 4 core; e)
The proposed amendment is therefore a Class III amendment.
ATTACHENT 2 NRC DOCKET 50-366-OPERATItC LICENSE ffF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSAL FOR TECHNICAL SPECIFICATION CHAPCES CYCLE 4 MAPLHGR APO MCPR The proposed change to the Technical Specification (Appendix A to Operating License PPF-5) would be incorporated as follows:
Remove Page Insert Page 3/4 2-1 3/4 2-1 3/4 2-2 3/4 2-2 3/4 2-3 3/4 2-3 3/4 2-4 3/4 2-4a 3/4 2-Aa 3/4 2-4b 3/4 2-4b 3/4 2-Ac 3/4 2-4d 3/4 2-4e 3/4 2-Af 3/4 2-6 3/4 2-6 3/4 2-7b 3/4 2-7b 3/4 2-7c 3/4 2-8 3/4 2-8
-3/4 5-1 3/4 5-1 B 3/4 1-2 B 3/4 1-2 B 3/4 2-1 B 3/4 2-1 B 3/4 '2-4 B 3/4 2-4 8 3/4 2-5 B 3/4 2-5 s
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