ML20247Q318

Application for Amend to License NPF-5,revising Tech Specs for Min Critical Power Ratio Safety Limit

ML20247Q318
Person / Time
Site:	Hatch
Issue date:	09/18/1989
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247Q324	List: ML20247Q318 ML20247Q326
References
HL-663, NUDOCS 8909280166
Download: ML20247Q318 (5)

Text

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It,";!em 0: + gos HL-663-000480 X7GJ17-H600 September- 18, 1989 U..S. Nuclear Regulatory. Commission ATTN: Document Control Room Washington, D.'C. 20555 EDWIN I. HATCH NUCLEAR PLANT - UNIT 2' NRC DOCKET 50-366 OPERATING LICENSE NPF-5 RE03EST TO REVISE TECHNICAL SPECIFICATIONS:

MCPR SAFETY LIMIT-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 a change to

'the Plant Hatch Unit 2 Technical Specifications, Appendix'A to Operating License NPF-5.

The proposed change involves a revision of the Plant Hatch Unit 2 Technical Specifications for the Minimum Critical Power Ratio Safety Limit.

Specifically, the proposed Technical Specifications change will reduce the Minimum Critical Power Safety Limit from'the current value of 1.07 to

.1.04 for two-loop operation and from 1.08 to 1.05 for single-loop operation.

Enclosure 1 provides a detailed description of the proposed change and the circumstances necessitating the change request.

Enclosure 2 details the bases for our determination that the proposed change does not involve a significant hazards consideration.

Enclosure 3 provides page change instructions for incorporating the proposed change. The proposed changed Technical Specifications pages for Unit 2 follow Enclosure 3.

To allow time for procedure revisions and orderly incorporation into copies of the Technical Specifications, GPC requests the proposed amendment, once approved by the NRC, be issued with an effective date to be no later than 60 days from the date of issuance of the amendment.

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8909280166,y j66 I 1 PDR ADOCl PDC I P

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U. S. Nuclear Regulatory Commission September 18, 1989 Page 2-

.i In. accordance with the requirements of 10 CFR 50.91, a copy of this letter and all. applicable enclosures will be sent to Mr. J. L. Ledbetter of the Environmental Protection Division of the Georgia Department of Natural Resources.

Mr. W. G. Hairston, III states that he is _ duly authorized to execute this oath on behalf of Georgia Power Company, and to the best of his knowledge and belief, the facts set forth in this letter are true.

GEORGIA POWER COMPANY By: M W W. G. Hairston, III Sworn to and subscribed before me this /J day of .1989.

L Noenus G ry Public

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MiC0h3SS10N EXPlRES DEC.15.1992 WGH/ gps

Enclosures:

1. Basis for Change Request

2. 10 CFR 50.92 Evaluation

3. Page Change Instructions cc: Georaia Power Company Mr. J. T. Beckham, Jr., Vice President - Plant llatch Mr. J. D. Heidt, Manager, Engineering and Licensing - Plant Hatch G0-NORMS U.S. Nuclear Reaulatory Commission. Washinaton D. C.

Mr. L. P. Crocker Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. Reaion II Mr. S. D. Ebneter, Regional Administrator Mr. J. E. Menning, Senior Resident Inspector - Hatch State of Georaia Mr. J. L. Ledbetter, Commissioner - Department of Natural Resources HL-663 000480

ENCLOSURE 1 PLANT HATCH - UNIT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 REQUEST TO REVISE TECHNICAL SPECIFICATIONS MCPR SAFETY LIMIT BASIS FOR CHANGE RE00EST PROPOSED CHANGE:

This proposed change will reduce the Plant Edwin I. Hatch Unit 2 Technical Specifications (TS) Minimum Critical Power Ratio (MCPR) Safety Limit from the current value of 1.07 to 1.04 for two-loop operation (TLO) and from 1.08 to 1.05 for single-loop operation (SLO). The change will also revise all associated Bases sections.

BASIS FOR PROPOSED CHANGE:

l Prior to the beginning of Cycle 9 for Hatch Unit 2, Georgia Power Company intends to load a second consecutive batch of high bundle R-factor (1 1.04) fuel manufactured by General Electric. This fuel is being loaded in order to achieve the maximum economic benefit from each fuel cycle. GE has confirmed that both reload batches 7 and 8 for Hatch 2 have bundle R-factors 2 1.04 and that the proposed 1.04 and 1.05 MCPR Safety Limits are applicable to Hatch 2, Cycle 9. Georgia Power Company will confirm the reduced MCPR Safety Limits are still applicable for the fuel loaded in subsequent cycles (i.e., Cycle 10 and beyond).

Using NRC-approved codes and methods, GE determined that the appropriate MCPR Safety Limit for fuel with a high initial R-factor is 1.04. As noted in the updated Bases section, the Safety Limit was calculated using the same uncertainties for all non-fuel related parameters as previously approved analyses. Only the fuel-related R-factor uncertainty was changed (from 1.6 to 1.5) to reflect the results of new physics method application j to bundles with higher enrichments. The NRC documented their concurrence l with GE's analysis and their generic approval of the 1.04 MCPR Safety Limit for these fuel types in their December 27, 1987, Safety Evaluation Report for " General Electric Standard Application for Reactor Fuel" (GESTAR-II),  ;

NEDE-24011-P-A, Amendment 14. In addition, GE evaluations confirmed that for SLO the .01 adder previously applied to the TLO Safety Limit also conservatively applies to SLO with a 1.04 TLO MCPR Safety Limit.

Therefore, the appropriate SLO Safety Limit is 1.05. Both of these Safety i Limits will conservatively ensure that 99.9% of the fuel rods in the core  ;

avoid boiling transition during the worst postulated anticipated 2

will operational occurrence.

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000480 El-1 l

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ENCLOSURE 2 PLANT HATCH - UNIT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 REQUEST TO REVISE TECHNICAL SPECIFICATIONS MCPR SAFETY LIMIT 10 CFR 50.92 EVALUATION PROPOSED CHANGE:

Description of Amendment Reauest: This proposed change will reduce the i Plant Edwin I. Hatch Unit 2 Technical Specifications (TS) Minimum Critical Power Ratio (MCPR) Safety Limit from the current value of 1.07 to 1.04 for  !

two-loop operation (TLO) and from 1.08 to.l.05 for single-loop operation l (SLO). The change will also revise all associated Bases sections.

Basis for Proposed No Significant Hazards Consideration Determination:

Georgia Power Company has evaluated this proposed amendment and determined that it does not involve a significant hazards consideration for the following reasons:

1. A reduction in the MCPR Safety Limit does not involve a significant increase in the probability or consequence of an accident previously evaluated because the use of high bundle R-factor fuel results in increasing conservatism with respect to the current MCPR Safety Limit.

Consequently, removal of this added conservatism translates into.an MCPR reduction that allows for higher energy cycles and more efficient fuel utilization without compromising plant safety.

2. This change does not create the possibility of a new or different kind of accident from any accident previously evaluated because it does not involve any change in plant equipment design or function.

3. This change does not involve a significant reduction in the margin of safety because NRC-approved codes and methods were used to determine that the proposed 1.04 MCPR Safety Limit will conservatively ensure that 99.9% of the fuel rods will avoid transition boiling during the worst abnormal operational occurrence if the core contains two sucessive reloads of high R-factor fuel. Additional confirmatory evaluations determined that the corresponding SLO MCPR Safety Limit is 1.05.

Bascd on the preceding assessment, Georgia Power Company has determined that this proposed amendment involves no significant hazards consideration.

HL-663 ,

J 000480 E2-1

1; ENCLOSURE 3

~ PLANT HATCH - UNIT 1 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 REQUEST TO 9.EVISE TECHNICAL SPECIFICATIONS NCPR SAFETY LINIT' PAGE CHANGE INSTRUCTIONS Removed Paae Insert Paae 2-1 2-1 B 2-1 B 2-1 B 2-4 B 2-4 B 3/4 2-3 B 3/4 2-3 Page 1 of 1

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