ML20005E879

Application for Amend to License NPF-5,revising Tech Specs Using Guidance in 52FR3788, NRC Interim Policy Statement on Tech Spec Improvements for Nuclear Power Reactors.

ML20005E879
Person / Time
Site:	Hatch
Issue date:	12/21/1989
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20005E880	List: ML20005E879
References
HL-738, NUDOCS 9001120025
Download: ML20005E879 (8)

Text

. . . _ _ _ . . . . . . . . .

W Georga Power Company

3. ,

. 333 Piedmont Avenue

' o' Atlanta, Georpa 30308 .

% ' ' - Totophone 404 5243195

..- MaihnD Address t Of on1 95 41" 2 J a ltBT' '

Irv M wern entne sprem W. G. Hairston, lH Senior Vce President Nuclear Operations HL-738 0293V December 21, 1989 U.S. Nuclear Regulatory. Commission ATTN: Document Control Desk Hashington, D.C. 20555 PLANT HATCH - UNIT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM RE00EST TO REVISE TECHNICAL SPECIFICATIONS 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 changes to the Plant Hatch Unit 2 Technical Specifications, Appendix A to Operating License NPF-5.

This submittal proposes to revise the Plant Hatch Unit 2 Technical Specifications using the guidance provided in 1) 52FR3788, "NRC Interim Policy Statement on Technical Specification Improvements for Nuclear Power Reactors," February 6,1987 and 2) NRC letter from T. E. Murley (NRC) to R. F. Janecek (BHROG), "NRC Staff Review of Nuclear Steam Supply System Vendor Owners Groups' Application of the Commission's Interim Policy Statement Criteria to Standard Technical Specifications," May 9, 1988. Additionally, guidance developed in the continuing dialogue between NRC and NUMARC (to which GPC has been a principle contributor) has- been utilized. GPC's Plant Hatch Unit 2 is the lead plant for Technical Specification Improvement for the Boiling Hater Reactor Owners Group.

The Limiting Conditions for Operations (LCOs), Applicabilities, Actions and Surveillance Requirements have been rewritten to be clear and concise. For certain specifications, GPC is proposing to add requirements in order to achieve consistency with other specifications, safety analyses, and plant hardware. GPC utilized the results of evaluations that have been reviewed and approved by the NRC in the development of these specifications. GPC also proposes technical changes that would relax requirements which are unduly restrictive and eliminate requirements that are unnecessary or inappropriate. These relaxations t are described and justified in Enclosure 3. g *

.g h, #

h6  ; $oS p sl f

I~icorgia Power U.S. Nuclear Regulatory Commission December 21, 1989 Page Two The current Technical Specifications which do not meet the Selection Criteria in Reference 1 will be relocated. The principle control process 1 for the relocated specifications is an improved implementation of 10 CFR i 50.59. GPC expects to modify the appropriate administrative controls to

address the improvements outlined in NSAC-125 (Guidelines for 10 CFR 50.59 Safety Evaluations, June 1989) by mid-1990.

Technical Specification Bases have been upgraded in accordance with NRC guidance. Each LCO, Applicability, Action, and Surveillance Requirement is addressed in the Bases. Additionally, each Bases has Background and Safety Analysis sections that provide general information about the system, component, or parameter addressed by the LCO, the relationship between the LCO requiremer.ts and the appropriate safety analyses, and the explanation of which criterion requires the specification -to be contained in the Technical Specifications. The Bases were developed principally from the Plant Hatch Unit 2 Final Safety Analysis Report (FSAR). In certain cases, the Bases conflict with the FSAR due to new analysis or information developed during this program.

The Bases utilize this new information and the FSAR will be updated at the appropriate time (prior to implementation of the proposed Technical Specifications).

Enclosed for your review are:

1. Proposed Hatch Unit 2 Technical Specifications.

2. Proposed Hatch Unit 2 Technical Specifications Bases.

3. Proposed No Significant Hazards Consideration Determination for all technical changes in accordance with 10 CFR 50.92. The proposed No Significant Hazards Consideration Determinations are numbered consistent with the proposed Technical Specifications.

To facilitate your review, GPC has also enclosed the following:

1. A comparison document that summarizes the proposed disposition of all existing requirements.

2. A markup of NEDC-31681 (BHROG Improved BHR Technical Specifications) showing necessary plant-specific changes to the .

generic Technical Specifications. This markup also provides discussions of the changes.

This submittal has been reviewed by the Plant Review Board and the Safety Review Board in accordance with existing Technical Specifications sections 6.5.1.6.c and 6.5.2.8.c. GPC is confident that this submittal meets NRC needs and expectations at this stage of the industry Technical Specification improvement process.

( ,

corgiaPOEerb U.S. Nuclear Regulatory Commission .

Decemter 21', 1989 Page Three Implementation of this amendment iii tentatively scheduled 1 year following NRC approval of the Plant Hatch Unit 1 improved Technical Specifications. (NRC approval of Unit 1 Technical Specifications has been assumed to occur in January 1991.) GPC plans to submit the Plant Hatch Unit 1 improved Technical Specifications in mid-1990.

Payment of the filing fee has not been enclosed, since in a letter from T. S. Murley (kRC) to J. F. Colvin (NUMARC), the NRC stated the resources used for - the review of the Plant Hatch Unit 2 proposed Technical Specifications (the BWR-4 lead plant) will be included in the base for annual fees collected under 10 CFR 171.

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. H. G. Hairston, III states that he is a Senior 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 and enclosures are true.

GEORGIA POWER COMPANY By: - cO . ~

. p> H. G. Hairston, III Sworn to and subscribed before me this A day of D e m u m 1989.

OwLn hWm )

Notary Public' JCJ/eb

Enclosures:

1. Proposed Technical Specifications

2. Proposed Technical Specifications Bases

3. Proposed Technical Specifications 10 CFR 50.92 Evaluations

4. Current Hatch Unit 2/ Proposed Hatch Unit 2 Technical Specifications Comparison Document

5. Proposed BWR STS/ Proposed Hatch Unit 2 Technical Specifications Comparison Document l

l l-

/

Jecnjia Pcnver afhi U.S. Nuclear Regulatory Commission December 21, 1989 Page Four c: Georaia Power Comoany Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch GO-NORMS U.S. Nuclear Reaulatory Commission. Washinaton. D.C.

Mr. L. P. Crocker, Licensing Project Manager - Hatch Mr. J. A. Calvo, Chief, Technical Specifications Branch U.S. Nuclear Regulatory Commission. Region II Hr. S. D. Ebneter, Regional Administrator Mr. J. E. Henning, Senior Resident Inspector - Hatch l

l l

l l

I l

1 l

0293V l

l

y. , . ,

• oro a Power C ca%

(

, ,f- ' -

, 7.33 F eumor8 A.e^ut Atan:a Georg a 30308 t eonone 404 E:6 3195 d I.ia bng Aaaress

.10 inse r'ess Center Parkway ' i L Post Ott ce Box 1295 I 8 rwngnam A+acama 35201 Vepnone 205 666 5581

, e tcy'.-rn es% '* c $. Yem

l. W. G. Heireton, all Senior V Ce Pret Den'

'JuClear ODerat Cn3 HL-738 0293V December 21, 1989 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 PLANT HATCH - UNIT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM REOUEST TO REVISE TECHNICAL SPECIFICATIONS 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 changes -

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

This submittal proposes to revise the Plant Hatch Unit 2 Technical -

Specifications using the guidance provided in 1) 52FR3788, "NRC Interim Policy Statement on Technical Specification Improvements for Nuclear Power Reactors," February 6,1987 and 2) NRC letter from T. E. Murley ,

(NRC) to R. F. Janecek (BHROG), "NRC Staff Review of Nuclear Steam Supply System Vendor Owners Groups' Application of the Commission's Interim Policy Statement Criteria to Standard Technical Specifications," May 9, 1988. Additionally, guidance developed in the continuing dialogue .

l between NRC and NUMARC (to which GPC has been a principle contributor) has been utilized. GPC's Plant .9atch Unit 2 is the lead plant for I- Technical Specification Improvement for the Boiling Water Reactor Owners L Group.

L The Limiting Conditions for Operations (LCOs), Applicabilities.

Actions and Surveillance Requirements have been rewritten to be clear and concise. For certain specifications, GPC is proposing to add requirements in order to achieve consistency with other specifications, safety analyses, and plant hardware. GPC utilized the results of evaluations that have been reviewed and approved by the NRC in the development of these specifications. GPC also proposes technical changes

that would relax requirements which are unduly restrictive and eliminate

, requirements that are unnecessary or inappropriate. These relaxations are described and justified in Enclosure 3.

l l

g or ia Power b U.S. Nuclear Regulatory Commission December 21, 1989 Page Two The current Technical Specifications which do not meet the Selection Criteria in Reference I will be relocated. The principle control process for the relocated specifications is an improved implementation of 10 CFR 50.59. GPC expects to modify the appropriate administrative controls to address the improvements outlined in NSAC-125 (Guidelines for 10 CFR 50.59 Safety Evaluations, June 1989) by mid-1990.

Technical Specification Bases have been upgraded in accordance with NRC guidance. Each LCO, Applicability. Action, and Surveillance Requirement is addressed in the Bases. Additionally, each Bases has Background and Safety Analysis sections that provide general information about the system, component, or parameter addressed by the LCO, the relationship between the LCO requirements and the appropriate safety analyses, and the explanation of which criterion requires the specification to be contained in the Technical Specifications. The Bases were developed principally from the Plant Hatch Unit 2 Final Safety Analysis F.eport (FSAR). In certain cases, the Bases conflict with the FSAR due to new analysis or information developed during this program.

The Bases utilize this new information and the FSAR will be updated at the appropriate time (prior to implementation of the proposed Technical Specifications).

Enclosed for your review are:

1. Proposed Hatch Unit 2 Technical Specifications.

2. Proposed Hatch Unit 2 Technical Specifications Bases.

3. Proposed No Significant Hazards Consideration Determination for  ;

r all technical changes in accordance with 10 CFR 50.92. The

! proposed No Significant Hazards Consideration Determinations are l numbered consistent with the proposed Technical Specifications.

1 To facilitate your review, GPC has also enclosed the following

1. A comparison document that summarizes the proposed disposition of I all existing requirements.

l

2. A markup of NEDC-31681 (BHROG Improved BWR Technical Specifications) showing necessary plant-specific changes to the generic Technical Specifications. This markup also provides discussions of the changes.

This submittal has been reviewed by the Plant Review Board and the Safety Review Board in accordance with existing Technical Specifications sections 6.5.1.6.c and 6.5.2.8.c. GPC is confident that this submittal meets NRC needs and expectations at this stage of the industry Technical I Specification improvement process. l

coig!) Poker b U.S. Nuclear Regulatory Commission December 21, 1989 Page Three Implementation of this amendment is tentatively scheduled 1 year following NRC approval of the Plant Hatch Unit 1 improved Technical Specifications. (NRC approval cf Unit 1 Technical Specifications has been assumed to occur in January 1991.) GPC plans to submit the Plant Hatch Unit 1 improved Technical Specifications in mid-1990.

Payment of the filing fee has not been enclosed, since in a letter

• from T. S. Murley (NRC) to J. F. Colvin (NUMARC), the NRC stated the resources used for the review of the Plant Hatch Unit 2 proposed Technical Specifications (the BHR-4 lead plant) will be included in the i base for annual fees collected under 10 CFR 171.

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. H. G. Hairston, III states that he is a Senior 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 and enclosures are true.

GEORGIA P0HER COMPANY By:

• O. / < - -

H. G. Hairston, III m

Sworn to and subscribed before me this A I) day of il m e h s 1989.

NG4n Notary bk f\W% Public' J

JCJ/eb l

Enclosures:

I

1. Proposed Technical Specifications

2. Proposed Technical Specifications Bases i 3. Proposed Technical Specifications 10 CFR 50.92 Evaluations

4. Current Hatch Unit 2/ Proposed Hatch Unit 2 Technical Specifications Comparison Document

5. Proposed BWR STS/ Proposed Hatch Unit 2 Technical Specifications i.omp;rison Oc: ament l

l

SeorgipPower A U.S. Nuclear Regulatory Commission December 21, 1989 Page Four 1

c: Georaia Power ComDany Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch i GO-NORMS I l

U.S. Nuclear Reaulttory Commission. Washinaton. D.C. l Mr. L. P. Crocker, Licensing Project Manager - Hatch  !

Mr. J. A. Calvo, Chief. Technical Specifications Branch l

U.S. Nuclear Reaulatory Commission. Reaion II l Mr. S. D. Ebneter, Regional Administrator Mr. J. E. Henning, Senior Resident Inspector - Hatch l

l l

l l

l 0293V l