ML20137F976

Application for Amend to License DPR-57,reflecting Addition of High Radiation Isolation Signal for Containment Purge & Vent Valves.Fee Paid

ML20137F976
Person / Time
Site:	Hatch
Issue date:	08/20/1985
From:	Beckham J GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20137F982	List: ML20137F976 ML20137F993
References
1973N, NED-85-577, TAC-56049, TAC-59542, NUDOCS 8508270138
Download: ML20137F976 (5)

Text

e-Georgia Power Company 333 Piedmont At enue

, Atlanta, Georgia 30308 Telephor0 404 526-7020 Ma*ng Ad&ess-Post Office Box 4545 Atlanta, Georgia 30302 g Georgia Power J. T. Beckham, Jr. me sauthern ciectnc :ycem Vice Presider.t and General Manager Nuclear Operations NED-85-577 1973N August 20, 1985 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 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS PURGE / VENT ISOLATION Gentlemen:

In accordance with the provisions of 10 CFR 50.90 as required by 10 CFR 50.59(c)(1), Georgia Power Company proposes to amend the Hatch Unit 1 Technical Specifications, Appendix A to Operating License DPR-57.

The proposed change revises the isolation actuation instrumentation section to reflect the addition of a high radiation isolation signal for the containment purge and vent valves.

Attachment 1 provices a detailed description of the proposed change and circumstances necessitating the change request.

Attachment 2 details the basis for our determination that the proposed change does not constitute an unreviewed safety question.

Attachment 3 details the basis for our determination that the proposed change does not involve significant hazards considerations.

Attachment 4 provides page change instructions for incorporating the proposed change.

The proposed changed Technical Specification pages follows Attachment 4.

Payment of filing fee is enclosed.

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Georgia Power A Director of Nuclear Reactor Regulation '

Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 August 20, 1985

-Page Two In order to allow time for procedure revision and orderly incorporation into copies of the Technical Specifications, we request that the proposed amendment, once approved by the NRC, be issued with an effective date to be no later than 30 days from the date of issuance of the amendment.

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

J. T. Beckham, Jr. 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 COMPANY By: b e

/ J. T. Beckham, Jf.

Sworn to nd subscribed before m this 20th day of August,1985.

Notary Public, Georgia, State at Large

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My Commission Expires Sept.18,1987

/ '

Notary Public JH/mb Enclosure xc: Mr. H. C. Nix, Jr.

Senior Resident Inspector Dr. J. N. Grace, (NRC-Region II)

Mr. J. L. Ledbetter 700775

ENCLOSURE 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS PURGE / VENT ISOLATION The proposed change will revise Section 3/4.2.A, Instrumentation Which Initiates Reactor Vessel and Containment Isolation, to reflect a modification planned for implementation during the Fall 1985 refueling outage. The modification satisfies the requirements of TMI Action Plan Item II.E.4.2.(7), which specifies that containment purge and vent valves close automatically on a high containment radiation signal. A detailed description of the modification was provided in our submittal dated April 10, 1984. The proposed change adds limiting conditions for operation and surveillance requirements for the radiation monitors which provide the isolation signals to the purge and vent valves. The isolation setpoint is based on limiting the radiation dose at the site borindary to the EPA Protective Action Guide limits of 1 Rem whole body and . Rem thyroid. The nominal setpoint of 100 Rem /Hr is approximately an order of magnitude lower than the actual containment radiation level at which isolation would need to occur to satisfy the off-site dose criterion. Furthermore, a 30-minute delay in valve closure is assumed, resulting in an extremely conservative setpoint. The purge and vent valves are also closed by previously existing, redundant and diverse signals.

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1 ENCLOSURE 2 ,

i e NRC DOCKET 50-321 OPERATING LICENSE DPR-57

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EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS PURGE / VENT ISOLATION Pursuant to 10 CFR 50.59, the Plant Review Board and Safety Review Board have reviewed the attached proposed amendment to the Plant Hatch Unit 1 Technical Specifications and have determined that' implementation of the proposed amendment does not constitute an unreviewed safety question.

PROPOSE 0-CHANGE Add the radiation monitors which provide the isolation signals to the purge and vent valves to Tables 3.2-1 and 4.2-1.

BASIS 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 because the change provides additional redundancy to previously existing containment isolation signals.

The possibility of an accident or malfunction of a different type than those analyzed in-the FSAR is not created by this change because no new failure mode-is introduced.

The margin of safety as defined in the Technical Specifications is not i reduced because the change results in an isolation signal which is in addition to the existing signals, assuring conformance with the accident analysis. -

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ENCLOSURE 3

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NRC DOCKET 50-321

...I OPERATING LICENSE DPR-57 ll. EDWIN I. HATCH NUCLEAR PLANT UNIT 1

.. REQUEST TO REVISE TECHNICAL SPECIFICATIONS PURGE / VENT ISOLATION Pursuant to 10 CFR 50.92, Georgia Power Company has evaluated the attached proposed amendment for Plant Hatch Unit 1 and has determined that its adoptionL would not involve a significant hazard. The basis for this determinationils as follows:

PROPOSED CHANGE Add the radiation monitors which provide the isolation signals to the purge and vent valves to Tables 3.2-1 and 4.2-1.

2 BASIS This change constitutes an additional restriction not presently included in the Technical Specifications. This change does not affect the probability or consequences of an accident or malfunction analyzed in the FSAR. This change does not create the possibility of an accident or

[ malfunction of a different type than any analyzed in the FSAR. The margin of safety as defined in the basis for any Technical Specification is' not affected. The effect of this change is therefore within the acceptance criteria and the change is consistent with Item (ii) of the

" Examples of Amendments that are Considered Not Likely to Involve

. Significant Hazards Considerations" listed on page 14,870 of the

! April 6, 1983, issue of the Federal Register.

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