ML20133B327

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Application for Amend to License DPR-57,changing Tech Specs to Add Spec & Table Addressing Component Cycle & Transient Limits to Section 5 & Table Number in Tech Spec 6.10.2.e.Fee Paid
ML20133B327
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 07/26/1985
From: Beckham J
GEORGIA POWER CO.
To: Stolz J
Office of Nuclear Reactor Regulation
Shared Package
ML20133B331 List:
References
1915N, 1915N5-540, NED-85-540, TAC-59308, NUDOCS 8508060141
Download: ML20133B327 (5)


Text

f l Georgia Power Company l 333 Piedmont Avenue j Atlanta, Georgia 30308

  • Telephone 404 526-7020 l

Mailing Address Post office Box 4545 Atlanta. Georgia 30302 h

Georgia Power J. T. Beckham, Jr. the scutnem elecinc system Vice President and General Manager Nuclear Operations NED-85-54C 1915N July 26, 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:

ADD SPECIFICATION AND TABLE ADDRESSING COMPONENT CYCLIC AND TRANSIENT LIMITS Gentlemen:

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

The proposed changes would add a specification and table addressing component cyclic and transient limits to Section 5.0 of the Technical Specifications, as well as change the table number referenced in Technical Specification 6.10.2.e. These proposed changes will clarify the record retention recuirements and provide a selected listing of the thermal cycle transient limits for the reactor pressure vessel in accordance with the listing contained in the Standard Technical Specifications.

Attachment 1 provides a detailed description of the proposed changes and circumstances necessitating the change reotgst.

Attachment 2 details the basis for our determination that the proposed changes do not constitute an unreviewed safety cuestion.

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

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

The proposed chanced Technical Soecification pages follow Attachment 4.

8508060141 850726 PDR ADOCK 05000321 P PDR ,

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Georgia Power d Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 July 26, 1985 Page 2 Payment of filing fee is enclosed.

In order to allow time for procedure revision and orderly incorporation into copies of the Technical Specifications, we recuest 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 recuirements 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 s Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.

GEORGIA POWER COMPANY By: d, -h

/ J. T. Beckham, Jr.

Sworn to and subscribed. efore me this 26th day of July,1985.

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,My Mr% Georgis, state at Iam NotsffPubTit ***Pt 18.1987 GDP/sm Enclosure xc: H. C. Nix, Jr.

Senior Resident Inspector J. N. Grace, (W C-Region II)

J. L. Ledbetter

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ATTAC N T 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

ADO SPECIFICATION Af0 TABLE ADDRESSING COMP 0ENT CYCLIC APO TRANSIENT LIMITS Plant Hatch Unit 1 Technical Specifications currently reference a

. non-existent Table for identifying component cyclic and. transient limits. The

- proposed changes will add a new specification and table to Section 5.0 of the

. Technical Specifications that lists selected cyclic and ' transient limits for the reactor pressure vessel. Also, Technical Specification 6.10.2.e

'(addressing the recording and retention reouirements of transient _. and operational cycles) will be corrected to reference the new table being added to .Section 5.0. The proposed changes to Section 5.0 of the Technical Specification will conservatively bound the design transient limits appearing in the Hatch *Mit 1_ updated FSAR and are consistent with the cyclic and transient limits in the Hatch Unit 2 Technical Specifications. Thus, these proposed changes will meet the Technical Specification reouirements for recording and retaining data on component cycling while not impacting plant safety.

F .

ATTACIDENT 2 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

ADD SPECIFICATION AND TABLE ADDRESSING COMPONENT CYCLIC AND TRANSIENT LIMITS 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.

PROPOSED CHANGE:

The proposed changes would add a specification and table to Section 5.0 of the plant Technical Specifications to define the reactor presnure vessel cyclic and transient limits to be monitored.

BASIS:

The probability of occurrence and the consequences of an accident or malfunction of equipment important to safety are not increased above those analyzed in the FSAR due to this change because the proposed cyclic and transient limits conservatively bound the design limits appearing in the FSAR.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because there is no

' impact on plant operation. These proposed changes will only add cyclic and transient limits for Technical Specification completeness.

The margin of safety as defined in the Technical Specifications is not reduced due to this change because new requirements are being added to the Technical Specifications.

PROPOSED CHANGE:

This proposed change would correct the table number being referenced in Technical Specification 6.10.2.e.

BASIS:

The probability of accurrence and the consequences of an accident or malfunction of equipment important to safety are not increased above those analyzed in the FSAR due to this change because this is an

- editorial change, made for Technical Specification consistency, and has no effect on plant operation.

The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new modes of plant operation are introduced. I l

The margin of safety, ns defined in the Technical Specifications is not l affected by this editorial change.

I

ATTACHMENT 3 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

' ADD SPECIFICATION AND TABLE ADDRESSING COMPONENT CYCLIC AND TRANSIENT LIMITS Pursuant to 10 CFR 50.92, Georgia Power Company has evaluated the attached proposed amendment of Plant Hatch Unit 1 and has determined that its adoption would not involve a significant hazard. The basis for this "

determination is as follows:

PROPOSED CHANC,5)

The proposed changes would add a specification and table to Section 5.0 of the plant Technical Specifications to define the reactor pressure vessel cyclic and transient limits to be monitored.

BASIS:

These changes are consistent with Item (ii) of the " p amples of Amendments that are Considered Not Likely to InvolveJSignificant Hazards Considerations: listed on page 14,870 of the Federal Register, April 6, 1983. The proposed changes introduce additional limits not presently included in the Technical Specifications and therefore, meet the Item (ii) requirements for an amendment involving no significant hazards considerations.

PROPOSED CHANGES:

The proposed change would correct the table number being referenced in Technical Specification 6.10.2.e.

BASIS:

This change is consin*.ent with Item (i) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Consideration" listed on page 14,870 of the Federal Register, April 6, 1983. The proposed editorial change is made to achieve consistency throughout the Technical Specifications and therefore meets the requirements of Item (i) for an amendment involving no significant hazards considerations.