ML20128R216

Application for Amend to License DPR-57,deleting Tech Spec Table 6.9.2-1 Re Requirements to Rept Results of Secondary Containment Leak Tests & Summaries of Primary Coolant Leakage to Drywell.Fee Paid

ML20128R216
Person / Time
Site:	Hatch
Issue date:	05/20/1985
From:	Beckham J GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20129A000	List: ML20128R216 ML20129A021
References
1649N, NED-85-358, TAC-57907, NUDOCS 8506040433
Download: ML20128R216 (6)

Text

r I Georgo Power Carpany I

333 Piedmont Av no:

Attint . Geogia 30300 Telept'one 404 S20 7020 Mail ng A&1ress Post Off'co Dou 4545 Atlarta, Geoig a 30302 Georgia Power i J. T. Beck ham, Jr. Ur snstrun r n roc astem Vice PreaWt and Gener al Manger nuueu cerraten . NED-85-358 1649N May 20, 1985 Director of Riclear Reactor Regulation Attention: Mr. John F. Stolz, Chiet Operating Reactors Branch No. 4 Division of Licensing U. S. Maclear Regulatory Comission l Washirgton, D. C. 20555

! NRC DOCK 11P 50-321 OPERATING LIQ 11SE DPR-57 EDWIN I. IIA'IOl NUCLEAR PIRIP UNIT 1 RIICEST '10 REVISE TErlINICAL SPECIFICATIONS:

PICIGED CIWG21 'lU SPirIAL REPOffrING 1&QUllRM2flS Gentlerren:

In accordance with the provisions of 10 CFR 50.90 an reojirmi ty 10 CFR 50.59 (c) (1) , Georgia Power Company (GPC) hereby proponos changen to the Technical Specifications, Appendix A to Operating Liconne DPR-57.

These proposal changes woJ1d delete from Plant llatch Unit 1 Technical Specifications Table 6.9.2-1, roojirements to report teruits of necondary containment Icak rate tests and turivriaries of primary coolant leakage to the drywell.

Attachment 1 provides a detailed description of the propocod changen and ciroamstances necessitating the change reolont.

Attachment 2 details the hanis for mr determination that the proposed changes do not conntitute an unreviewnl safety mention.

Attachment 3 details the basis for rur determination that the proponed changen do not involve significant hazards considerationn.

Attachnent 4 provides page change inntructions for incorporating the proposal chanje.

'nm proponed changed Technical Specification pagon follow Attachmont 4.

Payment of filing fee is enclorni. g I

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()f i 4 qf,q'3 Y 0506040433 050520 'I PDH ADOCK 05000321 P PDH

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Georgialbwer A Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 May 20, 1985 ,

Page Two l R1rsuant to the recnirements 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 Gaorgia Power Conpany and is althorized to execute this oath on behalf of Georgia Power Conpany, and that to the best of his knowledge and belief the facts set forth in this letter are true.

GEDRGIA POWER COMPANY

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By: yf 7 '>> of y J. T. Beckham, Jr.

Swo and albscribed fore me this 20th day of May, 1985.

N, N -' '~

getyy n bHc. Georgia. State at Large u . c .-. :-.1,- rs,- w la 1987 Notary ITIbTic CRP/ REB /mb Encloalre xc: H. C. Nix, Jr.

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

J. L. Ledbetter 700775

ATTACHMENT 1 m C DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 BASIS FOR CHANGE REQUEST Plant Hatch Unit 1 Technical Specification 6.9.2 requires, per Table 6.9.2-1, that a summary technical report of the secondary containment integrated leak rate test be submitted within three months following conduct of that test and that a report of primary coolant leakage into the drywell be submitted every five years. The proposed change would delete requirements for these reports from the Technical Specifications.

These reporting requirements were part of the original issue of the Hatch Unit 1 Technical Specifications, dated August 6,1974. It is believed that the reports may have been required at the time to augment NRC's data base on containment performance. However, since that time, reporting ,

requirements have significantly changed. Neither the Plant Hatch Unit 2 Technical Specifications nor GE BWR 4 Standard Technical Specifications contain requirements for submittal of these reports. l Table 6.9.2-1 requires that the integrated leak rate test of secondary containment include such parameters as wind speed, wind direction, outside

-and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rates. Although this report is defined in Table 6.9.2-1, there is no requirement in the Technical

, Specifications or in the existing codes, standards, and regulations for Plant Hatch thit 1 for the performance of such a test. Plant Hatch Unit 1 Technical Specification 4.7.C req'uires tests at appropriate times to demonstrate secondary containment operability by maintaining 1/4 inch of HO 2 vacuum in secondary containment, but there is no requirement to I perform an integrated leak rate test or to monitor various atmospheric parameters while performing such a test. Since no such test is defined or required, we propose that the associated reporting requirement be deleted from the Technical Specifications.

Table 6.9.2-1 also requires that primary coolant leakage to the drywell be reported to the EC once every five years. However, there is no definition or requirement of what should be in that report. Specific requirements and action statements exist in Technical Specification '3.6.G to stringently monitor and control the reactor coolant leakage into the drywell. Plant shutdown and NRC notification are required if the specified leakage rates are exceeded.

May 20, 1985

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ATTAC s l'(Continued)

As noted above, ~ specifications exist for both maintaining secondary

containment integrity and maintaining limits on reactor coolant leakage .into the drywell. The MtC has defined appropriate reporting requirements for the TechnicaliSpecifications 'in' 10 CFR 50.73, which requires reporting in the event that specified leakage rates are , exceeded. GPC therefore believes

. that the. reports proposed to be deleted are superfluous. The only presently unreported. area these reports would cover would be the test results of the routine maintenance of. secondary . containment integrity and the routine

. reactor coolant leakage to the drywell. Therefore, GPC requests that the

' MC delete the requirement for submittal of these two reports from the Plant Hetch Unit 1 Technical Specifications.

May 20, 1985

ATTACHMENT 2 W C DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 10 CFR 50.59 EVALUATION 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 change does not constitute an unreviewed safety question.

The probability of occurrence and the consequences of an accident or malfun: tion of equipment. Important to safety are not increased above those analyzed in the FSAR since the proposed change involves only administrati.ve reporting requirements. In addition, only reporting requirements dealing with routine operation of secondary containment operation or reactor coolant leakage to drywell would be deleted. All abnormal events would be reported through the requirements of 10 CFR 50.73, as appropriate.

The possibility of an accident or malfunction of a different type than onalyzed in the FSAR does not result because no changes to the plant modes of operation are being proposed.

The margin of safety as defined in the Technical Specifications is

~

unaffected by deletion of this administrative requirement.

May 20, 1985 c_-___-___-_

ATTACHMENT 3 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN.I. HATCH NUCLEAR PLANT UNIT 1 10 CFR 50.59 EVALUATION 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 adoption would not. involve a~ significant hazard. The basis for this determination is as follows:

This change is consistent with Item (1) of the " Examples of Amendments that are Considered -Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the Federal Register, April 6, 1983. Item (1) is defined as an administrative change to the Technical Specifications. Since the proposed change would delete reporting requirements in the Technical Specifications which provide the NRC with the routine testing results of secondary containment integrity and reactor coolant' into the drywell (Abnormal test results would be covered under 10 CFR 50.73), it is consistent with item (1)..

May 20, 1985