ML20030D699
| ML20030D699 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/08/1981 |
| From: | Head G GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20030D700 | List: |
| References | |
| TAC-46704, TAC-49705, NUDOCS 8109150469 | |
| Download: ML20030D699 (3) | |
Text
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333 PT *W! A vC%9 A!.3Na Gear 3 a 35 h TCne 424 52E7693 Va ' 7 Aotecs Wr'c" R 83 4545 Atanta o 9 7 9 a 303C2 September 8, 1981 G. F. Head Sev Vce Presce'"
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OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1
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b CONFIRMATORY SUBMITTAL - EMERGENCY RELIEF
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FOR DRYWELL INERTING TECHNICAL SPECIFICATION Gentlemen:
Pursuant to 10 CFR 50.90, as required by 10 CFR 50.59(c), Georgia Power l
Company proposes an timendment to the Unit 1 Technical Specifications (Appendix A to the Operating License).
The proposed change is confirmatory l
in nature; emergency relief was granted for Unit 1 on July 9, 1981.
The attached pages document the basis for the requested, and approved, change.
Technical Specification 3.7. A.5.b requires "within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period subsequent to placing the reactor in the RUN mode following a shutdown, the containment atmosphere oxygen concentration shall be reduced to less than 4%
l by volume and maintained in this condition." Howeve., during the startup in i
progress on July 8 and 9, it became apparent that oxygen cncentration would not be reduced to less than 4% by volume within the. required 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i
following having placed the mode switch to the RUN position due to problems with the system used to evaporate the nitrogen used to inert the containment.
At that time a request was made of the NRC for ar. 3dditional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, for a total of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> subsequent to entering the RUN mode, before oxygen concentration must be reduced below 4%.
Safety Evaluation - Drywell Inertim The basis for a 24-hour requirement on attaining a 4 percent oxygen concentration following entry into the RUN mode is to minimize the possibility of hydrogen combustion following a loss-of-coolant accident.
The 24-hour period was established, as stated in the bases for specification 3.7.A.5, as being sufficient to perform necessary drywell inspections and establish the required oxygen concentration.
The cuatrol is administrative and supplements the Containment Atmosphere Dilution (CAD) System.
The CAD system provides the basis for assuring containment integrity post LOCA.
1 Because the 24-hour limit is an administrative control, as opposed to providing a safety function, margins of safety are not reduced by allowing a longer period of time to complete drywell inerting.
The safety margin is provided by the CAD system.
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Georgia Power h Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission September 8, 1981 i
Page Two The safety analysis report uses the CAD system as basis for LOCA analysis;
- thus, the probability or co1 sequences of an accident or malfunction of equipment important to saiety previously analyzed -is not increased by the proposed change.
Similarly, because the 24-hour limit performs an administrative function only, no new accidents or malfunctJons not previously analyzed are created.
The proposed change is therefore not an unreviewed safety question.
Your excellent cooperation with our staff in the expeditious resolution of the request was greatly appreciated.
Oxygen concentration was brought below 4% in the additional time granted, averting an unnecessary shutdown cycle on the unit.
G. F. Head 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 C0lPANY By:
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G. F. Head Sworn to and subs ribed before me this 8th day of September,1981.
Notary Pubhc, Georgia, State at t.arge gj My Commiwon Egres Sept. 20,1983 Notary Public RDB/.Tb Attachment xc:
M. Manry R. F. Rogers, III
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ATTACHNENT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSEC CHANGES TO TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the attached proposed amendments to Operating License DPR-57 and has determined that:
a)
The proposed amendment does not require the evaluation of a new Safety Analysis Report or rewrite of the facility license; b)
The proposed amendment does not contain several complex issues, does not involve ACRS review, and does not require an environmental impact statement; c)
The proposed amendment does not involve a complex issue, an j
environmental issue or more than one safety issue; d)
The proposed amendment does involve a single safety issue, namely, the lengthening of the time requirement for attaining a 4 percent oxygen concentration in the drywell following entry into the RUN mode.
e)
The proposed change is therefore a Class III amendment.
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