ML20091Q478
| ML20091Q478 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/23/1992 |
| From: | Mccoy C GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20091Q481 | List: |
| References | |
| ELV-03308, ELV-3308, TAC-M82133, TAC-M82134, NUDOCS 9202040442 | |
| Download: ML20091Q478 (3) | |
Text
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. Goorgs Power Company
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- 40 loverness Center Pahay.
Post Oke Bus IND -
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c,n.uccov Georgia Power L
Vce Pfex1ent NMem Vr>gue Protect the so#en ek!rc system January 23, 1992 ELV-03308 1257 Docket Nos. 50-424 50-425 TAC-M82133 M82134 U. S. Nuclear Regulatory Commission
-ATTN: Document Control Desk Washington, D. C.
20555
- Gentlemen:
V0GTLE ELECTRIC GENERATING PLANT ADDITIONAL INFORMATION-AND AMENDED IECHNICAL SPECIFICATIONS-FOR FILTER HEATERS Georgia' Power Company-(APC) letter ELV-03182 dated _ November 11, 1991,-
transmitted a-request for Technical Specification changes relative to the testing requirements.for charcoal filters. At the request of the NRC, we are a mending the request by providing additional informati_on in this letter and in the-attachments to~this letter. of letter ELV_-03182 included the results of dose analyses which a
formed the bases-for the proposed revisions to the Technical Specifications.
These _ changes-reflect the revised assumptions concerning leakage and filter
- efficiencies.- The; details of-the effects of ther chunges on the original dose analyses are contained in proposed-revisions to ute description of the dose analyses in the FSARLThe proposed FSAR changes are included as-attachment I to this letter. These are provided for information.only and will be included in -
the annual FSAR update. These;pages describe-the dose analyses and the-assumptions and' results of the analyses. of. letter ELV-03182 referred to the fuel handling building post accidentifilter system..In the_ Technical Specifications, this system is-identifed as.the fuel handling building post accident ventilation-system.
_ The revised dose analyses used to support the proposed changes included a revised emergency core cooling system (ECCS) leakage rate,of 2 gpm for the duration of the accident.- Thistis a reduction in the amount of leakage-
-previously used in the-analyses, but remains within the guidelines of Standard Review Plan-15.6.5.1 for plants with ESF filter systems. The previously assumed value _of 50-gpm for the duration of the accident was-larger than necessary. The NRC, staff noted in the Safety Evaluation (NUREG-1137 dated June 1985) that the
. value could be_ substantially reduced. The new value of 2 gpm is well above the expected. leakage and is consistent with the value accepted by the NRC for use in p) 9202040442 920123 PDR-ADOCK-05000424 P
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1 Georgia Powerb U. -S. Nuclear Regulatory Commission
-ELV-03308
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Page 2
. similar calculations for other plants.
Technical Specification 6.7.4.a-requires that this leakage be maintained "as low as practicable."
-The control room emergency. filtration system (CREFS) was originally sized to handle a flow of 25,000 cubic feet per minute (CFM). The flow allowed by the Technical Specification is 19,000 cfm with a 10 percent tolerance. -Under these conditions the originally supplied heater has excess capacity. Analyses were performed to determine the required heater capacity at 19,000 i 10 percent cfm.
These analyses assumed maximum design temperature and 100 percent relative humidity for the inlet air, it was determined that only 74 kw of heater capacity is required to reduce the relative humidity to 70 percent.
The heater capacity proposed for the Technical Specification is 95 kw at 460 volts, which assures that the.necessary-heater capacity will be available for the CREFS even
-during minimum-voltage conditions, j
The changes requested in letter ELV-03182 do not involve any modifications to the: filter systems.
Except for the CREFS, revised analyses have been performed to demonstrate that the filters will perform their safety function without the heaters; therefore,_any contributions that the heaters make to-the filters' efficiency will result in additional conservatism.
Since the revised' dose analyses did-not take credit for the heaters, the required heater capacities in-the Technical. Specifications were revised. The revision included the replacement of the heater requirements range with a minimum heater requirement. The heater capacity upper limit is not required to
' limit excessive heat dissipation by the heaters. The thermal overload trips that are an existing part of_the system are unaffected by this proposed change. There are no changes to the heaters, the heater controls,- power supplies, or the provisions-that protect the charcoal from ignition. -Therefore, the proposed
' change will-not affect the level of fire protection provided for the charcoal filters.
-The proposed. Technical-Specifications-retained the-requirement to perform laboratory testing of the charcoal filters in accordance-with ANSI N510-1980.
It is understood that ANSI N510 requires that such testing be done according to ASTM D3803.
The NRC has suggested that the Technical Specifications would be
-improved-by referring directly.to_ ASTM D3803-89. This does-not change the requirements of the Technical: Specifications or the conclusions of the evaluation of significant-hazards that was included with letter ELV-03182.
Therefore GPC is amending the requested Technical Specification changes to include references to ASTM D3803-89 for laboratory testing of charcoal. The.
l revised pages are included as attachment 2 to this letter. The reference to
. ASTM D3803-89 is also' applicable to the surveillance requirements for the-control room filters on page 3/4-7-15 which was not affected by the initial
- request in letter ELV-03182. This page is also included in attachment 2, along with. revised instructions for incorporating the changes into the Technical Specifications. The pages in attachment 2 should replace the pages in enclosure 3 of ELV-03182 on a one for one basis.
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.T GeorgiaPower A U. S.- Nuclear Regulatory Commission ELV-03308 Page 3 Surveillance requirement 4.9.12.f. is not affected by the proposed changes-to the technical-specifications. During:the review of this page the NRC
.noted that this surveillance requirement differed from similar requirements for other systems in that it required removal of 99 percent instead of 99.95 percent of the test gas. The reason for this difference is that no credit is taken for the fuel handling building post accident ventilation system in the
-safety analyses. Rather than remove the system from the initial issue of the
- Technical Specifications, GPC requested,- and was-granted, slightly less.
stringent testing requirements for this system.
Mr. C. K. McCoy states that he is a 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 q
true.
GEORGIA POWER COMPANY By:
/
C. K. McCoy Sworn to and subscribed before me this Y day of LW.
, 1992.
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Notary 1 m w.wwumhhtsm 6.lfbb '
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=xc:- Geon '
Power Company Mr. W._B. Shipman Mr. M. Shelbani e
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NORMS t
-U. S. Nuclear Reculatory Commission Mr. -S. D. Ebneter, Regional-Administrator Mr. D. S. Hood,-Licensing Project Manager, NRR L
Mr. B. R. _ Bonser, _ Senior Resident Inspector, Vogtle
. State of Georaia Mr. J.-D. Tanner, Commissioner, Department of Natural Resources L
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