ML20012A674

Application for Amends to Licenses NPF-68 & NPF-81,revising Section 6.7.4.a by Removing Boron Recycle from Description Sys Included in Program to Reduce Leakage from Sys That Could Contain Highly Radioactive Fluids Following Accident

ML20012A674
Person / Time
Site:	Vogtle
Issue date:	03/01/1990
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20012A675	List: ML20012A674 ML20012A680
References
NUDOCS 9003120401
Download: ML20012A674 (6)

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[, ~ (Geotg.a Power Company. ,

333 P*edmont Amnue-

. Atlantit Georg:a 30308 '.

1 , Telephone 404 !s3195 Maihnh /ddress 40 ineness Cenior Parkway 1

, hnt Ottco Box 1295 '

D renitraham Arahama 35201 -

~ Telephone 205 BGB 5501 :

March 1, 1990 emean ec sem 4L: W. G. Holtston, all 4 Son.or Vice h00&nt Nuclear Opmeont ELV-01370 0259-Docket Nos~. 50-424 50-425--

• Nuclear Regulatory Commission U 'S, 4 ATTN:' Document Control Desk Washington, D. C. 20555.

Gentlemen: ,

V0GTLE ELECTRIC GENERATING PLANT REVISION TO TECHNICAL SPECIFICATION 6.7.4.a

.In accordance with the provisions of 10 CFR 50.90 and 10 CFR 50.59 Georgia Power Company (GPC) hereby. proposes to amend the~ Vogtle Electric Generating Plant-(VEGP) Units 1 and.2 Technical Specifications, Appendix -A:to Operating License NPF-68 and NFF-81..

- The proposed amendment- to the Technical Specifications will revise administrative. Section 6.7.4.a by removing Boron Recycle' from the description of systems-included in-the program to' reduce leakage from systems that could

. potentially. contain- highly radioactive fluids following.an accident.

This revision.to the Technical Specifications is administrative.in nature and not required in: order:to-support continued operation, or compliance with the c requirements:of. Specification 6.7.4. Nevertheless,'GPC recognizes that-the

change is necessary in order to provide consistency between the Technical S)ecifications and the-leakage reduction program as described in Supplement 3 of tle VEGP. Safety Evaluation Report.

Enclosure.1 provides a description of the proposed change and the basis for the change request."

. Enclosure 2 provides the basis for a determination that the proposed change does not. involve significant hazards considerations.

Enclosure.3 provides instructions for incorporating the proposed change .into the

Technical Specifications. The proposed revised page is provided in enclosure 3.

Pursuant to the requirements of 10 CFR 50.91 the designated state official will

'be-sent a copy of this lotter -and all applicable enclosures.

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1 GeorgiaPower A ,

U. S. Nuclear Regulatory Commission ELV-01370 Pace Two Mr. W. G. Hairston, III states that he is a Senior 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 and enclosures are true. ,

GEORGIA POWER COMPANY By: l<] b IIW W. G. Hairston, III-Sworn to and subscribed before me this /* day of ThcI , 1990.

11A i n b u h lotary Obblic

. gy cogmssionumESDtc.15,172 WGH,III/HWM/gm.

Enclosures:

1. Basis for Proposed Change

2. 10 CFR 50.92 Evaluation

3. Instructions for Incorporation c(w): Georaia Power Company Mr. C. K. McCoy Mr. G. Bockhold, Jr.

Mr. R. M. Odom Mr. P. D. Rushton NORMS U. S. Nuclear Reaulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. D. B. Matthews, Director, Project Directorate 11-3 Mr. R. F. Aiello, Senior Resident Inspector, Vogtle State of Georaia Mr. J. L. Ledbetter, Commissioner, Department of Natural Resources

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ENCLOSURE 1 V0GTLE ELECTRIC GENERATING PLANT REVISION TO TECHNICAL SPECIFICATION 6.7.4.a BASIS FOR PROPOSED CHANGE .[

Pronosed Chanoe Technical Specification 6.7.4 identifies programs that are required to be established, implemented and maintained for the Vogtle Electric Generating Plant .;

(VEGP).- Section S.7.4.a describes a program of inspection and testing to reduce ; -;

leakage in systems that could contain highly radioactive fluids during a serious transient or accident. The description includes a list of systems included in the program, one of these systems is the Chemical and Volume Control System (CVCS). Other systems associated with the CVCS are listed in parenthesis with. -

the CVCS system. One of these other systems is the Boron Recycle System. The proposed change to the Technical Specifications will delete the Boron Recycle System from the systems listed in parenthesis with the CVCS.

Basis In accordance with the TMI-2 Action Plan Requirements, Georgia Power Company described a program to reduce leakage of systems outside containment that might

'contain highly radioactive fluids. During the course of the NRC's review of. i this program it was.noted that the Boron Recycle System is not used during an-accident and is isolated by check valves and normally closed valves. Therefore, the NRC specifically noted in Supplement 3 of the:VEGP' Safety Evaluation Report that this system could be excluded from the program. When preparing the Technical Specification description of the leakage reduction program, the Boron Recycle System was identified with the CVCS ~ system which is included in the program. This change to the Technical Specifications will remove the reference

• to the Boron Recycle System resulting in consistency between the Technical Specifications and the NRC's Safety Evaluation Report. This will reduce the potential for misunderstanding the requirements for the leakage reduction -

program described in Technical Specification 6.7.4.a.

ENCLOSURE 2' V0GTLE ELECTRIC GENERATING PLANT REVISION TO TECHNICAL SPECIFICATION 6.7.4.a 10 CFR 50.92 EVALUATION Pursuant to 10 CFR 50.92 Georgia Power Company (GPC) has evaluated the attached proposed amendment to the VEGP Units 1 and 2 Technical Specifications and has determined that operation of the facility in accordance with the proposed-amendment would not involve significant hazards considerations.

Backaround This change to the Technical S)ecifications deletes the Boron Recycle System from the systec; listed with tie Chemical and Volume Control System in the description of the program to reduce leakage in systems that might contain highly radioactive material following a severe accident or transient. This has previously been reviewed and accepted by the NRC staff in Supplement 3 to the VEGP SafCtY Evaluation Report. Therefore, it is considered to be an 1

administrative change to the Technical Specifications that does not affect the leakage reduction program that is required by Specification 6.7.4.a.

Analysis This change to the description of the leakage reduction program will not affect the program to reduce leakage of systems containing highly radioactive material following an accident or transient because the Boron Recycle System will not contain such material. The change to the Technical Specifications is administrative in nature and does not indicate a change in the leakage reduction progra n that is currently in effect in accordance with Specification 6.7.4.a.

Results Based on the information presented above, the effects of the proposed change to the Technical. Specifications have been established using the criteria of 10 CFR 50.92 and the results are listed below:

1. The proposed change to this Technical Specification will not result in a significant increase in the probability of an accident previously evaluated because the relationship of the Boron Recycle System to the leakage reduction program has no effect on the probability or causes of accidents and transients. In addition, the purpose of this Technical Specification is not related to reducing the probability of accidents or transients. The consequences of an accident previously evaluated will not be affected by whether or not the Boron Recycle System is in the leakage reduction program because the Boron Recycle System is isolated from sources of highly radioactive material and would not contribute to any doses as a result of such transients or accidents.

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,c ENCLOSURE 2 (CONT'D)

REVISION TO TECHNICAL SPECIFICATION 6.7.4.a 30 CFR 50.92 EVALUATION

2. This change to the Technical Specifications is administrative in nature and does not represent' any physical change to the plant, the plant procedures or plant operating requirements. Therefore, it will not introduce the possibility of a new or different kind of accident.

3. The removal of the Boron Recycle System from the description of the leakage reduction program will not reduce the margin of safety contained in any safety analysis because leakage from the Baron Recycle System is not a factor in the safety _ analyses and the. system is isolated from systems that may potentially contain highly contaminated fluids.

Conclusion Based on the results of the preceding analyses GPC has determined that' this Technical Specification change does not involve a significant increase in the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any previously evaluated or involve a significant reduction in a margin of safety. Therefore, GPC concludes that the proposed change meets the requirements of 10 CFR 50.92(c) and does not involve a significant hazards considerations.

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i ENCLOSURE 3 V0GTLE ELECTRIC GENERATING PLANT REVISION TO TECHNICAL SPECIFICATION 6.7.4.a.

INSTRUCTIONS FOR INCORPORATION The proposed amendment to Section 6.7.4.a of the Vogtle Electric Generating Plant Technical Specifications would be incorporated as follows:  !

e Remove Paae Insert Paae 6-15 and 6-16* 6-15 and 6-16*

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• Overleaf page containing no change.

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