ML20045G302

Application for Amends to Licenses NPF-68 & NPF-81,revising TS 3.11.1.4,liquid Holdup Tanks,Incorporating Requirements for Annual Radioactive Effluent Release Rept

ML20045G302
Person / Time
Site:	Vogtle
Issue date:	07/02/1993
From:	Mccoy C GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20045G303	List: ML20045G302 ML20045G304
References
LCV-0002, LCV-2, NUDOCS 9307130157
Download: ML20045G302 (7)

Text

"

Georg a Power ComNny 40 Imerre; Center Parhuy Post oe.ce Box 1295 Dorungnxn. Aun una E201 l'oierhorm 20G 877 71?2 m

C. K. McCoy Georgia Power V,w PreN Nude yoque nopa the southvin t>l%lnc W5 fem July 2, 1993 Docket Nos. 50-424 LCV-0002 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Vogtle Electric Generating Plant Request to Revise Technical Specifications Semiannual Radioactive Fmuent Release Repg l

By letter dated December 7,1992, Georgia Power Company submitted proposed changes j to the Vogtle Electric Generating Plant (VEGP) Unit I and Unit 2 Technical l Specifications associated with the Semiannual Radioactive Effluent Release Report. The l frequency of submittal of the report was proposed to be changed to an annual basis m i accordance with a recent revision to 10 CFR 50.36a (57 FR 39353 dated  ;

August 31,1992). On March 31,1993, the Nuclear Regulatory Commission (NRC) l issued Unit I license Amendment No. 61 and Unit 2 license Amendment No. 40 which approved the proposed changes. Subsequent to issuance of the license amendments, Georgia Power Company discovered that an additional change to the Technical Specifications should have been included in the license amendment request. Specifically, Specification 3.11.1.4, Liquid Holdup Tanks, contained a reference to the Semiannual Radioactive Emuent Release Report which was inadvertently omitted during the  ;

preparation of the request. l In accordance with the new 10 CFR 50.36a, Georgia Power Company has prepared proposed changes to the VEGP Unit 1 and Unit 2 Technical Specifications to incorporate the requirements for an Annual Radioactive Emuent Release Repon relative to Specification 3.11.1.4. The proposed changes are consistent with those previously approved by the NRC. The proposed changes and bases for the changes are described in Enclosure 1 to this letter. Enclosure 2 provides an evaluation pursuant to 10 CFR 50.92 showing that the proposed changes do not involve significant hazards considerations. A copy of the proposed changes is provided in Enclosure 3.

In accordance with 10 CFR 50.91, the designated state omcial will be sent a copy of this letter and all enclosures.

7130157 93070g F 3 p ADOCK 03000424 t PDR l '.1' ta

U. S. Nuclear Regulatory Commission Page 2 Mr. C. K. McCoy states that he is a vice president of Georgia Power Company and is i 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: //

C. K.'McC Sworn to and subscribed before me this 2 day of ML, ,1993 J '

d.AA4 . k Nota'ry Public w top.(ssaD321,3UMti1M ,

CKM/TMM

Enclosures:

4

1. Basis for Proposed Change

2. 10 CFR 50.92 Evaluation

3. Proposed Technical Specification Changes c(w): Otofgia Power Company n Mr. J. B. Beasley Mr. M. Sheibani NORMS U. S. Nulkar Regulatory Commission Mr. S. D. Ebneter, Regional Administrator Mr. D. S. Hood, Licensing Project Manager, NRR Mr. B. R. Bonser, Senior Resident Inspector, Vogtle S_ tate of Ocorgia Mr. J. D. Tanner, Commissioner, Department of Natural Resources LCV-0002 r

l

. . .- - . . . . . .. . -.. ~ _ - .

l 1

l 1

1 I

Enclosure 1 Vogtle Electric Generating Plant Request to Revise Technical Specifications -1 Semiannual Radioactive EfTluent Release Report Basis for Change Requnt i 1

l l

~.

l I

e

,wy9 .rv - , -=w vm- - - -ye-- y- -wm-yr-s --

Enclosure !

Vogtle Electric Generating Plant Request to Revise Technical Specifications Semiannual Radioactive Efiluent Release Report Ilnis for Change Rc_ quest Panosed_ Change Revise Vogtle Electric Generating Plant (VEGP) Unit I and Unit 2 Technical Specification 3.11.1.4 in order to change the frequency of submittal of the Semiannual Radioactive Efiluent Release Report to an annual basis.

Basis for Proposed Change VEGP Unit I and Unit 2 Technical Specification 3.11.1.4, Action statement a., contains a reference to the Semiannual Radioactive Efiluent Release Report. It is proposed that this specification be revised to change the frequency of the report to an annual basis and rename it the Annual Radioactive Efiluent Release Report in order to implement the new 10 CFR 50.36a reporting requirements.

This proposed change is administrative in nature in order to reduce an unnecessary burden of governmental regulation. This change will in no way reduce the protection for the public health and safety. Also, this change is consistent with similar changes to the VEGP Technical Specifications which were approved by the Nuclear Regulatory Commission in Unit I license Amendment No. 61 and Unit 2 license Amendment No. 40, dated March 31,1993.

LCV-0002 El-1

.j Enclosure 2 Vogtle Electric Generating Plant Request to Revise Technical Specifications Semiannual Radioactive Efiluent Release Report 10 CFR 50.92 thpluation i

l l

i l

1

, - - -,,r, -. ., - ,. . - , - , - - - , , - - - - - - - ~ - - - . - - - - - - - , - - ,A-

. _ _ =-

Enclosure 2 Vogtle Electric Generating Plant i Request to Revise Technical Specifications Semiannual Radioactive EGuent Release Report

.LO_C.FR 50.92 Evaluatio.3 hopnsed Changes _

The proposed changes to the Vogtle Electric Generating Plant (VEGP) Unit I and Unit 2 Technical Specifications are required to implement the new 10 CFR 50.36a reporting requirement which allows the Semiannual Radioactive Emuent Release Report to be changed to an annual report..

Background

On August 31,1992, the Nuclear Regulatory Commission (NRC) placed a notice in the Federal Register (57 FR 39353) regarding several amendments to their regulations. One of the regulations revised was 10 CFR 50.36a, whereby the frequency of reporting the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous emuents was changed from semiannual to annual.. Such action was taken by the NRC in response to a Presidential memorandum requesting that selected Federal agencies review and modify regulations that would eliminate any unnecessary burden of governmental regulation and insure that the regulated community is not subject to duplicative or inconsistent regulation.

Accordingly, by letter dated December 7,1992, Georgia Power Company submitted proposed changes to the VEGP Unit I and Unit 2 Technical Specifications associated with the Semiannual Radioactive Emuent Release Report to change the frequency of submittal of the report to an annual basis. On March 31,1993, the NRC issued Unit I license Amendment No. 61 and Unit 2 license Amendment No. 40 which approved the proposed changes. Subsequent to issuance of the license amendments, an additional change to the Unit I and Unit 2 Technical Specifications was identified by Georgia Power Company which should have been included in the license amendment request. Specifically, Specification 3.11.1.4, Liquid Holdup Tanks, also includes a reference to the Semiannual Radioactive Emcent Release Report.

Therefore, in accordance with 57 FR 39353, Georgia Power Company proposes to satisfy the new 10 CFR 50.36a reporting requirement relative to Specification 3.11.1.4 in an Annual Radioactive Emuent Release Report which will replace the current semiannual report. This change is consistent with those proposed changes previously approved by I he NRC as referenced above.

LCV-0002 E2-1

l

- +. .

Enclosure 2 10 CFR 50.92 Evaluation Analysis The proposed changes to the technical specifications will allow for the implementation of the new 10 CFR 50.36a reporting requirement and fulfill the spirit of the Presidential memorandum. The proposed changes are administrative in nature and will not reduce the level of radiological control at VEGP. Compliance with applicable regulatory requirernents governing radioactive efliuents and radiological environmental monitoring, including 10 CFR 20 and Appendix 1 to 10 CFR 50, will continue to be maintained.

Georgia Power Company has reviewed the requirements of 10 CFR 50.92 as they relate to the proposed changes and has made the following determination:

1. The proposed changes do not involve a significant increase in the probability or coracquences of an accident previously evaluated. The proposed changes are administrat:ye in nature and do not involve any change to the configuration or method ofoperation of any plant equipment that is used to mitigate the consequences of an accic'ent. Also, the proposed changes do not alter the conditions or assumptions in any of the Final Safety Analysis Report (FSAR) accident analyses.

Since the FSAR accident analyses remain bounding, the radiological consequences previously evaluated are not adversely affected by the proposed changes. Therefore, it can be concluded that the proposed changes do not involve a significant increase in the probability or consequences'of an accident previously evaluated.

2. The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed changes are administrative in nature and do not involve any change to the configuration or method of operation of any plant equipment that is used to mitigate the consequences of an accident. Accordingly, no new failure modes have been defined for any plant system or component important to safety nor has any new limiting failure been identified as a result of the proposed changes. Also, there will be no change in the types or increase in the amount of efIluents released offsite. Therefore, it can be concluded that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. The proposed changes do not involve a significant reduction in a margin of safety.

The proposed changes are administrative in nature and do not adversely impact the plant's ability to meet applicable regulatory requirements related to radioactive efIluents and radiological environmental monitoring. The proposed changes would LCV-0002 E2-2

4.; -

Enclosure 2 10 CFR 50.92 Evaluation also eliminate an unnecessary burden of governmental regulation without reducing protection for public health and safety. Therefore, it can be concluded that the proposed changes do not involve a significant reduction in a margin of safety.

Conclusion Based on the preceding analysis, Georgia Power Company has determined the proposed changes to the technical specifications will not significantly increase the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety. Therefore, Georgia Power Company has determined the proposed changes meet the requirements of 10 CFR 50.92(c) and do not involve a significant hazards consideration.

l i

LCV-0002 E2-3

_ -.- _. .- - ~. _ _ -. ...