ML20207J981

Environmental Assessment & Finding of No Significant Impact Re NRC Consideration of Exemption from Requirements of 10CFR50.48(c) & 10CFR50,App R

ML20207J981
Person / Time
Site:	Hatch
Issue date:	11/28/1986
From:	Rivenbark G Office of Nuclear Reactor Regulation
To:	City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp
Shared Package
ML20207J969	List: ML20207J965 ML20207J981
References
TAC 61626, TAC 61627 NUDOCS 8701090082
Download: ML20207J981 (5)

Text

.. _ -..

?

7590-01 UNITED STATES NUCLEAR REGULATORY CO M ISSION ENVIRONMENTAL ASSESSNENT AND FINDING DF NO SIGNIFICANT IMPACT GEORGIA POWER COMPANY t

i OGLETHORPE POWER CORPORATION l

MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA I

DOCKET NOS. 50-321 and 50-366 4

The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an exemption from the requirements of 10 CFR 50.48(c) and i

i Appendix R to 10 CFR 50 to the Georgia Power Company, Oglethorpe Power j

Corporation, Municipal Electric Authority of Georgia, and the City of Dalton, Georgia (the licensees), for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 located in Appling County, Georgia.

1 4

ENVIRONMENTAL ASSESSMENT Identification of the Proposed Action: The licensee would be exempted from the requirements of Section III.G.I. Appendix R to 10 CFR 50 to th' e ' extent that repairs would be permitted to maintain hot shutdown for a fire in the Unit i

I and Unit 2 control room area.

The licensee would be exempted from the requirements,of Section III.G.2.

nii l

of Appendix R to 10 CFR 50 as follows:

1) to the extent that certain components within the suppression system / water curtain boundary within the following areas would not be required to be wrapped Unit 1 Reactor Building North of Column Line R7 Unit 1 Reactor Buildin,' South of Column Line R7 Unit 2 Reactor Building North of Column Line R19 Unit 2 Reactor Building South of Column Line R19 0701090082 870102 PDR ADOCK 05000321 e p.

PDR e

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

7590-01

. 2) to the extent that barriers would not be required between redundant pathways in the followina areas so that a fire in these areas will not lead to loss of control of the high pressure coolant injection (HPCII system:

l Unit 1 Reactor Building North of Column Line R7 i

Unit 2 Reactor Ruilding South of Column Line P19

?) to the extent that a 20-foot separation distance would not be required i

between redundant cables in the Intake Structure, outside of the automatic suppression areas.

The licensee would be exempted from the requirements of Section III.J. of l

Appendix R to 10 CFR 50 to the extent that 8-hour battery powered emergency lighting would not be required in the control room and in the yard.

i The licensee would be exempted from the schedular requirements of 10 CFP 50.48 and Appendix R to 10 CFR 50 to the extent that installation of new circuit breakers and fuses identified as necessary to ensure electrically l

coordinated circuits would not be required to be completed in Units 1 and 2 prior to the licensee's current implementation schedule November 30, 1986 but instead would be required to be completed by the end of the next scheduled i

refueling outage for each of these Units commencing after November 30, 1986.

As an interim compensatory measure, until these circuit breakers and fuses are installed, the licensee is required to provide procedures that direct the operator to reestablish power to the Appendix R components that are tripped as a result of the fire.

The exemption is responsive to the licensees application for exemption dated May 16,19f;6 as supplemented by letters dated July 22. September 23, October 31, November 14 and November 21, 1986, 4

I

s 3

7590-01 3

The Need for the Proposed Action: The exemption to Section III.G.I. to allow repai'rt to be made in order to maintain hot shutdown of the reactor is needed to allow greater flexibility _ and ensure reliable, long-term maintainability of hot shutdown conditions.

The exemption to Section III.G.2. to allow certain components within suppression system / water curtain boundary to not be wrapped is necessary because enclosure of these components would jeopardize their operability and would therefore be detrimental to overall plant safety.

Since the existing separation distances and barriers provides adequate protection to assure that the complete pathway is available to secure the HPCI system, the exemption to Section III.G.2. to eliminate the requirement that barriers be provided between redundant pathways to prevent loss of control of the HPCI system in the event of a fire in specified areas is needed to avoid unnecessary modifications and their associated costs.

The Commission issued an exemption to the requirements of 10 CFR 50.48 dated May 14, 1985 extending the deadline for completion of fire protection modifications requiring plant shutdown until November 30, 1986 for both Hatch q.

Units. The licensee has been unable to procure a few of the~ components required to complete these modifications by November 30, 1986, specifically the new circuit breakers and fuses identified as necessary to ensure required olectrically coordinated circuits.

In order to avoid shutting down the two Units until the parts are available or shutting down the two Units specifically for the purpose of installing these breakers and fuses the licensee needs an exemption to allow it to extend the installation completion schedule for these specific components until the end of the next scheduled.

refueling outage commencing after November 30, 1986 for each Unit.

l

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

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

(.

2 7590-01

-4 Environmental Impact of the Proposed Action:- The proposed action with respect to the exemptions from Sections III.G. and III.J. would not impact the ability 5

to effect safe shutdown of the plant in the event of a fire and would provide an acceptable level of safety, equivalent to that attained by compliance with these Sections of Appendix R to 10 CFR 50.

By using reasonable interim compensatory measures, the proposed exemption to the schedular requirements of 10 CFR 50.48 will provide a degree of fire protection such that there is no significant increase in the risk of fire.at this facility.

The probability of fires has not been increased and the post-fire radiological releases will not be greater than previously deteraired nor does the proposed exemption otherwise affect radiological plant effluents,.

Therefore, the Commission concludes that there are no significant radiological environmental impacts associated with this proposed exemption.

With regard to potential nonradiological impacts, the proposed exemption involves features located entirely within the restricted area as defined in 10 CFR 20.

It does not affect nonradiological plant effluents and has not other environmental impact. Therefore, the Commission concludes that there are no significant nonradiological environmental impacts associated with the proposed exemption.

Alternative Use of Resources: This action does not involve the use of i

resources not considered previously in connection with the Final Environmental Statements (FES) relating to this facility, FES for Hatch Units 1 and 2, USAEC 4

(October 1972) and FES for Hatch Unit 2, NUREG-0417 (March 1978).

Agencies and Persons Consulted: The Commission's staff reviewed the licensees' request and did not consult other agencies or persons.

i

2 7590-01

• FINDING OF NO SIGNIFICANT IMPACT

~

The Commission has determined not to prepare an environmental impact statement for the proposes exemption.

Based upon the foregoing environmental assessment, the Comission concludes that the proposed action will not have a significant effect on the quality of the human environment.

For further details with respect to this action, see the application for sxemption dated May 16, 1986 as supplemented by letters dated September 23, October 31 November 14, and November 21, 1986, which is available for public inspection at the Comission's Public Document Room,1717 H Street, N.W.,

Washington, D.C., and at the Appling County Public Library, 301 City Hall Drive, Baxley, Georgia.

Dated at Bethesda, Maryland, this 28th day of November, 1986.,

FOR THE NUCLEAR REGULATORY COMMISSION Wis-u eorge. Rivenbark, Acting Director Project Directorate #2 Division of BWR Licensing 6

5 w

--