ML20210U167

Discusses ATWS Mitigating Scram Actuation Circuitry Rule Implementation Schedule.Sufficient Info to Develop Submittal Available in Fourth Quarter 1987.Response to App a Scheduled for Submittal by 870227

ML20210U167
Person / Time
Site:	Farley
Issue date:	10/03/1986
From:	Mcdonald R ALABAMA POWER CO.
To:	Rubenstein L Office of Nuclear Reactor Regulation
References
NUDOCS 8610090437
Download: ML20210U167 (3)

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• Mamng Address Alibim2 Power Company 600 North 18th StrMt Post Office Box 2641 Birmingham. Alabama 35291 Te ephone 205 78340%

R. P. Mcdonald .

Senior Vice President Flintridge Building /\labama Power emrym ew v c s re October 3, 1986 Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. L. S. Rubenstein Gentlemen:

Joseph M. Farley Nuclear Plant - Units 1 and 2 Anticipated Transient Without Scram (ATWS) Rule Implementation Schedule On June 1,1984, the NRC approved publication of a final ATWS rule, 10CFR50.62 regarding the reduction of risk from ATWS events for light-water cooled nuclear power plants. Section 50.62(d) of the rule required.that each licensee develop and submit a proposed schedule for meeting the requirements of the rule.

By letter dated October 4,1985, Alabama Power Company ( APCo) submitted its response to the schedule submittal provision identified in Section 50.62(d). This response identified APCo's participation in tne L Westinghouse Owners Group (WOG) generic design program for ATWS Mitigating Scram Actuation Circuitry ( AMSAC). This letter also identified an intent to utilize an AMSAC based on the WOG generic design to meet the requi rements of the ATWS rule. The WOG AMSAC generic design, WCAP-10858, was submitted for NRC review and approval by letter dated July 25, 1985. Additionally, APCo's October 4,1985 letter stated that APCo would submit a schedule for meeting the requirements of the ATWS within 90 days of the issuance of the Safety Evaluation Report (SER) for the WOG AMSAC generic design. The SER was issued on July 7, 1986. Additionally, the NRC requested a schedule for responding to Appendix A of the SER by letter dated September 23, 1986.

APCo utilized the period prior to SER issuance to take actions that would allow for AMSAC implementation in a timely but controlled manner.

4 These steps included an engineering evaluation of proposed AMSAC systems, development of a detailed conceptual design for AMSAC

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10 8610090437 861003 9 PDR ADOCK 05000348 P PDR l

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Mr. L. S. Rubenstein October 3, 1986 U. S. Nuclear Regulatory Commission Page 2 installation, and an engineering walkdown at Farley Nuclear Plant to determine the impact of AMSAC on existing plant equipment. After receipt and evaluation of the SER, APCo determined that a revision to the conceptual design would be required regarding the AMSAC power supply. This revision is currently being reviewed.

APCo is currently in the process of procuring an AMSAC that will implement stesm generator low-low water level system logic. The supplier has stated that twelve months are required after receipt of order to design, fabricate, test, and deliver AMSAC. Despite the fact that engineering walkdowns are complete and the system logic has been determined, significant improvement to the twelve month period is not anticipated. .

The third refueling outages after July 26, 1984 for Farley Nuclear Plant are the Unit 1 eighth and Unit 2 fifth refueling outages. These outages are tentatively scheduled for March 1988 and September 1987, respectively.

After evaluating the implementation activities for AMSAC with respect to the tentative outage schedules above, APCo commits to implement AMSAC for Unit 1 during the eighth ref ueling outage. The scheduling constraints for Unit 2 are such that implementation during the fifth refueling outage may not be achievable. To implement AMSAC during the Unit 2 fifth refueling outage, the AMSAC supplier, APCo's design organizations, and APCo must expedite all design, fabrication, and testing without contingencies. It is APCo's goal to implement AMSAC for Unit 2 during the fifth refueling outage and every effort will be made to meet this goal. However, APCo commits to implementation of AMSAC for Unit 2 during the sixth refueling outage which is tentatively scheduled for March 1989.

In the SER, the NRC identified 14 items which should be addressed in plant specific submittals. These items (e.g., diversity, logic power supplies) and a response to Appendix A of the SER, which requests additional information on AMSAC isolation devices, will be addressed by APCo subsequent to the completion of all detailed AMSAC design activities. At present, the date for providing the requested information is not known. It is expected, however, that sufficient information to develop a submittal will be available in the fourth quarter of 1987 for all items except Appendix A. A response to Appendix A is scheduled to be submitted by February 27, 1987.

If there are any questions, please advise.

Respectfully submitted, ALABAMA POWER C Y T

( ', _ N R. P. Mcdonald RPM /JLO: dst-D-T.S.7 cc: See next page

l Mr. L. S. Rubenstein October 3,1986 U. S. Nuclear Regulatory Commission Page 3 cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford l

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