ML20211H127

Responds to Transmitting SER of Topical Rept WCAP-10858, ATWS Mitigating Sys Actuation Circuitry Generic Design Package. Implementation Schedule for Addressing plant-specific Design Features Encl

ML20211H127
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	10/29/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Chan T Office of Nuclear Reactor Regulation
References
TAC-59152, NUDOCS 8611040471
Download: ML20211H127 (3)

Text

.

k um,

~

W M M COuiptsif Bmt D Wmers Vce Presdort October 29, 1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. Terence L. Chan, Project Manager Project Directorate No. 3 Division of PWR Licensing-A U.S. Nuclear Regulatory Commission Washington DC 20555

Reference:

PGE (B. D. Withers) to Director, NRR Dated March 17, 1986, Revised Response to 10 CFR 50.62(d)

Response to NRC Safety Evaluation on AMSAC Generic Design Package This letter is in response to your letter of September 23, 1986, which transmitted a Safety Evaluation Report (SER) of Topical Report WCAP-10858, "AMSAC Generic Design Package". Your letter requested our schedules for addressing the plant-specific design features discussed in the SER, in Appendix A of the SER, and for implementation following NRC approval of our plant-specific design. Our schedules for each of these items are discussed below.

l The SER states that the NRC will review the implementation of plant-specific designs to evaluate compliance with ATWS rule requirements. The SER indi-

l. cates that a plant-specific submittal will be required which addresses i 14 key design areas (SER Pages 13 to 17) in addition to provision of specific information on AMSAC isolation devices (Appendix A).

I In the above reference, PGE proposed to implement AMSAC by the end of the l 1988 refueling outage or within 24 months after issuance of the SER, l whichever was later. However, this schedule did not envision NRC review and approval of plant-specific designs prior to implementation, which is now required per the SER. Obtaining NRC approval of our conceptual design

[ will delay the overall process because we will not proceed with material procurement until the design is approved. Assuming a minimum review and I

00 l 8611040471 861029 PDR ADOCK 05000344 ILht P PDR io m. xn m xeet Fbuxi Ow]cn 97204

W M M COsigJtz1f Mr. Terence L. Chan October 29, 1986 Page 2 approval time by the NRC, 6 months, plus the 24 months previously justi-fled, would place final implementation in early 1989, except for Plant operating considerations. Consequently, PCE provides the attached revised schedule and the following discussions in response to your request:

1. The plant-specific design features delineated in the'SER will be addressed in a plant-specific submittal by October 31, 1987. Part of this submittal will consist of schedules to supply additional informa-tion once the specific design is chosen and a vendor selected. Vendor selection is not expected until early or mid-1988.

2. Final implementation of AMSAC will be completed by the end of the 1989 refueling outage (approximately July _1989).

It is our understanding, based upon contacts with the Westinghouse Owners Group, that the NRC will allow operating plants to delay AMSAC installation

-beyond the third refueling outage after July 26, 1984 with adequate justi-fication. The schedule and justifications provided above are consistent with this goal.

Sincerely,

. -1 Bart D. Withers Vice President Nuclear c: Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission s

K TROJAN NUCLEAR PLANT-AMSAC IMPLEMENTATION SCHEDULE EF#

. 2?&

aRE 11/86 11/87 11/88 3/89 11/89 u te E?$

Preliminary Engineering 10 months l l

((

NRC Approval of Plant-Specific Features l 6 months l g Detailed Engineering

• l 17 months' l 5 Issue Specification l3 months l-M2terial Procurement l 12 months l Construction l5 months l l

? NSk

%g2*

- gi#

O (D N

- E.eR.

O a

4