ML19343C566
| ML19343C566 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 03/19/1981 |
| From: | Broehl D PORTLAND GENERAL ELECTRIC CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| TAC-46735, NUDOCS 8103240514 | |
| Download: ML19343C566 (3) | |
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March 19, 19 Q
nG Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:
Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
The recently enacted Appendix R to 10 CFR 50 contains fire protection requirements for nuclear power plants. Additional guidance is con-tained in the NRC letter dated February 20, 1981.
In accordance with 10 CFR 50.48(b), only Appendix R Sections III.G, Ill.J, and III.O apply to the Trojan Nuclear Plant. Additionally, fire protection provisions for Trojan have already been approved by the NRC in a Safety Evaluation Report (SER) dated March 9, 1978 and amended on March 25, 1980 and October 6,1980.
i The fire protection design at Trojan has been reviewed against the applicable sections of 10 CFR 50 Appendix R.
10 CFR 50.48(c)(5) requests the submission of design information on modifications required to satisfy Appendix R Section 7.II.G.3.
This information has already been submitted
-as part of Topical teport PGE-1012, " Trojan Nuclear Plant Fire-Protection l
Review", and can be found in our response to staf f position P.F.4 on l
Pages C-16 through C-26.
Additional details on safe shutdown capabili-ties can be found in Appendices C and G of PGE-1012. Please note, however, that only Train B decouple switches have been installed since safe shut.down capability for only one train of components is necessary.
l This is milowable per Appendix R Section III.G.I.a.
As discussed in PGE-1012, no credit was taken for fire-retardant coatings in the cable spreading room since safe shutdown can be achieved indepen-dent of the cable spreading room (CSR). For areas outside of the CSR, the criteria given in Appendix R Section III.G.2 are not met for all cases. The fire protection criteria used at Trojan is described in Appendix A and on Pages C-31 through C-32b of PGE-1012. Specific areas in which Appendix R Section III.G.2 criteria are not met are the intake structure (23-ft level), Fuel Building (45-ft level), Auxiliary Building
-(45-ft level), Turbine Building (45-ft level), and the cable penetration area outside of Containment. The fire protection design for these areas was discussed in the response to staf f position P.F.8 in Sections C and G of PGE-1012.
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Mr. Robert A. Clark March 19, 1981 Page two Fire protection Zar these areas was reviewed and approved by the NRC in the previously referenced Safety Evaluation Report. The cable fire protection in these areas affords an equivalent degree of protection as the methods required by Appendix R.
Associated circuits were discussed in the response to NRC Question No. 6 on Pages C-6 and C-7 of PGE-1012. A re-review was conducted to ensure that the response is valid for low-voltage circuits and instrument loops.
No cases were found where normal circuits associated with safe shutdown IE circuits were treated differently from lE circuits with respect to the fire protection review. Therefore, no changes due to associated circuits are necessary.
The emergency lighting system design was reviewed with respect to the requirements found in Appendix R Section III.J.
This review included lighting in the areas containing decouple switches and areas requiring manual operations. Most of the equipment that must be oper.ted to achieve hot shutdown is illuminated by both lights powered from the station batteries and lights powered from lE AC buses. However, four locations where hot shutdown actions must be taken have only lights powered from the 1E AC buses. Although this does not meet the Appendix R Section III.J requirement to have a battery powered emergency lighting i
source, the lighting is considered as reliable as the lighting from station batteries. Furthermore, power will be available for a signifi-cantly longer amount of time than the eight-hour requirement given in Appendix R Section III.J.
Therefore, no design changes are necessary in this area.
With regard to Appendix R Section III.0, a reactor coolant pump oil collection system will be provided as described in the response to Item 3.2.6 on Pages G-19 and G-20 of PGE-1012 and in the PGE to NRC letter
. dated May 14, 1980.
Installation of this system will be in conformance with the schedule given in 10 CFR 50.48(d). However, Westinghouse has recently identified a potential leakage site through the Resistance Temperature Detector conduit penetration in the reactor coolant pump motor. A design modification is being evaluated to include this poten-tial leakage source, and.you will be notified if' installation cannot be completed within the schedule guidelines of 10 CFR 50.48(d).
Fire protection rechnical Specification changes have been approved by the NRC and are in effect at Trojan. The only SER item not installed.
at this time (in addition to the oil collection system mentioned above)
'is the fire barrier in'the switchgear room (SER Item 3.16).
Installa-tion of this barrier.is scheduled to be completed prior to the startup of Cycle 4, which is well'within the. schedule limitations given in Paragraph 10 CFR 50.48(d).
Based on the above,. and on conversations with NRC reviewers,'we believe that the fire protection review for Trojan is complete 2nd that additional modifications will not significantly
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Mr. Robert A. Clark March 19, 1981.
Page three enhance fire prottetion safety at Trojan. The submission of additional fire protection information is not planned at the present time.
Sincerely,
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Mr. Lynn Frank, Director
' State of-Oregon Department of Energy i
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