ML19309E076
| ML19309E076 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/14/1980 |
| From: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19309E077 | List: |
| References | |
| NUDOCS 8004180361 | |
| Download: ML19309E076 (4) | |
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.;n-April 14, 1980 Trojan Nuclear Plant Docket 50-344 License NPF-1 License Change Application 59 Director of Nuclear Reactor Regulation ATTN:
Mr. A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
In response to your letters of March 25 and March 18, 1980 concerning Trojan fire protection modifications, attached are three signed and 40 conformed copies of License Change Application 59 requesting amendment of Operating License NPF-1 and the below itemized responses to your Staff Positions. This License Change Application has been evaluted to be a Class III request for amendment, and a check for $4,000 is attached in accordance with 10 CFR 170. PGE has transmitted a copy of this request to the Oregon Department of Energy for their consultation. Also attached is one signed copy of a Certificate of Service for License Change Appli-cation to the chief executive of the county in which the facility is located and the Director of the State of Oregon Department of Energy.
1.
NRC Requirement (3.2.2) Cable Tray Tests Our SER noted that the Licensee had proposed to perform cable tray tests to demonstrate the ability of the Train B switchgear room coolers to remove the heat generated by a fire in this room, and'thus, protect cables and equipment from the safety division not involved in the fire.
Subsequently, the Licensee decided not to perform the tests but to provide an analysis based on cable tray tests that had been recently performed by other organizations. We have reviewed the results of this analysis and find it unacceptable.
We will require that to provide adequate protection for redundant equipment and cabling I
8004180
?c?N: GEC.zid Esuc Ccpr:j Mr. A. Schwencer April 14, 1980 Page 2 in the switchgear room, one of the following should be provided:
(1) an alternate shutdown capability independent of this area; or (2) a 3-hr. fire-rated barrier to separate Train A and Train i
B equipment in the area; or (3) an automatic total flooding gas suppression system.
PGE Response A 3-hr. fire-rated barrier will be provided to separate Train A and Train B equipment in the Train B switchgear room.
2.
NRC Requirement (3.2.6) Containment Fire Suppression The Licensee's e.ommitment on the oil collection system satis-fied our guidelines with the exception of whether this system will be designed for leaks that could occur during a safe shutdown earthquake (SSE), and whether the potential for an SSE to cause the oil collection system to be dropped has been evaluated.
Subject to conformance to this requirement, this item is satisfactorily resolved.
PGE Response The oil collection system provided for the reactor coolant pumps will be seismically supported and will be sized for the largest oil leak that could occur during an SSE.
3.
Following extensive evaluation PGE has determined that modifica-tions that can assure prevention of cable spreading room (CSR) and control room fires are preferable to modifications that mitigate the consequences of such an event.
W'e are therefore proceeding with the design and installation of automatically initiated fire suppression systems in the CSR and control room cabinets containing redundant safe shutdown equipment in close proximity.
For this. reason, the decouple switch design described in PGE-1012 that was proposed to provide an alternate shutdown capability is not required and will not be implemented.
Comple-tion of the CSR fire suppression system is planned by Novem-ber 1,1980.
Installation of the fire suppression system in the control room cabinets necessitates the Plant be shut down; thus completion is scheduled for spring of 1981.
Fire watches will be placed in each area on a 24-hr.-per-day basis while the Plant is in operation until these modifications are complete. The specific system design information will be provided at a later date.
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. cdr.d Gsr.srJ 3:sdc Cerr;zr.y Mr. A. Schwencer April 14, 1980 Page 3 Your letter of March 25, 1980 requested a change to Technical Specifica-tion 6.2.2.f to reflect the manpower required to safely shutdown the Plant either from the control room or using the-remote shutdown method.
As reflected in our letter of June 18, 1979, a minimum of five operators can perform a safe Plant shutdown from outside the control room. The attached License Change Application 59 proposes changes to Technical Specification 6.2.2.a and Table 6.2-1 to clarify the minimum safe shutdown shift complement.
If you have any questions concerning this information, please contact me.
Sincerely, C. Goodwin, Jr.
Assistant Vice President Thermal Plant Operation and Maintenance CG/SML/sh/4mg6B15 Attachments c:
Mr. Lynn Frank, Director State of Oregon Department of Energy l
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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PORTLAND GENERAL ELECTRIC COMPANY, )
Docket 50-344 THE CITY OF EUGENE, OREGON, AND
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Operating License NPF-1 PACIFIC POWER & LIGHT COMPANY
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(TROJAN NUCLEAR PLANT)
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CERTIFICATE OF SERVICE I hereby certify that copies of License Change Application 59 to the Operating License for Trojan Nuclear Plant, dated April 14, 1980 have been served on the following by hand delivery or by deposit in the United States mail, first class, this 14th day of April 1980.
Mr. Lynn Frank, Director State of Oregon Department of Energy Labor & Industries Bldg., Room 111 Salem, Oregon 97310 i
Mr. Robert M. Hunt Chairman of County Commissioners Columbia County Courthouse St. Helens, Oregon 97051
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J. W. Lentsch, Manager Generation Licer. sing & Analysis Subscribed and sworn to before me this 14th day of April 1980.
Notary Public of Oregon My Commission Expires:
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