ML20236W992
| ML20236W992 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/04/1987 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| TAC-65350, NUDOCS 8712080355 | |
| Download: ML20236W992 (2) | |
Text
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.g David W. Cockfield Vice President, Nuclear December 4, 1987 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555
Dear Sir:
nj Component Coolinr, Water (CCW) System The purpose of this letter is to provide Portland General Electric Company's (PGE) plan of action for addressing the conclusions of a Nuclear Regulatory Commission (NRC) Safety Evaluation of the CCW System.
The referenced Safety Evaluation was transmitted to PGE by letter dated April 2, 1987. In PGE's May 6, 1987 letter, which responded in detail to the NRC's Safety Evaluation, we provided our reasons why a complete double-ended guillotine rupture of a Non-Seismic Category I pipe in the CCW System did not have to be considered for sy d em operability.
On November 12, 1987, Mr. Tom Walt of PGE met with Mr. Terence Chan of the 'fBC to discuss resolution of this issue.
As a result of that meeting, PGE has taken or plans to take the following actions:
1.
PGE will modify the CCW System or seismically support the non-seismic portions of the CCW System to meet the NRC's pipe break criterion described in the April 2, 1987 Safety Evaluation. This work will be completed by the end of the 1989 refueling outage.
2.
In the interim, PGE has completed a Justification for Continued Operation (JCO) for continued Plant operation until the modification has been com-pleted. This JC0 is based on operating the CCW System with the interface isolation valves for one train normally closed, and with all three CCW i
pumps' maintained in an operable status in accordance with applicable Technical Specification requirements.
9712080355 871204 PDR ADOCK 05000344 PDR.
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4 The precise inodifications Which"will be made have not been determined. ~
Two options are currently being evaluated:
(a) seismically supporting the.
non-seismic portions,of the system, or (b) installing a flow orifice which will restrict flow and indicate high-flow conditions-that will. activate-closure of the train-isolation valves. Other options may also exist'. We will' advise the NRC-by April 1, 1988.of-the' specific actions which will be
'taken.
Sincerely, I;
L et Mr. John B. Martin Regional' Administrator, Region V
- U.S. Nuclear Regulatory Commission Mr. Dave.Yaden, Director l
. State of Oregon Depa'*tment'of Energy Mr. R. C. Barr NRC Resident Inspector-(
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