ML19354E582
| ML19354E582 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 01/25/1990 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| GL-89-13, NUDOCS 9001310416 | |
| Download: ML19354E582 (3) | |
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l anuary 5,
o David W. Cockfield Vice President, Nuclear j
Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Creekside Oaks Office Park 1450 Marie Lane, Suite 210 Walnut Creek CA 94596
Dear Mr. Martin:
Nuclear Regulatory Commission (NRC)
Generic Lotter 89 Service Water System Problems Affecting Safety-Related Equipment Generic Letter (GL) E9-13 requests that each licensee supply information about their respective service water systeam to assure the NRC of compliance to the requirements of the General Design Criteria (GDC) in Title 10 of the Code of Federal Regulations Part 50, Appendix A and Section XI of Appendix B.
In addition, the NRC requests information to confirm that the safety functions of the service water systems are being met.
i The NRC recommends five actions to be taken by licensees to comply with the requirements of tho generic letter.
The,five actions,nre (I) implement and maintain an ongoing program of surveillance and control techniques to significantly reduce the incidence of flow blockage problems as a result of biofouling, (II) conduct a test program to verify the heat transfer l
capability of all safety-related heat exchangers cooled by service water, (III) ensure by establishing a routine inspecticn and maintenance program l~
for open-cycle service water system piping and components that corrosion,
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erosion, protective coating failure, allting and biofouling cannot degrade the performance of the safety-related systems cooled by service water.
l (IV) confirm that the service water system will perfots its intended l
function in accordance with the licensing basis for the plant and i
(V) confirm that maintenance practices, operating and emergency procedures, I
and training that involves the service water system are adequate to ensure that safety-related equipment cooled by the service water system will i
function as intended and that operators of this equipment will perform effectively.
All five recomnandations require for the most part, completion of licensee actions before plant startup following the first refueling outage beginning i
nine months or more after the date of CL 89-13.
The first refueling outage 9001310416 90012; PDR ADOCK 05000344 (Q
P PDC O S W Sa! mon Street Portand. Oregon 97204
e.
John B. Martin January 25, 1990 Par.e 2 l
for the Trojan Nuclear Plant beginning nine months or more from July 18, 1989 is the 1991 refueling outage. The 1991 refueling outage is scheduled l
to begin in March 1991.
l In response to the recommended actions in CL 89-13, Portland General' i
Electric (PCE) has developed a detailed action plan to address all actions recommended in GL 89-13.
The detailed action plan identifies individual responsibilities and action completion dates to assure that.the intent of every action required by CL 89-13 is completed in a timely manner. Where an alternate course of action is taken from the generic letter recommendations, appropriate plant records will be maintained to document the justification that the alternative program will ensure that the safety i
functions of the service water system are being met.
All generic letter recommendations will be applied to the open-cycle Service Water System (SWS).
In addition, recommendations IV and V will be l
applied to safety-related closed-cycle intermediate cooling water systems l
[e.g., Component Cooling Water System (CCWS)). Where the adequacy of a i
chemistry control program cannot be confirmed for a closed-cycle system,
)
Recommendations II and III will be evaluated for applicability to these 1
systems.
l i
l A macro-biofouling program is currently being perfected to preclude flow j
blockage due to biofouling in the SWS (NRC Recommended Action I).
The program will be evaluated against the NRC recommended program outlined in of the generic letter.
A listing of all safety-related heat exchangers cooled by the SWS has been i
developed. The heat transfer capability of these heat exchangers will be verified to ensure that the associated equipment will perform its intended safety function (NRC Recommended Action II).
Initial testing will be i
performed to develop baseline data. Following initial testing, the frequency of periodic retest will be at least-once each fuel cycle. After three tests, a frequency for subsequent testing will be developed based on the trend results.
Inspections and maintenance will be utilized in lieu of testing when testing is impractical. Justifications will be documented When this j
alternative is utilized. Initial testing will be completed by the end of the 1991 refueling outage.
The existing Trojan Nuclear Plant inspection and maintenance programs will be expanded to monitor the SWS (NRC Recommended Action III). The programs, I
as a minimum, will address cerrosion, erosion, protective coating failure, silting and biofouling. The expanded programs will be established by the end of the 1991 refueling outage.
A single active failure analysis will be performed to confirm the SWS will perform its intended functions in accordance with the licensing basis for the plant (NRC Recommended Action IV).
The analysis will incorporate the
l,....
Portland GeneralBasicCompey John B. Martin January 25, 1990 Page 3 results from an as-built system.walkdown. This confirmation will be completed by the end of the 1991 refueling outage.
A review will be performed to confirm that maintenance practices, operating and emergency procedures, and training are adequate to ensure that safety-related equipment cooled by the SWS will function as intended and-that operators of this equipment will perform effectively (NRC Recommended i
i Action V).
This confirmation will be completed by the end of the 1991 l
refueling outage.
l l
PGE will provide a status of the action plan developed to respond to l
GL 89-13 in September 1990. In addition, as requested per the generic letter, PGE will confirm to the NRC that all the recommended actions have i
been implemented within 30 days of each completion.
i l
Sincerely, c:
U.S. Nuclear Regulatory Commission Attn:
Document Control Desk i
Washington, D.C.
20555 Mr. David Stewart-Smith State of Oregon Department of Energy l
Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant subscribed and sworn to before me this 25th day of January 1990.
Nc.
4 Notary Public of Oz4gon i
My Commission Expires:
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