ML19248C868

From kanterella
Jump to navigation Jump to search
Responds to IE Bulletin 79-04 Re Incorrect Weights for Velan Check Valves in Piping Analyses.Definitive Info Unavailable on Six Velan Check Valves Installed at Facility.Final Rept Will Be Submitted When Outstanding Info Is Available
ML19248C868
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 05/01/1979
From: Broehl D
PORTLAND GENERAL ELECTRIC CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 7907050400
Download: ML19248C868 (2)


Text

-

T3W l'on ruxn Gnxnn.u. Er.nc rine Co3nuxv a' ' 4 l2l % V/ 13 A L M O rd STHLtT Po H T L.A N D, O P E O O N 9 72 0 4 D,,,J. D H O E H L.

.s

..... _,.....m..

l Docket flo. 50-344 Uc

\\1, m

May 1, 1979 M r. R. 11. Engelken, Director Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plaza 1990 11 California Blvd.

Walnut Creek, CA 94596

Dear Sir:

On March 30, 1979, you transnitted to us IE Eulletin 79-04 concerning use of incorrect weights for Velan check valves in piping analyses. We have reviewed all available information and, as indicated in the attached response to the subject bulletin, are lacking definitive information on only six Velan check valves installed at Trojan. A final report will be submitted when this outstanding information is available.

Sincerely,

,;/

/

v k

c:

Director Office of Inspection and Enforcement (3)

Director State of Oregon Department of Energy 7 9 0 7 0 5 0 4 co p,

,v

%,5.m*

IE Bulletin 79-04 Response Page 1 of 1 TROJAN NUCLEAR PLANT 1.

3, 4, or 6-in. diameter Velan swing check valves are installed in Seismic Category I piping systems as follows:

a.

Reactor Coolant System b.

Safety Injection (SI) System Chemical Volume and Control System (CVCS) c.

d.

Auxiliary Feedwater System e.

Main Steam System (supply to Auxiliary Feed Pump Turbine Driver) f.

Make-up Water Treatment System (Containment Isolation).

2.

Velan has informed us that the weights of all valves purchased directly by PCE are acceptable as listed on the engineering drawings used by our architect engineer, Bechtel, in their pipint; analyses.

The weights indicated by Velan on their drawings were determined by calculation.

Our Nuclear Steam Supply System (USSS) supplier, Westing-house, has informed us that acceptabic valve weights were used in their piping analyses.

We have yet to verify the use of acceptable valve weights for six valves supplied by Westinghouse, but within the scope of Bechtel's piping analyses. The six valves in question are in CVCS (4) and SI (2) systems.

Westinghouse is presently checking the weights on engineering drawings used by Bechtel in their piping analyses to verify if they were acceptable.

From information available at this time, we are confident that acceptable weights were used in Bechtel's analyses. We will submit a final response to IE Bulletin 79-04 when information is available on these last six valves.

k 3, 4 & 5.

At this time, we have no indication that unacceptable valve weights were used in analyses, thus no reevaluation is currently planned.

No modifications to the systems listed in Item 1 were or are required to piping systems or their supports because of changes in valve weights.

If unacceptable weights were used for the remaining six valves, plans for reevaluation and any required modifica-tions will be indicated in our final response.

)D1 iO$

DJE/JMS/4sb7A9 LUi

,_,-.;,