ML20071N566
| ML20071N566 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 05/25/1983 |
| From: | De Lorenzo R WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, GO1-83-0208, GO1-83-208, NUDOCS 8306070113 | |
| Download: ML20071N566 (2) | |
Text
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Washington Public Power SupplyS stem g
P.O. Box 968 3000 GeorgeWashingtonWay Richland,WashinQ 2 (509)372-5000 di May 25, 1983 N ?[
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G01-83-0208 Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Attention:
Mr. D.M. Sternberg, Chief Reactor Projects Branch No. 1
Subject:
NUCLEAR PROJECTS N0. 1 & 4 Docket Number 50-460 & 50-513 10CFR50.55(e) POTENTIALLY REPORTABLE CONDITION REACTOR VESSEL INTERNALS BOLTS
Reference:
Telecon, C. R. Edwards, Supply System to J.0. Elin, Region V. Nuclear Regulatory Commission, dated May 2,1983.
In the above reference, the Supply System informed your office of a potentially reportable deficiency in accordance with the requirements of 10CFR50.55(e).
Attachment A of this report includes a statement of the potentially reportable condition and the Project's planned action.
Due to the extended construction delay of the WNP-1/4 Projects, we will provide your office with a status report upon restart of construction.
In the event that corrective action is completed or a resolution is reached before our construction restart we will then provide your office with a final report.
If you have any questions or desire further information, please advise.
R. A. De Lorenzo Program Director (821)
RAD:RL:cmo Attachment cc:
TA Mangelsdorf, Bechtel (861)
V Mani, UE&C (897)
V Stello, Director of Inspection NRC A Toth, NRC (917Q)
ORM (847) e306070113 830525 PDR ADOCK 05000460 S
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ATTACHMENT A WNP-1/4 DOCKET 50-460 & 50-513 POTENTIALLY REPORTABLE 10CFR50.55(e) CONDITION REACTOR VESSEL INTERNALS BOLTS BACKGROUND We have been informed by Babccck & Wilcox of what may be a potential safety concern regarding bolt material used in the reactor vessel internals.
While some applicable data has previously been made available to the NRC by B&W in respect to the 177FA plants, it is our purpose to report on the applicability of this potential safety concern as it relates to the WNP-1 and 4 Projects.
DESCRIPTION OF DEFICIENCY Reactor vessel internals at various B&W operating plants have undergone examination of their bolted connections and there have been instances where UT abnormal indications or failure of bolts have been found. While the probable cause for this condition has not been confirmed, conditions seem to be restricted to bolts made from age hardened austenitic steel designated A-286, Cond. A.
SAFETY IMPLICATION While no direct safety implications are currently being postulated, the number of affected bolts is the cause for concern.
There are several hundred of this type of age hardened austenitic steel bolts that are used in the reactor vessel internals of WNP-1 and 4.
The possibility of this type of material not performing as expected could require an extensive bolt change-out program.
CORRECTIVE ACTION B&W is participating in an inspection program on operating plants and we are to be advised of the results.
Due to the extended construction delay, we will inform your office of the status of this condition upon restart of construction.
In the event that correcti ve action is completed or a resolution is reached before construction restart, we will then provide your office with a final report.
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