ML20028H856
| ML20028H856 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/22/1991 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-91-006, CON-NRC-91-6 IEB-89-002, IEB-89-2, NUDOCS 9101310160 | |
| Download: ML20028H856 (2) | |
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' Electnc POWER COMPANY j-n1 w M,myn Po b 20a6 wmum w.W20t utma mL VPHPD-91-030 URC-91-006 January 22, 1991 Document Control Desk U.
S.
NUCf. EAR REGUI.ATORY COMMTSSTON Mail Station F1-137 l
Washington, DC 20555 Gentlemen:
l DOCKET No. 50-301 BULLETIN 89-02 RESPONSE l
CHECK VALVE BOLTING INSPECTION POINT BEACH NUCLEAR PLANT UNIT 2 NRC Bulletin 89-02 required that licensees disassemble and inspect safety-related Anchor / Darling Model S350W check valves supplied with A193 Grade B6 Type 410 stainless stool retaining block studs.
Four of these valves are installed in each unit at the Point Beach I
Nuclear Plant.
The bulletin also required licensees to review other safety-related check valves to determine if similar designs and materials are used.
Seven similar safety-related valves and one important but not safety-related valve were identified in cach unit.
All the Unit 1 check valves subject to this bulletin were inspected during the Spring 1990 refueling outage.
The studs were visually inspected, and no cracks were found.
This action was reported to the NRC in our letter dated July 25, 1990.
The Anchor / Darling Model S350W valves installed in Unit 2 were inspected during the Fall 1989 refueling outage.
This inspection was reported to the l
NRC in our letter dated January 25, 1990.
The other eight Unit 2 valves were inspected during the Fall 1990 refueling outage.
The valves were reassembled with new ASTM A-564 Type 630 stainless steel bolting to alleviate future stress corrosion cracking concerns.
Although we intended to inspect and test the bolts that were removed from these valves, the bolts from six of the eight valves were inadvertently disposed of before visual inspections and hardness tests could be performed.
The bolts from the remaining two valves showed no indications of cracks.
Hardnces ranged from RC 26 to RC 42.
1 9101310160 910122 PDR ADOCK 05000301
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- e Document Control Desk January 22, 1991 Page 2 i
This letter concludes our actions on the check valve bolting inspections required by NRC Bulletin 89-02 at the Point Beach Nuclear Plant.
Very truly yours, l'
//
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- d.,w '! "6 C.
W.
Fa9 Vice President Nuclear Power Copy to:
NRC Resident Inspector NRC Regional Administrator l
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