ML20006B709
| ML20006B709 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/25/1990 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-008, CON-NRC-8 IEB-89-200, VPNPD-90-039, VPNPD-90-39, NUDOCS 9002050277 | |
| Download: ML20006B709 (2) | |
Text
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Wosconson
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Electnc POWER COMPANY 231 W Mchryn Po. Box 2046. Mawoukee WI 53201 (414)221 2345 4
VPNPD-90-039 10 CFR 50.59(f)
NRC-008 January 25, 1990 U. S. NOCLEAR REGULATORY COMMISSION Document Control-Desk Mail Station P1-137 Washington, D. c.
20555 Gentlemen:
DOCKET 50-301 BULLETIN 89-02 RESPONSE CHECK VALVE BOLTING INSPECTION POINT BEACH NUCLEAR PLANT. UNIT 2 As required by NRC Bulletin 89-02, all Anchor-Darling Model S350W check valves were inspected for cracked internal-bolting during.
the most recent refueling outage of Point Beach Nuclear Plant,'
-Unit 2.
Results of the inspections are given below.
2SI-842 A and B Safety Iniection' Accumulator Discharae' Check Valves-The four studs were visually inspected.. No1 indications'of cracks were=foiand.
Hardness of the: studs ranged from'Rc20 to-27.
SI-867 A and B-Cold Leo Safety _Iniection Check Valbes-A detailed visual inspecti$n of'the studs was not performed' because of the significant radiation dose. expected during the-necessary cleaning.
_A qualitative " ring" test-(striking the-studs with a han.mer) was performed; Land-there was no: indication of discontinuity.within the. studs. -Hardness'of theistuds' ranged-from'Rc19 to 21.
A surface. exam of the studs was"not performed because we do.not:
intend to~ reuse the studs and because of the difficulty'and i
exposure associated with cleaning'the studs to a: condition to
--i obtain aimeaningful liquid penetrant exam.
9002050277 900125 D
PDR ADOCK 05000301
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l NRC Document Control Desk l
January 25, 1990 i
Page 2 l
Since Anchor-Darling now recommends using studs made from t
ASTM A-564 Type.630, new studs of this material were obtained i
from Anchor-Darling and installed in each of the valves.
l t
since'no cracks were detected and stud hardness was generally below the Rc26 threshold of concern for stress corrosion cracking, we concluded that the operability of these valves was not adversely affected during the time the original studs were installed.
l Inspection of the same valves in Unit 1 is planned for the next refueling outage in April-May 1990.. The condition of those studs will be reported when inspection results are available.
Very truly yours, e
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C. W.
Fay Vice President l
Nuclear Power Copies to NRC Regional Administrator, Region III t
NRC Resident Inspector Subscribed'and sworn to before me this.2M day of heavy
, 1990.
Notary Public, State of Wisconsin My Commission expires 3~- 2 7 - 7 0,
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