ML20083N261

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Forwards Revised Table 1 to Correct Typographical Error Re Two 10-inch Check Valve Identification Numbers in 820811 Response to IE Bulletin 82-02 Re Degradation of RCPB Fasteners
ML20083N261
Person / Time
Site: Point Beach  
Issue date: 01/24/1983
From: Burstein S
WISCONSIN ELECTRIC POWER CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
REF-SSINS-6820 IEB-82-02, IEB-82-2, NUDOCS 8302010603
Download: ML20083N261 (3)


Text

r-Msconsin Electnc eowen couraur 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 January 24, 1983 Mr. J. G. Keppler, Re.gional Administrator Office of Inspection and Enforcement, Region III U.

S. NUCLEAR REGULATORY COMMISSION 799 Roosevelt Road Glen Ellyn, Illinois 60137

Dear Mr. Keppler:

DOCKET NOS. 50-266 AND 50-301 REVISION TO REPLY TO IE BULLETIN NO. 82-02 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In IE Bulletin No. 82-02 dated June 2, 1982, the NRC notified PWR Licensees of incidents of severe degradation of threaded fasteners in closures of the reactor coolant pressure boundary of various PWR nuclear plants.

The bulletin instructed Licensees to perform specific actions concerning threaded fasteners including an augmented inservice inspection of these threaded fasteners, specifically, bolting less than or equal to two inches in diameter.

Table 1 of Wisconsin Electric's reply to IE Bulletin No. 82-02 dated August 11, 1982, which listed applicable bolting at Point Beach, incorrectly listed two ten-inch check valves as SI-842C and SI-842D.

The correct valve identification numbers for these two valves are SI-867A and SI-867B.

The revised Table _1,

enclosed, corrects these typographical errors.

We reaffirm our commitment to follow the actions of Wisconsin Electric's August 11 reply to IE Bulletin No. 82-02.

With the exception of the reactor coolant pump seal assembly upper and lower flanges, which are ASME Section XI exempt, the ASME Section XI examinations of bolting less than two inches listed in Table 1 will be supplemented with a surface examination.

1 Very truly yours, r

i l

C302010603 830124 l

PDR ADOCK 05000266 Executive Vice President O

PDR Sol Burstein Enclosure l

Copy to NRC Resident Inspector

_1 JAN 2 7 E63

Table 1 Page 2

^

NO STUD OR NUT BOLTING LUBRICANT USE OF EVIDENCE OF BOLT BOLT MATL MATL SIZE USED FURMANITE WASTAGE OR SCC ER Check Valve SI-867A

^~

8^-194 16 1-5/8" AS Body-to-Cap GR-B7 GR-21I Check Valve SI-867B 8^~

^~

16 1-5/8" AS Body-to-Cap GR-B7 GR-211 In 1981, one stud shows Check Valve SI-853A SA-193 SA-194 12 1-5/8" AS evidence of localized Body-to-Cap GR-B7 GR-2H orrosion wastage.

Check Valve SI-853B SA-193 SA-194 12 1-5/8" AS Body-to-Cap GR-B7 GR-211 Check Valve SI-853C SA-193 SA-194 12 1-5/8" AS Body-to-Cap GR-B7 GR-211 Check Valve SI-853D SA-193 SA-194 12 1-5/8" AS Body-to-Cap GR-B7 GR-211 EOTES:

NL - Neolube No. 2 lubricant AS - Loctite Antiseize lubricant (1)

Westinghouse specification No. BDS70041AL (2)

Replaced gasket (3)

Seal welded body-to-bonnet connection and lubricated and retightened the bolting.

(4 )

For each case of leakage, a visual exam was performed of connection after repairs to verify leaktight integrity at normal operating pressure.

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