ML18057B509

Forwards Action Plan to Resolve Generic Ltr 90-06,Generic Issue 70 Re PORV & Block Valve Reliability & Generic Issue 94 on Addl Low Temp Overpressure Protection for LWRs

ML18057B509
Person / Time
Site:	Point Beach
Issue date:	11/14/1990
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-90-117, REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, VPNPD-90-470, NUDOCS 9103140294
Download: ML18057B509 (3)

Text

W1scons1n e

Electnc POWEA COMPANY 231 W. Mlel'ligo~. P.O. Box 20t~, Mllwo!Jkee. \'VI 53201 (414) 22'1*2~5 VPNPD 470 NRC 117 November 14, 1990 Oocwnent Control Desk U S Nuclear Regulatory Commission Mail Station Pl-137 Washington, DC 20555 Gentleman:

Dockets 50-266 and 50-301 B53sponse to Generic Letter 90-06 Resolution of Generic Issues 70 and 94 PQint Beach Nuclear Plant Units l and 2 Generic Letter 90-06, issued on June 25, 1990, and received on July 9, 1990, provided the NRC's plan for resolution of Generic Issue 70, "Power-operated Relief Valve and Block Valve

• Reliability," and Generic Is-sue 94, "Additional Low-Temperature overpressure :Protection for Light-Wat.er Reactors." Licensees were requested to review the proposed actions identified in enclosures A and B to the generic letter and advise the NRC staff, within 180 days .of the date of the letter, of th.eir plans relating to PORV' s and block valves and low-temperature overpressure protection. In

.particular, we are requested to indicate whether we intend to follow the staff positions, as applicable, included in the letter's enclosures or whether we intend to propose alternative measures.

We are also asked to provide our proposed schedule for this implementation.

We have completed our review of the information provided with this generic letter. In general, we are Coll\lnitting to comply with the requirements and actions specified in this letter and its enclosures. We also believe that the schedule for implementation of these actions as proposed by the N'RC, that is by the end of the first refueling outage that starts six months or later from the date of the letter, is reasonable. We, therefore, are also committing to implement these actions, or submit the necessary license amendment application for modification of our Technical Specifications, within that schedule. A summary action plan for resolution of these generic issues at the Point Beach Nuclear Plant I is attached. ~a1-1 r:J. .

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• November 14, 1990 Paga 2 Please review the attached action plan and the implementation schedule. lf you have any questions concerning our activities in this regard, please let us know.

Very truly yours,

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c. w. /ayf Vice President Nuclear Power C'WK/pek Attachment Copies to NRC Regional Administrator, Region III NRC Resident Inspector Subscribed and sworn~o before me this Jbti.day of \1q~.~ , 1990.

Notary Public, State="iWiSCOnsin My Commission expires S:* .2~ -:J..--+~

Blind copies to Boston, Krieser, Lipke, Maxfield, Newton, Al.3.3 EO'd 91:£1flHl18-Ll-N~I'

• ACTION PLANS FOR RESOLUTION OF NEC G_ENERIC ISSUES 70 AND 94 POINT BEACH NUCLEAR UNITS 1 AND :2 A. Generic Issue 70, "Power-Operated Relief Valve and Block Valve Reliability"

l. The PORVs and block valves are within the scope of an operational quality assurance program that is in compliance with 10 CFR 50 Appendix B. By May 15, 1991, we shall further verify that:

a. The PORVs and block valves are on the operational OA list.

b. The maintenance program for the PORVs and block valves is based on manufacturer's recommendations and guidelines and is implemented by trained personnel.

c. Replacement parts and spares for existing PORVs and block valves are procured in accordance with the .

original construction codes and standards.

2. The PORVs, the valves in the PORV control air systems, and the block valves will be included in an inservice testing program covered by Subsection IWV of Section XI of the ASME Boiler and Pressure Vessel Code. This action will be completed by May 15, 1991. By this date we shall also include the block valves in our NRC Generic Letter 89-10 MOV testing program.

3. A license amendment application will be filed by May 15, 1991, to modify the limiting conditions of operation for PORVs and block valves. This Technical Specification revision will follow, to the extent possible, the intent of the model specifications provided with the generic letter, but will be submitted in the existing format of the Point Seach Technical Specifications.

B. Generic Issue 94, "Additional Low*Temperature overpressure Protection for Light-Water Reactors" To provide the added assurance of low-~emperature overp~essure protection (LTOP) availability, we shall revise the current technical specification for operation of the overpressure mitigating system, 15.3.15, to reduce the allowable time interval for which one PORV may be inoperable from seven days to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This amendment application will be submitted to the NRC by May 15, 1991.

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