ML20246F689

Requests Extension of Deadline for Response to Generic Ltr 89-04 Until 901003 in Order to Submit New 120-month Insp Program.Use of O&M Stds Also Requested

ML20246F689
Person / Time
Site:	Point Beach
Issue date:	07/05/1989
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Swenson W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
CON-NRC-89-079, CON-NRC-89-79 GL-89-04, GL-89-4, VPNPD-89-371, NUDOCS 8907130359
Download: ML20246F689 (2)

Text

_ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

f*:

a, . . .

Wisconsin Electnc POWER COMPANY 231 W. Michigan. Ro. Box 2046' . Milwaukee, WI 53201 [414) 221-2345 VPNPD-89-371' NRC 079 July. 5, 1989 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, D.C. 20555 Attention: Mr. Warren'Swenson, Project Manager Project Directorate III-3 Gentlemen:

DOCKET NOS. 50-266 AND 50-301 GUIDANCE ON INSERVICE TESTING PROGRAMS SCHEDULE FOR RESPONSE TO GENERIC LETTER NO. 89-04 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In a letter dated April 7, 1989, Wisconsin Electric Power Company, licensee for the Point Beach Nuclear Plant, was notified that our applications for license amendments to change the Technical Speci-fications for. inservice testing programs, dated February 17, 1977 and November 27, 1978, had been denied. In the notice of denial, the NRC stated that new guidance for inservice testing programs had been issued in Generic Letter 89-04 dated April 3, 1989. The letter specified that the Point Beach inservice testing program should be msdified or revised as necessary in order to be in compliance with the positions presented in Generic Letter 89-04.

Once this is achieved, we may proceed with a new application to amend the licenses and modify the technical specification.

As you know, Generic Letter 89-04 requests that licensees review their inservice program and amend the program as necessary to conform with the eleven code requirements or staff approved positions presented in Attachment 1 to the generic letter. If conformance with these positions require system or equipment modifications, licensees are also requested to complete such

. modifications within 18 months of the date of the confirming letter. That letter, a description of changes needed to the inservice testing program and a schedule for the modifications are requested to be submitted within six months of the date of the generic letter. l You should be advised that the present 120-month inspection interval for Point Beach Units 1 and 2 will expire in December 1990. Pursuant to 10 CFR 50.55a, an updated inspection program B907130359 890705 0; ,'

PDR- ADOCK 05000266; p PNU; ' AsubsWan onUmwnEneyOmentd>n

--.____-.____ _ ___ _ J

,- j Document Control Desk July 5, 1989

~Page 2.

4 must be submitted and be in place prior to that time. We are concerned that our review of the present program to establish )

conformance with the positions of Generic Letter 89-04 together ]

with the submission for NRC review of any program changes neces-sary to establish conformance to the generic letter would not be ,

an appropriate utilization of resources. We therefore intend to {

commence the development of our next 120-month inspection interval l and incorporate the positions of Generic Letter 89-04 in one effort. In order to accomplish this, we request that the six month response deadline for the generic letter be extended to October 3, 1990, when we will submit our new 120-month inspection program. At that time, we will provide a complete program revision which will address the requirements given in Generic Letter 89-04 and will identify any modifications needed.

It is further requested that the NRC authorize' Wisconsin Electric to develop our next 120-month program using O&M Standards 6 and

10. As you know, 10 CFR 50.55a, Item g.4.ii requires that a 120-month inspection interval program use as its basis the latest edition and addenda of the ASME Code referenced in the regulations 12 months prior to the start of the inspection interval. The regulation at 10 CFR 50.55a(b)(2) presently referencesSection XI of the ASME Boiler and Pressure Vessel Code through the 1986 Edition. The ASME Code 1987, Addenda 1988 references O&M Stan-dards. These standards contain significant improvement regarding pump and valve testing provisions. Therefore we desire to incor-porate these provisions in our program. We understand that the NRC will probably be endorsing these standards but not until l December 1989. In order for us to proceed with the orderly development of our next inservice testing interval program, we hereby further request that the NRC authorize our use of the O&M 6 and 10 standards.

We request that you notify our staff by the end of August 1989 of your decision regarding authorization to extend the deadline for our response to the generic letter and use of the O&M standards.

Very truly yours,

/s . .

YOf' C. W. Fay Vice President Nuclear Power Copies to NRC Resident Inspector NRC Regional Administrator, Region III

_ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ - _ _ _ . _