ML19345F526
| ML19345F526 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/10/1981 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19305F314 | List: |
| References | |
| NUDOCS 8102180192 | |
| Download: ML19345F526 (2) | |
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Wisconsin Electnc a coww 231 W. MICHILAN, P.O. BOX 2046. VILWAUKEE, WI 53201
~
February 10d 19811 m
n Mr. H.
R.
Denton, Director Office of Nuclear Reactor Regulation U.
S. NUCLEAR REGULATORY COMMISSION Washington, D.
C.
20555
Dear Mr. Denton:
DOCKET NOS. 50-266 AND 50-301 INSERVICE INSPECTION PROGRAMS FOR PUMPS AND VALVES POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 On February 12, 1979 the Commission published in The Federal Register a notice concerning a revision to 10 CFR 50 Section 50.55a which changed the basis for inservice inspection and testing requirements for safety class components of nuclear power plants.
The revised regulation requires that all nuclear power facilities meet, to the extent practical, the inservice inspection and testing requirements of Section XI of the ASME Boiler and Pressure Vessel Code, as specified in 10 CFR 50.55a Paragraph (b).
Licensees were required at that time to update their inservice testing programs every 20 months.
Wisconsin Electric filed license amendment requests (Change Request Nos. 42 and 58) on February 17, 1977 and November 27, 1978 for Point Beach Nuclear Plant, Units 1 and 2, respectively, for Technical Specification changes necessitated by the revised inservice testing requirements as required by the Code of Federal Regulations.
To date the NRC has not completed its review of either license amendment requested or the associated inservice testing program descriptions which were submitted May 20, 1977 and February 19, 1979 for Units 1 and 2, respectively.
The attached inservice testing programs for Point Beach Units 1 and 2 were developed in compliance with the most recent rules and regulations of 10 CFR 50.55a and Section XI of the ASME Boiler and Pressure Vessel Code, 1977 Edition through Summer 1978 Addenda.
These programs are for the 120-month interval as stipu-lated in 10 CFR 50.55a g(4) (ii).
These programs are to replace in their entirety the previous submittals for pump and valve testing for both units.
These new programs should be promptly reviewed and 810 218 0 Pi1L p
1, '
,o I
Mr. H.
R. Denton February 10, 1981 the requested reliefs granted.
The reliefs requested and the bases for the reliefs are presented in Appendices A and B for the pump and valve testing programs, respectively.
As discussed in the bases for aach relief requested, we believe that conformance with the specific code requirement is impractical for the Point Beach facility ar.d that pursuant to 10 CFR 50.55a Paragraph (g) ( 6) the Commission is authorized to grant such relief.
The Technical Specification changes previously referenced stand in agreement with these revised programs and should be expedited.
It is our position that approval of these Technical Specification changes needs to be completed prior to implementation of these new inservice testing programs.
Accordingly, we do not plan to implement the enclosed Point Beach Nuclear Plant, Units 1 and 2, inservice testing programs until 90 days after receipt of the NRC's approval of both the relief requests and Technical Specification changes.
Should you have any questions regarding the attached programs or require additional clarification or details, please contact us.
Very truly yours, C. W. Fay, Director Nuclear Power Department Attachments Copy (Without Attachments) to NRC Resident Inspector