ML20041C430

Application for Amend to License DPR-24,consisting of Tech Spec Change Request 42,changing Tech Specs 15.4.2 Re Inservice Insp of Safety Class components,15.4.5 Re Pump & Valve tests,15.4.7,15.4.8 & 15.6.9

ML20041C430
Person / Time
Site:	Point Beach
Issue date:	02/17/1977
From:	WISCONSIN ELECTRIC POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20041C405	List: ML20041C404 ML20041C407 ML20041C430 ML20041C432
References
NUDOCS 8203010377
Download: ML20041C430 (3)

Text

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

s. m ,

(L, g j E*1 CLOSURE 5

\%.?

VhSCCDSin Eisctric eowca couesur 231 WEST MICHIGAN, MILWAUKEE WISCONSIN 53201 February 17, 1977 fic. Denard C. Rusche, Director Office of fluclear Reactor Pequlation U. S. !!UCLEArt RiGULATORY CCmI">3 ion Rishington', D, C. 20555

Dear fir. Rusche:

DOCKET liO. 50-266 IllSERVICE IilSPECTIO'l 0F SAFCTY CLASS C0 !PO'iE iTS TEClit!ICAL SPECIFICATI0li CilA;!GE REGUEST NO. 42 POIllT GEACH iillCLt'AR PLANT U:!IT 1 In accordance trith Section 50.59 of 10 CFR 50, Wisconsin Electric Power Conpany and Wisconsin f4tchigan Power Company (Licensees) hereby request an acend-ment to Facility Operating Licensu CPR-24 to inccrpcrate changes to the Technical Specifications for P9 int Beach Nuclear Plant Unit "o.1. The attached changes to the Technical Specification are in corpliance with Section 50.55a paracraph (c)(5) of 10 CFR GC which requires arendment of the technical specifications to confora the specifications to the updated ins:Tvice inspection and testing prograas for safety . class components mandated by Staction 50.55a.

On February 12,197G, notice was puMished in the Federal Registar of

, a revision to 10 CFR 50 Section 50.SSa which changed the inservice inspection and testing requirements for nuclear power plant safety class components. Brie fly, this revised regulation requires that all nuclear power facilities meet, to the extent practical, the inservice inspection requirenents of Suction XI of the AS;1E Cciler and Pressure Vessel Code, edition and aWenda as specified in 50.5Ea paragraph (b). Licensees am required to update their inservice inspection prograa prior to each 40 month inservice inspection interval and update the Dump and valve inservice testing program every 20 months. If conflicts exist bettaen the ASiiE Section XI code anj the plant's technical specification, Licensaes are required to subnit a proposed auendaent to the tacha1 cal specifications for HRC approval at least six months prior to the start of the next ins;:ection interval .

Your letters of Acril 25, 1976 and ilovember 22, 1975 provided further guidance on this subject and included sanple technical specification language.

0 8203010377 820223 PDR ADOCK 05000266 -

O PDR

________ _a

, Mr.' Benard C. Rusche - Page Two February 17, 1977 He are presently in the process of updating the inservice insoection progrca for Point Beach nuclear Plant Unit 1 to the 1974 edition Emer 1975 Addenda of the ASME Section XI code. As a result of this program update, and considering your guidance regarding sample technical soecification language, we propose the following technical specification changes: (Revised pages are attached)

1. Specification 15.4.2.B. - The existing section has been completely deleted and revised language which follcus the HRC guidance has been substituted. Licensees have included scocific language to confirm that all containacnt isolation valves shall be tested in acccrdance with the provisions of Appendix J to 10 CFR 50 " primary Reactor Containment Laakage Testing for Water-Cooladed Power Reactor ".

We have also provided language to clarify that, per section 50' 55a paragraph (g)(5)(iii), if the licensee has determined that confor..:ance with a code requirement is impractical, licensee shall notify the Comission and submit information to support his determination.

2. Specification 13.4.5.II items A and n - These items which specified certain pump and valve tests have been deleted as they are superseded by ASME Section XI valve and pur:p testing code requirements.

3. Specification 15.4.7 - This specification on main steam step valve periodic testing is supersaded by AS?;E Section XI valve testing code requirements and has been deleted.

4. Specification 15.4.8 - This specification on auxiliary feedwater purps periodic testing is supers edad by ASME Section XI pume testing code requirements and has been deleted.

5. Specification 15.6.9.a - Item G of this snecification required a one time review of the inservice insocction progran at the end of the first five years of operation. This review has been done in connection with this mandatory update of the inservice inspeccion progrca. Thi,s requirement may thus be deleted.

' fir. Cenard C. Rusche - Page Three.. February 17, 1977 As specified in 10 CFR Part 50, we are enclosing three signed originals and thirty-seven copies of this license amendment request and procosed technical specification change. The next 40 month inspection interval for Point Beach Unit 1 will begin on August 21, 1977. Our proposed inservice inspection and testing program shall be subu:itted at least 90 days prior to that date. Should you have any questions concerning these proposed technical specification changes, please contact us as soon as possible.

Very truly yours.

, r =

I Sol Ilurstein Executive Vice President Attachments Subscribed and swcrn to before me this 17th day of February,1977.

Ifothry Public, State of Wisconsin ity coraission expires January 15, 1978 bec: Messrs. C. S. McNeer J. L. Ellefson R. H. Gorske/A. W. Finke G. A. Reed T. R. Wilson Gerald Charnoff C. W. Fay e