ML20070G755

Application to Amend Licenses DPR-24 & DPR-27,consisting of Tech Spec Change Request 86 to Address NUREG-0737,Item II.K.3.3, Reporting Safety & Relief Valve Failures & Challenges, in Response to Generic Ltr 82-16

ML20070G755
Person / Time
Site:	Point Beach
Issue date:	12/15/1982
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20070G760	List: ML20070G755 ML20070G770
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.03, TASK-TM GL-82-16, TAC-49748, TAC-49749, NUDOCS 8212220422
Download: ML20070G755 (3)

Text

i l%SCORSin Electnc m coum 231 W. MICHIGAN, P.O. BOX 2046, MiOlWME, WI 53201 December 15, 1982 CERTIFIED MAIL Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. R. A. Clark, Chief Operating Reactors, Branch 3 Gentlemen:

DOCKET NOS. 50-266 AND 50-301 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 86 NUREG;p737 TECHNICAL SPECIFICATIONS (GENERIC LETTER NO. 82-16)

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with 10 CFR 50.59, Wisconsin Electric Power Company (Licensee) hereby requests amendments to Facility Operating Licenses DPR-24 and DPR-27 to incorporate the following change to the Technical Specifications for Point Beach Nuclear Plant, Units 1 and 2. Technical Specification Change Request No.

86 was originally requested by the Nuclear Regulatory Commission (NRC) in Mr. D. G. Eisenhut's letter to All Pressurized Power Reactor Licensees dated September 20, 1982. Licensee examined each item in Enclosure 1 to Mr. Eisenhut's letter and found that all items, except one, are satisfactorily covered by current Technical Speci-fications or are under review by the NRC as a license amendment.

Only the current Technical Specification associated with Item 12 deviated from the guidance outlined in Enclosure 1. This request represents Licensee's submittal to cover the additional requirement delineated in Item 12.

The attached proposed Technical Specification change has been patterned after the model specification guidance provided with Mr. Eisenhut's letter, however, the format of the existing Point Beach Technical Specifications has been maintained.

Specifically, the change was added to Section 15.6.9.1.B.2.d,

" Plant Reporting Requirements", to cover the additional requirement to annually report all challenges to the pressurizer power-operated relief valves sal pressurizer safety valves. The reporting of pressurizer power-operated relief valve failures is ccvered in Section 15.6.9.2.A.l.

B212220422 821215 O kD \ go h -

PDR ADOCK 05000266 \CV P PDR 9\ g}g/ ._

Mr. H. R. Denton December 15, 1982 The following list provides the status of Point Beach Technical Specifications, or submitted change requests, with respect to Enclosure 1 to Mr. Eisenhut's letter:

ITEM STATUS

, 1. STA Training (I. A.1.1.3) Completed 8/20/81.

2. Limit Overtime (I . A. l . 3) Requirements are addressed by administrative procedures. ,

3. Short Term Auxiliary Feedwater T.S. No. 76 submitted 4/27/82.

System Evaluation (II.E.1.1)

4. Safety Grade AFW System T.S. No. 76 submitted 4/27/P2.  ;

Initiation and Flow Indication

5. Dedicated H2 Penetrations Not applicable.

6. Containment Pressure Setpoint Justification approved P/14/81.

7. Containmant Purge Valve Amendment Nos. 64/69 approved (II.E.4.2.6) 10/4/82. ,

8. Radiation Signal on Purge Valves Amendment Nos. 64/69 approved (II.E.4.2.7) 10/4/82.

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9. Upgrade B&W AFW System (II.K.2.8) Not applicable. _,

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10. (Note: Item 10 did not appear in --

Mr. Eisenhut's letter.) ,

11. B&W Thermal-Mechanical Report Not applicable. g 'a '

N (II .K. 2.13) ,

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12. Reporting SV and RV Failures Attached. .s_J and Challenges (II .K . 3. 3) ..

See T.S. 15.3.5, Tablo'

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13. Anticipatory Trip on Turbine .

Trip (II.K.3.12) 15.3.5-2. s

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Licensee has reviewed the requirements of 10 CFR 170.22 ,

regarding schedule of fees for facility license amendment reviews and approvals. It is our determination that this license ameldment application involves an administrative change and can be classified as a Class II amendment for Facility Operating License DPR-24.

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The license amendment for Facility Operating License DPR-27, Point Beach Unit 2, should be a duplicate of the Unit 1 amendment and, ,

therefore, is classified as a Class I amendment, Accordingly, we .

have enclosed a check in the amount of $1,600 as full payment for  !

l the amendment reviews and approvals.

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Mr. H. R. Denton December 15, 1982 Included ith this amendment application is a proposed revised paga for the Point Beach-Nuclear Plant Technical Specifications. This-page has a' margin bar opposite the In accordance with Commission

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addition to the Sp'ecifications.

regulations, Licensee.has. enclosed three signed originals and 40 copies of this license amendment application. Should you have any questions regarding this submittal, please let us know.

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Very truly yours, Assistant Vice President C. W. Fay ,

Attachment (Check No. 707200)

Copy to NRC Resident Inspector o s s

Subscribed and sworn to before me this 15~/ k day of Decembei'1.982. - ~

kngm Qh r-,

Notary 5pbli2, State of Wisconsin

'- My Comnission expiresv hS, /,14fY ..

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