ML19347D011

Application to Amend License NPF-8,authorizing Temporary Relief from App a Tech Specs to Perform Augmented Low Power Test 501-7-007 Natural Circulation,Cooldown & Boron Mixing. Class III Amend Fee Encl

ML19347D011
Person / Time
Site:	Farley
Issue date:	02/27/1981
From:	Clayton F ALABAMA POWER CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML19347D012	List: ML19347D011 ML19347D013
References
NUDOCS 8103100530
Download: ML19347D011 (4)

Text

{{#Wiki_filter:~ Alabima Powtr Company 600 Nor*. i 18th Street Post O'fece Box 2641 Dirmingham. Altbama 35291 Teohone 205 250-1000 F. L. CLAYToN, JR. - Senior Vice President Alabama Power February 27, 1981 me soumern electre sysw 3 1 9 Docket No. 50-364 W 4

                                                                         /l                            %

Director, Nuclear Reactor Regulation ' ' U. S. Nuclear Regulatory Commission [[J 3 - Washington, D.C. 20555 g [W,R,pf' 0,. g o. - s Attention: Mr. A. T. Schwencer Vn ',. s . R< s / N Gentlemen: d I. JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 AMEN 0 MENT TO OPERATING LICENSE NO. NPF-8 APPENDIX A TECHNICAL SPECIFICATIONS Alabama Power Company hereby requests that an amendment to the Farley Nuclear Plant Unit 2 Technical Specifications be approved granting temporary relief from certain Technical Specification items in order to perform aug-mented low power test 501-7-007, " Natural Circulation Cooldown and Boron Mixing". Revision 3 to the Farls ' Nuclear Plant Unit 2 Special Low Power ~ Test Safety Evaluation, which includes the Technical Specification relief that Alabama Power Company is hereby requesting is enclosed. These items are designated Class III in accordance with 10CFR170 requirements. A check for $4,000 is also enclosed to cover the fees required for a Technical Spec-ification amendment. In accordance with 10CFR50.30(c)(1)(i), three (3) signed originals and thirty-seven (37) additional copies of this proposed amendment are enclosed. If you have any questions, please advise. Very truly yours, A F. L. Clayton, r. FLCJr/RWS:nac Sworn to and subscribed before me this37//, day of /0/m,q , 1981. Enclosures cc: Mr. R. A. Thomas  ; Mr. G. F. Trowbridge /g Mr. L. L. Kintner (w/ Enclosure) NOTkRYhUBbIC~ Mr. W. H. Bradford (

                                                    )

My Coninission Expires: dd f 8103100 5 3 o

e-

      -                                                                            4   s
              ,                                                             .g            APW-A-5542 Westinghouse           Water Reactor                            wearcacii
                                                                            * **"8 " "

Electric Corporatlan Divisions Sct 355 Pittsisgn Pennsylvania 15230 _. February 18, 1981

            . Mr. O. D. Kingsley, Manager                                S.O. APR-4705 Nuclear Engineering and Technical Support Alabama Power Company      ..

600 North Eighteenth Street

            -Birmingham, AL      35203

Dear Mr. Kingsley:

JOSEPH M. FARLEY NUCLEAR PLANT UNIT 2 Special Low-Power Tests Safety Evaluation Attached is Revision 3 of the Farley Unit 2 Special Low-Power Tests Safety Evaluation" report for the performance of the natural circulation tests. This revision incorporates the Boron Mixing and Cooldown Test (Test 7) ,- which will be performed ~ utilizing decay heat following the 100-hour plant performance test run. Also attached is the Safety Evaluation Checklist applicable to this revision of the above document. If you have any questions concerning the above, please contact the undersigned. 1 Si e y .

 ~

caf6' . ,i L. E. Conway/je J. L. Vota, Mana Attachment Southern Company ects cc: 0. D. Kingsley ll, lA A. A..Vizzi ll, l A

0. Batum. lL, lA R..P. Mcdonald ll, lA F. E. Ehrensperger lL, lA V. C. Valekis ll, lA H. O. Thrash ll, lA W. G. Hairston 2L, 2A m m O

             .,,                                                                                ,...,.,.                     g .

ATTACEMENT 1 _. Custocier Reference No(s). WestinghouseReferenceNo(s). (Change Control or RFQ as Applicable) WESTINGHCUSE NUCLEAR SAFETY EVALUATICN CHECK LIST PAGE 10F 3 (1) NUCLEARPLANT(S) Farley Unit 2

                .\

(2) CHECX LIST APPLICABLE TO: APR Special Test Program (Rev. 3 of SER) (Subject of Change) . , (3) The written safety evaluation of the revised procedure, design change or modif! cation required by ICCFR50.59 has been prepared to the extent recuired and is attact.ed. If a safety evaluation is not required or is incomplete for any reasen, explain en Page 3. Parts A and 8 of 'this Safety Evaluation Check List are to be cocoleted only en the basis of the safety evaluation perforced.

                    .            CHECX LIST - PART A                                                                       .

(3.1) Yes No X A change to the plant as described in the FSAR?

 ~

(3.2) Yes No X A change to precedures as described in the FSAR? (3.3) Yes X No A test or experiment not described in the FSAR? (3.4) Yes X No A change to the plant technical specifications (Appendix A to the Operating License)? (4) CHECX LIST - PART 3 (Justification for Part B answers must be included on Page 3.) l (4.1) Yes No X Will the prebability of an accident previcusly evaluated in the FSAR be increased?

           ~

(4.2) Yes X No Will the consequences of an accident previously evaluated in the FSAR be increased? 4 (4.3) Yes No X May the possibility of an accident which is different than any already evaluated in the FSAR te created? N I . C 35

• C pang Al.-l

               ,,                                                                                     , . -,n    *
                                                                                                                                !   - 1
      .. I
             , . ATTACH. MENT 1 (Continued)                                                                                         l Customer Reference No(s).

I j Westinghchse Peference No(s). (Change Control or RFQ as Applicable) WESTINGHCUSE NUCLEAR SAFETY EVALUATIC.1 CHECX LIST PAGE 2 0F 3 (4.4) Yes

• No X- Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?

(4.5) Yes X No Will the consequences of a malfunction of equip,ent

                  \

• important to safety previously evaluated in the FSAR be increased?

X (4.6) Yes No May the possibility of a malfunction of equipeent c-

• important to safety different than any already evaluated in the FSAR be created?

(4.7) Yes X No Will the margin of safety as defined in the bases to any technical specification be reduced? If the answers to any of the above questions are unknews, indicate under (5) RIMARKS - and expitin on Page 3. If the answer to any of the above questions in (4) cannot be answered in the negative, based en written safety evaluation, the change cannot te a:preved without an appiteation

                       .for license amendment submf tted to NRC pursuant to ICCFR50.SO.

(5) REMARKS: i J N. ', t *. y' (6) APPROVAL LAC,0ER ($fgnatures): [ (6.1) Prepared by (Nuclear Safety): G. E. Lang M[. , . c, 7 //28(

             .                                                                 y                t'? i    .v-  - :r--

(6.2) Coordinated with (Engineer (s): R jLp s,.yA. McIn tved (7, A7en,t/ ' 2-u-;/ (6.3) Ecordin, sting Group ~ Manager (s):  ![,y%,-sv e.10 Johnson /E/#' qwd02enisa te. 2 , t. - 4

                       .       (6.4) Nuclear Safety Group Manager:          D. G. Bevard 'MM cate: 2-/4 - 9/
                            - (6.2) R. Radclif e                          (6.3) P. K. Doshi.2 t, h p,.

ygg y1741 7/i7/3n noru is224c pace Al-2

f. ( .u wn-i  ; -

       ,        ,,    ATTACHME.'4T 1 (Continued)

Custa:wr Reference No(s). 1 f 3 Westinghcuse Reference No(s).

         ,                              .                                              (ChangeCentrolcrRFQasApplicable) e WESTINGPNSE NUCLEAR SAFETY EVALUATICN CHECK LIST PAGE 3 0F 3 The following sumarizes the justification, t,ased upon the written safety evaluatienII)      ,

for answers given in Part 8 of the Safety Evaluatien Check List: See NS-LAA-80-73

  ..        ;                                                  .

s. N 8 .

r .

 ..        I                                                                                                          -

f . 3 Reference to dccu:nent(s) containing written safety evaluation: NS-LAA-80-73 ,,

                     ./            PREPARED BY:       G. E. Lan9
                                                                               ,b k b OATE: 7- ' I l - N e

7;ca ss m e PAGE A l_-3}}