ML19331D946

Forwards Special Low Power Tests Safety Evaluation, & Draft Startup Test Procedures, Cooldown Capability of Charging & Letdown Sys, Natural Circulation, & Forced Circulation Cooldown.

ML19331D946
Person / Time
Site:	Farley
Issue date:	09/02/1980
From:	Clayton F ALABAMA POWER CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML19331D947	List: ML19331D946 ML19331D948 ML19331D949 ML19331D950 ML19331D951 ML19331D952 ML19331D953
References
NUDOCS 8009040386
Download: ML19331D946 (7)

Text

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Alab :m; Power Compan 600 North 18th Street Post Office Box 2641 THIS DOCUMENT CONTAINS e-- '* Birmengham Alabama 35 !91 Telepnene 205 250-1000 POOR QUALITY PAGES .

F. L. CLAYTON, JR. b Senior Vice President Alabama Power the southem erectic 5ys:em September 2, 1980 Docket No. 50-364 Mr. Darrell G. Eisenhut, Director l Division of Licensing Office of Nuclear Reactor Regulation l U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Eisenhut:

Augmented Low-Power Startup Test Program Joseoh M. Farley Nuclear Plant - Unit 2 Enclosed for your review are the following Alabama Power Company I Farley Nuclear Plant Unit 2 Special Low-Pcwer Startup Test Procedures  !

along with the corresponding Westinghouse Safety Evaluation Report:

! APC0 Test Number Title 501-7-001 Cooldown Capability of the Charging and Letdown System 501-7-002 Natural Circulation 501-7-003 Natural Circulation with Simulated '

Loss of Power Conditions 501-7-004 Effect of Steam Generator Secondary Side Isolation on Natural Circulation 501-7-005 Forced Circulation Cooldown l Test Numbers 501-7-001 through 501-7-005 incorporate tests 1-7 and 9a.

Test 9b is presently under development and will be forwarded prior to I receipt of Full Power license. Test 9b will not be perfonned until completion of the power ascension program and the vendor NSSS acceptance test.

If you have any questions, please advise.

Very trul 'yoDrs, b '[

Q. L. Clayton, Jr.

RWS:de I Enclosures cc's shown on page 2 80 0 9040 386a  ;

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Mr. Darrell G. Eisenhut, Director September 2, 1980 -

U. S. Nuclear Regulatory Comission Page 2 i-i cc: Mr. R. A. Thomas Mr. G. F. Trowbridge i

Mr. L. L. Kintner  ;

Mr. W. H.- Bradford i

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bc: Mr. R. P. Mcdonald Mr. H. O. Thrash Mr. O. D. Kingsley, Jr.

Mr. J. A. Moonry Mr. K. W. McCracken Mr. R. E. Hollands -

Mr. O. Batum Mr. J. R. Crane Mr. A. A. Vizzi I

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Electric Corporation Divisions  !

l 5:d55 H. O. T. , . _- . - _ P.ns:1gn Per.5Jvanta 15230 R.P.M.

August 28, 1980 Mr. O. Batum, Manager Nuclear Safety & Licensing S.O. APR-4705 j .....

Southern Ccmpany Services, Inc.

REF: a) APCo Letter FMP-80-0950, 6/17/80 Bi ing m 35202

Dear Mr. Batum:

JOSEPH M. FARLEY NUCLEAR PLANT .

APR SER for Natural Circulation Special Tests Attached is the Safety Evaluation Report-(SER) for the performance of the natural circulation "special tests" at the Joseph M. Farley Nuclear Plant, Unit 2. This safety evaluation is based on the Farley, Unit 2 special test procedures, received via Reference a), including Westinghouse ccmments resulting

- from the review of these test procedures and previous Westinghouse SER's for other NT0L plants. Consistent with the Westinghouse position and since Farley, Unit 2 will not perform test 8, and 9B may be perfonned using decay heat, tests 8 and 9B have not been included in this evaluation.

If you have any questions pursuant to the above, please contact the undersigned.

Sincerely, L. E. Conway/je J.L.Vota,danag)er Attachment Southern Co. any Projects cc: 0. Batum ll, lA o12 u .

A. A. Vizzi il g  %.

F. E. Ehrensoerger ll 4' .O R. P. Mc0ccaid IL O '3 V. C. Valekis IL $ 3, W. G. Hairston IL N

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NS-QA-1 1 7 ,

ATTACHMENT 1 -

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Castame Reference No(s).

,~ ~3, Westinghouse Reference Mo(s).

(Change Control or RFQ as Appifcable)

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ME5n NGHOUSE i

- 1 IslCLEAR SAFETT EVALUATICN CHECK LIST i

PAGE 10F 3 I

(1) NUCLEARPUUIT(S) Farley Unit 2

.\ . l APR Special Test Program (2) CHECK LIST APPU CABLE Tra (Subject of Change) .

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(3) The written safety evaluation of' the revised procedure, design change or modificatich required by 10CFR50.53 has been prepared to the extant required and is attached.

If a safety evaluation is not required or is incompleta for any reason, explain on

. Page 3. .

Parts A and 5 of'this safety Evaluation Chect List are to be completed only on the basis of the safety evaluation performed.

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. CM cK LIST - PART A l (3.1) Yes no X A change to the plant as described in the FSART (3.2) Yes No X A change to procedures as described in the FSART A test or experiment not described in the FSAR?

(4.3) Yes X No (3.4) Yes X No A change to the plant technical specifications (Appendix A to the Operating License)?

(4) CHECK LIST - PART 5 (Justification for Part 8 answers must be included on Page 3.)

(4.1) Yes No X will the probability of an accident previously ,

i evaluated in the FSAR be increased?

• X Will the consequences of an accident previously

- (4.2) Yes No avaluated in the FSAR be increased?

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(4.3) Yes No X May the possibility of an accident which is different than any already evaluated in the FSAR be created?

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,' NS-QA-1 0 e .

ATTACHMENT 1 (Continued) l Customer Reference Mo(:).

. 1 Westinghouse Refertnce h1(s).  ? E-(Change Control or RFQ at Applicable) j IE3TINGHOUSE mc ras SAFETY EVAWATION CHECK LIST 9 AGE 2 0F 3 (4.4) Yes no X- Will the probability of a malfunction of equipment fsportant to safety prwfously evaluated in the F5AR be increased?

'(4.5) Yes X to Will the consequences of a malfunction of equipment

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

v(4.5) Yes ,, _ No X May the possibility of a malfunction of equipment

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important to safety different than any already evaluated in the F5AA be created? "

(4.7) Yes X Ao Will the margin of safety as defined in the' bases to any tachatcal specification be reduced?

If the answers to any of the above questions are unkneen, todicata unde.r (5) REMut3 -

and explain on Page 3.

If the answer to any of the above questions fn (4) cannot be answered in the negative, based'as writtan safety evaluation, the change cannot be approved wit %.:t an application -

.for license mondeant subsittad' to MAC pursuant to 10CFR50.SO.

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(5) RE M ut3: ,

N. $

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t (8) APPROVAL UQOS (Signatures):

(6.1) Prepared by (Nuclear Safety):- G. E. Lang. ,h.hef g,,,. S'-MO (s.2) coordinated with (Engineer (s): B. A. McIndNYNnentW:M MO ,

(6.3) toordinating Group hneger(s):W. J. Johns . A. Dzen M h N #

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. (6.4) Nuclear Safety Group Manager: D. G. Revard Mk8 Date: 7-X -TC (6.2) #su'go (6.3) b M' R. Radcliffe P. K. Coshi -

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NS-QA-1 0 ATTACHMENT 1 (Continued) .

Customer Referenca .'fo(s).

idestinghouse Reference Mo(s).

(Change Control or RFQ as Applicable) ,

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. 'l1 idESTINGHCUSE .

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!EICLEAR SAFETY EVALUATICM CHECX LIST )

PAGE 3 0F 3 l

The following summarizes ?Sa Justification, based upon the written safety evaluationb.

for answers given in Part S of the Safet/ Evaluation Check List:

See NS-LAA-80-73

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$Ukforence to docuent(s) containing writtan safety evaluatics:

.NS-LAA-80-73

./ PREPAaro sv: r, e- Ianc N[ OATE: b'2b' bO I

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