ML20236M926

Notification of 871117 & 18 Meetings W/Util & Eg&G at Site to Discuss Outstanding Questions on 2nd 10-yr Program on Inservice Testing of Pumps & Valves Previously Submitted to Util

ML20236M926
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/09/1987
From:	Dick G Office of Nuclear Reactor Regulation
To:	Calvo J Office of Nuclear Reactor Regulation
References
NUDOCS 8711130334
Download: ML20236M926 (3)

Text

.: -. ...

Docket'No. 50-313 November 9,31987 q MEMORANDUM FOR: Jose A. Calvo, Director Project Directorate - IV H Division of Reactor Pro;'ects - III, ",

IV, V and Special Pro;ects FROM: George F. Dick, Jr. , Project Manager Project Directorate IV Division of Reactor. Projects' III, IV, V and Special Projects

SUBJECT:

FORTHCOMING MEETING WITH' ARKANSAS POWER AND' LIGHT COMPANY-(AP&L) TO RESOLVE 0UTSTANDING QUESTIONS ON 2nd 10-YEAR PROGRAM ON INSERVICE.

TSTING OF PUMPS AND VALVES PREVIOUSLY TRANSMITTED 1 TO AP&L l DATE & TIME: November 17 and 18, 1987' 8:30 a.m. - 5:00 p.m. .,

1 LOCATION: Arkansas Nuclear One j Russellville, Arkansas PARTICIPANTS: NRC/NRR EGG AP&L G. Dick C. Ransom G. Woerner.

A. Masciantonio .S. Hartly S. McGregor B. Baker l s/

GeorgeF.-Dick,Jr.,ProjectManager ProjectDirectorate-IV Division of Reactor Projects -III, IV, V and Special Projects t cc: See next page l

• Meetings between NRC technical staff and licensees are open for interested 'l members of the public, petitioners, interveners, or other parties to attend'as observers pursuant to "Open Meeting Statement of NRC Staff Policy", -

43 Federal Register 28058, 6/28/78.

/PM PD4/D k:sr JCalvo/ffG 11/df/87 11/y/87

$okilS00c$$ y3 i P

h , . , .

l  !

____.l 1

j. Mr. G. Campbell l Arkansas Power & Light Company Arkansas Nuclear One, Unit 1 cc:

Mr. J. Ted Enos, Manager Nuclear Engineering and Licensing  ;

Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 Mr. James M. Levine, Director Site Nuclear Operations Arkansas Nuclear One P. O. Box 608 Russellville, Arkansas 72801 Mr. Nicholas S. Reynolds Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.

l Washington, D.C. 20036 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission P. 0. Box 2090 Russellville, Arkansas 72801 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Mr. Frank Wilson, Director Division of Environmental Health Protection Department of Health Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72201 Honorable William Abernathy County Judge of Pope County Pope County Courthouse Russellville, ,,ekansas 72801

DISTRIBUTION

Docket File _ 4 NRC PDR Local PDR PD4 Reading T. Murley/J. Sniezek F. Miraglia D. Crutchfield DR4A G. Dick W. Lanning OGC-Bethesda E. Jordan J. Partlow Receptionist J. Calvo A. Masciantonio C. Ransom, EGG S. Hartly, EGG G. Woerner S. McGregor B. Baker G.ACRS (10)

GPA/PA V. Wilson B. Kolostyak i

w '

/rt3 4 fr 5 3.

June 30, 1987 l

Docket Nos. 50-361 4 50-362 Southern California Edison Company 2244 Walnut Grove Avenue i P. O. Box 800 l Rosemead, California, 91770 Attention: M. Medford, Manager Nuclear Engineering and Licensing  ;

Gentlemen:

The review of your response to IEB 85-03, " Motor-Operated Valve Comon Mode l Failures During Plant Transients Due to Improper Switch Settings," dated May  !

19, 1986, indicates the need for additional information before the program to assure valve operability can be approved. The specific information requests 4 are included in the attachment.

The information requested in the attachment should be sent within 30 days of -

the date of this letter to: 1 Richard J. Kiessel k Division of Operational Events Assossment' l Nuclear Regulatory Commission Washington, D.C. 20555 A copy of this response.should be sent to the regional office.

Sincerely,

/s/

Dennis F. Kirsch, Director ,

Division of Reactor Safety and Projects Region V

Enclosure:

1. RAI for San Onofre 2 and 3

"'~ ~ ~~'

cc w/ enclosure: ,

B. Falkenberry

=' ^ A *^ -

. D. Kirsch L- - -

J. Melfi ]67'k55W6 % p j RV/jk N. . .

R UEST COPY REQIJEST Y' REQUEST Y RE/ UEST l t% bbPY-/ N0/ l 75E / N0 NO YES YES.-/ 0 l

/ N

'g - MELFI p - R HA PATE (IRSCH 6/10/87 6//d/87 6L?o/87 6/ 87 .

i

-Page 1lof 11 ,

REQUEST FOR ADDITIONAL INFORMATION (RAI) RE: -

Review of Responses to Action. Item e of IE Bulletin 85 Licensee: .

• Unit (s): San Onofre 2,3' '

Southern California Edison Company Date of Response: . 05-19-86 2244 Walnut Grove Avenue P. 0.: Box 800 Respondent:'

Rosemead, California 91770 M. Medford Manager (Nuclear.En Licensing) gineering and The information provided in your response-to 85-03'was found to be deficient in some areas.. 'Action: PleaseItemprovide.the e of IE Bulletin; additional' information necessary to resolve the following comments and questions:

1.

Unlisted MOVs 2HV-9340. -9350, -9360 and 9370 in discharge' lines of thel 1 safety injection tank system are shown normally open-(fail: locked);on drawings 40113A-4 and 40113B-5 for Unit 2.- If power .f s removed from the ' i motors and these MOVs are locked open, please state this in your' response. Otherwise, address the effect of assuming inadvertent -

equipment operations as required by Action ' Item a of the bulletin and.

revise attachments 2 and 3, pages 1 thru 4 of 6, of the response o,f-05-19-86 to include these valves.

Note: For Unit 3, see drawings 40113AS03-4 and '01138S03-5.

4 2.

Has water hammer determination due to valve of. pressure closure been considered in the differentials? If no, please explain.

3.

Unlisted HOVs HV-9300 and HV-9301 are shown locked open_in suction lines from the RWST to the HPSI pumps, in zones F-8 of drawings 40112A-11' (Unit 2)and40112AS03-8(Unit.3). Similarly located MOVs at other C-E:

plants are listed for inspection in accordance with bulletin requirements.

05-19-86 Please revise attachments 2 and 3=of the response of? ..

to include these _MOVs, or justify' their exclusion. As required.

by Action Item a of the. bulletin, consider the effect of inadvertent equipment operations.

4.

Please expand the proposed program for action items.b, e and 'd of-~the-bulletin to include description of a method possibly needed_to '

extrapolate pressure. valve stem thrust measured at le.ss- than, maximum differential:

g p: 1 g a (se 3 L phs ED S t '

j f' u Np,s; i

}.

e 43$b; y s a

_ __