ML13324A842

Forwards Request for Addl Info Re 860408 Investigative Rept on Water Hammer Event.Schedule for Responses to Questions Will Be Determined by Discussions W/Nrc Project Manager

ML13324A842
Person / Time
Site:	San Onofre
Issue date:	04/29/1986
From:	Dudley R Office of Nuclear Reactor Regulation
To:	Baskin K Southern California Edison Co
References
NUDOCS 8605050461
Download: ML13324A842 (7)

Text

APR ? 198 Docket No.:

50-206 Mr. Kenneth P. Baskin, Vice President Nuclear Engineering Safety and Licensing Department Southern California Edison Company 2244 Walnut Grove Avenue P.O. Box 800 Rosemead, California 91770

SUBJECT:

SAN ONOFRE, UNIT 1 The NRC staff review of your April 8, 1986 Investigative Report on the San Onofre-Unit 1 Water Hammer event is ongoing. Our review has determined that several items require further information, as per discussions in several previous telephone calls. Specific questions are provided in the enclosure to this letter.

The schedule for responses to these questions will be determined by discussions with your NRC Project Manager.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P. L.96-511.

Richard F. Dudley, Project Manager Project Directorate #1 Division of PWR Licensing-A cc:

See Next Page Office:

P AD#1 PD/PAD#1 Surname:

RDudley/tg GLear Date:

04/A,/86 04/A/86 8605050461 860429 PDR ADOCK 05000206 S

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ENCLOSURE REQUEST FOR ADDITIONA NOMTO

1. Provide schedules for the implementation isted in Section 6.5.73 Of the April 8o 1986 report.

2*

srovdetesa of all78,18 rorrective actions

2. Provide the status and schedule Of Your efforts to respond to IE Information Notice 84-90, dated December 7. 1984.

Will these efforts evaluate the containment pressure response considering the effect of Superheat due to tube bundle uncover in steamline break transients?

3. Submit for s taff review the re-analyses of Loss of Normal Feedwater and nd 6.1.2.3 Of the April 8, 1986 report.

in6.22

4.

indication of safety injection on loss of Power.

conthe new Power source for the SI annunciator auxili contact chain "backed up by an" or is ian uerriabrelay Supply (UPS)?01sita nnerpbepor b*

Is the new Power source the same Power source preventedr If not, indicate how Spurious indication is C. Is the new Power source Class 1E and diesel backed?

SrDuisre the Power sources for the UPS and their priorities. Is

5. Spurious remote indication for safeguard load sequencers.

a. Section 62.411 indicates that sequencer 1 and spare logic board were tested. Was sequencer 2 and the Plant ing tested? If not, address the acceptability of not testing this equipment

6. Reactance b

.ypass circuit breaker.

a. Will the alarms be both local and in the control room?

b. Are the alarms actuated on the conditions diesel generato breaker closed and reactance breaker closed, or some other conditions?

C. When will the openain9 procedures be modified incorporate the action to be taken in the event that this alarmtosounds?

7.

Vital~ bus 4.

a.

Descrb o wer se~

i tehe u s p S

, e h t a e

• sb r r a o e Soure? ources fo h tae is Vtallth thatw l maintinedPowerSours 4 il it b tbe Prvided as onle 01 lSiona7 Pndeend

8.

Wha ws US iZed to accoun for~ndn 1 fl 4160 volt ervotage hi h-u re l a s test? What otcbe?

tcat Was thehiso test ea 1a u applied c a b le w s t e b e e f r th h W h 5 then a

abts high po rt abS ss redt If the tes Pets a

Cale as asastpvotg

9.

U d that no maximu rf e d uotaea res*~ h grou d l-su at io ancg~ org pionag rsi ane teste t 71~~

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b 9 tst t n e -ni a ac~~~o Oldts V~us dut an e do th lower than the resist t Of a m g h P rov i d e t ore v a l v e s e - h Oprton Of the b oegon opr nemaue Of histass and rationale etado 7ns~at onvaluevi7 S ex reel tests~~~fo aC t e te t c nec e an/ rf How do thes Ptng t 4t r t hes es tst data c m a e t s f u d t s.,

f~~~h tprevi~C~

oud s -3 ad "As lf What ~~

o he t ea sts m r C a d ot e q i m Y a ' e t 11~

WhatY,, Of 4160Vt a s o pa ef r s f P r o m d o n t h e a l e t y e a n d ema t d f o r ' r e p l afeS t

i ngf 5

2.befor e t 5 What n testab e d?

Provide i cir uie on thst S t m t e h d f r ms l c e (iec ee~r t

Prro id any Oth r

fo e t b i h t O fin a f Or m n t hr i g s O uhr re or -9 EG&G E C D Survei( anc e le t i a eq1mf~tStIngp Pormfr monistem) ce eqU7P~ e t) t,

Pogram as no e 1 3,

in eg rn ade t o n h ao rn c o t h ea v n l c Iti eeenced in Seto 6a2.1e ared bte eletema d s gn change 7e~ 1 e re er toi20 a c av ine Plaeinte re71abi~6 (page 6-102 ty 0

te enhnem thetion b

l m e t e d t ee a7 we e et a d i n l l beim e n r *c 7 i y f t e e O u Che w il Powe dca toPan P l e m n t e h a t Mu 5 t h a t m e n t t o t hc e a l

~t e r im e s c r i b e n ca t e a ndila -t a

d.

15o i l o s s f

n o f

when

. Has any evaluation or analys bt r

to assess the auxiliary tran is e Performe to trend h test results Provide inomtoif

any, e

in I condto n elaiiy 1.P o i n f o r mate t iv o n,n y i t h i s r e g a r d.

n a n e i a i i y 1. W o ide p e es Vo tage value at which the insulation resistance tests were Performed for transformer C and other electricalequipment

16.

Would the 4160 volt bus sources parallell annuniciator with 10 second time delay include the diesel ge e a o s u c Wh n i Is p rl l d With the Offs te source?

g n r t r s u c h n i s P r l e e

• Is there any o

parao aeled ch aa l~e1, P

n r d eAw hen / the di e e g n ra o m y b with auxiliary A

c or s this mode of oeat lee actranseafdwold r e eselre gen Isti eo ope rae e

a pabean t

he proposed new Procedures?

18.

On Page 8-2, Item 6, "Guidance will be issued to address the reenergizato Of station auxiliar equipme using diesel

-for NRC revie When wil or On C reiw t

guidape be issued and/or submitted 19I On page 8.3, reference is made to the evaluation of the material condition of electrical e c

be suitted tusNR of the cable failure.

When will this eruto c be to mitedf caso f the abl result Of this report be eoalu ati s eva ua tt e t o f owe wil be cable and/or how the in hpaval atinrf t err mai in anbe hnldby SCE? act Of this evaluation on existing cable, if 0.The LOVATi and end remaining if so, how will fsequence iet

21.

For Pip0insid Csrlaiit

-f tthis light a single light and

a.

i Inside Containment on Feedwater Line B.

a. Did the licensee ultrasonically replaced?

inspect each weld that was not

b. Will the licensee ultrasonicall replacement line and the welds onpect eah weld in the the existing line?

e w l s c n e t n h e l c m n i e t

c. Will the licensee reacmntine to replacement line to the existing linspect the welds

d. Identify ASME Code and Addenda standard, including class, used to inspect these welds.

-4 feedwaer inndzl atonsded njon-c a to. steam generator E-183 f-Indicate size (length and depth) of flaw remaining in containment Penetration C-3C.

22.

For Piping Outside Containment on Feedwater Line B

a. Identify ASME Code and Addenda standard including class, used to inspect these welds

b. Identify size (length and depth) of all seven indications remaining in welds of these pipes.

e a n n

APR 2 1986 DISTRIBUTION:

Docket Files NRC PDR Local PDR TNovak P. Shuttleworth R. Dudley G. Lear OELD E. Jordan B. Grimes J. Partlow G. Bagchi (EB)

G. Zech (IE/VPB)

E. Merschoff (IE/VPB)

A. Chaffee (RV)

P. Narbut (RV)

ACRS (10)

PD#1 r/f PD#1 s/f