ML20050T194

Forwards Request for Addl Info Re Auxiliary Feedwater Reliability Assessment.Response to Be Submitted by 820507

ML20050T194
Person / Time
Site:	Crystal River
Issue date:	04/01/1982
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Hancock J FLORIDA POWER CORP.
References
NUDOCS 8204140627
Download: ML20050T194 (4)

Text

,h

.:j C

'O APRIL, 01 1982 DIS W BUTION:

ORB #4 Rdg H0rnstein k

File DEisenhut EBlackwood NR SMiner OELD L PDR RIngram AE0D Docket flo. 50-302 IE ACRS-10 m

o N

A Gray File Mr. John A. Ilancock l'.ECEi!VCD 3 Vice President, iluclear Operations P

M 0 81992*

nrecmn,ma 'i Florida Power Corporation ATTH: linnager, fluclear Licensing 3

" ff" "

P. O. Box 14042, fi. A.C. H-2 St. Petersburg, Florida 33733 y

M I

SUBJECT:

CRYSTAL RIVER UllIT 110. 3 AUXILIARY (E!!ECGETICY) FEEDWATER RELIABILITY ASSESSMEllT Fron our review of the infomation you provided with regard to Crystal River Unit lio. 3 Auxiliary (Emergency) Feedwater Reliability Assessnent we find that additional infomation is required.. The infomation required is outlined intthe enclosure.

In order to expedite our review schedule, this infomation requirement was provided in draft form to your staff over one month ago. To date we have received some of the infomation fron your staff but it has not been sufficient to allow our consultants to pmceed with the review. Therefore in order' to not delay our review further we mquest that you provide your response to this request for additional infomation by May 7,1982.

If you cannot meet this date, please provide your alternative schedule within seven days fmm receipt of this letter.

The reporting and/or mcordkeeping requimnents contained in this letter affect fewer than ten mspondents; therefore, Om clearance is not required under P.L.96-511.

Sincerely, 302I0101 SIGUED M X20hn F. STOM' John F. 3tolz, Chief Operating Reactors Branch #4 Division of Licensing

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page 8284140627 820401 PDR ADOCK 05000302 P

PDR

.O. RB#.4: DL C

4:DL omcep g

...,..c......

su m me> SMj.n.erf.c',,,,,

f E!./ / 82

,JS,to,/$,

4../................

oue>

Nac ronu sie oo.aos Nacu cao OFFIClAL RECORD COPY usa m ini-sa no

50-302 4

Crystal River Unit Noe 3 Florida Power C@rporation cc w/ enclosure (s):

Mr. S. A. Brandimore Florida Power Corporation Mr. Robert B. Borsum Vice President and General Counsel Babcock & Wilcox P. O. Box 14042 Nuclear Power Generation Division St. Petersburg, Florida 33733 Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. Wilbur Langely, Chairman Board of County Commissioners Mr. Tom Stetka Resident Inspector Citrus County U.S. Nuclear Regulatory Commission Iverness, Florida 36250 Routa #3, Box 717 Crystal River, Florida 32629 Regional Radiation Representative Mr. T. C. Lutkahaus EPA Region IV Nuclear Plant iianager 345 Courtland Street, N.E.

Florida Power Corporation Atlanta, Georgia 30308 P. O. Box 219 Crystal River, Florida 32629 Bureau of Intergovernmental Relations 660 Apalachee Parkway Crystal River Public Library Tallahassee, Florida 32304 668 N. W. First Avenue Crystal River, Florida 32629 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission, Rcgion II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 l

Enclosure b

CRYSTAL RIVER UNIT NO. 3 AUXILIARY (EMERGENCY) FEEDWATER RELIABILITY ASSESSMENT REQUEST FOR ADDITIONAL INFORfiATION 1.

The results are not presented in a manner that lends itself to a "NUREG-0611-type" compariscn.

For example, unavailability given LOOP _ is not tabulated.

LOOP appears as a basic event on the fault tree; was this entered as the probability of LOOP given LMFW? How was this handled?

2.

A narrative description of cut sets was provided, but no quantitative details were given. What were the contributions from the dominant cut sets?

3.

Failure data were not given. What are they?

4 What probabilities were assigned to failure events on the fault trees?

5.

Regarding fault tree events EFV3ZZLC and EFV4ZZLC, which refer to valves left closed after maintenance:

a) Are these the only valves which are closed for pump maintenance?

b)

Is the position of these valves indicated in the control room?

c) Are these maintenance acts staggered?

6.

Regarding valves EFV33, EFV14 EFV32, EFV11:

The drawing indicates that these are normally open, but the fault tree (EFW INITIATE) contains events in which these " fail closed." Is this because the logic requires them to close and subsequently reopen? Or should the event be considered a plugging event? Is there ever a flow test to verify that they are open?

7.

Regarding stop check valves EFV-7 and EFV-8:

These valves have events " spuriously closes" on the fault tree.

Is this the same as plugging, or does this refer to the valves being actively closed?

If it is the latter, is this an operator or maintenance error?

Under what circumstances (especially testing or maintenance) are these valves supposed to be closed? Is there a flow test to verify that they are open?

Is their status indicated in the control room?

8.

Maintenance on valves does not appear on the fault tree. NUREG-0611 suggests that maintenance on valves should be assessed (Refer to Table III-2 of NUREG-0611).

For example, is there a reason not to assess maintenance on the steam admission valve (ASV5) by analogy to that assessed in WASH-1400 (Table II 5-9 and page II-107)?

L r* 9.

Previous NRC comment expressed concern over a single valve in the cooling water supply to EFP-1. Was this remedied? What are the contributors to the unavailability of cooling water to EFP-1?

10. Are there single failures in the Vector logic that can isolate both discharge paths from a given pump? Example: Channel D logic can isolate both paths from EFP-1. Are there failures (E.G. power failures) in channel D that isolate both paths?

11.

Under what conditions do the EFWS pumps trip?

(E.G. Loss of suction? High discharge pressure?)

If recirculation is not available, are the pumps damaged, or do they trip?

I

.,m s

-