ML17310B223

Forwards Request for Addl Info to Continue Staff Review of Licensee 940218 Request for Amend to Change Sf Pool Configuration

ML17310B223
Person / Time
Site:	Palo Verde
Issue date:	04/13/1994
From:	Linh Tran Office of Nuclear Reactor Regulation
To:	Conway W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
References
TAC-M88992, TAC-M88993, NUDOCS 9404190348
Download: ML17310B223 (8)

Text

t Docket Nos.

50-528, 50-529 and 50-530 Hr. William F.

Conway Executive Vice President, Nuclear Arizona Public Service Company P.O.

Box 53999

Phoenix, Arizona 85072-3999

Dear Hr. Conway:

April 13, 1994

SUBJECT:

SPENT FUEL POOL HODIFICATION PALO VERDE NUCLEAR GENERATING STATION (TAC NOS.

H88992, H88991, AND H88993) r In reviewing your request for amendment dated February 18, 1994, related to changing the spent fuel pool configuration, we find that the additional information identified in the enclosure is needed to continue our review.

We request that you respond to the additional information within 60 days of your receipt of this letter.

This request for information affects fewer than 10 respondents.

Therefore, it is not subject to Office of Hanagement and Budget review under Pub.

L.96-511.

tI Please contact us should you have any questions regarding this request.

Sincerely, Original signed by:

Linh N. Tran, Project Hanager Project Directorate IV-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional Information cc w/enclosure:

See next page DISTRIBUTION Docket File, (P1-22)

NRC 5 Local PDRs PDIV-3 R/F JRoe EAdensam TQuay DFoster-Curseen LTran BHolian OGC, (15818)

ACRS (10)

LKopp, (8E23)

KPerkins, RIV/WCFO OFFICE LA PDIV-3

~

PH/PDI V-3 PH/PD IV-3 D/PDIV-3 IIAME DFoster-Curseen LTran:mk BHol ian~

TQuay 4

I g DATE Cga>

ga

/ I~ /~4 j L$ /94

/ I'5 /94 OFFICIAL RECORD COPY/

F ILENAHE: A: iPV88992. SFP

+404>903 05000528 48 940413 PDR ADOCK PDR P

mph'g gP)gR ~@

l 4

I J

g4

~gA A@00

~c~

P

+

O~

tp nO I

L Cy

+n

~O

~>>*<<+

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-000I April 13, 1994 Docket Nos.

50-528, 50-529 and 50-530 Mr. William F.

Conway Executive Vice President, Nuclear Arizona Public Service Company P.O.

Box 53999

Phoenix, Arizona 85072-3999

SUBJECT:

SPENT FUEL POOL MODIFICATION PAL'0 VERDE NUCLEAR GENERATING STATION (TAC NOS.

M88992, M88991, AND M88993)

In reviewing your request for amendment dated February 18, 1994, related to changing the spent fuel pool configuration, we find that the additional information identified in the enclosure is needed to continue our review.

We request that you respond to the additional information within 60 days of your receipt of this letter.

This request for information affects fewer than 10 respondents.

Therefore, it is not subject to Office of Management and Budget review under Pub.

L.96-511.

Please contact us should you have any questions regarding this request.

Sincerely,

Enclosure:

Request for Additional Information cc w/enclosure:

See next page Linh N. Tran, Project Manager Project Directorate IV-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

l'I

Mr. William F.

Conway Arizona Public Service Company Palo Verde CC:

Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street

Phoenix, Arizona 85007 James A. Beoletto, Esq.

Southern California Edison Company P. 0.

Box 800

Rosemead, California 91770 Senior Resident Inspector Palo Verde Nuclear Generating Station 5951 S. Wintersburg Road

Tonopah, Arizona 85354-7537 Regional Administrator, Region IV U. S. Nuclear Regulatory Commission Harris Tower

& Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street

Phoenix, Arizona 85040 Chairman Maricopa County Board of Supervisors 111 South Third Avenue

Phoenix, Arizona 85003 Jack R.

Newman, Esq.

Newman

& Holtzinger, P.C.

1615 L Street, N.W., Suite 1000 Washington, D.C.

20036 Mr. Curtis Hoskins Executive Vice President and Chief Operating Officer Palo Verde Services 2025 N. 3rd Street, Suite 220

Phoenix, Arizona 85004 Roy P.

Lessey, Jr.,

Esq.

Akin, Gump, Strauss, Hauer and Feld El Paso Electric Company 1333 New Hampshire Ave., Suite 400 Washington, D.C.

20036 Ms. Angela K. Krainik, Manager Nuclear Licensing Arizona Public Service Company P. 0.

Box 52034

Phoenix, Arizona 85072-2034

L

~

ENCLOSURE RE VEST FOR ADDITIONAL INFORMATION PALO VERDE SPENT FUEL POOL MODIFICATION PALO VERDE NUCLEAR GENERATING STATION 1.

Provide the name of the organization that performed the criticality calculations?

2.

What organization performed the qualification of the analytical methods?

3.

In view of the previous discrepancies discovered in the analysis of the Millstone 2 spent fuel pool, discuss the acceptability of the use of these methods (CEPAK code) for the criticality analysis for Palo Verde.

4.

In Section

3. 1 of your submittal, you referenced Table 5-1 that contains the Assembly Burnup-Initial Enrichment data; please provide this table.

5.

Provide a discussion on how the uncertainty in the depletion calculations was determined and included in the analysis?

6.

On page 7 of 9 of the submittal, please clarify the minimum monolith thickness uncertainty?

7.

Provide the range of temperature variation that was used in the uncertainty analysis?

8.

The proposed new wording of TS 5.6. 1. l.b should be between "adjacent storage cell locations" rather than "adjacent storage rack locations."

If you agree, provide a revised TS page in your response.

9.

Since TS 5.6. 1.2 was only applicable for the first core loading, provide a discussion as to why it has not been replaced by a TS representative of the new (unirradiated) dry storage

racks, which have been analyzed for up to 4.30 weight percent U-235 assemblies?

10. Since the criticality analysis was performed only for initial assembly enrichments up to 4.30 weight percent, TS Figure 5.6-1 should only extend to 4.30 weight percent instead of the 5.0 weight percent upper limit shown.

11. Since there are many individual fuel rod distributions that could give a

radially averaged enrichment of 4.30 weight percent U-235 but that could result in different storage rack reactivities, discuss why your calculations are considered to be bounding.

~

~

sc 4

J