ML17306B253

Forwards Request for Addl Info Re Review of Reload Methodology Topical Rept

ML17306B253
Person / Time
Site:	Palo Verde
Issue date:	01/26/1993
From:	Trammell C Office of Nuclear Reactor Regulation
To:	Conway W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
References
TAC-M85153, TAC-M85154, TAC-M85155, NUDOCS 9301290254
Download: ML17306B253 (6)

Text

3anaury 26, 199 Docket Nos.

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

Conway Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999

Phoenix, Arizona 85072-3999

SUBJECT:

RELOAD METHODOLOGY TOPICAL REPORT PALO VERDE NUCLEAR GENERATING STATION (TAC NOS.

H85153, M85154, AND H85155)

We have conducted a preliminary review of the Reload Analysis Methodology Report transmitted with your letter of November 25, 1992.

This review has resulted in the comments contained in the enclosure which we request you address 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, Original signed by Charles H. Trammell, Senior Project Manager Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Enclosure:

Comments cc w/enclosure:

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 Janaury 26, 1993 Docket Nos. 50-528, 50-529 and 50-530 Hr. William F.

Conway Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999

Phoenix, Arizona 85072-3999

SUBJECT:

RELOAD METHODOLOGY TOPICAL REPORT PALO VERDE NUCLEAR GENERATING STATION (TAC NOS.

M85153, M85154, AND H85155)

We have conducted a preliminary review of the Reload Analysis Methodology Report transmitted with your letter of November 25, 1992.

This review has resulted in the comments contained in the enclosure which we request you address 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:

Comments

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Charles H. Trammell, Senior Project Manager Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation cc w/enclosure:

See next page

Mr. William F.

Conway Arizona Public Service Company Palo Verde CC:

Nancy C. Loftin, Esq.

Corporate Secretary

& Counsel Arizona Public Service Company P. 0.

Box 53999, Hail Station 9068 Phoenix, Arizona 85072-3999 James A. Beoletto, Esq.

Southern California Edison Company P. 0.

Box 800

Rosemead, California 91770 Senior Resident Inspector U.S. Nuclear Regulatory Commission HC-03 Box 293-NR Buckeye, Arizona 85326 Regional Administrator, Region V

U. S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Hr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Hr. William A. Wright, Acting Director Arizona Radiation Regulatory Agency 4814 South 40 Street

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

Phoenix, Arizona 85003 Jack R.

Newman, Esq.

Newman 8 Holtzinger, P.C.

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

20036 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.

Bradley W. Jones, Esq.

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

20036

ENCLOSURE COMMENTS ON PALO VERDE RELOAD METHODS TOPICAL REPORT 1.

The topical is marked proprietary but specific proprietary information is not bracketed.

2.

Reference is made to a Boron Dilution Alarm System (BDAS) to alert the operator to a boron dilution event.

The BDAS setpoint is based on a relative fractional increase in subcritical multiplication and is evaluated during each reload analysis.

In view of the recent problems encountered with the Westinghouse Boron Dilution Mitigatian System which used the same type of input for initiation, there should be additional discussion pertaining to the acceptability of the BDAS setpoint including such items as uncertainties and inverse count rate vs. boron concentration relationship.

3.

Recently, it was determined that CE plants may be operating with non-conservative tilt values in the TS due to the fact that larger values may have been assumed in the safety analyses.

The topical report should address which transients assume an initial azimuthal tilt and what maximum value is assumed.

4.

Statistical convolution is used for the CEA ejection, locked

rotor, and inadvertent opening of a SGADV to determine the number of fuel rods in DNB.

Do any other events use convolution?

5.

Comparisons to CE results are somewhat muddled since the APS Cycle 3 calculations were done for a longer Cycle 2 cycle length than the CE calculations and beyond the actual Cycle 2 burnup.

It would seem that proper benchmarking would require identical initial conditions.

Although, for the most part, the differences between the results are small, it is difficult to determine whether the comparisons would be better or worse for identical initial conditions.

6.

Since the LOCA analysis is done by CE, is the input to the LOCA analysis supplied to CE by APS or is it generated by CE?

What effect do the differences between the APS and CE calculated parameters that are input to LOCA analysis have on LOCA results?

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