ML20197B818

Forwards RAI Re Main Steam Safety Valve Setpoint Tolerance Change.Response Requested to Be Provided within 30 Days of Date of Ltr

ML20197B818
Person / Time
Site:	Callaway
Issue date:	02/27/1998
From:	Westreich B NRC (Affiliation Not Assigned)
To:	Randolph G UNION ELECTRIC CO.
References
TAC-M99419, NUDOCS 9803120119
Download: ML20197B818 (3)

Text

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o 1 February 27, 1958 Mr. Garry L. Randolph ))

Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, Missouri 65251

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAl) REGARDING MAIN STEAM SAFETY VALVE SETPOINT TOLERANCE CHANGE (TAC NO. M99419)

Dear Mr. Randolph:

By letter dated August 8,1997, and supplemented by letters dated December 16,1997, and January 20,1998, Union Electric (UE) submitted an applicatio,1 for amendment to Faci'ity Operating License No. NFP-30 for the Callaway Plant, Unit 1. Specifically, you requested to revise technical specification tables to revise sensor errors and reduce the setpoint tolerances for the main steam line safety valves.

Ijl, The staff has reviewed your submittal and determined that further information is needed to

$ complete our review. The requested information is included as an enclosure to this letter.

h Please provide your response to the staff's RAI within 30 days of the date of this letter in order g to s ipport the staff's myiew schedule. If you have any questions rega 1ing the content of this RAI, please contact me at (301) 415-3456.

Sincerely, Original Signed By Barry C. Westreich, Proj,ect Manager Project Directorate IV-2 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation a

Docket No. 50-483 DISTRIBUTION:

Docket File ACRS l

Enclosure:

Request for Additional Information PUBLIC PDIV 2 Reading l EGA1 WJohnson, RIV g cc w/ encl: See next page WBateman PGwynn, RIV l

)

BWestreich OGC,015B18 1 EPeyton TCollins DOCUMENT NAME: CAL 99419.RAI kh OFC PDIV-2/PM PDIV-2/LA NAME' sVeir:h E@

DATE 2/h/98 2GfT98 OFFICIAL RECORD r,OPY 9803120119 980227 PDR ADOCK 05000483 P PDR

.o Mr. Garry L. Randolph -2 February 27, 1998 cc w/ encl:

Professional Nuclear Mr. Otto L. Maynard Consulting, Inc. Pret der,t and Chief Executive Officer 19041 Raines Drive Wolf Creek Nuclear Operating Corporation Derwood, Maryland 20855

• P.O. Box 411 Burlington, Kansas 66839 Gerald Chamoff, Esq. .

Thomas A. Baxter, Esq. Mr. Dan 1. Bolef, President Shaw, Pittman, Potts & Trowbridge Kay Drey, Representative 2300 N. Street, N.W. Board of Directors Coalition Washington, D.C. 20037 for the Environment 6267 Delmar Boulevard Mr.rl.D. Bono University City, Missouri 63130 Supervising Engineer Quality Assurance Regulatory Support Mr. Lee Fritz Union Electric Company Presiding Commissioner .

Post Office Box 620 Callaway County Court H:,use Fulton, Missouri 65251 10 East Fifth Street Fulton, Missouri 65151 U.S. Nuclear Regulatory Commission Resident inspector Office Mr. Alan C. Passwater, Manager 8201 e .'C Road Licensing and Fuels Steedman, Missouri 65077-1302 Union Electric Company '

Post Office Box 66149 Mr. J. V. Laux, Manager St. Louis, Missouri 63166-6149 Quality Assurance Union Eled-ic Comp ny Post Office Box 6P Fulton, Missouri 66251 Manacer- Electric Department Missoud Public Service Commission 301 W. High Post Office Box 360 i

Jefferson City, Missouri 65102 l Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mr. Ronald A. Kucera, Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, Missouri 65102 s

ie UNION ELECTRIC COMPANY CALLAWAY PLANT. UNIT 1 DOCKET NO 50-483 REQUEST FOR ADDITIONAL INFORMATION REGARDING MSSV TOLERANCE C ANGE

1. Discuss how the 1-second response time of pressurizer pressure-high trip is ensured and what licensing basis document this limit is controlled by.

2. Address the Westinghouse NSAL-94-001 and NRC IN 94-60 issues related to neutron g flux high setpoint and its relation to the number of MSSVs inoperable.

3. With regard to safety valve accumulation, it is the staffs position that either this must be accounted for as has been done in the past (3% accumulation) or a justification based on test data presented for an citemative method. An attemative method was reviewed for another plant (see Palo Verde safety evaluation dated May 16,1994) which accounts for a pressure increase resulting from appropriate delays in valve opening time. Please provide further justification of your proposed method with regard to valve accumulation.

4. Your position to not account for test instrument uncertainties of +2/-1% is inconsistent with approved methods by which instrument uncertairdies are calculated or accounted for. Please account for this uncertainty or provide further Justification for its exclusion.

5. In the FSAR, the initial assumptions are discussed with respect to RCS peak pressure.

How are they applied for the MSS peak pressure analyses and how does this ensure conservative analyses with regard to the MSS 7

6. What effect will crediting pressurizer pressure control have on the MSS peak pressure analyses?

7. The staffs RAI, dated December 9,1997, asked the licensee to provide various data to allow the staff to understand certain details of the change requestad by the licensee.

The response to the RAI did not allow this understanding.

The staff requests that the licensee provide:

(a) Reference 4, the Westinghouse methodology; (b) A copy of the previous setpoint calculation; (c) A copy of the new setpoint calculation; and (d) An explanation of any clifferences between (b) and (c).

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