ML20216J288

Forwards Request for Addl Info Re Heat Up & Cool Down Curves & Max Allowable Power Operated Relief Valve Setpoint Curve for Cold Overpressure.Requests Response within 30 Days of Date of Ltr

ML20216J288
Person / Time
Site:	Callaway
Issue date:	03/13/1998
From:	Westreich B NRC (Affiliation Not Assigned)
To:	Randolph G UNION ELECTRIC CO.
References
TAC-M99918, NUDOCS 9803230398
Download: ML20216J288 (4)

Text

a March 130 1998 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 (RAI) REGARDING PRESSURE / TEMPERATURE LIMITS CHANGE (TAC NO. M99918)

Dear Mr. Randolph,

By letter dated October 17,1997, and supplemented by letter dated March 3,1998, Union Electric (UE) submitted an application for amendment to Facility Operating License No. NFP-30

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for the Callaway Plant, Unit 1. Specifically, you requested to revise technical specification heatup and cooldown curves and the maximum allowable power operated relief valve setpoint ,

curve for cold overpressure.

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.

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Please provide your response to the staff's RAI within 30 days of the date of this letter in order to support the staff's review schedule. If you have any questions regarding the content of this RAI, please contact me at (301) 415-3456.

l Sincerel Origk 'nal Signed By '

Barry C. Westreich, Project Manager Project Directorate IV-2 Division of Reactor Projects lil/IV j Office of Nuclear Reactor Regulation Docket No. 50-483 DISTRIBUTION:

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- Mr. Garry L. Randolph March 13, 1998 cc w/ encl:

Professional Nuclear Mr. Otto L. Maynard Consulting, Inc. President and Chief Executive Officer 19041 Raines Drive Wolf Creek Nuclear Operating Corporation Derwood, Maryland 20855 P.O. Box 411 Burlington, Kansas 66839 Gerald Charnoff, 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. H. 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 House Fulton, Missouri 65251 10 East Fifth Street Fulton, Missouri 65151 U.S. Nuclear Regulatory Commission Resident inspector Office Mr. Alan C. Passwater, Manager 8201 NRC 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 Electric Company Post Office Box 620 Fulton, Missouri 65251 Manager- Electric Department Missouri Public Service Commission 301 W. High Post Office Box 360 Jefferson City, Missouri 65102 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 UNION FI FCTRIC COMPANY Call AWAY PLANT. UNIT 1 REQUEST FOR ADDITIONAL INFORMATION REGARDING COMS SETPOINT DEVELOPMENT

. The following requests for additonal information is based on the staff's review of the Union Electric Company's March 3,1998 submittal (ULNRC-3576) related to the proposed changes to the cold overpressure mitigation system (COMS) setpoints of Callaway Plant:

1. Input assumption #8 in the March 3,1998 submittal states that the pressure uncertainty calculated by Westinghouse is 85 psi, and the temperature uncertainty calculated by Westinghouse is 16* F, and includes 14*F streaming effect. These uncertainties are different from Section 4 of WCAP-14894, which states that the heatup and cooldown curves in Figures 1 and 2 (of WCAP-14894) include margins of 10*F and 60 psi for possible instrumentation errors.

Clarify the differences and/or consistencies in the values of uncertainties discussed above by providing (a) a breakdown of each uncertainty component (such as allowances for instrument errors and RCS temperature and pressure differences between the sensor locations and the reactor vessel limiting beltline region), (b) a discussion of how these uncertainties are applied to the heatup and cooldown pressure / temperature limit curves, the design basis analyses of mass and heat input transients, and the establishment of the PORV setpoints.

2. Input Assumption item #2 states that " Reference 3 provides composite flows from the two pumps over a range of RCS pressures.... The analysis conservatively uses flow rates which were increased to 105% of the calculated flow."

a. Provide the title of " Reference 3" and provide individual mass flow rates as a function of RCS pressure for the two pumps (i.e., a centrifugal charging pump and a " normal" charging pump).

b. Confirm that the mass injection rates in Table 1 of the March 3 submittal, which indicates 100% of the NCP and CCP flows, are indeed 105% of the combined flow from both pumps.

3. Provide the PORV relieving capacities as a function of RCS pressure and valve opening, and how they are applied in the analyses for the design basis mass and heat injection transients.

4. The design basis analysis results for mass and heat injection transients are described in Tables 1 and 2, respectively.

.s '

a. Provide a comparison of the PORV setpoints, the resulting RCS peak pressures, and the pressure / temperature hmits (x 110%), with pressure and temperature uncertainties accounted for.

b. Desenbe how Table 3.

• Maximum Allowable Function Generator Setpoints,"

is derived from the results of Tables 1 and 2.

5. Provide the upper pressure limit of the COMS to maintain the integrity of the PORV piping with a discussion of how the value is selected.

6. As part of the findings from the NRC Maine Yankee Lessons Leamed Task, the staff needs to verify that, when applying codes or methodologies described in a topical report by vendors or licensees for licensing actions, the conditions or restrictions specifed in the safety evaluation report accepting the topical report are met. Therefore, it is requested that each submittal listing all restrictions and conditions specifed in the SERs for the referenced topical reports, as well as an evaluation demonstrating conformance with these restrictions and conditions. Since the COMS setpoint analysis referenced the methodologies described in WCAP-14040, Rev. 2, please list all conditions and restrictions, if any, related to the COMS setpoint methodologies in the SERs of WCAP-14040, and other referenced topical reports, if any, and provide an evaluation of their conformance.

J

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