ULNRC-04635, Revision to Technical Specification 3.5.5 Seal Injection Flow.

Revision to Technical Specification 3.5.5 Seal Injection Flow.

ML021070539
Person / Time
Site:	Callaway
Issue date:	04/08/2002
From:	Blosser J AmerenUE
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ULNRC-04635
Download: ML021070539 (4)

Text

Union Electric One Ameren Plaza 1901 Chouteau Avenue PO Box 66149 St. Louis, MO 63166-6149 314.621.3222 April 8, 2002 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555 Gentlemen: ULNRC-04635 WAmeren DOCKET NUMBER 50-483 UE UNION ELECTRIC COMPANY CALLAWAY PLANT REVISION TO TECHNICAL SPECIFICATION 3.5.5 "SEAL INJECTION FLOW"

Reference:

ULNRC-04583 dated December 13, 2001 In the letter referenced above, Union Electric Company transmitted an application for amendment to Facility Operating License No. NPF-30 for the Callaway Plant. During the NRC review of that amendment application, two questions arose. The attachment provides the responses to those questions.

If you have any further questions on this amendment application, please contact us.

Very truly yours, j* John D. Blosser Manager-Regulatory Affairs GGY/mlo Attachment A-tbl a subsidiaryof Ameren Corporation

STATE OF MISSOURI )

S S CITY OF ST. LOUIS )

David Shafer, of lawful age, being first duly sworn upon oath says that he is Superintendent Licensing, Regulatory Affairs, for Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

By y _ _

David Shafer f Superintendent Licensing Regulatory Affairs SUBSCRIBED and sworn to before me this day of I , 2002.

MELISSA L. ORR Notary Public - Notary Seal STATE OF MISSOURI City of St. Louis My Commission Expires: June 23, 2003

cc: M. H. Fletcher Professional Nuclear Consulting, Inc.

19041 Raines Drive Derwood, MD 20855-2432 Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack Donohew (2)- OPEN BY ADDRESSEE ONLY Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop OWFN 7E1 11555 Rockville Pike Rockville, MD 20852-2738 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 Ron Kucera Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Denny Buschbaum - TXU Comanche Peak SES Farm Road 56 P.O.Box 1002 Glen Rose, TX 76043 Pat Nugent - PG&E Mail Stop: 104/5/536 P.O. Box 56 Avila Beach, CA 93424 Mr. Scott M. Head - STPNOC Mail Code N5014 P.O. Box 289 Wadsworth, TX 77483 Scott Bauer Palo Verde Nuclear Generating Station Arizona Public Service Company Mail Station: 7636 P.O. Box 52034 Phoenix, AZ 85072-2034 Revised 11/7/01

NRC QUESTIONS

1. To show that the referenced generically approved LOCA analysis methodology applies to Callaway, provide a statement that the licensee and its vendor have ongoing processes which assure that the LOCA analysis input values for peak cladding temperature-sensitive parameters bound the as-operated plant values for these parameters.

Response

UE and Westinghouse have reload design processes in place that assure that the LOCA analysis input values that are sensitive for peak cladding temperature (PCT) bound the as-operated plant values. Under these reload design processes, critical input parameters for the LOCA analyses are identified and confirmed. The LOCA analyses employ these values using approved methodologies that produce conservative results. This assures that the PCT-sensitive parameters in the Westinghouse analyses are bounding relative to plant operation.

2. To show that the measurement uncertainties in RCS pump seal cooling flow and ECCS flow discussed in the LAR are accounted for, provide a statement that the measurements discussed in the LAR are included in the ongoing processes referred to in the previous item 1.

Response

The uncertainties associated with the development of ECCS flows are considered in the reload design processes discussed above. The reload design processes require any changes identified by UE to be evaluated by Westinghouse for impact on the current analyses of record. The LOCA methodologies require many input values (UE-controlled values that represent plant operation) to be used in developing the analyses of record. In particular, the RCP seal injection line flow curve developed for Technical Specification (TS) 3.5.5 accounts for pressure and flow measurement uncertainties. The required RCP seal injection line flow will be demonstrated by Callaway Plant surveillance procedure to meet the new TS curve.

Plant flow balance procedures also maintain the ECCS flow rates within the minimum and maximum analyzed flow rates used in the LOCA analyses. These flow balance procedures contain acceptance criteria for ECCS flow rates that account for flow measurement uncertainties.