ML20057B716

Requests Addl Info on Plant Reload Analyses Amend.List of Questions Encl.Response to Questions Needed within 14 Days of Ltr Receipt

ML20057B716
Person / Time
Site:	Comanche Peak
Issue date:	09/22/1993
From:	Bergman T Office of Nuclear Reactor Regulation
To:	William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
References
TAC-M86654, TAC-M86655, NUDOCS 9309230177
Download: ML20057B716 (3)

Text

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September 22, 1993 l' . ,

Docket Nos. 50-445 and 50-446 Mr. William J. Cahill, Jr.

Group Vice President, Nuclear TU Electric Company 400 North Olive Street, L.B. 81 .

Dallas, Texas 75201 i

Dear Mr. Cahill:

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SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON COMANCHE PEAK STEAM ELECTRIC i STATION UNITS 1 AND 2, RELOAD ANALYSES LICENSE AMENDMENT (TAC NOS. i M86654 AND M86655) j During the review of Comanche Peak Steam Electric Station Units 1 and 2 l license amendment request, " Reload Analyses," submitted by letter dated l May 28, 1993, the NRC staff has determined the need for additional information. Enclosed is a list of questions. ,

l The reporting requirements contained in this letter affect fewer than ten i respondents; therefore, OMB clearance is not required under Public Law 96-511. 1 We request your response to the questions within 14 days of the receipt of this letter to enable the staff to complete its review in a timely manner. I Sincerely, Original Signed By Thomas A. Bergman, Project Manager l Project Directorate IV-2 ,

Division of Peactor Projects III/IV/V 4 Office of Nuclear Reactor Regulation

Enclosure:

DISTRIBUTION Request for Additional Docket-Filer HBalukjian Information NRC PDR SAthavale Local PDR TBergman (2) cc w/ enclosure: PDIV-2 R/F EPeyton See next page JRoe EJordan EAdensam ACRS (10)

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OFFICE PDIV-2/LA PDIV-2/PM PDIV-2/D NE (key n e e, $ Black DATE 9/Dt/93 9/p//93 9/$$/93 / / / /

con (YEMNO M MD'M) ~

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YES/NO YES/NO FILENAME: B:\RA186654 "

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S Mr.' William J. Cahill, Jr. September 22, 1993 cc w/ enclosure:

Senior Resident Inspector Jack R. Newman, Esq.

U.S. Nuclear Regulatory Commission Newman & Holtzinger P. O. Box 1029- 1615 L Street, N.W.

Granbury, Texas 76048 Suite 1000  :

i Washington, D. C. 20036 Regional Administrator, Region IV ,

U.S. Nuclear degulatory Commission Chief, Texas Bureau.of Radiation Control-

. 611 Ryan Pitt a Drive, Suite 1000 Texas Department of. Health  :

Arlington, Texas 76011 1100 West 49th Street >

Austin, Texas 78756 f Mrs. Juanita Ellis, President . "

Citizens Association for Sound Energy Honorable Dale McPherson .

1426 South Polk County Judge r Dallas, Texas 75224 P. O. Box 851  ;

Glen Rose, Texas 76043 s i Owen L. Thero, President ,

Quality Technology Company  :

P. O. Box 408  !

201 West 3rd Lebo, Kansas 66856-0408 Mr. Roger D. Walker, Manager i' Regulatory Affairs for Nuclear Engineering Organization Texas Utilities Electric Company  ;

400 North Olive Street, L.B. 81  !

Dallas, Texas ' 75201 ] ,

Texas Utilities Electric Company '

c/o Bethesda Licensing 3 Metro Center, Suite 610 Bethesda, Maryland 20814 William A. Burchette. Esq.

Counsel'for Tex-La Electric Cooperative of Texas Jorden, Schulte, & Burchette i 1025 Thomas Jefferson Street, N.W.

Washington, D.C. 20007 GDS Associates, Inc.

Suite 720 1850 Parkway Place Marietta, Georgia 30067-8237 ,

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ENCLOSURE OUESTIONS ON COMANCHE PEAK REVIEW ON REVISED REACTOR CORE SAFETY LIMITS The following questions relate to the May 28, 1993, application for amendments to the Comanche Peak Steam Electric Station (CPSES) Units 1 and 2.

1. The licensee discussed the use of different co-resident fuel assembly.

designs (page 6 of 21, Attachment 2). Provide the reference for the method that has been used for the core reload with mixed fuel for CPSES Unit 1, Cycle 4. Have all the provisions from the reference been satisfied such as that required for the analysis for the effect of stress from seismic forces between the different fuel types (Siemens and Westinghouse) .and the DNBR penalty factors required for transition cores?

2. The licensee discussed meeting the minimum measured flow requirement in, i Technical Specification (TS) 3.2.5c (page 6 of 21, Attachment 2). Will this reload incorporate low leakage core loading? Elf so, this type of ,

loading has resulted in increased hot streaming in many plants, resulting in reduced indicated RCS flow rates. What will be the effect of this reduced indicated RCS flow for CPSES Unit 1, Cycle 4? Provide the total flow rates in gpm measured from the calorimetric heat balance '

for the' current cycles for Units I and 2. Also, provide the references that approved the 1.8 percent uncertainty for the flow measurement and the 0.5 percent for the effects of lower plenum flow anomaly. ,

3. Provide the reference for the approved method used for obtaining the Overtemperature and Overpower N-16 reactor trip setpoints for obtaining ,

the total uncertainty (page 12 of 21, Attachment 2). '

4. Explain the difference between how the power is calculated using the N-16 power indication and that from the calorimetric power indication (page 11 of 21, Attachment 2). f l

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