ML18033B504

Requests Response to Encl Request for Addl Info Re TVA 900806 License Amend Request to Revise Tech Specs Re Level 1 Low Reactor Pressure Vessel Water Level by 901005

ML18033B504
Person / Time
Site:	Browns Ferry
Issue date:	09/07/1990
From:	Ross T Office of Nuclear Reactor Regulation
To:	Kingsley O TENNESSEE VALLEY AUTHORITY
References
NUDOCS 9009140117
Download: ML18033B504 (6)

Text

Docket No. 50-260 September 7,

1990 Mr. Oliver D. Kingsley, Jr.

Senior Vice President, Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37401-2802

SUBJECT:

RE(VEST FOR ADDITIONAL INFORMATION - BROMNS FERRY NUCLEAR PLANT, Ul'lIT 2, PROPOSED TECklNICAL SPECIFICATION AMENDMENT (NO. 291)

REGARDING LEVEL 1 LOW REACTOR PRESSURE VESSEL (RPV)

MATER LEVEL The NRC staff reviewed Tennessee Valley Authority's (TVA) license amendment application dated August 6, 1990, which proposed to revise the Technical Specifications (TS) of Brooms Ferry, Unit 2.

Subsequently, the staff determined that additional information would be necessary for us to complete our evaluation of TVA's proposed TS revisions.

Please provide us with your response to this request for additional information, as detailed in the enclosure, as soon as possible - but no later than October 5, 1990, so that we may continue to support your schedule for restart of Unit 2.

If you have any questions, please call Mr. David H. Moran, Project Engineer at (301) 492-1326.

The reporting and/or recordkeeping requirements in this letter affect fewer than ten respondents.

Therefore, OMB clearance is not required.

S incerely, Original signed by Thierry M. Ross, Project Manager Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:

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Mr. Oliver D. Kirgsley, Jr.

CC:

V Mr. Marvin Runyon, Chairman Tennessee Valley Authority ET 12A 7A 400 West Summit Hill Drive Knoxville, Tennessee 3?902 Mr. Edward G. Wallace

Manager, Nuclear Licensing and Regulatory Affairs Tennessee Yalley Authority 5N 157B Lookout Place Chattanooga, Tennessee 37402-2801 Mr. John B. Waters, Director Tennessee Valley Authority ET 12A 9A 400 West Summit Hill Drive Knoxville, Tennessee 37902 Mr. W. F. Willis Chief Operating Officer ET 12B 16B 400 West Summit Hill Drive Knoxville, Tennessee 37902 General Counsel Tennessee Yalley Authority 400 West Summit Hill Drive ET 118 33H Knoxville, Tennessee 37902 Mr. Dwight Nunn Vice President, Nuclear Engineering Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street ChattanGGga, Tennessee 37402-2801 Dr. Mark 0. Medford Vice President and Nuclear Technical Director Tennessee Valley Authority 6N 38A Lookout Place Chattanooga, Tennessee 37402-2801 Mr. 0. J. Zeringue, Site Director Browns Ferry Nuclear Plant Tennessee Yalley Authority P. 0.

Box 2000

Decatur, Alabama 35602 Mr. P. Carier, Site Licensing Manager Browns Ferry t)uclear Plant Tennessee Valley Authority P. 0.

Box 2000

Decatur, Alabama 35602 Mr. L. W. Myers, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0. Box 2000

Decatur, Alabama 35602

Chairman, Limestone County Commission P. 0. Box 188

Athens, Alabama 35611 Claude Earl Fox, M.D.

State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.

Atlanta, Georgia 30323 Mr. Charles Patterson Senior Resident Inspector Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission Route 12, Box 637

Athens, Alabama 35611 Tennessee Yalley Authority Rockville Office 11921 Rockville Pike Suite 402 Pockvi1 le, Maryland 20852

ENCLOSURE RE(VEST FOR ADDITIONAL IhFOM/ATION OR CLARIFICATION 2

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NR. 2ll EEEII I'EE" IIAT¹ ERR=!:REACT 2

Reference:

Letter from E.

G. Mallace to NRC dated August 6, 1990 2.

Provide documentation (surveying records) for the reactor pressure vessel zero elevation.

Provide documentation (surveying records) for the following instrument elevations:

3.

LIS-3-56A-D (TS Table 3.2.A)

LIS-3-58A-D (TS Table 3.2.B Provide the following information for the above listed instruments:

4.

5.

6.

range setpoint accuracy drift (manufacture) drift from calibration data (if known) elevation at vessel nozzles used for instrument sensing, including a schematic diagram identifying area temperature and vertical distance of the sensing lines in each area for all modes of operation calculation used for determination of setpoint Briefly describe the administrative procedures for controlling changes to instrument setpoints and incorporation of these changes into surveillance procedures.

On Table 3.2.B Instrument Channel - Peactor Low 'liater Level (LS-3-58A-D) is listed twice.

Does the LS have two separate switches within each of the four instrumentsl Is there an input to the ADS from a separate switch and another separate switch for the CSS7 In Enclosure 3, "Reasons and Justification for Changes" there is the following statement:

"The allowance of instrument accuracies in the deter-mination of the actual trip setpoint provides conservative assurance that the trip function will be performed at or before reaching the analytical limit."

In this context, does performance of the "trip function" take into account intrinsic delay factors such as those associated with closure of the level instrument switch, logic relay output, main steam line valve closure, motor breaker closure, or water transport time to the reactor vessels

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