ML20062A524
| ML20062A524 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/09/1990 |
| From: | Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9010220127 | |
| Download: ML20062A524 (4) | |
Text
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ol i
5N.157B Lookout Place 00T 091990 TVA-BFN-TS-291 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Centlement In the Matter of
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Docket No.-
50-260
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Tennessee Valley Authority
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BROWNS FERRY NUCLEAR PIANT (BFN) - TVA BFN TECHNICAL SPECIFICATION (TS)l NO.
291~- REVISION TO LEVEL 1 LOW LEVEL REACTOR PRESSURE VESSEL (RPV) WATER LEVEL The subject request for TS change was submitted August 6, 1990.:.By t
correspondence from T. M. Ross (NRC).to 0. D. Kingsley (TVA), dated.
i September 7,1990, the NRC requested additional information to complete.'their evaluation of this proposed change. The enclosure provides additional inforcation requested by NRC for the requested TS change.
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There are no commitments contained in chis submittal.
If there are any quest. ions concerning this information, pleasel telephone, Patrick P. Carier at (205) 729-3570.
Very-truly yours, TENNESSEE VALLEY AUTHORITY E. G. Wallace, Manager Nuclear Licensing and t
Regulatory Affairs-l Enclosure l
cc: See page 2 l
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- d. 44 9010220127 901009 DR ADOCK O go An Equal Opportunity Employer h6 /
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1 00T 09l1990 U.S. Nuclear Regulatory Commission ec (Enclosure):
American Nuclear Insurers--
Attention: Librarian The Exchange, Suite 245 270 Farmington Avenue Farmington, Connecticut 06032 Ms. S. C. Black, Deputy Director Project Directorate II-4 U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike-Rockville, Maryland 20852-Mr. Charles R. Christopher, Chairman Limestone County Commission P.O. Box 188 Athens, Alabama 35611 Dr. C. E. Fox 1
State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36194 Mr. J. E. Jones General Electric Company i
735 Broad Street Suite 1108 James Building Chattanooga, Tennessee 37402 NRC Resident. Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. Thierry M. Ross, Project Manager U. S. Nuclear Regulatory Commission l
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW,' Suite'2900 Atlanta, Georgia 30323 i
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ENCLOSURE-ADDITIONAL INFORMATION REQUESTED BY NRC.- TS.291k
.i Additional Information Requested
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1.
Provide documentation (surveying records) for-the reactor pressure 3vesse1L zero elevation.
i TVA Response The reactor pressure vessel zero elevation is 578'3" ms1. This elevatian;is documented on drawing 729E424, Revision C.
A copy-of this drawing has been i
made available for NRC review at the TVA office in Rockville, Maryland.
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Additional Information Requested 2.
Provide documentation-(surveying records) for the following instrument i
elevations:
LIS-3-56A-D (TS Table 3.2.A) i LIS-3-58A-D (TS-Table 3.2.B) j i
TVA Response i
The instruments listed are analog trip units (ATU). 'The elevations of t'he ATUs have no impact on the setpoints.- The elevationsloftthe associated. level'
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transmitters, LT-3-56A-D and LT-3-58A-D are documented in_the setpoint and-l scaling calculations. Typically, the instrument elevations'are measuredifrom the floor elevation at the instruments location. A copy of=these calculations has been'made available for NRC review at-the TVA office in Rockville,.
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Additional Information Requested j
3.
Provide the following information for the above listed instruments:
range setpoint accuracy drift (manufacture) drift from calibration data (if known) elevation at vessel nozzles used for instrument sensing, including-a
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schematic diagram identifying area temperature and vertical distance of the sensing lines in each area for all modes of operation calculation used for determint. tion of_setpoint
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1 Page 2 of 3-i TVA Response These instrument loops (Rosemount transmitter and ATUs) were installed during.
this outage.
Insufficient data exists to establish drift-from the calibration!
data.
Instrument sense line data in lieu of schematicidiagrams is included in j
the setpoint and scaling calculations.. The remaining information. requested is:
included.in the setpoint and scaling calculations.,A copy of these" calculations has been made available at the TVA office in Rockville,' Maryland.
Additional Information Requested 4.
Briefly describe.the administrative procedures-for controllingfchanges toi instrument setpoints and incorporation of these changes into surveillance procedures.
TVA Response Setpoint and scaling calculations are performed:to' determine'the~ appropriate instrument setpoint(s). Any changes to setpoints are then: transmitted via appropriate design-output documents to the'responsib1'e organization (s) for procedure revisions and implementation. The responsible organization (s).
revises appropriate procedure (s) and implements the setpoint change (s). After the responsible organization (s) complete the procedure' revision (s)fand~
implement the change (s), the design organization is notified of, completion ~, by.
the responsible organization (s).= When:the design organization lhas been'.
notified-of completion, the involved design-output documentiis closed.-lIflthe:
setpoint changes impact Technical Specification (TS) values,-the above!
described process is coordinated-with-a request for/IS amendment to'the NRC.
If a TS change is required, the setpoint change'and procedure: revisions ;are.
implemented after NRC approval of the amendment or?the associated component / system is considered to be inoperable until the'requestLis approved..
Additional Information Requested l
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5.
On Table 3.2.B-Instrument Channel - Reactor Low Water Level (LS-3-58A-D)
I is listed twice. Does the LS have two separate switches; within each of the four instruments? Is there an input-to-the ADS from a separate-1 switch and another separate switch-for the CSS?
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TVA Response i
The functions performed by LS-3-58A-D are' accomplished by the use of-multiplier relays controlled by the individual ATUs.
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1 Additional Information Requested
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6.; - In Enclosure 3, " Reasons and ' Justification.for Changes" thdre'is the.
l following statement:- "The' allowance of instrumentJaccuracies~!n the determination of the actual trip' set' oint provides conservative as.crance '
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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~thoseo associated with closure of the' level instrument switch : logic l relay.
L output, main stream line valve clo.ure, motor' breaker closure, or water transport time to the reactortvessel?:
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TVA Response The setpoints are established to ensure that the trip function ~is performe'd at or before reaching the analytical limit for,the process variabi'e. 'In this:
l context the-trip function is the' change of state of;the1ATU= contacts.',The L
analytical value for ' this: trip function' is' conservatively: established to j!
ensure the safety function-(i.e., valve closure, pump start, flow to vessel,1 etc.) is accomplished consistent with.the' assumptions in.the applicable s'afetyr analysis.
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