ML20011B140
| ML20011B140 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/12/1981 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 8112040263 | |
| Download: ML20011B140 (4) | |
Text
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y DISTRIBUTION NOV 12 1981 Docket File NSIC LB#4 r/f TIC DEisenhut TERA EAdensam ACRS (16)
CStahle Docket Nos.:
50-327/328 MDuncan RTedesco SHanauer RVollmer Mr. H. G. Parris 7ua73ey j,473qgz, Manager of Power RMattson Tennessee Valley Authority RHartfield, MPA 500A Chestnut Street, Tower II 0 ELD Chattanooga, Tennessee 37401 OIE (3) bec: L/PDR
Dear Mr. Parris:
NRC/PDR
Subject:
Request for Infomation on Sequoyah Fire Protection Enclosed are requests for additional infomation on fire protection that are based on our review of your October 1,1981, report. This information was also discussed in our October 27, 1981, meeting concerning differences in the Sequoyah plant design and the requirements of certain sections in 10 CFR Part 50, Appendix R.
Your responses are requested by December 15, 1981.
Sincerely, Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
As stated s of7r cc:
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SEQUOYAH Mc. H. G. Parris Manager of Power Tenne:se Valley Authority 50'~d. Chestnut Street, Tower II Chattanooga, Tennessee 37401 cc: Herbert S. Sanger, J r., Esq.
General Counsel Tennessee Valley Authority 400 Commerce Avenue E 11B 33 Knoxville, Tennessee 37902 Mr. H. N. Culver Tennessee Valley Authority 400 Ccmmerce Avenue, 249A HE3 Knoxville, Tennessee 37902 Mr. Bob Faas
'destinghouse Electric Corp.
P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. Mark Burzynski Tennessee Valley Authority 400 Chestnut Street, Tower II Chattanooga, Tennessee 37401 Mr. J. F. Cox Tennessee Valley Authority 400 Commerce Avenue, L'10Cl31C Knoxville, Tennessee 37902 Resident Inspector /Sequoyah NPS c/o U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379
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- REQUEST FOR ADDITIONAL INFORMATION SEQUOYAH NUCLEAR PLANT 1 & 2 SAFE 4
SHUTDOWN IN THE EVENT OF FIRE i
AUXILIARY SYSTEMS BRANCH j
1.
The safe shutdown logic diagram '(Figure 1-1) of the Sequoyah safe shutdown a
submittal dated October 1,1981 indicates that credit is taken-for the
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sse of automatic control functions to achieve and maintain hot shutdown conditions.
During the meeting 10/27/81,-the applicant indicates that all automatic control logic may be lost in the event of a fire in the auxiliary instrument room. Please provide a discussion of how hot shut-down will be achieved and maintained in the event of a fire in the auxiliary instrument room, or any other area in which automatic functions j
can be rendered inoperable. This discussion should address the use of i
alternate instrumentation and controls methods, and all systems to which 4
automatic function or control will be-disabled, a
1 2.
Provide a discussion of the auxiliary control room (ACR) with respect to-l electrical isolation from the main control room (MCR), dedicated instrumen-4 tation which will monitor required system parameters (i.e., pressure, temperature, tank levels), and manual actions required to transfer control from the MCR to the ACR.
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3.
Provide a list of system parameters which must be monitored to assure proper i
plant conditions during hot shutdown and cold shutdown operation. Provide a list of instrumentation / alarms which will monitor these system parameters and t-component functions in the event of fire (e.g., pressurizer pressure indicator, f
cold leg / hot leg temperature, steam generator. pressure and level, pump running i
indicators, condensate storage tank level). Verify that the applicable indica-tors are available in the MCR, ACR and other remote shutdown boards.
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4.
In many instances, one control / actuation signal will cause the actuation of several functional components. Verify that the depressurization of the primary side via interfacing system will not occur due to the actua-tion of system components resulting from the fire induced generation of spurious signals from associated circuitry. Your discussion should include the means of preventing RHR isolation valve actuation, uncontrolled letdown, pressurizer PORV actuation, or operation of any valve or component which would prevent the system (s) from performing its functional objectives.
5.
Verify that procedurcs which describe tasks that are to be performed to effect the shutdown method have been developed and are available to appropriate plant personnel. Also, demonstrate that the manpower required to perform the shutdown functions in accordance with your procedures, as well as to provide fire brigade members to fight the fire is available as required by the fire brigade technical specifications.
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