ML19339A500
| ML19339A500 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/14/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-80-06, IEB-80-6, NUDOCS 8011040140 | |
| Download: ML19339A500 (4) | |
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T76 TENNESSEE VALLEY AUTHORITY-g CHATTANOOGA, TENNESSEE 374o1 400 Chestnut Street Tower II October 14, 1980 Mr. James P. O'Reilly, Director
.' Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303
Dear !*r. O'Reilly:
OFF OF7NSPECTION AND ENFC'. CEMENT BULLETIN 80 RII:JPO
-259, -260, -2963 Enclosed is progress report number 5 for work related to IE Bulletin 80-06 for the Browns Ferry Nuclear Plant. This report reflects the progress of work to date since our letter dated September 10, 1980, from me to you. If you have any questions regarding this matter, please get in touch with Jim Domer at FTS 857-2014.
Very truly yours, TENNESSEE VALLEY AUTHORITY
. M. Mills, Manager Nuclear Regulation and Safety Subscribed agd sworn o
fore me this [Iday of [)P 1980.
OJLh!Yl-L Motary Public My Commission Expires Enclosure ec: Office of Inspection and Enforcement (Enclosure)
U.S. Nuclear Regulatory Commission
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Division of Reactor Operations Inspection Washington, DC 20555 t
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EFCLOSURE IE BULLETI?! 80-06 PROGRESS REPORT 110. 5 BRO'41S FERRY !!UCLEAR PLANT UNITS 1_ a (DOCKET NOS. 50-259,'-260, -2n6) '
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1 The results of the drawing review for Browns Ferry Nuclear Plant, completed since our last transmittal, are as follows.
A.
Automatic Blowdown System The ESF signals originating f rom the blowdown system are tabulated below:
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Drywell High Pressure
. PS-10-100A, B, C, and D Reactor Vessel Low-Water Level LIS-2-3-72A, B LIS-2-3-79A, B LIS-2-3-83A, B The ESF signals identified from schematics as originating from the automatic blowdown system have been verified in response to IE Bulletin No. 30-06.
The automatic relief valves could change position upon the reset of an ESF signal.
Two minutes af ter receipt of high drywell pressure, low reactor vessel water level, and either two core spray pumps running or one RHR pump running, the automatic relief valves will open. Resetting these signals will cause the valves to close.
Logic bus A accident signals are reset by handswitches 2E-S3A and 2E-S 2A.
Logic bus B accident signals are reset by handswitches 2E-S3B and 2E-S2B.
We have determined that these devices changing state do not constitute a safety problem.
B.
Standby Liquid Control System We have determined that there are no ESF actuation signals associated with this system.
C.
Standby Cas Treatment The ESF signals originating from the primary containment isolation system which interface with the SBCT system are tabulated below.
ESF Signal Device Number Refueling Zone Vent Exh Rad Trip 17-52A, B Reactor Vessel Low-Water Level 2-3-101A, B, C, and D N,.
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l The ESF signals identified from our schematics as interfacing with the standby gas. treatment have been verified in response to IE Bulletin No. 80-06. The devices actuated by these signals re=ain in their emergency position upon reset of the ESF actuation signal.
D.
Miscellaneous Systems We have reviewed the following miscellaneous systems and have found that none generate or receive an ESF actuation signal not covered by previous system reviews.
Reactor Vessel Temperature-Monitoring Nuclear Boiler Process Instrumentation Jet Pump Instrumentation Reactor Recirculation Recirculation Pump Trip Reactor Manual Control Rod Position Indication Feedwater Control Startup Range Neutron Monitoring Power Range Neutron Monitoring Area Radiation Monitoring Radwaste Building Radiation Monitoring Steam Leak Detection Control Rod Drive Hydraulic Instrumentation Radwaste Disposal Reactor Water Cleanup Fuel Pool Cooling and Cleanup Primary Containment Instrumentation Off-Gas Emergency Equipment Cooling Water Reactor Building Closed Cooling Water Solid Waste Packaging The f ollowing ESF signals generated by the process radiation monitoring i
have been previously analyzed as part of the primary containment isolation system.
ESF Signal Device Number Main Steam Line High Radiation 17-251A, B, C, and D Reactor Zone Vent Exhaust Radiation 17-452A and B Refueling Zone Vent Exhaust Radiation 17-458A and B All ESF signals actuating equipnent in the. residual heat removal service water system will be tabulated as part of the diesel generator. system.
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