ML20002B716
| ML20002B716 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/03/1980 |
| 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 8012220595 | |
| Download: ML20002B716 (6) | |
Text
{{#Wiki_filter:e [' TENNESSEE VALLEY AUTHORITY J [/(2_ CH ATTANOOG A. TENNESSEE 37401 ( , 400 Chestnut Street Tower II. -
..[0 ud:;
.. :> *n <z .
December 3, 1980 1, . .. s
$ to 'M 31 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 Mr. O'Reilly:
OFEICE-OF ~ INSPECTION _ AND ENFORCEMENT BULLETIN 80 RII:JPO g-259,-260,_-2952 The drawing review for the sub,]ect btilletin has been completed. The results of this review not previously reported are included in Enclosure 1. Enclosure 2 provides a list of those devices to be tested, and a schedule for performing this testing. If you have any questions regarding this matter, please get in touch with Jim Domer at FTS 857-2014. Very truly yours, j TENNESSEE VALLEY AUTHORITY 1 l L. b. Mills, nager Nuclear Regulation and Safety Subscribj;d d sworn to before me this O1 day of I M
- 1980.
(LLL b - 6 Notary Public My Commission Expires , Enclosures cc: Office of Inspection and Enforcement (Enclosures) U.S. Nuclear Regulatory Commission Division of Reactor Operations Inspection Washington, DC 20555
$012220 An Eaual C c:crturit- E r.al::ycr
c' . ENCLOSURE 1 1.0 Diesel Generator Controls The ESF signals which actuate the diesel generator controls originate in the core spray system and are listed below: Interposing Relays to ( ESF Signal Device No. Diesel Generator Controls Drywell High Pressure PS-2-10-101A 14A-K11A l and -101C 14A-L35A l Reactor Vessel Low LIS-2-3-72A 14A-K11A Water Level LITS-2-3-79 A 14A-K35A Reactor Pressure Low PS-2-3-52A and 14A-K11A
-52C 14A-K35A Drywell High Pressure PS-2-10-101B 14A-K11B and -101D 14 A-K35B l Reactor Vessel Low LIS-2-3-72B 14A-K11B .
l Water Level LITS-2-3-79B 14A-K35B ! Reactor Pressure Low PS-2-3-52B and 14A-K11B
-52D 14A-K35B The diesel generator (s) can change state under certain conditions l on reset of the ESF signals. TVA is analyzing the effect of these devices changing state and expects to transmit the results of these analyses on or before January 9, 1981.
2.0 480V Load-Shed Logic ! The ESF signals which actuate the 480V load-shed logic originate in the core spray system and are listed below: Interposing Relays to ESF Signal Device No. 480V Load-Shed Logic Drywell High Pressure PS-2-10-101A and 14A-K34A
-101C Reactor Vessel Low LIS-2-3 -72 A, 14A-K34A Water Level LITS-2-3-79A Reactor Pressure Low PS-2-3-52A and C 14A-K34A 1 Drywell High Pressure PS-2-10-101B and 14A-K34B
-101D Reactor Vessel Low LIS-2-3-72B 14A-K34B Water Level LITS-2-3-79B a.' actor Pressure Low PS-2-3-52B and D 14A-K34B l
,6 The 480V load-shed logic operates to shutoff various non-safety-related and safety-related devices powered from the 480V shutdown power system upon receipt of the ESF signal and a' signal indicating that one or more diesel generators are connected to the respective 4160V shutdown board. Some devices are reenergized after a time delay, some devices are reenergized upon reset of the ESF signal, and some must be manually reenergized. TVA is analyzing the effect of these devices changing state and expects to transmit the results of these analyzes on or before January 9,1981. 3.0 Residual Heat Remcval Service Water System The ESF signals which automatically start each RHR service water pump are the same signals that actuate the diesel generator controls. Upon receipt of an ESF signal, each RHR service water pump starts after 28 seconds if offsite power is available, or after 14 seconds if the diesel generator is running. Each pump must be manually tripped following reset of the ESF signal. Therefore, this does not violate the criteria established by Bulletin 80-06.
--m --
, =w. - -
. ENCLOSURE 2 Devices to be Tested During Unit Operation The following list consists of those devices that could be tested on each unit with the unit in operation without violating the plant technical specifications or taking unnecessary or unwarranted actions which could possibly result in a unit shutdown. Device Residual Heat Removal System Radwaste System 10-18 (FCV-74-48) 20-82 (FCV-77-2A) 10-32 (FCV-74-78) 20-83 (FCV-77-2B) 10-17 (FCV-74-47 20-94 (FCV-77-15A) 10-198A (FCV-74-{m2) 20-95 (FCV-77-15B)
~
10-33 (FCV-74-77). 10-198B( FCV-74-103) Ventilation System 10-195A (FCV-74-119) 10-195B (FCV-74-120) FSV-31-150B 10-16A (FCV-74-7) Emergency Press Fan A 10-16B (FCV-74-30) Emergency Press Fan B 10-26A (FCV-74-60) 10-26B (FCV-74-74) Standby Gas Treatment (SBGT) System 10-31A (FCV-74-61) 10-34 A (FCV-74-59) FCo-65-3 10-34B (FCV-74-73) FCO-65-4 10-38A (FCV-74-58) FCo-65-16 10-38B (FCV-74-72) FSV-65-17 10-39A (FCV-74-57) FCO-65-22 10-39B (FCV-74-71) FCo-65-24 10-154 A (FCV-74-52) FCo-65-25 10-154B (FCV-74-66) FCo-65-26 Standby Gas Treatment (SBGT) System FCO-65-38 FCo-65-39 FSV-65-51 FCO-65-52 FSV-65-66 FCO-65-67 SBGT Filter Train Humidity Control Heater Trains A, B, and C SBGT Filter Train Charcoal Heaters A, B, and C SBGT Building 2 Sump Pumps C and D SBGT Blower Trains A, B, and C SBGT Fans A and B e
, '$ Devices to be Tested During Unit Shutdown -
Those devices which function as part of the emergency core cooling (ECC) systems should be tested during plant shutdown. This does not include devices of the low-pressure coolant injection system, which could be tested during plant operation. Testing the ECC systems' devices with the plant shut down would avoid placing unnecessary challenges and demands on these systems, would minimize the use of temporary alterations, and would minimize the overall effect on plant operation. This includes devices in systems 71 (reactor core isolation cooling system), 73 (high-pressure coolant injection system), 75 (core spray system), and part of system 74 (residual heat removal system). Also, those devices in systems 64, 76, and 84 (primary and secondary containment systems) would be tested during plant shutdown to avoid possible Browns Ferry technical specification violations and overheating of the main steam tunnel and drywell areas. Other devices to be tested during plant shutdown are listed below. Device Main Steam System Recirculation Sampling System 2-80A (FCV-1-14) 2-298 (FSV-43-13) 2-80B (FCV-1-26) 2-299 (FSV-43-14) 2-80C (FCV-1-37) 2-80D (FCV-1-51) . Reactor Water Cleanup System 2-86A (FCV-1-15) 2-86B (FCV-1-27) 12-15 (FCV-69-1) 2-86C (FCV-1-38) 12-18 (FCV-69-2) 2-86D (FCV-1-52) 12-68 (FCV-69-12) 2-74 (FCV-1-55) l 77 (FCV-1-56) Vacuum System Radiation Monitoring System Condenser Vacuum Pump 1A FCV-90-254A Condenser Vacuum Pump 1B FCV-90-254B l FCV-66-36 FCV-90-257B FCV-66-40 FCV-90-255 FCV-90-257A Drywell Air Supply System Reactor Recirculation System l FSV-32-62 I FSV-32-63 2-65A (FCV-68-35) l Drywell Press Compressor 2-65B (FCV-68-33)
- 2-53A (FCV-68-3) 2-53B (FCV-68-79)
Power Distribution Panel 9-54 Power Distribution Panel 9-55 I
r ; 4 For the items listed below, further resolution defining the scope and extent of the test will be required. Device Diesel Generators A, B, C, & D Diesel Generators 3A, 3B, 3C, & 3D Fuel Pool Cooling Pumps 1A & IB Reactor Water Cleanup Recir-Reactor Water Cleanup Demin- culating Pumps 1A & 1B eralizer Holding Pumps 1A,1B Control Bay Water Chillers A & B 250V Battery Chargers 1, 2A, Shutdown Board Room Exhaust
& 2B Fan 1A Shutdown Board Room Emergency Diesel Generators A, B, C, D, Supply Fan 1B Air Compressor A Diesel Generators A, B, C, D, Air Compressor B Test Schedule It was estimated that it would take approximately two months to write the .
test, six weeks to obtain the necessary approvals required to perform the testing, and one month for each unit to test those devices which could be tested with the unit in operation. The remainder of the testing, that which must be performed during unit shutdown, will be performed on the following schedule: unit 1, spring 1981 outage; unit 3, fall 1981 outage; unit 2, spring 1982 outage. l I l l l . l l l i l i _- - _}}