ML19318A866
| ML19318A866 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/12/1980 |
| From: | Widner W GEORGIA POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-80-06, IEB-80-6, NUDOCS 8006240296 | |
| Download: ML19318A866 (8) | |
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June 12, 1980 GeorgiaPower
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.,rr, mm,wr U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement
REFERENCE:
Region II - Suite 3100 RII: JP0 101 Marietta Street, NW 50-321/50-366 Atlanta, Georgia 30303 I&E Bulletin 80-06 ATTENTION: Mr. James P. O'Reilly Gentlemen:
The following information is submitted in response to I&E Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls.
In accordance with Item 1 of the bulletin, we have reviewed drawings for essential safety systems with and without Manual Reset logic Circuitry for both units. With the following exceptions, all associated safety equipment was found to remain in its emergency mode Lf ter roset of the ESF or Manual Logic Reset signals.
Two systems for each unit, the Au tic epressurization System (B21C for Unit 1, 2B21C for Unit 2), and the
.c".a and Oxygen Analyzer System (P338 for Unit 1, 2P33B for Unit 2) were found to return ?y design to their pre-emergency mode upon reset of the Manual Logic Reset.
'his operation is justified as follows:
The Automatic Depressurization System ( ADS) is designed such that.it will automatically open the designated seven safety relief valves 120 seconds after all of the following conditions are satisfied:
1.
Reactor water level at Low Level 3.
2.
A high drywell pressure signal is initiated.
3.
A low pressure pump is running.
The system design is such that if cne of the initiating signals has cleared and the ADS logic reset button is depressed, all seven valves will go closed. The intent is that the valves operate as a set in order to provide the required blow-down rate, in addition to assuring equal torus load and temperature distribution; therefore, the design, as installed, meets the intent of the requirement as outlined in the bulletin.
The hydrogen and oxygen analyzers form a closed system outside the A00/
containment. The system is used to continuously monitor H2 and 02 con-g centrations in the primary containment. The reset of the ESF actuation llI 8 00624 02ff Q
Georgia Power d U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II - Suite 3100 June 12, 1980 Page Two signal re-opens the primary containment isolation valves for the system and provides the capability to monitor the primary containme-atmosphere immediately after an accident. The system is designed t
,he same pressure and temperature ratings as the primary containment. Since this system performs the singular function of monitoring H2 and 02 concentrations after an accident, the reset function meets the design intent of the system and the requirements as outlined in the bulletin.
Item 2 requested that we verify that the actual installed instrumentation and controls are consistent with the schematics reviewed in Item 1 by con-ducting a test to demonstrate that all equipment remains in its emergency mode upon removal of the various isolating or actuation signals.
In accordance with this item, we have provided attachments detailing the type of functional tests and frequencies of system testing per the Technical Specifications for Units 1 and 2.
Item 3 requires no further written response since all systems have been investigated and justified.
If you have any questions, please contact this office.
Sincerely, M
W. A. Widner Vice President and General Manager Nuclear Generation REB /mb Attachments l
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/and subscribed before me ?.his 12th day of June, 1980.
Als h. Notary Public
% % %,3 My commission bcares Sept 20 Director of the Office of Inspection and Enforcement,1983 xc:
' Director of the Division of Operating Reactors, Office of Nuclear Re.. tor Regulation /
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NRC IE BULLETIN 80 06 ESSENTIAL SYSTEMS TEST Page 1 of 2 E.1. HATCH NUCLEAR PLANT Unit 1 INTERVAL TEST T ECH. SPEC. REF.
SYSTEM NO.
SYSTEM DESCRIPTION RECUIRED SECTION NO.
vnce per oper.
Table 4.2-1, A71 Nuclear Steam Supply Shutoff System cycle Pace 3.2-26 B213 Steam Leak Detection System See note I See note 2 Once per oper.
Table 4.2-4, B21C Auto Depressurization System cycle Page 3.2-34 Reactor Recirculation Pump Tested with Table 4.2-5, B31A M.G. Set "A" System LPCI Pace 3.2-36 Reactor Recirculation Pump Tested with Table 4.2-5, B31B M.G. Set "B" System LPCT Page 3.2-26 Once every 18 4.4.A.2, C41 Stand By Licuid Control System months Pace 3.4-2 Start Up Range Neutron Monthly, See C51A Monitoring System Table 4.2-7 See once 3.2-40 Every 3 Table 4.2-7, CSIB Power Ranee Neutron Monitorine System months Pace 3.2-40 Traversign In Core Probe Once per oper.
Table 4.2-1, CSID Calibration System cycle Pace 3.2-26 Once per oper.
C61 Primary Containment Isolation System evele 4.7.C.1 Table 4.1-1, C71B Reactor Protection System Everv 3 months Page 3.1-7 D11 Process Rsdiation Monitoring Svstem See note 2 See note 3 Once each oper.
Table 4.2-1, E11 Residual Heat Removal System evcle Pace 3.2-36 Once each oper.
Table 4.2-6, E21 Core Spray System cycle Page 3.2-39 Once each oper.
Table 4.2-2, E41 High Pressure Coolant Injection cycle Pace 3.2-29 Once each oper.
Table 4.2-3, E51 Reactor Core Isolation Cooling System cycle Pace 3.2-30 Reactor Water Clean Up and once each oper.
Table 4.2-1, G31B Demineralizer Sy; tem cycle Page 3.2-26 Table 4.2-8, N62 Off Gas System once each month Page 3.2-42 P33B E>irogen and Oxygen Analyzer System Every 6 months Table 4.2-11 React?r Building Service P41A Water Syc*em See note 7 Table 4.2-1 PS2 Plant Instrument Air System See note 11 See note 11 Once each oper.
P70 Drywell Pneumatic System cycle See note 8 Normal Station Service R20C 600 volt Svstem See note 4 See note 4 Emergency Station Service R20L 4160 volt System See page 3.9-3 4.9.A.4 Emergency Station Service R20M 600 volt System See page 3.9-3 4.9.A.5 Emergency Station Service R20N 120/208 volt Svstem Everv 7 davs 4.9.A.3
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o NRC IE BULLETIN 80 06 ESSENTIAL SYSTEMS TEST E.1. HATCH NUCLEAR PLANT Unit 1 INTERVAL TEST TECH. SPEC.REF.
SYSTEM NO-SYSTEM GESCRIPTION REQUIRED SECTION NO.
125/250 volt Station Battery and R42A Dirtribution System Every 7 days 4.9.A.3 R42B 125 Volt Diesel Generator Batteries Every 7 days 4.9.A.3 4.9.2.A, R43A Diesel Generator IA, System Once each month Page 3.9-11 4.9.2.A, R43B Diesel Generator B System once each month Pace 3.9-11 4.9.2.A, R43C Diesel Generator IC System Once each month Pace 3.9-11 Once each oper.
R44 250 voit Inverter System cycle See note 5 Once each oper.
4.2-2, T41B Safeguard Equipment Cooling System cycle Pace 3.2-?9 Reactor Building Once each oper.
T41C Ventilation System evele See note 9 Once each oper.
T46 Stand By Cas Treatment System cvele 3.7.A.8 T47 Drywell Cooling System See note 6 Table 4.2-5 Containment Atmosphere Once per oper.
T48A Dilution System evele 3.7.A.6 Once per oper.
T48C Nitrocen Inerting Svstem evele 3.7.A.6 Turbine Building Leak U61 Detection Svstem See note 2 See note 10 Diesel Building Heat X41A and Ventilation System See note 9 2.4-4 4
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i Notes for Unit 1 Steam Lrak Detection System is a monitoring system 1.
consis'.ing of resistance temperature detectors and has no E.S.F. trip signal logic.
This monitoring' system is.in use during normal ope-2.
therefore system testing is not recuired.
- ration, Instrueent calibration is performed per Technical Specification Section 4.3.6.1.
The Process Radiation Monitoring System involves 3.
Radiation Detectors in ventilation exhausts and Isolation logic is tested with Containment filters.
Isolation Systems per Technical Specifications Table 3.6.5.2-1.
The 600 volt Station Service System for Power Dist-4.
ribution is in use during normal operation and is covered in Technical Specification Section 3.8.1.2
-2.2.
Inverters supply power to Residual Heat Removal 5.
Sysrca valves and are tested with R.H.R. per Tech-
'tcal Specification Section 3.2-36, Drywell Cooling System units are stopped on L.O.C.A.
6 is signal from Core Spray System. Therefore test considered part of Core Spray System.
Plant Service Water System supplies cooling water to 7
essential systems eauipment and pumps. Therefore it is tested with Core Cooling Systems such as R.H.R.,
Core Spray, etc..
The Drywell Pneumatic System with essential isolation 8.
valves is functionally tested with Containment Iso-lation Systems per Technical Specification Section 3.6.
Ventilation Systems with essential isolation functions 9.
are functionally tested with Containment Isolation Systems per Technical Specification Section 3.6.
Turbine Building Leak Detection System is a monitoring 10.
system consisting of. resistance temperature detectors and has no E.S.F. trip signal logic.
Instrument Air System is in constant operation,
. Plant 11.
Therefore no specific functional test is recuired to i
verify operation.
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NRC IE BULLETIN 80 06 ESSENTIAL SYSTEMS TEST E.1. HATCH NUCLEAR PLANT Unit 2 SYSTEM NO.
SYSTEM DESCRIPTION INTE pE ED SEC O N At least once 4.3.2-1, 4.6.3-2, 2A71 Nuclear Steam Supply Shutoff System per 18 months 4.3.4-2 Nucle 6-Doiler Process At least once 4.3.1-2, 2B21A Instrume,tation Svstem oer is nnnehn 4.191 2B21B Steam Leak Detection System See note 1 See note 2 At least once 2B21C Auto Depressurization System per 18 months 4.5.2.A Reactor Recirculation Pump Tested with 2B31A M.G. "A" Svstem LPCI System 4.4.1.1/4.5.3 Reactor Recirculation Pump Tested with 2B31B M.G.
"B" System LPCI Svstem 4.4.1.1/4.5.3 Start Up Range Neutron 4.3.1-1, 4.3.5, 2C51A Monitoring System Once oer 31 davs 4.3.6.5 2C51B Power Range Neutron Monitoring Systen Table 4.3.1-1 4.3.1.1 Start Up Range Detector 2C51C Drive Control System Once per 31 davs 4.3.6.5 B & C At 1 cast once 2C61 Primary Containment Isolation System per 18 months 4.6.3.2 At least once 2C71B Reactor Protection System per 18 months 4.3.1.2 2D11 Process Radiation Monitoring System Table 4.3.6.1.1 4.3.6.1 At least once 2E11 Residual Heat Removal System oer 31 davs 4.9.12 2E11A R.H.R. Service Water System Once ner 31 davn 4.7.1.1-At least oncc 2r2tA core snrnv synea ner 18 months 4.5.3.1.D Core Spray and R.H.R. Jockey At least once 2E21B Pumo Svstem oer 18 months 4.5,3.1.D Main Steam Valve At least once 2E32 Leakace Control System oer 18 months 4.6.1.4.C High Pressure Coolant At least once 2r41 Injection System per 18 months 4.5.1.C.1 At least once 2E51 Reactor Core Isolation Cooling Syster per 18 months 4.7.3.C.1 2P33B 0xveen Analvrer System Once per 31 days 4.3.6.4-1 At least once 2P41 Plant Service Water System per 18 months 4.7.1.2.E Reactor Building
'?41A Service Water System See note 3 4.9.12/4.7.1 Reactor Building Closed 2P42 Cooling Water System See note 4 4.7.1/4.9.12 2P52A Plant Instrument Air Systen See note 5 See note 5 2P64 Drywell Chilled Wa'er System See note 6 See note 6 Once per 18 2P70 Drvwell Pneumatic System months 4.6.3.2
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NRC IE BULLETIN 80 06 ESSENTIAL SYSTEMS TEST Page 2 of 2
E.. I. HATCH NUCLEAR PLANT Unit 2 INTERV TEST TEC SPEC E F.
SYSTEM NO.
SYSTEM DESCRIPTION Emergency Station Service At least once 2R20L 4160 volt Svstem oer 7 davs 4.8.2.1.1 Emergency Station At least once 2R20M Service 600 voit System per 7 days 4.8.2.1.1 Emergency Station Service At least once 2R20N 120/208 volt System per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.8.2.1.2 125/250 volt Station Battery and At least once 2R42A Distribution System ner 7 days 4.8.2.~3.1 At least once 2R42B 125 volt Diesel Generator Batteries oer 18 months 4.8.1.1.3.C At least once 2R43A Diesel Generator 2A System per 18 months 4.8.1.1.2 At least once 2R43B Diesel Generator B System per 18 months 4.8.1.1.2 At least once 2R43C Diesel Generator 2C System per 18 months 4.8.1.1.2 At least once 2R44 250 voit D C Inverter System per 31 days 4.8.2.1.1 2T41B Safeguard Equipment Cooling System See note 7 See note 7 Reactor Building At least once 2T41C Ventilation System per 18 months 4.6.5.2.C.2 At least once 2T46 Stand By Gas Treatment System per 18 months 4.6.6.1.1.D.2 At least once 2T47 Drywell Cooling Svstem per 92 days 4.6.6.3 Containment Atmosphere At least once 2T48A Dilution System per 18 months 4.6.6.I'.1.D.2 Drywell to Torus Differential 2T48D Pressure System Everv 31 davs 4.3.6.3-1 Post L.O.C.A.
At least once 2T49 Hvdrocen Recombiner System oer 18 months 4.6.6.2.B.4 Turbine Building 2U61 Leak Detection System See note 8 See note 8 Diesel Building and Cooling Towers 2X41A Heatinc and Ventilation System See note 9 See note 9 Control Building 2Z41 Ventilation System See note 9 3.6.5.2-1
Notes for Unit 2 1.
Steam Leak Detection System is a monitoring system consisting of resistance temperature and has no E.S.F._ trip signal logic.
2.
This monitoring system is in use during normal ope-ration, therefore system testing is not required.
Instrument calibration is performed per Technical Specification Table 4.3.2-1, 3.
This system is a sub system of Plant Service Water System and is tested accordingly.
4 Reactor Building Closed Cooling Water System es-sential isolation valves are tested in accordance with Technical Specification Section 4.6.3.2 covering Containment Isolation Systems.
5.
Plant Instrument Air System is in constant ope-ration, therefore no specific functional test is recuired to verify operation.
6.
Drywell Chilled Water System isolation valves are functionally tested with containment isolation sys-tems per Technical Specifications Section 4.6.5.2.
7.
Safeguard Equipment Cooling Systems are tested with the essential systems they are cooling such as R.H.R.,
Core Spray, etc..
8.
Turbine Building Leak Detection System is a monitoring system consisting of resistance temperature detectors and has no E.S.F. trip signal logic.
9.
Ventilation Systems with essential isolation functions are functionally tested with containment isolation systems per Technical Specifications Section 4.6.5.2.
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