ML20137W160
| ML20137W160 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/14/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8602200070 | |
| Download: ML20137W160 (11) | |
Text
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'e Pubhc Service Electric and Gas Company Ccrbin A. McNeill, Jr.
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4800 Vice President -
Nuclear February 14, 1986 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission f
7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing
Dear Ms. Adensam:
TESTABILITY OF BAILEY SOLID STATE LOGIC MODULES i
HOPE CREEK GENERATING STATION DOCKET NO. 50-354 f
Public Service Electric and Gas Company (PSE&G) hereby submits the attached to document commitments made during recent discussions with the NRC regarding the testability of the Bailey 862 Solid State Logic Modules.
PSE&G commits to implement a surveillance test program for a total test population of 577 modules as specified in Attachment 1.
The entire test population will be tested at a rate of
~
5% per month.
The module test selection criteria is based upon modules which perform a safety-related control function or provide a status of safety-related equipment.
Safety-related I
equipment status is limited to valve open/ closed, motor running / stopped and circuit breaker closed / tripped.
[
This program entails removing those modules, identified by system in Attachment 1, and performing bench tests of j
the logic modules beginning with the issuance of a full l
power license.
The bench test will confirm that the logic modules input / output logic functions as designed.
The results of each test will be documented and maintained in a retrievable data base.
This program will continue until sufficient statistical data is obtained to verify the reliability of the Bailey 862 Solid State Logic Modules.
L h
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I
e Director of Nuclear 2
2-14-86 Reactor Regulation Should you have any questions on the subject filing, please do not hesitate to contact us.
Sincerely, 1
Attachment C
D.H. Wagner USNRC Licensing Project Manager R.W.
Borchardt USNRC Senior Resident Inspector d
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4 TEST POPULATION ATTACHMENT #1 POWER DISTRIBUTION SYSTEM (4.16KV)
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1-3-3 1-3-3 1-3-3 1-3-3 i.
1-3-5 1-3-5 1-3-5 1-3-5 1-3-8 1-3-8 1-3-8 1-3-8 l-3-11 1-3-11 1-3-11 1-3-11 1-4-2 1-4-2 1-4-2 1-4-2 1-4-3 1-4-3 1-4-3 1-4-3 1-4-5 1-4-5 1-4 1-4-5 1-4-8 1-4-8 1-4-8 1-4-8 t
1-4-11 1-4-11 1-4-11 1-4-11 1-7-2 1-7-2 1-6-13 1-6-12 i
1-7-3 1-7-3 1-7-2 1-7-2 l-7-4 1-7-4 1-7-3 1-7-3 l
l-7-12 1-7-13 1-7-4 1-7-4 1
1-7-13 i
STANDBY DIESEL GENERATOR AC652 BC652 CC652 DC652 l-8-2 1-8-2 1-8-2 1-8-2 1-8-3 1-8-3 1-8-3 1-8-3 1-8-5 1-8-5 1-8-5 1-8-5 i -
1-8-6 1-8-6 1-8-6 1-8-6 i
t' REACTOR RECIRCULATION PUMP BREAKER AC652 BC652 CC652 DC652 4.
1-9-2 1-9-2
'l-9-7 1-9-7 POWER DISTRIBUTION SYSTEM (480V)
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AC652 BC652 CC652 DC652 1-6-2 1-6-2 1-6-2 1-6-2 i
1-6 1-6-7 1-6-7 1-6-7 1-6-12 1-6-12 1-7-11 DIESEL AREA CHILLERS (H-88)
L AC652 BC652 CC652 DC652 4-4-2 4-4-2 4-4-2 4-4-2 4
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REACTOR BUILDING HVAC (H83,84)
AC652 BC652 CC652 DC652 4-4-7 4-4-7 4-4-12 4-4-10 4-4-8 4-4-8 4-6-2 4-6-2 4-4-9 4-4-9 4-6-3 4-6-3 4-6-2 4-6-2 4-6-5 4-6-5 4-6-3 4-6-3 4-6-8 4-6-8 4-6-5 4-6-5 4-6-13 4-6-13 4-6-8 4-6-8 4-6-12 4-7-2 4-6-13 4-7-3 4-6-14 4-7-5 4-7-2 4-7-8 4-7-3 4-7-5 4-7-8 FIRE PROTECTION (H-22)
AC652 BC652 CC652 DC652 4-8-2 BREATHING AIR (H-15)
AC652 BC652 CC652 DC652 4-9-2 4-9-4 AUXILIARY BUILDING CHILLED WATER (H-90)
AC652 BC652 CC652 DC652 4-10-2 4-9-11 4-10-2 4-9-7 4-10-3 4-10-2 4-10-3 4-9-8 4-10-5 4-10-3 4-10-5 4-9-9 4-10-6 4-10-5 4-10-6 4-10-2 4-10-7 4-10-6 4-10-7 4-10-3 4-10-10 4-10-7 4-10-10 4-10-5 4-10-11 4-10-10 4-10-11 4-10-6 4-10-12 4-10-12 4-10-7
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f-AUXILIARY BUILDING HVAC (H-89)
AC652 BC652 CC652 DC652 4-7-3 4-7-3 4-7-4 4-7-4 4-7-5 4-7-5 4-7-7 4-7-7 4-7-8 4-7-8 4-7-9 4-7-9 4-7-10 4-7-10 4-7-13 4-7-13 I
4-7-14 4-7-14 4-8-3 4-8-3 4-8-4 4-8-4 4-8-5 4-8-5 4-9-9 4-10-12 4-9-10 4-10-13 CHILLED WATER (H-87) i AC652 BC652 CC652 DC652 4-9-2 4-9-2 4-9-3 4-9-3 4-9-4 4-9-4 4-9-5 4-9-5 4-9-6 4-9-7 i
STATION SERVICE WATER SYSTEM (J-10)
AC652 BC652 CC652 DC652 5-3-2 5-3-2 5-3-2 5-3-2 5-3-4 5-3-4 5-3-4 5-3-4 5-3-5 5-3-5 5-3-5 5-3-5 5-3-7 5-3-7 5-3-7 5-3-7 5-3-12 5-3-12 5-4-2 5-4-2 5-4-2 5-4-2 5-4-3 5-4-3 5-4-4 5-4-3 5-4-8 5-4-8 5-4-8 5-4-8 5-4-9 5-4-9 5-4-9 5-4-9 5-4-12 5-4-12 i
5-4-12 5-4-12 5-4-13 5-4-13 5-4-13 5-4-13 5-6-10 5-6-2 5-6-2 5-6-11 5-6-5 5-6-5 5-6-8 5-6-8 5-6-10 5-6-10 t
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4 CONDENSER AND REFUELING WATER STORAGE AND TRANSFER (J-08)
AC652 BC652 CC652 DC652 5-9-9 5-9-2 5-9-9 NUCLEAR BOILER (J-41)
AC652 BC652 CC652 DC652 5-10-2 5-10-4 5-9-2 5-10-2 5-10-4 9-9-9 5-10-2 5-10-4 9-9-10 5-10-4 5-10-6 9-9-11 5-10-6 5-10-8 9-9-12 5-10-8 5-10-10 5-10-10 REACTOR WATER CLEANUP (J-44,45)
AC652 BC652 CC652 DC652 5-10-9 5-7-2 5-10-11 5-7-4 5-7-6 5-7-8 REACTOR AUXILIARIES COOLING SYSTEM (J-13)
AC652 BC652 CC652 DC652 5-7-11 5-7-12 5-6-12 5-7-13 5-7-13 5-6-13 DEMINERALIZED WATER MAKEUP AND STORAGE (J-18 )
AC652 BC652 CC652 DC652 5-9-5 PLANT LEAK DETECTION (J-25)
AC652 BC652 CC652 DC652 5-9-3 5-9-3 5-9-4 5-9-4
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5 REACTOR RECIRCULATION SYSTEM (J-43,791E40AC)
AC652 BC652 CC652 DC652 9-10-2 8-9-8 8-9-10 9-10-2 SAFETY AUXILIARIES COOLING SYSTEM (J-ll)
AC652 BC652 CC652 DC652 8-3-2 8-3-2 8-3-2 8-3-2 8-3-3 8-3-3 8-3-3 8-3-3 8-3-4 8-3-4 8-3-4 8-3-4 8-3-5 8-3-5 8-3-5 8-3-5 8-3-7 8-3-7 8-3-7 8-3-7 8-3-12 8-3-12 8-3-10 8-3-12 8-4-2 8-4-2 8-4-2 8-4-2 8-4-3 8-4-3 8-4-3 8-4-3 8-4-4 8-4-4 8-4-5 8-4-5 8-4-5 8-4-5 8-4-6 8-4-6 8-6-2 8-6-2 8-6-2 8-6-2 8-6-3 8-6-3 8-6-3 8-6-3 8-6-5 8-6-5 8-6-5 8-6-5 8-6-6 8-6-6 8-6-6 8-6-6 8-6-8 8-6-8 8-6-10 8-6-10 8-6-10 8-6-10 8-6-14 8-6-14 STANDBY LIQUID CONTROL (J-48)
AC652 BC652 CC652 DC652 8-8-4 8-7-8 8-8-7 8-8-7 8-7-10 8-8-11 8-7-13 AUTOMATIC DEPRESSURIZATION SYSTEM (791E403AC)
AC652 BC652 CC652 DC652 9-9-9 9-9-11 9-9-10 9-9-12 9-9-11 9-9-12
6 HIGH PRESSURE COOLANT INJECTION (J-55)
AC652 BC652 CC652 DC652 8-10-5 8-9-8 8-10-6 8-9-9 8-10-7 8-10-8 l
8-10-9 8-10-10 8-10-11 REACTOR CORE ISOLATION COOLING (J-49)
AC652 BC652 CC652 DC652 8-9-5 8-9-4 8-9-6 8-9-5 8-9-7 8-9-8 8-9-9 SOLID RADWASTE (J-6)
AC652 BC652 CC652 DC652 8-10-2 8-10-2 8-10-2 8-10-3 8-10-5 8-10-6 LIOUID RADWASTE (J-61)
AC652 BC652 CC652 DC652 8-10-7 8-10-9 RESIDUAL HEAT REMOVAL (J-51,791E401AC)
AC652 BC652 CC652 DC652 9-4-2 9-4-2 9-4-2 9-4-2 9-4-3 9-4-3 9-4-3 9-4-3 9-4-4 9-4-4 9-4-4 9-4-4 9-4-5 9-4-5 9-4-8 9-4-5 9-4-6 9-4-6 9-4-10 9-4-7 9-4-7 9-10-4 9-4-8 9-4-8 9-4-9 9-4-9 9-10-4
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CORE SPRAY (J-52)
AC652 BC652 CC652 DC652 9-6-13 9-6-13 9-6-15 9-6-15 9-6-14 9-6-14 9-6-15 9-6-15 CONTROL ROD DRIVE (J-46)
AC652 BC652 CC652 DC652 9-10-7 PRIMARY CONTAINMENT ISOLATION SYSTEM (J-102)
AC652 BC652 CC652 DC652 9-7-9 9-10-2 9-9-2 9-9-2 9-9-2 9-10-4 9-9-4 9-9-4 9-9-3 9-10-6 9-9-6 9-9-6 9-9-6 9-10-7 9-9-7 9-9-7
. CONTAINMENT ATMOSPHERE CONTROL (J-57)
AC652 BC652 CC652 DC652 9-7-2 9-8-2 9-7-2 9-7-2 9-7-3 9-8-3 9-7-3 9-7-3 9-7-4 9-8-4 9-7-4 9-7-4 9-7-5 9-8-5 9-7-5 9-7-5 9-7-6 9-8-6 9-8-2 9-8-5 9-8-13 9-8-3 9-8-6 9-8-15 9-8-4 9-8-8 9-8-5 9-8-9 9-8-6 9-8-10 9-8-8 9-8-13 9-8-9 9-8-15 9-8-11 9-8-13 9-8-15 REDUNDANT REACTIVITY CONTROL SYSTEM (J-109)
AC652 BC652 CC652 DC652 9-7-8 9-7-9 12-6-9 12-6-10 12-6-12 12-6-12
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SCRAM DISCHARGE VOLUME (791E414AC)
AC652 BC652 CC652 DC652 9-10-9 HYDROGEN RECOMBINER SYSTEM (J-58)
AC652 BC652 CC652 DC652 12-7-2 12-7-2 12-7-2 12-7-2 12-7-3 12-7-3 12-7-3 12-7-3 12-7-4 12-7-4 12-7-4 12-7-4 FUEL POOL COOLING (J-53 )
AC652 BC652 CC652 DC652 12-4-2 12-4-2 12-4-3 12-4-3 12-4-6 12-4-6 12-4-7 12-4-8 12-4-9 12-4-9 12-4-10 12-4-11 12-4-12 12-4-13 12-4-14 12-4-14 12-6-2 12-6-2 PRIMARY CONTAINMENT INSTRUMENT GAS (J-59)
AC652 BC652 CC652 DC652 12-8-2 12-8-2 12-8-2 12-8-2 12-8-4 12-8-4 12-8-4 12-8-4 12-8-6 12-8-5 12-8-6 12-8-8 12-8-6 12-8-8 12-8-8 12-8-10 12-9-2 12-8-11 12-9-3 12-8-12 12-9-4 12-9-2 12-9-3 12-9-4 LOCA/ LOP FAN OUT (J-105)
AC652 BC652 CC652 DC652 12-10-2 12-10-2 12-10-2 12-10-2 12-10-4 12-10-4 12-10-4 12-10-4
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MAIN STEAM ISOLATION VALVE SEALING SYSTEM (J-72)
AC652 BC652 CCC32 DC652 12-4-2 12-4-2 12-4-3 12-4-3 12-4-4 12-4-4 12-4-5 12-4-5 12-4-6 12-4-6 12-4-7 12-4-7 12-4-8 12-4-8 12-4-9 12-4-9 12-6-2 12-6-2 12-6-4 12-6-4 12-6-6 12-6-6 12-6-13 i
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