ML13333B280
| ML13333B280 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/16/1985 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-64883, NUDOCS 8507240258 | |
| Download: ML13333B280 (45) | |
Text
Docket No. 50-206 LICENSEE:
Southern California Edison Company FACILITY: San Onofre-Nuclear Generating Station, Unit No. 1
SUBJECT:
SUMMARY
OF JUNE 26, 1985 MEETING On June 26, 1985 members of the NRC staff met with representatives of Southern California Edison Company (SCE). The meeting was requested by SCE to discuss its approach to meeting the requirements of Section III.G of Appendix R to 10 CFR Part 50 (fire protection). is a list of attendees. Copies of the viewgraphs presented by SCE are shown in.
SCE and consultants discussed the evaluation methodology used in the compliance review with regard to Section III.G, reviewed the plant fire area/fire zones, and discussed six potential exemption requests that have been identified to date but not formally submitted for NRC review and approval.
SCE also discussed the proposed dedicated shutdown system. This system will have a new, dedicated diesel generator. Changes in the dedicated shutdown system since the original April 24, 1984 submittal include use of pressurizer heater group "D" heaters to provide pressure control (together with controlled actuation of the PORV previously proposed), addition of a third auxiliary feedwater pump this forthcoming outage (balance of the third auxiliary feedwater train is scheduled to be installed during the second refueling outage from now), and dedication of a new area for the dedicated shutdown system on the west side of the reactor auxiliary building.
The NRC staff indicated that it would provide draft proposed technical specifications for testing the dedicated diesel generators for SCE's information.
The licensee plans to complete the fire protection modifications during the outage scheduled to begin November 30, 1985.
ftacd by 6507240258 850716 Walter Paulson, Project Manager PDR ADOCK 05000206 Operating Reactors Branch No. 5 F
PDR',
Division of Licensing
Enclosures:
As stated DISTRIBUTION Docket File JZwolinski BGrimes NRC PDR WPaulson ACRS (10)
Local PDR OELD NRC Participants ORB# 5 Reading EJordan DL:ORB#r DL:ORB#5 DL: RB#5 DL:ORR#5 Clamerso n WPaulson'W RDudley JZwolinski ee/
07/0/85 07/o /85 07 ( /85 07/\\b/85
36ARREGU W,
UNITED STATES NUCLEAR REGULATORY COMMISSION 00 WASHINGTON, D. C. 20555 July 16, 1985 Docket No. 50-206 LICENSEE:
Southern California Edison Company FACILITY:
San Onofre Nuclear Generating Station, Unit No. 1
SUBJECT:
SUMMARY
OF JUNE 26, 1985 MEETING On June 26, 1985 members of the NPC staff met with representatives of Southern California Edison Company (SCE). The meeting was requested by SCE to discuss its approach to meeting the requirements of Section III.G of Appendix R to 10 CFR Part 50 (fire protection). is a list of attendees.
Copies of the viewgraphs presented by SCE are shown in.
SCE and consultants discussed the evaluation methodology used in the compliance review with regard to Section III.G, reviewed the plant fire area/fire zones, and discussed six potential exemption requests that have been identified to date but not sormally submitted for NRC review and approval.
SCE also discussed the proposed dedicated shutdown system. This system will have a new, dedicated diesel generator. Changes in the dedicated shutdown system since the original April 24, 1984 submittal include use of pressurizer heater group "D" heaters to provide pressure control (together with controlled actuation of the PORV previously proposed), addition of a third auxiliary feedwater pump this forthcoming outage (balance of the third auxiliary feedwater train is scheduled to be installed during the second refueling outage from now), and dedication of a new area for the dedicated shutdown system on the west side of the reactor auxiliary building.
The NRC staff indicated that it would provide draft proposed technical specifications for testing the dedicated diesel generators for SCE's information.
The licensee plans to complete the fire protection modifications during the outage scheduled to begin November 30, 1985.
Walter Paulson, Project Manager Operating Reactors Branch No. 5 Division of Licensing
Enclosures:
As stated
ENCLOSURE ATTENDANCE LIST JUNE 26, 1985 MEETING NRC STAFF AND SOUTHERN CALIFORNIA EDISON COMPANY NAME ORGANIZATION W. Paulson NRC R. Ornelas SCE, Licensing J. Kittler Impell Corporation D. Barreres SCE, Station G. Weber Impell Corporation J. Yann SCE PE M. Short SCE Project Manager T. Roell Fluor J. Conway Impell Corporation J. Stang NRR/ORB #5 P. Dudley ORB P5 T. Chandrasekaran NRR/DSI/ASB J. Wermiel NRR/DSI/ASB
ENCLOSURE 2 AGENDA I. INTRODUCTION (R, ORNELAS)
II. APPENDIX R, III.G COMPLIANCE REVIEW (J, CONWAY, IMPELL)
A. EVALUATION METHODOLOGY B. REVIEW OF PLANT FIRE AREAS/ZONES C. POTENTIAL EXEMPTION REQUESTS III.
DEDICATED SHUTDOWN SYSTEM CONCEPT (G, WEBER, IMPELL)
IV. DEDICATED SHUTDOWN SYSTEM DESIGN (T, ROELL, FLOUR)
A. DESIGN CRITERIA B. SYSTEM DESCRIPTION C. IN-SERVICE PERIODIC TESTING
INTRODUCTION 10 CFR50A48 AND APPENDIX R ISSUED 2/17/81 "ALTERNATE SHUTDOWN SYSTEM" SUBMITTED 6/30/82 NRC SER ON "ALTERNATE SHUTDOW SYSTEM" ISSUED 11/18/82 NRC SCHEDuLAR ExEMPTION ISSUED 2/23/83 NEW START DATE 10/31/83 e
DEDICATED SHuTDOWN SYSTEM (DSS)
SUBMITTED 4/24/84 NRC QUESTIONS ON DSS PROPOSAL ISSUED 12/13/84 s RESPONSE TO QUESTIONS ON DSS PROPOSAL suBMiTTED 5/21/85 o SCE/NRC MEETINGS ON DSS PROPOSAL 6/26/85 PURPOSE AGENDA CLARIFIED 81-12 GENERIC LETTER INFOFMATION SUBMITTAL 7/31/85 s
ExEmPTIONS TO BE SUBMITTED AS SOON AS AVAILABLE COMPLIANCE DUE DATES NoN-DSS RELATED - STARTUP FOR CYCLE 9 OPERATION DSS-4/30/86
SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 APPENDIX R SECTION III.G EVALUATION METHODOLOGY IDENTIFY SAFE SHUTDOWN COMPONENTS PREPARE SAFE SHUTDOWN FAULT TREES REEVALUATION OF FIRE AREA/ZONE BOUNDARIES FOR APPENDIX R COMPLIANCE FOR SSD COMPONENTS IDENTIFIED, REVIEW STATION ELEMENTARY DIAGRAM, WIRING DIAGRAM, AND LOOP DIAGRAMS TO IDENTIFY CIRCUITS THAT COULD AFFECT SAFE SHUTDOWN IF DAMAGED BY FIRE PREPARE BLOCK DIAGRAMS TO SHOW FUNCTIONAL RELATIONSHIP BETWEEN SSD CIRCUITS AND COMPONENTS
SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 TYPICAL BLOCK DIAGRAM CONTROL RM PANEL 1FY1111P1 CIRCUIT NO.(TYP.)
NCI6 (iX11,U)
WIRE NO.(TYP.)
IFM1113K2 (1X14,1X13,1X15, IFM1111C1 1X11,1X16) 1,1~l(1X11,C1,C2,CS,C13) 1FM1111C2 (1XIIC21
,C2,C43,C53)
CONTROL RM CONTROL RM CONTROL RM PANEL ELAY PAEI PANEL C71 FC60 C13A FM1111C3 IFYIZIPO1 (C1IC23,C33,C32,C63,C73,UI)
(iX21,U)
OUTSIDE I
4 8 0 V M C C:
C O N T A IN M E N T C NTI N T
1 FY12I1P04T (CI1.U1)JNTONISD N
CONTAINMENT IFYI21PO2JB65L0F IFF12PO PO2 (C11,UI)
IFY121PO4 (CIUI)lFMI(C4 1 I (C11IUR) JUNCTIO N
NSCI7 BOX CONTAINMENT 1FYY121PO2 (U1,CI,1),33 1FY1 1PO7 I
IFY121POS 3 U )
FY 21 O (C1,UI) 1FM111C CV2 JBSI RA 21FC52 R F B
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APPENDIX R SECTION III.G EVALUATION METHODOLOGY DEVELOP DATABASE OF$
PREPARE PLANT O
SSO COMPONENTS AREA DRAWINGS SSD CIRCUITS HIGHLIGHTING THE RACEWAY LOCATION OF FIRE AREAS/ZONES SSD RACEWAY(S)
AND PRODUCE COMPUTER SORTS PERFORM SPURIOUS PERFORM COMMON COMPERFORM OPERATION POWER SUPPLY CMO NLSR EVALUAT IONEVLAINELUTO EVALUATE SSD CIRCUITS FOR BREAKER HOT SHORTS, COORDINATION SHORTS TO GROUNDIALYS AND OPEN CIRCUIT PERFORM EALUATION TO APPENDIX R, FSECTION III&*21 2
APPENDIX R SECTION III.G EVALUATION METHODOLOGY IDENTIFY IDENTIFY IDENTIFY IDENTIFY IDENTIFY AREAS WHERE AREAS WHERE AREAS WHERE AREAS WHERE AREAS OF EXEMPTIONS TO MODIFICATIONS DSS WILL BE ALTERNATE COMPLIANCE APPENDIX R, ARE REQUIRED REQUIRED SHUTDOWN WILL SECTION 111.6 BE REQUIRED ARE JUSTIFIED BERQIE EVALUATE TO APPENDIX R SECTIONS II.G.3 AND III.L PREPARE ENGINEERING REPORT DOCUMENTING RESULTS OF EVALUATION AND PREPARE LICENSING REPORT DOCUMENTING DEVIATIONS AND REQUESTS FOR EXEMPTIONS
REVIEW OF PLANT FIRE AREAS/ZONES DEDICATED SHUTDOWN ALTERNATE SHUTDOWN PENDING ANALYSIS
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I POTENT IAL EXEMPTIONS TO BE PROPOSED
- 1. FIRE ZONE BOUNDARIES
- 2. LACK OF CONTROL ROOM SUPPRESSION
- 3. PARTIAL SUPPRESSION FOR FIRE AREAS/ZONES
- 4. PARTIAL DETECTION FOR FIRE AREAS/ZONES
- 5. USE OF FIRE PROOF CABLES FOR DEDICATED SHUTDOWN SYSTEM
- 6. SOURCE RANGE MONITOR FOR DEDICATED SHUTDOWN SYSTEM
o PROPOSED EXEMPTION THE USE OF ZONE BOUNDARIES AS BASIS FOR ANALYSIS o REASON FOR EXEMPTION PLANT LAYOUT UTILIZES OUTDOOR AREAS TO HOUSE SAFE SHUTDOWN EQUIPMENT/SYSTEMS LOCALIZED NATURE OF COMBUSTIBLE LOADING LIMITS DEVELOPMENT OF FIRES o BASIS FOR EXEMPTIONS LOW FIRE LOADING SUBSTANTIAL PHYSICAL SEPARATION FAST RESPONSE OF DEDICATED FIRE BRIGADE o EXEMPTION APPLICATIONS FIRE ZONE 2J -
YARD AREA FIRE ZONE 23 -
PENETRATION AREA FIRE ZONE 9A -
TURBINE BUILDING GROUND FLOOR
o PROPOSED EXEMPTION LACK OF CONTROL ROOM AUTOMATIC SUPPRESSION o REASON FOR EXEMPTION PLANT CAN ACHIEVE AND MAINTAIN SAFE SHUTDOWN FROM THE REMOTE SHUTDOWN PANEL INADVERTENT OPERATION OF AUTOMATIC SUPPRESSION SYSTEM COULD CAUSE NEEDLESS EVACUATION OF CONTROL ROOM o BASIS FOR EXEMPTION CONTROL ROOM IS CONTINUOUSLY MANNED DETECTION SYSTEMS ARE PROVIDED MANUAL SUPPRESSION IS AVAILABLE FAST RESPONSE OF DEDICATED FIRE BRIGADE CONTROL ROOM IS SEPARATED FROM OTHER AREAS BY 3 HOUR RATED BARRIERS LOW PROBABILITY OF TRANSIENTS o EXEMPTION APPLICATION FIRE AREA 16 CONTROL ROOM COMPLEX
o PROPOSED EXEMPTION PARTIAL SUPPRESSION IN FIRE AREAS OR FIRE ZONES o REASON FOR EXEMPTION SUPPRESSION PROVIDED WITHIN THE FIRE AREA/ZONE TO COVER LOCAL HAZARDS AND/OR PROTECT SAFE SHUTDOWN COMPONENTS o BASIS FOR EXEMPTION SEPARATION OF REDUNDANT/ALTERNATE SAFE SHUTDOWN SYSTEMS LOCATION OF IN-SITU COMBUSTIBLES CONFIGURATION UF EXISTING SUPPRESSION SYSTEM(S)
FAST RESPONSE OF DEDICATED FIRE BRIGADE o EXEMPTION APPLICATIONS FIRE ZONE 2J -
YARD AREA FIRE ZONE 2A -
REACTOR AUXILIARY BUILDING LOWER LEVEL FIRE ZONE 9A -
TURBINE BUILDING
o PROPOSED EXEMPTION PARTIAL DETECTION IN FIRE AREAS OR FIRE ZONES o REASON FOR EXEMPTION DETECTION SYSTEMS ARE PROVIDED WITHIN THE FIRE AREA/ZONE TO COVER LOCAL HAZARDS AND/OR PROTECT SAFE SHUTDOWN COMPONENTS o BASIS FOR EXEMPTION LOCATION OF IN-SITU COMBUSTIBLES CONFIGURATION OF EXISTING DETECTION SYSTEM SEPARATION OF REDUNDANT/ALTERNATE SAFE SHUTDOWN SYSTEMS o EXEMPTION APPLICATIONS FIRE ZONE 2A -
REACTOR AUXILIARY BUILDING LOWER LEVEL
o PROPOSED EXEMPTION USE OF FIRE PROOF CABLES FOR DEDICATED SHUTDOWN SYSTEM o REASON FOR EXEMPTION PROTECTION EQUIVALENT TO APPENDIX R REQUIREMENTS IS PROVIDED FOR THE DEDICATED SHUTDOWN SYSTEM o BASIS FOR EXEMPTION FIRE TEST AND PRODUCT DATA ON 3/1 HOUR FIRE PROOF CABLE CONFIGURATION OF FIRE AREA o EXEMPTION APPLICATIONS 1 HOUR RATED CABLE -
INSIDE CONTAINMENT 3 HOUR RATED CABLE -
PENETRATION AREA
o PROPOSED EXEMPTION SOURCE RANGE NEUTRON MONITOR NOT PART OF DEDICATED SHUTDOWN SYSTEM o REASON FOR EXEMPTION SAFE SHUTDOWN CAN BE ACCOMPLISHED WITHOUT THE USE OF THIS MONITOR AT SONGS-1 o BASIS FOR EXEMPTION OPERATOR WILL VERIFY REACTOR SUBCRITICAL BEFORE EXITING CONTROL ROOM CONTROL ROD MOVEMENT ACCIDENT NOT POSTULATED CONCURRENTLY WITH FIRE BORON DILUTION IS THE ONLY OTHER CREDIBLE EVENT RESULTING IN REACTIVITY CHANGES PREVIOUS EVALUATION OF BORON DILUTION EVENT HAS SHOWN PROBABILITY OF OCCURRENCE IS LOW PROBABILITY OF BORON DILUTION EVENT REDUCED DURING IMPLEMENTATION OF DEDICATED SHUTDOWN SYSTEM SINCE NORMAL POWER SUPLIES ARE DEENERGIZED
SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 DEDICATED SHUTDOWN SYSTEM
- 1. OVERVIEW o
OBJECTIVE o
PRIMARY FUNCTIONS o
APPROACH
- 2. DESIGN BASIS o
DESIGN BASIS EVENT o
ASSUMPTIONS
- 3. PROCESS PARAMETERS o
DECAY AND SENSIBLE HEAT REMOVAL o
PRIMARY SYSTEM REACTIVITY AND INVENTORY CONTROL o
PRIMARY SYSTEM PRESSURE AND TEMPERATURE CONTROL o
STEAM GENERATOR AND AUXILIARY FEEDWATER
- 4. SHUTDOWN SCENARIO
1.0 OVERVIEW o OBJECTIVE TO PROVIDE IN CONJUNCTION WITH NORMAL AND ALTERNATE SYSTEMS THE CAPABILITY TO ACHIEVE AND MAINTAIN COLD SHUTDOWN FOR ANY POSTULATED FIRE IN ACCORDANCE WITH THE SAFE SHUTDOWN REQUIREMENTS OF 10CFR5O APPENDIX R.
o PRIMARY FUNCTIONS DECAY HEAT REMOVAL RCS COOLDOWN REACTIVITY CONTROL PRIMARY SYSTEM INVENTORY CONTROL PRIMARY SYSTEM PRESSURE CONTROL
1.0 OVERVIEW(CONTINUED) o APPROACH DECAY HEAT REMOVAL AND RCS COOLDOWN USING STEAM GENERATORS ONLY REACTIVITY AND INVENTORY CONTROL BY INJECTION OF BORATED WATER VIA RCP SEALS PRIMARY SYSTEM PRESSURE CONTROL USING PRESSURIZER PORV AND HEATERS DEDICATED SOURCE OF POWER INDEPENDENT OF NORMAL POWER SOURCES TO ENABLE USE OF EXISTING SHUTDOWN EQUIPMENT
0 0
2.0 DESIGN BASIS o DESIGN BASIS EVENT REACTOR INITIALLY AT FULL POWER A FIRE OCCURS IN EITHER THE 4KV SWITCHGEAR ROOM, THE CONTROL ROOM OR THE GROUND ELEVATION OF THE TURBINE BUILDING (ZONE 9A)
LOSS OF OFFSITE POWER o ASSUMPTIONS REACTOR AND TURBINE ARE TRIPPED REACTOR COOLANT PUMPS ARE NOT AVAILABLE RESIDUAL HEAT REMOVAL PUMPS ARE NOT AVAILABLE COMPONENT COOLLING WATER PUMPS ARE NOT AVAILABLE SALT WATER COOLING PUMPS ARE NOT AVAILABLE STEAM GENERATOR AND PRESSURIZER LEVELS ARE INITIALLY NORMAL LETDOWN AND SEAL WATER FLOW PATHS ARE ISOLATED THE RCS IS INTACT EXCEPT FOR REACTOR COOLANT PUMP SEAL LEAKAGE
3.0 PROCESS PARAMETERS o DECAY AND SENSIBLE HEAT DECAY HEAT DETERMINED ACCORDING TO THE REQUIREMENTS OF ANSI/ANS-5.1-1979 OPERATING HISTORY BASED ON 3 CYCLES OF 18 MONTHS FULL POWER OPERATION WITH 2 MONTHS REFUELING SENSIBLE HEAT BASED ON 0.52X10 BTU/*F o NATURAL CIRCULATION DECAY AND SENSIBLE HEAT IS REMOVED BY NATURAL CIRCULATION IN THE PRIMARY SYSTEM AT COLD SHUTDOWN THE SYSTEM PROVIDES 1/2% DECAY HEAT 3% CORE FLOW 9*F AT ALL REFERENCED TO FULL POWER CONDITION DETAILS ON THE NEXT VIEWGRAPH
8 AT 100 PERCENT LOAD CORE FLOW = 78.10 lb/hr CORE TEMP. DIFFERENCE CORE THERMAL P. = 1340 Mwtl 3
Th1 - Tel LD 2
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10 10--.
9z 8
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-100 PERCENT LOAD C3 10 7
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DECAY HEAT RATEr PERCENT OF CORE W
3 THERMAL POWER 2
0.1 1 I I I IIIIII I II Ill[I I I 1111 1
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10 100 1000 TIME (HR)
FIGURE 4-3 NATURAL CIRCULATION CORE FLOW RATE AND TEMPERATURE DIFFERENCE
3.0 PROCESS PARAMETERS (CONTINUED) o PRIMARY SYSTEM REACTIVITY AND INVENTORY CONTROL 3750 ppm BORIC ACID SOLUTION FROM RWST IS INJECTED INTO THE PRIMARY SYSTEM THE BORIC ACID SOLUTION PROVIDES:
- 1. 5% SHUTDOWN MARGIN
- 2. COMPENSATES FOR THE PRIMARY SYSTEM SHRINKAGE DUE TO COOLDOWN AND LEAKAGE THROUGH THE RCP SEALS THE TOTAL REQUIRED FLOW IS 26 GPM (14 GPM FOR MAXIMUM SHRINKAGE, 6 GPM FOR KNOWN/UNKNOWN TECH. SPEC LIMITS ON LEAKAGE, 6 GPM FOR RCP SEAL LEAKAGE)
THE REQUIRED TOTAL INVENTORY IS 64000 GALONS
110000 RCS SHRINKAGE 00 7500 I
0 so 1
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L5000 RCS MAKE-UP TO MEET
212*F
- 2. SINGLE-PHASE FOR T < 212*F STEAM GENERATOR EFFECTIVENESS HAS ENOUGH MARGIN TO PROVIDE THE REQUIRED COOLDOWN COOLANT IS SUPPLIED FROM THE AFW HEADER AND EXIT FROM THE STEAM HEADER FULL AFW FLOW (375 gpm) ALLOWS TRANSITION TO SINGLE PHASE OPERATION AT APPROXIMATELY 60 HR.
FULL FLOW OPERATION UNTIL COLD SHUTDOWN AFW FLOW IS THEN GRADUALLY REDUCED TO FOLLOW THE DECAY HEAT
4.0 SHUTDOWN SCENARIO DECAY HEAT REMOVAL AND COOLDOWN IS INITIATED BY STEAM DUMP TO ATMOSPHERE.
HEAT IS TRANSPORTED BY NATURAL CIRCULATION ON THE PRIMARY SIDE AND BY AFW FLOW ON THE SECONDARY SIDE REACTIVITY AND PRIMARY SYSTEM INVENTORY IS CONTROLLED BY BORATED WATER INJECTION THROUGH THE RCP SEALS.
RCP SEAL INTEGRITY IS INITIALLY MAINTAINED BY THE EMERGENCY THERMAL BARRIER PUMP AND LATER BY SEAL WATER INJECTION FROM THE CHARGING SYSTEM.
PRIMARY SYSTEM PRESSURE IS CONTROLLED BY ON/OFF CONTROL OF THE PRESSURIZER HEATER GROUP D BANK, AND CONTROLLED ACTUATION OF THE PORV.
COOLDOWN IS CONTINUED SO THAT:
" UPPER HEAT VOIDING IS PREVENTED NDTT LIMITS ARE NOT EXCEEDED
" COLD SHUTDOWN IS ACHIEVED WITHIN 72 HOURS
DSS PRESENTATION T. L. ROELL June 26, 1985
- Objective of DSS
- Design Criteria Changes subsequent to 4/84 submittal System Functional Design Charging Pump Auxiliary Feedwater Pump Pressurizer Heaters Steam Dump Single Phase Secondary Letdown Diesel Generator Control Panel Block Diagram
- System General Arrangements Equipment Location Cable Routing DSS Facilities Summary
PRIMARY COOLANT PRESSURE CONTROL SCHEMATIC DIAGRAM SV 3403 PCV 430C RCS FLASHPOT r*
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DSS INSTRUMENTATION NEW INSTRUMENTS AT DSS PANEL:
PRESSURIZER PRESSURE INDICATOR ( WIDE RANGE )
MAIN STEAM HEADER PRESSURE INDICATOR LOOP Aof REACTOR COOLANT TEMP.
INDICATOR HOT LEG LOOP B' REACTOR COOLANT TEMP. INDICATOR ( HOT LEG )
LOOP "C" REACTOR COOLANT TEMP. INDICATOR ( HOT LEG )
SWITCH: PRESSURIZER PORV CONTROL OTHER INSTRUMENTS:
MAIN STEAM HEADER PRESSURE TRANSMITTER LOOP NAN REACTOR COOLANT TEMP. TRANSMITTER ( HOT LEG )
LOOP '" REACTOR COOLANT TEMP. TRANSMITTER ( HOT LEG )
LOOP "C" REACTOR COOLANT TEMP. TRANSMITTER ( HOT LEG )
THIRD AUX. FEEDWATER PUMP FLOW METER PRESSURE INDICATOR AT LETDOWN STATION
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DSS PANEL FUNCTIONS REQ D. FOR INSTRUMENT DSS PRESSURIZER PRESSURE INDICATOR X
PRESSURIZER LEVEL INDICATOR X
A STEAM GEN. LEVEL INDICATOR X
B STEAM GEN. LEVEL INDICATOR X
oC" STEAM GEN. LEVEL INDICATOR X
LOOP "An REACTOR COOLANT TEMP.
IND.
(COLD LEG) x LOOP IB REACTOR COOLANT TEMP. IND. (COLD LEG) x LOOP C REACTOR COOLANT TEMP. IND. (COLD LEG) x STEAM DUMP CONTROLLER (CV76-79)
X SWITCH: STEAM DUMP CONTROL TRANSFER X
MAIN STEAM HEADER PRESSURE INDICATOR X
LOOP "A" REACTOR COOLANT TEMP. IND. (HOT LEG) x LOOP "B" REACTOR COOLANT TEMP. IND. (HOT LEG) x LOOP C REACTOR COOLANT TEMP. IND. (HOT LEG) x SWITCH: PRESSURIZER PORV CONTROL X
(CV530 & CV546)