ML13333B456
| ML13333B456 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/07/1986 |
| From: | Dudley R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-82-28, NUDOCS 8610150464 | |
| Download: ML13333B456 (51) | |
Text
1 n0r 0 7 1988 f
Docket No. 50-206 LICENSEE:
Southern California Edison Company (SCE)
FACILITY: San Onofre Nuclear Generating Station Unit 1 (SONGS-1)
SUBJECT:
SUMMARY
OF MEETING ON OCTOBER 2, 1986 REGARDING INADEQUATE CORE COOLING INSTRUMENTATION On October 2, 1986, a meeting was held between members of the NRC staff and personnel from SCE in Bethesda, Maryland. A list of attendees is provided in. Presentation material used by SCE at the meeting is provided in.
The purpose of the meeting was to discuss the licensee's June 20, 1986 submittal which requested a deviation from the NRC staff position detailed in Generic Letter 82-28 regarding the installation of a Reactor Coolant Inventory Tracking System (RCITS). The ongoing staff review of the submittal resulted in specific concerns that needed to be resolved prior to deciding to undertake review of the probabilistic risk assessment (PRA) also contained in the licensee submittal.
The licensee presentation addressed the following issues:
(1) unique design aspects of the SONGS-1 reactor coolant, secondary coolant and ECCS systems that in many cases are more conservative than newer plants, (2) an analysis of instances in which inadequate core cooling might occur at SONGS-1 (based upon existing instrumentation and emergency operating procedures) and an evaluation of the benefits of an RCITS in these instances, (3) a description of existing RCITS designs and what modifications would be required to install them in SONGS-1, (4) results of a value impact analysis of the installation of an RCITS at SONGS-1, and (5) proposed upgrades to existing instrumentation and procedures.
6610150464 861007 PDR ADOCK 05000206 P
-2 In response to a staff question regarding what RCITS designs had been installed in other reactors with vessels similar to SONGS-1, SCE stated that a Combustion Engineering Heated Junction Thermocouple Reactor Vessel Level Instrumentation system had recently been installed in the Haddam Neck plant, at a cost of $5 million. This cost is much lower than the $13 million estimated by SCE (based on a conceptual design) but is also significantly higher than the $1-2 million estimated by the NRC when the staff position was adopted. The NRC staff also noted that the PRA described by the licensee only addressed design-basis accident scenarios and that a major benefit of an RCITS would be its usefulness in accident scenarios beyond the design-basis of the facility.
The NRC staff reached no conclusions at the meeting regarding the SCE June 20, 1986 deviation request. When the ongoing staff review is completed the results will be provided to the licensee via formal correspondence.
Richard F. Dudley, Project Manager Project Directorate #1 Division of PWR Licensing-A
Enclosures:
As Stated cc's:
See Next Page Office:
P /PAD#1 S
PARP#
Surname: RDudley/tg K9sch CBerlinger GLear Date:
10/
/86 10/7/86 10/7/86 10/7 /86
.019 Mr. Kenneth P. Baskin San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 cc Charles R. Kocher, Assistant Joseph 0. Ward, Chief General Counsel Radiological Health Branch James Becletto, Esquire State Department of Health Southern California Edison Company Services Post Office Box 800 714 P Street, Office Bldg. 8 Rosemead, California 91770 Sacramento, California 95814 David R. Pigott Mr. Hans Kaspar, Executive Director Orrick, Herrington & Sutcliffe Marine Review Committee, Inc.
600 Montgomery Street 531 Encinitas Boulevard, Suite 105 San Francisco, California 94111 Encinitas, California 92024 Mr. Stephen B. Allman Ann C. Vasques, Chief San Diego Gas & Electric Company Radiological Programs Division P. 0. Box 1831 Governor's Office of Emergency Svcs.
San Diego, California 02112 State of California 2800 Meadowview Road Sacramento, CA 95832 ResidMEnt Inspector/San Onofre NPS c/o U.S. NRC P. 0. Box 4329 San Clemente, California 92672 Mayor City of San Clemente San Clemente, California 92672 Chai rman Board of Supervisors County of San Diego San Diego, California 92101 Director Energy Facilities Siting Division Energy Resources Conservation &
Development Commission 1516 - 9th Street Sacramento, California 95814 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane Walnut Creek, California 94596 Dieco
ENCLOSURE 1 October 2, 1986 - ICCI Meeting San Onofre, Unit 1 Attendance NAME ORGANIZATION R. Dudley NRC-PAD#1-PM R. J. Lee SCE T. G. Hook Erin Engr.
Jack Rainsberry SCE Larry Bennett SCE Thomas Morgan Erin Engineering Carl H. Berlinger NRC-PARS Larry Phillips NRC-DBL/RSB Gene Hughes Erin Engineering Rudy Karsch NRC-RSB PRESENTATION OF INADEQUATE CORE COOLING INSTRUMENTATION RESPONSE TO GENERIC LETTER NO. 82-28 SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 OCTOBER 2, 1986 BETHESDA, MARYLAND
AGENDA INADEQUATE CORE COOLING ANALYSIS AT SONGS-1
> o INTRODUCTION o SONGS-1 UNIQUENESS o ANALYSIS OF INADEQUATE CORE COOLING AT SONGS-1 o SYSTEMS ANALYSIS o RISK ANALYSIS o ACCIDENT CONSEQUENCES o REACTOR COOLANT INVENTORY TRACKING SYSTEMS AT SONGS-1 o VALUE IMPACT ANALYSIS OF INADEQUATE CORE COOLING WITH REACTOR COOLANT INVENTORY TRACKING SYSTEM INSTALLED AT SONGS-1 o SCE PROPOSED UPGRADES
SUMMARY
/CONCLUSIONS
ICC REGULATORY GUIDANCE o
TMI o
FAILURE TO DETECT ICC -
NO SMM o
FAILURE TO BELIEVE ICC INSTRUMENTATION o
FAILURE TO RESPOND TO ICC CONDITIONS o
ICC INSTRUMENTATION IMPORTANT o
PROCEDURE UPGRADE o
TRAINING UPGRADE o
ENVIRONMENTAL QUALIFICATION o
HARDWARE UPGRADES o
GENERIC LETTER 82-28 o
ICC INSTRUMENTATION REVIEW o
REACTOR COOLANT INVENTORY TRACKING SYSTEM (RCITS)
ICC HAS SIGNIFICANT l
l SCE ATTENTION l
SCE EVALUATION OF ICC INSTRUMENTATION AT SONGS-1 o
ECCS PERFORMANCE EXCEEDS THAT OF OTHER PLANTS o
PRESENCE OF NEED FOR INJECTION CLEAR IMMEDIATELY o
EOI'S PROVIDE APPROPRIATE INSTRUCTION o
TRAINING ASSURES ICC RECOGNITION AND RECOVERY o
CAREFUL ANALYSIS FOCUSES RESOURCES ON PROCEDURES RATHER THAN ADDITIONAL INSTRUMENTATION o
OFFSITE CONSEQUENCE OF ACCIDENT IS LESS THAN FOR MOST OTHER SITES o
COST HIGH WITH MUCH LOWER PAYBACK I
INSTALLATION OF A RCITS l
I AT SONGS-1 NOT NECESSARY I
AGENDA INADEQUATE CORE COOLING ANALYSIS AT SONGS-1 o INTRODUCTION o SONGS-1 UNIQUENESS o ANALYSIS OF INADEQUATE CORE COOLING AT SONGS-1 o SYSTEMS ANALYSIS o RISK ANALYSIS o ACCIDENT CONSEQUENCES o REACTOR COOLANT INVENTORY TRACKING SYSTEMS AT SONGS-1 o VALUE IMPACT ANALYSIS OF INADEQUATE CORE COOLING WITH REACTOR COOLANT INVENTORY TRACKING SYSTEM INSTALLED AT SONGS-1 o SCE PROPOSED UPGRADES o
SUMMARY
/CONCLUSIONS
SONGS-1 GENERAL DESIGN CHARACTERISTICS o
LOW POWER LEVEL -
1347 MW t o
2085 PSIG o
STAINLESS STEEL FUEL CLADDING o
LOW STEAM GENERATOR OPERATING PRESSURE -
710 PSIG o
HIGH HEAD, HIGH CAPACITY ECCS I
SONGS-1 IS AN EARLY GENERATION PWR l
l OF CONSERVATIVE DESIGN I
SONGS-1 PRIMARY SYSTEM o
POWER LEVEL -
ONLY 1347 MW (39% OF NEWER PLANTS) o POWER DENSITY -
4.8 KW/ft (84% OF NEWER PLANTS) o OPERATING PRESSURE -
2085 PSIG (93% OF NEWER PLANTS) o RCS VOLUME -
5.2 FT 3/MWt (60% HIGHER THAN NEW PLANTS) o VOLUME OF WATER ABOVE CORE HEIGHT -
4.8 FT 3/MWt (44% GREATER THAN NEWER PLANTS) o SIGNIFICANTLY LESS PIPING WITHIN RCS PRESSURE BOUNDARY THAN NEWER PLANTS (STEAM GENERATORS ARE ONLY 16' FROM REACTOR VESSEL) o SMALLER PIPING DIAMETERS THAN FOUND IN NEWER PLANTS I
I I
SONGS-1 PRIMARY I
l MORE FORGIVING l
I _
_ I
SONGS-1 SECONDARY SYSTEM o
SG PRESSURE -
710 PSIG (ONE AND A HALF AS MUCH MARGIN TO DESIGN LIMITS AS NEWER PLANTS) o SG INVENTORY -
32 LB/MWt (10% MORE THAN NEWER PLANTS) o NO MSIV'S AND MFIV'S -
FEWER SECONDARY-INDUCED TRANSIENTS SECONDARY SIDE l
MORE FORGIVING l
BASED ON DESIGN EVALUATION SINCE PRIMARY HAS MORE OPERATING MARGIN TO DESIGN AND SECONDARY HAS MORE OPERATING MARGIN TO DESIGN THEN CHALLENGES AT SONGS-1 LESS LIKELY AND MORE TIME TO DETECT AND RESPOND I
LESS LIKELY NEED AND I
MORE TIME I
SONGS-1 OPERATIONAL CHARACTERISTICS o
LOWER TRANSIENT FREQUENCY -
39% OF AVERAGE o
REDUCED POWER LEVEL o
HAS OPERATED FOR 15 YEARS -
PROVEN EQUIPMENT AND EXPERIENCED STAFF I
SONGS-1 LESS LIKELY TO SUFFER I
I ICC CHALLENGE AND HAS GOOD I
OPERATING RECORD
ECCS INJECTION CAPABILITY HIGH HEAD, HIGH CAPACITY SAFETY INJECTION SYSTEM o
ONE TRAIN PROVIDES:
5,375 GPM INJECTION (DESIGN BASIS) 1,800 GPM @ 1000 PSIG o
MAXIMUM INJECTION CAPABILITY UP TO 20,000 GPM @50 PSIG LARGE CAPACITY CHARGING SYSTEM o
ONE TRAIN HANDLES 3/8" LOCA WITH NONE OR SLIGHT LOSS OF NORMAL RCS PRESSURE o
FLOW UP TO 300 GPM PER PUMP DURING LOCA o
FLOW @ 1000 PSIG IS COMPARABLE TO HPSI FLOWS AT OTHER PLANTS AT SG SAFETY VALVE SETPOINT l SONGS-1 HAS A HIGH l I
PERFORMANCE ECCS I
SAN UNDFRE UNIT 1 SAFETY INJECTIuN SYSTEM TO FIRST PT F.C OUTSIDE CONTAINHENT INSIDE CONTAINMENT HP HEATER V
HV852A RCS LOOP A COLD MOVB50A S15004 LEG REFUELING WATER STORAGE TANK MI EDAE SAFETY INJECTION PUMPS C R S - D -
1 P U M P S F..
H F.O.
_0 F\\SS-438 HV851A LSI304 HVB53A FWS-G-3A FROM SECDND C.RCS LOtP PT LP HEATER HV954A B COLD MOV050B sisQ10 LEG SIS320 FROM SECOND F.C.
- r.
3 FWS-439 HV851B SIS303 HV853B FWS-G-3B STS301 SIS-G-50B RCS LOOP C COLD MOV850C SIS003 LEG TO FIRST PT F.C.
mCU IllC-lTc o r V CTA 1H#G D
'O F
VC~----LA MfIV-IIOQC VCC3307 BEACTC WA0h-VflC304 VCC,33E V--2 TOl CCV FEAT DC0WMR CRS--F-lIF R~w~ATt t737A c
w:
MOTh6 CVN
'M CWMM LDNE Lap A F'l CV 737B WAT F.YCJW*f ALDLY SPRIAY
-4 u
ZJl LINIZRE JNI T A
OIRQIN 5-(Z C.
TO RCP SUPPLY F.C.
FILTER A
FCV-11151D SIS F.D.
TO RCS F.0 COLD LEG A RCP-315 FCV-1115A RCP-317 MOV-356 TO RCP SUPPLY FILTER B FCV-1115E FLR F.D.
TO RCS MOV-18OLDCSEG B
RCP-360 FCV-15B RCP-362 MOV-357 TO RCP SUPPLY MDV-19 F.C.
FCV-1115F SIS sm MSUPPLY FILTE F..
TO RCS RCP-316 FCV-115C RCP-319 MOV-358 COLD LEG C RCP C-425 RCP-301 RCP-309 RCP C-42 RCP-3n0I2 RCP-310
COMPARSION OF SONGS-I AND TYPICAL PWR DESIGN BASIS INJECTION FLOW SMALL BREAK 5000-LOCA........................
- SONGS-I
-e TYPICAL PWR SAFETY :INJECTIpN SYSTEM FLOW!
INJECTION FLOW (GPM) 3000 --------
2000 ------
CHARGING SYSTEM tooo ---------:
F.
0..
0 50 100 150 200 400 600 700 800 900 1000 1100 1200 1300 RCS PRESSURE (PSIG)
- 0 TIMING -
A KEY SAFETY FACTOR o
TMI DEMONSTRATED SIGNIFICANCE OF TIMING o
LONGER TIME ALLOWS MORE COGNITION o
LONGER TIME PROVIDES MORE OPPORTUNITY TO RECOVER o
TIMING DRIVEN BY SYSTEM VOLUMES, PRESSURES, AND FLOW RATES I
SONGS-1 HAS MORE TIME I
I TO RESPOND I
SONGS-1 DESIGN AND OPERATION o
SONGS-1 IS A SIMPLE PLANT OF CONSERVATIVE DESIGN o
PRIMARY SYSTEM MORE FORGIVING o
SECONDARY SYSTEM MORE FORGIVING o
FEWER TRANSIENTS o
MORE TIME AVAILABLE TO RESPOND TO TRANSIENTS o
ECCS HAS GREATER CAPABILITY II l
SONGS-1 HAS UNIQUELY I
BETTER RESPONSE TO TRANSIENTS
AGENDA INADEQUATE CORE COOLING ANALYSIS AT SONGS-1 o INTRODUCTION o SONGS-1 UNIQUENESS
> o ANALYSIS OF INADEQUATE CORE COOLING AT SONGS-1 o SYSTEMS ANALYSIS o RISK ANALYSIS o ACCIDENT CONSEQUENCES o REACTOR COOLANT INVENTORY TRACKING SYSTEMS AT SONGS-1 o VALUE IMPACT ANALYSIS OF INADEQUATE CORE COOLING WITH REACTOR COOLANT INVENTORY TRACKING SYSTEM INSTALLED AT SONGS-1 o SCE PROPOSED UPGRADES
SUMMARY
/CONCLUSIONS
INADEQUATE CORE COOLING (ICC)
DEFINITION o
TWO PHASE FROTH BELOW TOP OF CORE AND o
CORE HEATUP IN EXCESS OF PREDICTED PREREQUISITE FOR CORE DAMAGE ICC IS CORE HEATUP BEYOND DESIGN I
BASIS AND POTENTIAL FOR CORE DAMAGE
ICC AT SONGS-1 WITH EXISTING INSTRUMENTATION SBLOCA BOUNDS EVENTS WHERE ICC INSTRUMENTATION USEFUL o
SG TUBE RUPTURE o
OVERCOOLING EVENT o
LOSS OF INSTRUMENT BUS OR CONTROL SYSTEM UPSETS o
PUMP SEAL FAILURES SBLOCA SIZES OF CONCERN -
3/8" TO 2.55" o
3/8" -
CHARGING HANDLES WITHOUT PRESSURE DROP o
2.55" -
LOOP SEAL BLOWS IN LESS THAN 400 SECONDS WITH DESIGN BASIS SI FLOW ICC INSTRUMENTATION BENEFICIAL l
IN SBLOCA EVENTS
3/8" TO 2.55" BREAK SIZE -
RANGE IS NARROWER THAN OTHER PWR's (NEWER PLANTS UP TO 4")
0 o
MAXIMUM CLAD TEMPERATURE IS 850 F o
PLANT RESPONSE INDEPENDENT OF RCP STATUS o
NO DRAINING OF LOOP SEAL(S)
FOR 3/8" TO 2.55" BREAKS o
SI FLOW MATCHES OR EXCEEDS BREAK FLOW I
NEED FOR ICC INSTRUMENTATION I I
AT SONGS-1 LESS CRITICAL l
I SINCE SBLOCA RANGE NARROWER I
ICC DETECTION AT SONGS-1 INSTRUMENTATION o PRESSURIZER PRESSURE o REDUNDANT SUBCOOLING MARGIN MONITORS (2) o REDUNDANT CORE EXIT THERMOCOUPLES (28) o REDUNDANT RCS HOT LEG RTD's (6)
AUTOMATIC RESPONSE o SIS SIGNAL ON LOW PRESSURIZER PRESSURE OR HIGH CONTAINMENT PRESSURE o SI INITIATES, CHARGING CONTINUES PROCEDURES o NO DIRECTION TO TERMINATE INJECTION EARLY o CRITICAL SAFETY FUNCTION STATUS TREES o
REVIEWED IN 2 MINUTES AND EVERY 20 MINUTES OR WHEN OPERATORS LEAVING A PROCEDURE o DIRECTS SPECIFIC REVIEW OF ICC INSTRUMENTATION INDICATIONS o 1 OF 2 SMM'S o
5 OF 28 CET'S o
2 OF 6 HOT LEG RTD'S I
EMERGENCY PROCEDURES AND REDUNDANT I
INSTRUMENTATION ASSURE DETECTION I
I OF ICC I
DETECTION RANGE OF ICC INSTRUMENTATION AT SONGS-1 too 90 -
50 TOP OF CORE REACTORr+
VESSEL 50 LEVEL (PERCENT) 40 30 BOTTOM OF CORE
- 1.
20 i
1I I
S70-OHOL CETS ICC INSTRUMENTATION
NUCLEAR GENERATION Si EMERGENCY OPERAG INSTRUCTION O1-1.0-1 UNIT 1 REVISION 1 PAGE 3 OF 29 CRITICAL SAFETY FUNCTION STATUS TREES PRIORITY - 2 CORE COOLING IS RCS YES ARE FIVE OR MORE YES s1o-1.2-1 SUBCOOLING CORE EXIT TC'sTo
-I$" LESS THAN GREATER THAN Inadequate 400F?
NO 1200 0F?
NO Core Cooling ARE ANY TWO YES RCS HOT LEG RTD's GREATER THAN 6800F?
NO ARE IV OR 7;;MREC YES SggggggiglS1-1.-
2 CORE EXIT TC's Response To GREATER THAN Potential 6800F?
NO-Loss of Core Cooling 0
0 0
000000 501-1.2-3 Response To Saturated Core Cooling Conditions CSF SATISFIED
ICC PROCEDURES o
EOI S01-1.2-3, RESPONSE TO SATURATED CORE COOLING CONDITIONS OBJECTIVE TO RESTORE 0
40 F SUBCOOLING MARGIN BY ESTABLISHING SI AND CHARGING FLOW o
EOI 501-1.2-2, RESPONSE TO POTENTIAL LOSS OF CORE COOLING OBJECTIVE TO PREVENT ICC CONDITION BY ESTABLISHING SI AND CHARGING FLOW o
EOI S01-1.2-1, RESPONSE TO INADEQUATE CORE COOLING OBJECTIVE TO PREVENT CORE DAMAGE BY ESTABLISHING ALTERNATE MEANS OF FLOW I
GRADED RESPONSE TO CONDITIONS I
I LEADING TO ICC ASSURES DETECTION l
l AND APPROPRIATE RESPONSE I
I _
_ I
RESPONSE TO ICC AT SONGS-1 o THREE EMERGENCY PROCEDURES DESCRIBING RESPONSE TO ICC o DIRECTED TO RESPONSE PROCEDURES FROM CRITICAL SAFETY FUNCTION STATUS TREES PROCEDURE o PRIMARY OBJECTIVE TO MAINTAIN SI AND CHARGING FLOW o USE OF SPECIFIC ALTERNATE FLOW PATHS DIRECTED IF SI FLOW CANNOT BE MAINTAINED I
A I
PROCEDURES ASSURE RESPONSE TO ICC
RISK ANALYSIS PERSPECTIVE o
MUST DEFINE WINDOW OF VULNERABILITY o
MUST CALCULATE CHALLENGE FREQUENCY o
THEN ESTABLISH RESPONSE TO BE TAKEN o
AND EVALUATE PROBABILITY OF SUCCESS o
INCLUDE CAPABILITY THE MODIFICATION WOULD ADDRESS I
MODEL ALLOWS l
l QUANTIFICATION OF l
I VULNERABILITY I _
1
RISK OF CORE DAMAGE WITHOUT RCITS
-2 o SBLOCA FREQUENCY OF 2 X 10 /YR ASSUMED CONSERVATIVE o INSTRUMENTATION AND PROCEDURES MODELED IN FAULT TREES o SI INITIATED, ULTIMATELY TERMINATED AND REINITIATED (AUTO OR MANUAL) -
CONSERVATISM o RECIRCULATION MODELED o CHARGING CONTRIBUTION NOT INCLUDED IN INJECTION MODEL -
CONSERVATISM o CONSIDERABLE ATTENTION TO INSTRUMENTATION AND OPERATOR RESPONSE I
RISK OF CORE DAMAGE WITH I
I EXISTING INSTRUMENTATION AND I I
PROCEDURES ANALYZED I
RESULTS OF RISK EVALUATION o
CORE DAMAGE FREQUENCY LOW (<4E-5/YR) o MAIN CONTRIBUTORS o
FAILURE OF INITIAL SI (HARDWARE) o FAILURE DURING SWITCHOVER TO RECIRCULATION (RWST LEVEL) o FAILURE OF EXISTING INSTRUMENTATION -
ALMOST NEGLIGIBLE o
UNCERTAINTY IS LARGE I
RISK LOW, INFORMATION AVAILABLE l TO OPERATOR NOT A I
l MAJOR CONTRIBUTOR I
CONSEQUENCES OF ACCIDENT o
SMALLER SOURCE TERM SINCE CORE SIZE IS SMALLER 1347 MW t o ECCS CAPABILITY HIGH FOR SBLOCA o ONLY ONE SECTOR IS POPULATED BY CIVILIANS (OTHERS ARE OCEAN OR SPARSELY-POPULATED MILITARY RESERVATION) o LOW RISK PROFILE CONFIRMED BY CRAC ANALYSES I
OFFSITE CONSEQUENCES I l
ARE LOWER I
AGENDA INADEQUATE CORE COOLING ANALYSIS AT SONGS-1 o INTRODUCTION o SONGS-1 UNIQUENESS o ANALYSIS OF INADEQUATE CORE COOLING AT SONGS-1 o SYSTEMS ANALYSIS o RISK ANALYSIS o ACCIDENT CONSEQUENCES E> o REACTOR COOLANT INVENTORY TRACKING SYSTEMS AT SONGS-1 o
VALUE IMPACT ANALYSIS OF INADEQUATE CORE COOLING WITH REACTOR COOLANT INVENTORY TRACKING SYSTEM INSTALLED AT SONGS-1 o
SCE PROPOSED UPGRADES
SUMMARY
/CONCLUSIONS
RCITS CHARACTERISTICS CE -
HEATED JUNCTION THERMOCOUPLE (HJTC) SYSTEM o
TEMPERATURE DETECTORS AT LEVEL INCREMENTS IN VESSEL o
SIMPLE DESIGN o
REMOVAL OF IN-CORE INSTRUMENTATION o
LEVEL INDICATION RESOLUTION LIMITED o
VESSEL LEVEL MONITORED ONLY DOWN TO TOP OF CORE W -
REACTOR VESSEL LEVEL MONITORING (RVLIS) SYSTEM o
MEASURES VESSEL DELTA P o
RVLIS INDICATION DEPENDENT ON RCP STATUS o
COMPLEX SYSTEM WITH NUMEROUS COMPONENTS l
RCITS ARE NOT WITHOUT l
l LIMITATIONS I
TYPICAL CE HJTC SYSTEM ELECTRICAL CONNECTORS CONTAINMENT AND CABLES WALL PRESSURE BOUNDARY COMPONENTS HJTC PROBE ASSEMBLY SUPPORT STRUCTURE FOR PROBE ASSEMBLY
TYPICAL W RVLIS SYSTEM HYORAULIC ISOLATOR (TYPICAL)
HEAD TINSTRUMENT HEADTRAIN 8
RACK PENETRATION TRAIN O
TRAIN 9 SEAL TABLE 4-CONTAINMENT WALL T
- 0 PROBLEMS OF RCITS INSTALLATION AT SONGS-1 o GENERIC W RVLIS CANNOT BE INSTALLED AT SONGS-1 NO VESSEL BOTTOM PENETRATIONS o USE OF W RVLIS REQUIRES NEW DESIGN -
HIGH COST, DECREASED LEVEL INDICATING RANGE o HJTC -
CHANGE REACTOR VESSEL HEAD PENETRATIONS FOR PROBE o HJTC -
ANALYSIS OF CORE HYDRAULICS EFFECTS REQUIRED o RELOCATION OF INSTRUMENTATION IN SMALL CONTROL ROOM o
$13+ MILLION TO INSTALL -
OTHERS PLANTS < $5 MILLION o COST SIGNIFICANTLY HIGHER PER MWe FOR SONGS-1 SINCE RATED POWER IS 1/3 OTHERS o COST SIGNIFICANTLY HIGHER FOR SONGS-1 SINCE ONLY 18 YEARS OF OPERATING LIFE REMAINS PER LICENSE I
I I
COST IS VERY HIGH l
I DUE TO UNIQUE DESIGN l
ALARA CONSIDERATIONS OF RCITS INSTALLATION AT SONGS-1 o
>40 MAN-REM DOSE EXPECTED FROM INSTALLATION o
MAN-REM DOSE TO MAINTAIN SYSTEM EXPECTED TO BE HIGH (APPROX. 1 MAN-REM/YR)
PLANT ALARA OBJECTIVES l
l WOULD BE COMPROMISED l
AGENDA INADEQUATE CORE COOLING ANALYSIS AT SONGS-1 o
INTRODUCTION o
SONGS-1 UNIQUENESS o
ANALYSIS OF INADEQUATE CORE COOLING AT SONGS-1 o
SYSTEMS ANALYSIS o
RISK ANALYSIS o
ACCIDENT CONSEQUENCES o
REACTOR COOLANT INVENTORY TRACKING SYSTEMS AT SONGS-1
> o VALUE IMPACT ANALYSIS OF INADEQUATE CORE COOLING WITH REACTOR COOLANT INVENTORY TRACKING SYSTEM INSTALLED AT SONGS-1 o
SCE PROPOSED UPGRADES o
SUMMARY
/CONCLUSIONS
VALUE OF RCITS AREA OF EXISTING I
RCITS RISK l
CAPABILITY VALUE FREQUENCY OF l
NA NO CHANGE SBLOCA I
DETECTION OF l
DATA l
CET'S DATA DETECTION OF I
COGNITION l
RESPONSE
I EOI'S I
NO CHANGE I
I l
RCITS ONLY ADDS MORE I l
DATA TO DETECT ICC l
Il I
RISK OF CORE DAMAGE WITH RCITS INSTALLED o RCITS MODELED AS BACKUP TO EXISTING ICC INSTRUMENTATION o ASSUMED RCITS INDICATION WOULD DIRECT USE OF EOI's S01-1.2-2, RESPONSE TO POTENTIAL LOSS OF CORE COOLING OR SO1-1.2-1, RESPONSE TO INADEQUATE CORE COOLING DEPENDING ON LEVEL o
DECREASE OF CORE DAMAGE FREQUENCY SMALL
-12 8 x 10
/YR FOR RCITS TO BE USEFUL, THE FOLLOWING WOULD HAVE TO FAIL:
BOTH SMM'S OR 5 RTD'S OR OPERATOR ACTION TO INITIATE SI AND FLOW 24 CET'S I
I RCITS WOULD l
HAVE MINIMAL VALUE AT l
SONGS-1
DETECTION RANGE OF ICC INSTRUMENTATION AT SONGS-1 so 90 7o-HOT LEGS 60-TOP OF CORE REACTOR VESSEL LEVEL (PERCENT) 40
'o BOTTOM OF CORE 20 Sm WTC RYIS RTD'S CET'S TCC INSTRUMENTATION
VALUE AND IMPACT OF RCITS AT SONGS-1 o
SAFETY ENHANCEMENT
-12 o
MINIMAL -
8 x 10
/YR REDUCTION IN CORE DAMAGE FREQUENCY o
COST o
HIGH -
$13 MILLION o
ALARA CONSIDERATIONS o
HIGH
>40 MAN-REM I
VALUE IS LOW AND l
l IMPACT IS HIGH l
I1 _
I
AGENDA INADEQUATE CORE COOLING ANALYSIS AT SONGS-1 o INTRODUCTION o SONGS-1 UNIQUENESS o ANALYSIS OF INADEQUATE CORE COOLING AT SONGS-1 o SYSTEMS ANALYSIS o RISK ANALYSIS o ACCIDENT CONSEQUENCES o REACTOR COOLANT INVENTORY TRACKING SYSTEMS AT SONGS-1 o
VALUE IMPACT ANALYSIS OF INADEQUATE CORE COOLING WITH REACTOR COOLANT INVENTORY TRACKING SYSTEM INSTALLED AT SONGS-1
[> o SCE PROPOSED UPGRADES
SUMMARY
/CONCLUSIONS
SCE PROPOSED UPGRADES o
ENHANCED ICC PROCEDURES o
CET UPGRADES o
DISPLAY UPGRADES o
SPDS ENHANCEMENT I
A I
ALTERNATIVES ARE MORE COST EFFECTIVE
COMPARISON OF OPTIONS II I
AREA OF l EXISTING l
RCITS l
VALUE OF RISK l CAPABILITY j
VALUE SCE RESPONSE FREQUENCY l
OF SBLOCA l NA NO CHANGE l NO CHANGE I
ANOTHER IMPROVED DETECTION OF l SMM, RTD'S l
DETECTION l BASELINE ICC-DATA l CET'S l
SYSTEM CAPABILITY I
IMPROVED DETECTION OF I PROCEDURES -
I l
BASELINE ICC-COGNITION l EOI'S I
NO CHANGE I CAPABILITY
_ I _
_ I I
I I
I IMPROVED I PROCEDURES -
l I
BASELINE
RESPONSE
l EOI'S I
NO CHANGE l CAPABILITY I
I _
_ I _
COGNITION AND RESPONSE ADDRESSED l
l BEST BY PROCEDURE/TRAINING UPGRADES I
AGENDA INADEQUATE CORE COOLING ANALYSIS AT SONGS-1 o
INTRODUCTION o
SONGS-1 UNIQUENESS o
ANALYSIS OF INADEQUATE CORE COOLING AT SONGS-1 o
SYSTEMS ANALYSIS o
RISK ANALYSIS o
ACCIDENT CONSEQUENCES o
REACTOR COOLANT INVENTORY TRACKING SYSTEMS AT SONGS-1 o
VALUE IMPACT ANALYSIS OF INADEQUATE CORE COOLING WITH REACTOR COOLANT INVENTORY TRACKING SYSTEM INSTALLED AT SONGS-1 o
SCE PROPOSED UPGRADES E>o
SUMMARY
/CONCLUSIONS
CONCLUSIONS/
SUMMARY
o SONGS-1 IS UNIQUE o
EXISTING ICC INSTRUMENTATION & PROCEDURES ARE ADEQUATE o
RCITS HAS LIMITED BENEFIT AT SONGS-1 o
RISK OF CORE DAMAGE FROM ICC IS LOW AT SONGS-1 o
VALUE OF RCITS NEGLIGIBLE AT SONGS-1 o
INSTALLATION OF RCITS AT SONGS-1 WOULD HAVE SIGNIFICANT COSTS AND ALARA IMPACTS o
ENHANCED PROCEDURES AND TRAINING COUPLED WITH HARDWARE UPGRADES WILL BE MORE EFFECTIVE IN ASSURING SAFETY I
SCE ALTERNATE UPGRADES I
SHOULD BE APPROVED I
Distribution Copies:
Docket Files NRC PDR Local POR PAD#1 r/f PAD#1 s/f TNovak NThompson, DHFT GLear RDudley PShuttleworth OGC-Bethesda Eordan BGrimes JPartlow ACRS (10)
NRC Participants