ML16341E960
| ML16341E960 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/11/1989 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-71387, TAC-71388, NUDOCS 8901190366 | |
| Download: ML16341E960 (70) | |
Text
January 11, 1989 DOCKET NOS.: 50-275 and 50-323 LICENSEE:
PACIFIC GAS AND ELECTRIC COMPANY (PGImiE)
FACILITY:
DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1
AND 2
SUBJECT:
SUMMARY
OF JANUARY 5, 1989 PUBL'IC MEETING TO DISCUSS PROPOSED USE OF VANTAGE 5 FUEL ASSEMBLIES IN DIABLO CANYON UNITS 1
AND 2 (REFERENCE LAR 88-08 AND TAC NOS.
71387 AND 71388)
On January 5,
1989 the NRC staff met with the licensee and its consultants to discuss the use of Vantage 5 fuel assemblies in Diablo Canyon.
The licensee had proposed the use of Vantage 5 fuel in a license amendment application submitted on November 29, 1988.
In this application, the licensee proposed to begin using Vantage 5 fuel during Operating Cycle 4.
Cycle 4 is scheduled to start in October 1989 for Unit 1 and in April 1990 for Unit 2.
Cycles 4 and 5
would be mixed cores.
That is, some fuel would be the low-parasitic (LOPAR) assemblies used in Cycles 1, 2 and 3, and some would be Vantage 5 assemblies.
Cycle 6 and all subsequent cycles would contain only Vantage 5 fuel.
The meeting agenda is given in Enclosure l.
Attendees at the meeting are given in Enclosure 2.
The slides presented by the licensee are given in Enclosure 3.
At the conclusion of the meeting, the NRC staff indicated that the meeting had been helpful in gaining a better understanding of the proposed license amendment, and requested that the licensee provide additional information in two areas.
Specifically, the staff requested that the licensee:
(1) identify where the November 29, 1988 application addresses each of the thirteen conditions set forth in the staff's generic safety evaluation report approving the" use of Vangage 5 fuel, and (2) provide the details of the analysis used to demonstrate control rod insertabi lity for the current Diablo Canyon fuel.
original signed by Harry Rood, Senior Project Manager Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects-
Enclosures:
1.
Agenda 2.
Attendees 3.
PG&E Slides cc w/encls:
see next page DRSP/PD5 HRood:dr G
n ghton 01/( I /89 01/)i/89 8901i90366 SPOiii PDR ADOCK 05000275 P
PDC DISTRIBUTION NRC 8
LPDRs BGrimes LPhi 1 lips GKnighton OGC EJordan PDV Files ACRS-10 GHodges SWu MJohnson HRood JLee
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I UNITED STATES NUCLEAR REGULATORY COMMI ION WASHINGTON, D. C. 20555 January 11, 1989 DOCKET NOS.: 50-275 and 50-323 LICENSEE'ACIFIC GAS AND ELECTRIC COMPANY (PGSE)
FACILITY:
SUBJECT:
DIABLO CANYON NUCLEAR PONER PLANT, UNITS 1
AND 2
SUMMARY
OF JANUARY 5, 1989 PUBLIC MEETING TO DISCUSS PROPOSED USE OF VANTAGE 5 FUEL ASSEMBLIES IN DIABLO CANYON UNITS 1
AND 2 (REFERENCE LAR 88-08 AND TAC NOS.
71387 AND 71388)
On January 5,
1989 the NRC staff met with the licensee and its consultants to discuss the use of Vantage 5 fuel assemblies in Diablo Canyon.
The licensee had proposed the use of Vantage 5 fuel in a l'icense amendment application submitted on November 29, 1988.
In this application, the licensee proposed to begin using Vantage 5 fuel during Operating Cycle 4.
Cycle 4 is scheduled to start in October 1989 for Unit 1 and in April 1990 for Unit 2.
Cycles 4 and 5
would be mixed cores.
That is, some fuel would be the low-parasitic (LOPAR) assemblies used in Cycles 1, 2 and 3, and some would be Vantage 5 assemblies.
Cycle 6 and all subsequent cycles would contain only Vantage 5 fuel.
The meeting agenda is given in Enclosure l.
Attendees at the meeting are given in Enclosure 2.
The slides presented by the licensee are given in Enclosure 3.
At the conclusion of the meeting, the NRC staff indicated that the meeting had been helpful in gaining a better understanding of the proposed license amendment, and requested that the licen'see provide additional information in two areas.
Specifically, the staff requested that the licensee:
(1) identify where the November 29, 1988 application addresses each of the thirteen conditions set forth in the staff's generic safety evaluation report approving the use of Vangage 5 fuel, and (2) provide the details of the analysis used to demonstrate control rod insertabi lity for the current Diablo Canyon fuel.
Enclosures:
1.
Agenda 2.
Attendees 3.
PGSE Slides cc: w/encls - see next page Harry Ro
, Senior Project Manager Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects
1
~ !
I f
Mr. J.
D. Shiffer Pacific Gas and Electric Company Diablo Canyon CC:
Richard F. Locke, Esq.
Pacific Gas 5 Electric Company Post Office Box 7442 San Francisco, California 94120 NRC Resident Inspector Diablo Canyon Nuclear Power Plant c/o U.S. Nuclear Regulatory Commission P. 0.
Box 369 Avila Beach, California 93424 Janice E. Kerr, Esq.
California Public Utilities Commission 350 McAllister Street San Francisco, California 94102 Ms. Sandra A. Silver 660 Granite Creek Road Santa Cruz, California 95065 Mr.
W. C. Gangloff Westinghouse Electric Corporation P. 0.
Box 355 Pittsburgh, Pennsylvania 15230 Managing Editor San Luis Obispo County Telegram Tribune 1321 Johnson Avenue P. 0.
Box 112 San Luis Obispo, California 93406 Mr. Leland M. Gustafson, Manager Federal Relations Pacific Gas and Electric Company 1726 M Street, N.
W.
Washington, DC 20036-4502 Dian M. Grueneich Marcia Preston Law Office of Dian M. Grueneich
'380 Hayes Street, Suite 4
San Franci sco, Gal iforni a 94102 Mr. Dick Blakenburg Editor 8 Co-Publisher South County Publishing Company P. 0.
Box 460 Arroyo Grande, California 93420 Bruce Norton, Esq.
c/o Richard F. Locke, Esq.
Pacific Gas and Electric Company Post Office Box 7442 San Francisco, California 94120 Dr. R.
B. Ferguson Sierra Club - Santa Lucia Chapter Rocky Canyon Star Route Creston, California 93432 Chairman San Luis Obispo County Board of Supervisors Room 270 County Government Center San Luis Obispo, California 93408 Director Energy Facilities Siting Division Energy Resources Conservation and Development Commission 1516 9th Street Sacramento, California 95814 Ms. Jacquelyn Wheeler 3033 Barranca Court San Luis Obispo, California 93401
f L
f
Pacific Gas II Electric Company Diablo Canyon CC:
Ms. Laurie McDermott, Coordinator Consumers Organized for Defense of Environmental Safety 731 Pacific Street, Suite 42 San Luis Obispo, California 93401 Mr. Jack McGurk, Acting Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building 0'8 Sacramento, California 95814 Regional Administrator, Region V
U.S. Nuclear Regulatory Co(omission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Ms.
Nancy Culver 192 Luneta Street San Luis Obispo, California 93401 President California Public Utilities Commission California State Building 350 McAllister Street San Franc isco, Ca 1 iforni a 94102 Michael M. Strumwasser, Esq.
Special Assistant Attorney General State of California Department of Justice 3580 Wilshire Boulevard, Room 800 Los Angeles, California 90010
r
/
f
Q ENCLOSURE I PGKE VANTAGE 5 MEETING WITH NRC JANUARY 5, 1989 AGENDA NRC INTRODUCTORY REMARKS PGKE INTRODUCTORY REMARKS VANTAGE 5 DESCRIPTION NUCLEAR-THERMAL/HYDRAULICDESIGN MECHANICAL OVERVIEW CHAPTER 15 ACCIDENTS OVERVIEW PGSE
SUMMARY
NRC STATEMENTS
F
ENCLOSURE 2
ATTENDEES Public Meeting on Use of Vantage 5 Fuel in Diablo Canyon
- Thursday, January 5,
1989 NAME S.
Bh~a tacharya C. 0. Coffer Stan Davidson Michael A. Emery R.
P. Knott Y. C.
Lee B. S.
Lew Mike Muenks D.
W. Ogden L. Phillips Harry Rood, Hans Schierling Anthony M. Silari T. F.
Timmons James Tomkins G.
C.
Wu Shih-Liang Wu ORGANIZATION PGSE/NRA Westinghouse/Fuel Licensing Westin'ghouse/Nuclear Safety Westinghouse/Product Development
& Testing Westinghouse/Product Development 8 Testing PGSE/NRA Westinghouse/NFBU Projects PGSE/NRA NRC/NRR/DEST/SRXB NRC/NRR/PDV Tenera Westinghouse/Nuclear Safety Westinghouse/Nuclear Safety PG8E/Nuclear Operations PGSE/NRA NRC/NRR/DEST/SRXB
/
ENCLOSURE 3 HRO OL GY F
A TA E LI ENSI G
E E T o
"KICKOFF" MEETING INTRODUCING VANTAGE 5 DESIGN MAY 1983 FEATURES TO NRC CORE PERFORMANCE BRANCH o
SUBMITTAL OF "REFERENCE CORE REPORT VANTAGE 5 FUEL ASSEMBLY" WCAP-10444 DEC 1983 o
STARTUP OF FULL SCALE IFBA DEMO PROGRAM IN TURKEY POINT UNIT 4, CY 10 o
STARTUP OF IFM GRID DEMO PROGRAM IN MCGUIRE UNIT 1, CY 2 MAY 1984 JUN 1984 o
STARTUP OF ALL VANTAGE 5 FEATURES DEMO PROGRAM DEC 1984 IN VIRGIL SUMMER CY 2 o
SER ISSUED ON WCAP-10444 JUL 1985 o
SUBMITTAL OF UE CALLAWAY VANTAGE 5 LICENSING AMENDMENT o
SER ISSUED FOR CALLAWAY VANTAGE 5 LICENSING AMENDMENT o
SUBMITTAL OF SCGEE VIRGIL SUMMER VANTAGE 5 AMENDMENT o
SER ISSUED FOR VIRGIL SUMMER VANTAGE 5 LICENSING AMENDMENT o
SUBMITTAL OF PGRE DIABLO CANYON UNITS 1 AND 2 VANTAGE 5 LICENSING AMENDMENT MAR 1987 OCT 1987 MAY 1988 NOV 1988 NOV 1988 o
SCHEDULED SUBMITTAL FOR CP8L SHEARON HARRIS VANTAGE 5 LICENSING AMENDMENT MAR 1989
l 1
VANTAGE FUEL ASSEMBLY FEATURES o
OPTIMIZED ROD DIAMETER o
ZIRCALOY GRIDS (EXCEPT TWO INCONEL END GRIDS) o INTERMEDIATE FLOW MIXER GRIDS o
AXIAL BLANKETS INTEGRAL FUEL BURNABLE ABSORBERS o
RECONSTITUTABLE TOP NOZZLE EXTENDED BURNUP CAPABILITY
1
VANTAGE 5 FEAT RE A
EPTA CE A D EXPERIE E
(NUMBER OF REACTORS USING PARTICULAR FEATURE)
PLANT 14X14
, (9 PLANTS)
AXIAL
~BLANKET 3I IFM 1
X1 LY
~IFB EX BIJ
~RT 1I 1I 4I 2S 3S 15X15 (9
PLANTS) 1S 1I 2S 3I 3S 3I 4S 16X16 (2 PLANTS) 1S 1S 17X17 (40 PLANTS) 4I 5S 2I 3S 3I 5S 4I 11S 10I 15S TOTAL NO.
OF REACTORS (60 PLANTS) 13 24 39 KEY: "I" INDICATES VANTAGE 5 FEATURE IN SERVICE IN REACTOR AS OF JULY 88 "S"
INDICATES VANTAGE 5 FEATURE SCHEDULED FOR SERVICE IN REACTOR AS OF JULY 88
I
COMPARISON OF VANTAGE 5 SAFETY. PARAMETERS AND DESIGN FEATURES PARAMETER FEATURE FUEL TYPE CY3 CY4 LOPAR LOPAR/V5 DIABLO CANYON UNITS 1 2 CALLAWAY CY2 CY3 VIRGIL SUMMER CY4 CY5 LOPAR/OFA LOPAR/
LOPAR LOPAR/V5 OFA/V5 POWER 3338/3411 3338/3411 3411 3565 2775 2775 1.55 1.62/1.65 1.55 1.65*
1.55 1.62/1.68 Fq 2.32 2.45 2.32 2.50*
2.28 2.45 PMTC YES YES NO YES*
NO YES SGTP 15K 10K 10K 15K
- TO BE IMPLEMENTED IN CY4 FOR STARTUP IN 1989
8 DPP IT1 Y LE I
PLA CYCLE f TRANSITION CYCLE CYCLE LENGTH, EFPD LOPAR ASSEMBLIES VANTAGE 5 ASSEMBLIES STARTUP DATE FIRST 375 137 56 12/89 391 61 NONE 132 193 5/91 12/92 SECOND ALL V-5
C
THERMAL-YDRAULI E I APPR ED METH D
o DESIGN METHODOLOGY WCAP-8567 "IMPROVED THERMAL DESIGN PROCEDURE" o
DNB METHODOLOGY FOR LOPAR FUEL WRB-1 WCAP-8763-A, NEW WESTINGHOUSE CORRELATION WRB-1 FOR PREDICTING CRITICAL HEAT FLUX IN ROD BUNDLES WITH MIXING VANE GRIDS" FOR VANTAGE 5 FUEL WRB-2 WCAP-10444-P-A "REFERENCE CORE REPORT VANTAGE 5 FUEL ASSEMBLY" o
TRANSITION CORE METHODOLOGY WCAP-9500-A, "REFERENCE CORE REPORT 17X17 OPTIMIZED FUEL ASSEMBLY.
LETTER FROM E.
P.
RAHE (W)
TO MILLER (NRC)
NS-EPR-2573, WCAP-9500 AND WCAP 9401/9402 NRC SER MIXED CORE COMPATABILITY ITEMS.
LETTER FROM M.
W.
HODGES (NRC)
TO W. J.
JOHNSON (W),
NRC SER ON VANTAGE 5 TRANSITION CORE EFFECTS o
FUEL ROD PERFORMANCE WCAP 8720 "IMPROVED ANALYTICALMODELS USED IN WESTINGHOUSE FUEL ROD DESIGN COMPUTATIONS."
WCAP-8720-A2, "REVISED PAD CODE THERMAL SAFETY MODEL" WCAP-8691 "FUEL ROD BOW EVALUATION"
I
NUCLEAR DESIG APPR VED METHODS o
MCAP-10444-P-A
"REFERENCE CORE REPORT VANTAGE 5
FUEL ASSEMBLY o
MCAP-9272-P-A
"MESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY" o
MCAP-9485-P-A PALADON WESTINGHOUSE NODAL COMPUTER CODE"
i
o CRITERIA (SRP 4.2, APPENDIX A) o PG&E INTERFACE AUDITS PERFORMED INPUT INFORMATION/DATA (I.E.,
SAME SPECTRA AS IN ORIGINAL ANALYSIS)
KEY MODEL PARAMETERS CONFORMANCE WITH CRITERIA NRC COMMENTS ON OTHER VANTAGE 5 APPLICATIONS ALI PG&E COMMENTS WERE RESOLVED AND ANALYSIS WORK WAS ACCEPTED
l
VANTAGE 5 SER REVIEW
, o GENERAL REVIEW OF SEISMIC/LOCA LOAD ANALYSES ACCEPTANCE CRITERIA METHODS APPLICABILITY GRID STRENGTH CONSIDERATIONS COMBINATION OF SEISMIC AND LOCA LOADS o
DIABLO CANYON PLANT SPECIFIC ANALYSES o
CONCLUSIONS STATING THAT ALL ACCEPTANCE CRITERIA ARE MET
l f
ANTAGE ENERIC T PI AL REPORT WCAP-1 444
SUMMARY
OF SER CONCLUSIONS OF STRUCTURAL INTEGRITY o
"VANTAGE 5
REPRESENTS SLIGHT IMPROVEMENT OVER OFA DESIGN WRT TO STRUCTURAL DYNAMIC RESPONSE".
(OFA SHOWN PREVIOUSLY TO BE SUPERIOR TO LOPAR DESIGN IN DYNAMIC RESPONSE) o FOR EACH PLANT APPLICATION IT MUST BE DEMONSTRATED THAT THE APPLIED SEISMIC/LOCA LOADS CONSIDERED IN WCAP-9401 BOUND THE PLANT IN QUESTION OR ELSE ADDITIONALANALYSES MUST BE PERFORMED ADDITIONAL ANALYSES HAVE BEEN PERFORMED FOR THE DIABLO CANYON UNITS
I
RE EI MI AND L AAALY E A CEPTA E
RITERIA RP 4 2 APPE DIX A o
LOCA ACCEPTANCE CRITERIA ACCEPTABLE TEMPERATURE AND OXIDATION LIMITS FOR ECCS NO FUEL ROD FRAGMENTATION CONTROL ROD INSERTABILITY o
SEISMIC ACCEPTANCE CRITERIA NO FUEL ROD FRAGMENTATION CONTROL ROD INSERTABILITY
k
ER IE F A ALY IS STEPS o
GRID LOAD DETERMINATION (INCL. FUEL ASSEMBLY DEFLECTION)
SEISMIC WAVE GENERATION HYDRAULIC -BLOWDOWN FORCES REACTOR PRESSURE VESSEL MODEL DETERMINES CORE PLATE MOTIONS FUEL ASSEMBLY/CORE MODELS DETERMINE GRID LOADS/FUEL ASSEMBLY DEFLECTION o
STRESS ANALYSIS OF FUEL RODS AND GUIDE THIMBLES TO DETERMINE FUEL ROD INTEGRITY AND CONTROL ROD INS ERTABILITY o
CORE COOLABLE GEOMETRY EVALUATION, IF NECESSARY, BASED ON GRID LOAD RESULTS
FUEL ASSEMBLYSEISMIC/LOCA ANALYSISPROCEDURE HYDRAULIC FORCES REACTOR INTERNALS MODEL CORE PLATE MOTION REACTOR CORE MODEL F/A DEFLECTION AND IMPACT FORCES ARllFICIAL SESMIC WAVE GRID LOAD F/A DEFLECTION
RESPONSE
SPECTRA GRID STRENGTH EVALUATION F/A COMPONENT INTEGRITY 123703-1.0Ehl030201 JANUARY4,1989 GRID STRENGTH ALLOWABLE STRESSES THIMBLETUBE STABILITY
METH 0 F
R RID LOAD DETERMINATIO o
METHODS APPROVED BY NRC DURING REVIEW OF WCAP-9401 o
COMBINATION OF SEISMIC AND LOCA LOADS BASED ON REQUIREMENTS OF SRP 4.2, APPENDIX A
RID SPA ER TRENGTH o
TEST PROCEDURES REVIEWED AND APPROVED PREVIOUSLY BY NRC o
TEST CONDITIONS PER SRP 4.2, APPENDIX A o
STATISTICAL TREATMENT OF GRID STRENGTH TEST DATA PER SRP 4.2, APPENDIX A 95 PERCENT CONFIDENCE LEVEL OF THE TRUE MEAN DETERMINES GRID STRENGTH
E MENT F
RITERIA CRITERIA RID DEF RMATI NO GRID DEF RMATIO TEMPERATURE/
OXIDATION LIMIT COOLABLE GEOMETRY EVALUATION NO IMPACT FUEL ROD INTEGRITY FUEL ROD STRESS ANALYSIS BASED ON FUEL ASSEMBLY DEFLECTION FUEL ROD STRESS ANALYSIS BASED ON FUEL ASSEMBLY DEFLECTION CONTROL ROD INSERTABILITY THIMBLE TUBE STRESS ANALYSIS THIMBLE TUBE STRESS ANALYSIS
0 A
DIABLO A YO PLANT PECIFIC ANALY ES o
SEISMIC INPUT/ASSUMPTIONS TIME-HISTORY METHOD USED TO OBTAIN FUEL ASSEMBLY DEFLECTIONS AND GRI D IMPACT LOADS HOSGRI AND DOUBLE DESIGN EARTHQUAKES CONSIDERED ACCELERATION
RESPONSE
SPECTRA FOR THE TIME HISTORI ES ENVELOPE THE DESIGN SPECTRA FOR DDE AND HOSGRI HOSGRI DETERMINED TO BE MOST LIMITING FOR FUEL ANALYSIS o
LOCA INPUT/ASSUMPTIONS MOST LIMITING PIPE BREAKS AT:
(1)
REACTOR PRESSURE VESSEL INLET NOZZLE (2)
REACTOR COOLANT PUMP OUTLET NOZZLE
A E
IDERED o
FULL CORE VANTAGE 5 o
TRANSITION CORES I/3 VANTAGE 5, 2/3 LOPAR 2/3 VANTAGE 5, 1/3 LOPAR
0
NLUI o
BOTH VANTAGE 5 AND LOPAR FUEL (EITHER AS FULL CORES OR TRANSITION MIXED CORES)
MEET ALL STRUCTURAL INTEGRITY CRITERIA RELATED TO SEISMIC AND LOCA CONDITIONS o
INCORPORATION OF VANTAGE 5 FUEL PROVIDES IMPROVED SEISMIC/LOCA GRID LOAD MARGINS AND ELIMINATES GRID DEFORMATION WHEN A FULL CORE OF VANTAGE 5 IS OBTAINED
AFETY ANALY I o
KEY ASSUMPTIONS VANTAGE 5 F~
=
1.65 LOPAR F~
=
1.62 SGTP
=
15X TECH.
SPEC.
Fq
=
2.45 DESIGN FEATURES OF VANTAGE 5 o
ANALYSIS METHOD EXISTING g SAFETY ANALYSIS METHOD IDENTIFIES PARAMETER CHANGES ON A CYCLE-BY-CYCLE BASIS COMPARES AGAINST EXISTING SAFETY ANALYSIS ASSUMPTIONS PERFORM ANALYSIS/EVALUATIONOF ALL ACCIDENTS AFFECTED BY THE CHANGES o
AFFECTED TRANSIENTS WERE REANALYZED/REEVALUATED
7
NO -L A
HAPTER 1
A ALY E o
FUEL FEATURES ADDRESSED:
FUEL ROD DIMENSION AXIAL BLANKETS IFBA AND MABA INTERMEDIATE FLOM MIXER GRIDS RECONSTITUTABLE TOP NOZZLE FUEL ENRICHMENT EXTENDED BURNUP FUEL ASSEMBLY DESIGN THIMBLE PLUG DELETION o
DESIGN SAFETY ANALYSIS ASSUMPTIONS:
PMTC (+5 pcm/deg-F TO 70K, RAMP TO 0.0 AT 100X)
F~ (1.62 / 1.65)
F (2.45)
STEAM GENERATOR TUBE PLUGGING (15K)'
APPROVED METHODOLOGY HAS BEEN USED IN ALL REANALYSES WCAP-10444-P-A, SEPTEMBER,
- 1985, REFERENCE CORE REPORT V5, (SEE SECTION 5.0)
-L A
HAPTER 1
A ALY E 0
CHAPTER 15 ACCIDENTS REANALYZED:
A.
CHAPTER 15.2 ROD WITHDRAWAL FROM SUBCRITICAL ROD WITHDRAWAL AT POWER RCCS MISOPERATION BORON DILUTION PARTIAL LOSS OF FLOW STARTUP OF INACTIVE LOOP LOSS OF EXTERNAL LOAD / TURBINE TRIP LOSS 'OF NORMAL FEEDWATER STATION BLACKOUT EXCESSIVE HEAT REMOVAL (FEED SYSTEM MALFUNCTION)
SUDDEN FEEDWATER TEMPERATURE REDUCTION EXCESSIVE LOAD INCREASE ACCIDENT ACCIDENTAL RCS DEPRESSURIZATION ACCIDENTAL DEPRESSURIZATION OF MAIN STEAM SYSTEM SPURIOUS SAFETY INJECTION B.
CHAPTER 15.3 MINOR SECONDARY SYSTEM PIPE BREAKS COMPLETE LOSS OF FORCED REACTOR COOLANT FLOW SINGLE RCCS WITHDRAWAL AT FULL POWER
t
NON-LOCA HAPTER 1
ANALYSES C.
CHAPTER 15.4 MAJOR SECONDARY SYSTEM PIPE RUPTURE (STEAM/FEED)
SINGLE REACTOR COOLANT PUMP LOCKED ROTOR RUPTURE OF A CONTROL ROD DRIVE MECHANISM HOUSING o
CONCLUSIONS:
ANALYSES SUPPORT TECHNICAL SPECIFICATION CHANGES INFORMATION FOR FSAR UPDATES IS PROVIDED AND GIVES RESULTS FOR THE NEW ANALYSES WHICH ARE ACCEPTABLE ALL EXISTING SAFETY CRITERIA ARE MET FOR THE NON-LOCA ACCIDENTS
7
LO A A ALYSES F R
A TAGE 5 FUEL I.
FULL CORE VANTAGE 5 FUEL o
15'TEAM GENERATOR TUBE PLUGGING o
NO GRID DEFORMATION MODELLED o
TOTAL CORE PEAKING FACTOR (F<)
OF 2.50 o
HOT CHANNEL ENTHALPY RISE FACTOR (F~)
OF 1.65 o
RESULTS:
A.
LARGE BREAK LOCA o
1981 EVALUATION'ODELMITH BASH o
PEAK CLAD TEMPERATURE (PCT)
= 2071'F FOR Cp 0 4 BREAK B.
SMALL BREAK LOCA o
NOTRUMP EVALUATION MODEL o
PCT = 1358'F FOR 4 INCH BREAK
LOCA ANALY E F
R A TAGE 5 F EL II.
TRANSITION CORE EFFECTS HYDRAULIC RESISTANCE o
BLOWDOWN EFFECTS BOUNDED BY FULL CORE VANTAGE 5 o
CORE REFLOODING EFFECTS MODELLED USING A
TWO CHANNEL VERSION OF THE BART CODE o
17 X 17 LOPAR TO VANTAGE 5 MODELLED SPECIFICALLY o
MAXIMUM PCT PENALTY DUE TO HIGHER HYDRAULIC RESISTANCE FOR THE VANTAGE 5 ASSEMBLY IS 50'F FOR LARGE BREAK LOCA o
SMALL BREAK LOCA IS NOT AFFECTED BY HYDRAULIC RESISTANCE MISMATCH, THEREFORE VANTAGE 5 RESULTS REMAIN BOUNDING
J'
LOCA A ALY E F
R A TA f FUEL III. TRANSITION CORE EFFECTS GRID DEFORMATION A.
17 X 17 LOPAR FUEL o
15K STEAM GENERATOR TUBE PLUGGING o
22K GRID CELL MAXIMUM DEFORMATION MODELLED o
TOTAL CORE PEAKING FACTOR (F~)
OF 2.45 o
HOT CHANNEL ENTHALPY RISE FACTOR (F>>)
OF 1.62 k
o 1981 EVALUATION MODEL WITH BASH o
4000 MWD/MTU BURNUP MODELLED o
PCT = 1980'F
J V
V
.I A
LOCA A ALYSE F
R A TA E
FUEL III. TRANSITION CORE EFFECTS GRID DEFORMATION B.
VANTAGE 5 FUEL o
15K STEAM GENERATOR TUBE PLUGGING o
39.3X GRID CELL MAXIMUM DEFORMATION MODELLED o
TOTAL CORE PEAKING FACTOR (F~)
OF 2.50 o
HOT CHANNEL ENTHALPY RISE FACTOR (F~)
OF 1.65 o
1981 EVALUATION MODEL WITH BASH o
PCT = 2108'F
C, v
~r, l
, ~
LOCA ANALYSE F
R A TA E
FUEL III. TRANSITION CORE EFFECTS GRID DEFORMATION C.
SMALL BREAK LOCA o
EVALUATION BASED ON VANTAGE 5 SBLOCA ANALYSIS o
39.3X GRID CELL MAXIMUM DEFORMATION MODELLED o
CONSERVATIVE ESTIMATE OF DECREASE IN VAPOR MASS FLOW RATE o
INCREASE IN PCT OF 154'F o
PCT = 1512'F
k g P S
MMARY o
SIMILAR TO OTHER NRC-APPROVED VANTAGE 5 APPLICATIONS o
SEISMIC AND LOCA EVENTS DO NOT PRECLUDE:
COOLABLE GEOMETRY CONTROL ROD DROP MAINTAINING FUEL INTEGRITY o
ACCIDENTS WITHIN REGULATORY GUIDELINES
0,
. ~
(pX u 4' I