ML20235X706
| ML20235X706 | |
| Person / Time | |
|---|---|
| Issue date: | 07/20/1987 |
| From: | Leech P Office of Nuclear Reactor Regulation |
| To: | Berkow H Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-669A NUDOCS 8707240292 | |
| Download: ML20235X706 (22) | |
Text
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July 20, 1987 Project No. 669 1
MEMORANDUM FOR:
Herbert N. Berkow, Director Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects l
FROM:
Paul H. Leech, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects
SUBJECT:
MEETING WITH EPRI AND UTILITY STEERING COMMITTEE RELATIVE TO ALWR PROGRAM On July 1, 1987, representatives of the Electric Power Research Institute (EPRI) and the Chairman of its ALWR Utility Steering Committee met with the staff management in order to brief them on the ALWR program. The persons who attended the meeting are listed in Enclosure 1. consists of 19 viewgraphs which were used for the briefing. As indicated, the topics included the basis and support for the program, regulatory stabilization, the features and status of the ALWR Requirements Document, small plant (400-600 MWe) concepts, the significance of NRC review and concurrence, and recommendations for the review process.
The recommendations by EPRI and the Steering Committee emphasized the need for high-level management involvement in NRC's review of the Requirements Document. They also recommended that an addendum to NUREG-1197 be issued to clarify certain details of the NRC review process.
Original signed by Paul H. Leech, Project Manager Standardization and Non-Power Reactor Project Cf ractorate Division of Reactor Projects III, IV, Y and Special Projects
Enclosures:
As stated DISTRIBUTION:
1 Docket; File.
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UNITED STATES I' )
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July 20, 1987 Project No. 669 MEMORANDUM FOR:
Herbert N. Berkow, Director
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Standardization and Non-Power j
i Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects FROM:
Paul H. Leech, Project Manager Standardization and Non-Power Reactor Project Directorate j
Division of Reactor Projects III, IV, i
V and Special Projects
SUBJECT:
MEETING WITH EPRI AND UTILITY STEERING COMMITTEE RELATIVE TO ALWR PROGRAM On July 1,1987, representatives of the Electric Power Research Institute (EPRI) and the Chairman of its ALWR Utility Steering Comittee met with the staff management in order to brief them on the ALWR program. The persons who attended the meeting are listed in Enclosure 1.
. consists of 19 viewgraphs which were used for the briefing. As indicated, the topics included the basis and support for the program, regulatory stabilization, the features and status of the ALWR Requirements Document, small plant (400-600 MWe) concepts, the significance of NRC review and concurrence, and recommendations for the review process.
The recommendations by EPRI and the Steering Committee emphasized the need for high-level management involvement in NRC's review of the Requirements Document. They also recommended that an addendum to NUREG-1197 be issued to clarify certain details of the NRC review process.
Le Paul H. Leech, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects
Enclosures:
As stated
ENCLOSURE 1 ATTENDANCE AT JULY I, 1987 MEETING IN BETHESDA, MD CONCERNING THE ADVANCED LWR PROGRAM 1
NAME AFFILIATION i
Edwin B. Kintner Chairman, ALWR Steering Committee, and Exec. VP, GPU Nuclear Corporation l
John T. Taylor VP, EPRI Nuclear Division Jack Berga EPRI, Washington, D.C. Representative, Daniel N. Noble EPRI, Senior ALWR Program Manager, Jack Devine EPR1, ALWR Program Manager, V. Stello NRC, Exec. Director for Operations Thomas Murley NRC, Director, ONRR James Sniezek NRC, Deputy Director, ONRR Richard Starostecki NRC, Associate Director, ONRR Frank Miraglia NRC, Associate Director, ONRR Dennis Crutchfield NRC, Director of Reactor Projects --
III, IV, V and Special Projects, ONRR Frank Schroeder NRC, Assistant Director for Region IV Reactor and Special Projects. ONRR l
l-Herbert Berkow NRC, Director, Standardization and Non-Power Power Reactor Projects, NRR Paul Leech NRC, Project Manager, Standardization and Non-Power Reactor Projects. ONRR Eric Beckjord NRC, Director, Office of Research l
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ENCLOSURE 2 y
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EPRI ALWR REQUIREMENTS DOCUMENT J
REGULATORY REVIEW NRC/FPRl/ DOE SENIOR MANAGEMENT MEETING JULY 1, 1987 i
E. E. KINTNER J. J. TAYLOR J. C. DEVINE, JR.
D. M. NOBLE
MEETING AGENDA UTILITY NEEDS AND PERSPECTIVES FACTORS UNDERLYING THE EPRI-DOE ALWR PROGRAM APPLYING EXPERIENCE AND. KNOWLEDGE FOR A FUNDAMENTALLY IMPROVED ALWR CONGRESSIONAL SUPPORT FOR STANDARD PLANTS
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SUMMARY
OF THE EPRI.ALWR PROGRAM REGULATORY STABILIZATION (WITH EXAMPLES OF OPTIMIZATION ISSUES)
REQUIREMENTS DOCUMENT (WITH BRIEF
SUMMARY
OF TECHNICAL APPROACH, FEATURES IN CHAPTERS 3 AND 4)
SMALL PLANT EVALUATIONS (WITH BRIEF
SUMMARY
OF SMALL-PLANT CONCEPTS, DESIGN l
DIRECTION) l 1
PROGRAM INTERACTION WITH NRC 1
-THE SIGNIFICANCE OF NRC REVIEW AND APPROVAL OF ALWR REQUIREMENTS DOCUMENT I
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RECOMMENDATIONS FOR NRC REVIEW PROCESS l
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FACTORS UNDERLYING THE EPRI-DOE ALWR PROGRAM LITTLE POSSIBILITY OF ANY U.S. UTILITY INITIATING A NUCLEAR PLANT IN THE NEAR FUTURE HOWEVER THE U.S. WILL NEED AT SOME FUTURE TIME TO BUILD MORE NUCLEAR PLANTS FUTURE PLANTS SHOULD TAKE MAXIMUM ADVANTAGE OF THE GREAT BODY OF EXPERIENCE, FAVORABLE AND UNFAVORABLE, DEVELOPED FROM THE MORE THAN 100 PLANTS NOW OPERATING.
IN PARTICULAR, THEY SHOULD USE THE LWR TECHNOLOGY BASE.
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WE SHOULD NOT WAIT UNTIL THE NEED IS UPON US T0 EXTRACT LESSONS FROM THE EXPERIENCE OF THE LAST TWO DECADES, WE SHOULD BEGIN NOW TO ANALYZE OUR EXPERIENCE AND TAKE STEPS TO APPLY THOSE LESSONS i
I 8882 DAN-4
WHAT ARE THE LESSONS?
'ALWR PLANTS SHOULD BE SIMPLE, AND THEREFORE EASIER TO BUILD AND OPERATE THEY SHOULD HAVE INCREASED MARGINS, AND THEREFORE BE MORE ROBUST AND FORGIVING IN OPERATION THEY SHOULD, TO THE DEGREE rilACT! CABLE, D.EPEND CN NATURAL PHENOMENA LIKE REACTIVITY CO-EFFICIENTS AND GRAVITY FOR CONTROL AND DECAY HEAT REMOVAL THESE WOULD LEAD TO A. SAFER PLANT, AND PERCEIVED TO BE SAFER BY THE PUBLIC THEY SHOULD LEND THEMSELVES TO EASIER CONSTRUCTION THEY SHOULD PROVIDE A SOUND BASIS FOR STANDARDIZATION THEY SHOULD PROVIDE A SOUND BASIS FOR REGULATORY STABILIZATION THESE SHOULD LEAD TO COST REDUCTIONS 88820AN {
HOW ARE THESE LESSONS BEING APPLlED?
ALWR PROGRAM IS A BROADLY COOPERATIVE EFFORT INVOLVING-MANY UTIL1T1ES THROUGH EPRI, AND WITH THE SUPPORT OF THE' DEPARTMENT OF ENERGY.
i MAJOR NUCLEAR SUPPLIERS AND ARCHITECT-ENGINEERS ARE.
PARTICIPATING BUT THE MANAGEMENT OF THE PROGRAM IS IN THE HANDS OF THE POTENTIAL CUSTOMERS WHO NOW HOLD THE EXPERIENCE AND WILL HAVE TO PROVIDE THE FINANCE FOR ANY FUTURE PLANTS I
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CONGRESSIONAL SUPPORT FOR STANDARD ALWRs ENCOURAGIN3 SUPPORT FOR STANDARD DESIGNS IN LANGUAGE 0F HOUSE APPROPRIATIONS COMMITTEE BILL FOR 1988 DOE BUDGET FUNDING FOR DOE-ALWR PROGRAMS IS SUPPORTED 1HE.NRC IS URGED "T0 MOVE EXPEDITIOUSLY TDWARD IMPLEMENTATION OF APPROPRIATE STANDARDIZATION REFORMS" THE NRC IS ENCOURAGED TO SUPPORT DEPARTMENT OF ENERGY AND INDUSTRY EFFORTS TO OBTAIN STANDARD, CERTIFIED DESIGNS 8882 DAN-7 Y
ELEMENTS OF THE EPRI ALWR PROGRAM REGULATORY STABILIZATION OBJECTIVE IS TO PROVIDE ASSURANCE THAT AN ALWR WOULD BE LICENSED NRC ENDORSEMENT OF THE ALWR REALIZED THROUGH:
ACCEPTANCE OF RESOLUTIONS TO GSI's AND USI's ACCEPTANCE OF OPTIMlZATIONS TO CURRENT NRC REQUIREMENTS ISSUANCE OF AN SER FOR THE REQUIREMENTS DOCUMENT WHICH STATES:
AGREEMENT WITH THE DESIGN PRINCIPLES, PHILOSOPHY AND REQUIREMENTS RELATED TO SAFETY, AS IN THE.
REQUIREMENTS DOCUMENT NUREG-1197 " ADVANCED LIGHT WATER REACTOR PROGRAM" i
SIGNIFIES PROGRESS MADE TOWARD REGULATORY STABILIZATION OBJECTIVES 1
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8882 DAN-8 9
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ALWR OPTIM12AT10N SUBJECTS 1
l FIVE OPTIMIZATION SUBJECTS FOR CHAPTER 1 WERE SUBMITTED TO NRC ON MARCH 24, 1986.
NRC'S RESPONSE WAS PROVIDED JUNE 6, 1986, THE ISSUES:
LEAK BEFORE BREAK METHODOLOGY OPERATING BASIS EARTHQUAKES AND DYNAMIC ANALYSIS METHODS SOURCE TERM EQUIPMENT SEISMIC QUALIFICATION BY EXPERIENCE TORNADO DESIGN ONE OPTIMIZATION SUBJECT FOR CHAPTER 3 WILL BE SUBMITTED TO l
NRC ON 6 JULY 1987:
BWR MAIN STEAM LINE VALVES AND LEAKAGE CONTROL SEVEN OPTIMIZATION ISSUES ARE ANTICIPATED FOR CHAPTER 5:
HYDROGEN CONTROL IN BWRS BWR STANDBY GAS TREATMENT SYSTEM ELIMINATION OF MISSILE SHIELDS FOR ROD EJECTION 10 DINE RELEASE CHEMICAL FORM CONTAINMENT ISOLATION APPENDlX R HYDROGEN GENERATION DURING SEVERE ACCIDENTS
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,4 THE EPRI ALWR PROGRAM's ELEMENTS-(CONT'D)
RE00lREMEuTS DOCUMENT THE DOCUNENT IS A 13-CHAPTER SET OF REQUIREMENTS FOR ALWR DESIGN AND CONSTRUCTION ESTABLISHED FROM AN DWNER/0PERATOR PERSPECTIVE ITS SCOPE IS THE ENTIRE PLANT NOT A COMPREHENSIVE SET OF REQUIREMENTS TECESSARY FOR DESIGN SAFETY, INVESTMENT PROTECTION, AND ECONOMICS ARE MAJOR FACTORS IN PREPARING REQUIREMENTS REQUIREMENTS DOCUMENT REFLECTS THE NEEDS OF UTILITIES REPRESENTED BY THE ALWR STEERING COMMITTEE EPRI DIRECTS AND C00RDINATES FOUR DESIGN TEAMS AND CONSULTANTS IN THE PREPARATION OF REQUIREMENTS UTILITIES ARE ENDORSING STANDARD PLANT FEATURES l
SPECIFIED IN THE REQUIREMENTS DOCUMENT AS A BASIS FOR NATIONAL STANDARD PLANT DESIGNS l
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g PROGRESS TO DATE REQUIREMENTS DOCUMENT CHAPTER 1 - OVERALL REQUIREMENTS SUBMITTED TO NRC IN JULY '86; SER IS EXPECTED SHORTLY CHAPTER 2 - POWER GENERATION SYSTEMS-SUBMITTED TO NRC IN OCTOBER '86, INITIAL NRC COMMENTS ARE 'lN HAND, RESOLUTION PROCESS UNDERWAY -
CHAPTER 3 - REACTOR COOLANT SYSTEM AND AUX 1LIARIES AND CHAPTER 4 - REACTOR SYSTEMS ARE COMPLETE AND WERE SUBMITTED TO NRC THIS WEEK.
CHAPTER 5 - ENGINEERED SAFEGUARDS SYSTEM IS IN SMOOTH DRAFT FORM, KEY TECHNICAL ISSUES ARE STILL BEING RESOLVED.
CHAPTER 6 - ARRANGEMENTS-AND STRUCTURES BASELINE FOR CHAPTER HAS BEEN PREPARED AND SUBMITTED TO USC CHAPTER 10 - INSTRUMENTATION AND CONTROLS IS IN THE EARLY PLANNING STAGES 88820AN-19
CHAPTER 3 - SIGNIFICANT MAJOR IMPROVEMENTS FUR ALWR-PWR: -
MAXIMUM REACTOR COOLANT TEMPERATURE LIMIT.
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IMPROVED TRANSlENT PERFORMANCE LARGER PRESSURIZER AND SPRAY CAPACITY INCREASED STEAM GENERATOR SECONDARY SIDE-INVENTORY IMPROVED RELIABILITY OF RCP SEAL AUXILIARIES AND RCP SEAL INTEGRITY UNDER STATION BLACK 0UT SIMPLIFIED LOW TEMPERATURE OVERPRESSURE PROTECTION BWR:
USE OF INTERNAL RECIRCULATION PUMPS ELIMINATION OF RECIRC-PIPING IMPROVED PLANT PERFORMANCE, CONTROL REDUCED LOCA VULNERABILITY HIGHER CAPACITY REACTOR WATER CLEANUP SYSTEM 9999-10 l
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CHAPTER 4 - SIGNIFICANT IMPROVEMENTS FOR ALWR BWR AND PWR:
ROBUST FUEL DESIGN WITH AT LEAST-15% THERMAL MARGIN AND ENHANCED ABILITY TO MANEUVER, ACCEPT OPERATIONAL
'TRANSlENTS AND AVOID LIMITING CONDITIONS OF OPERATION LONGER LIFE CONTROL RODS FUEL DESIGNED FOR HIGH BURNUP AND LONG FUEL CYCLES
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REACTOR VESSEL CAPABLE OF 60-YEAR LIFE WITHOUT OPERATING PENALTIES UPGRADED VESSEL FABRICATION METHODS (N0 WELDS IN CORE BELTLINE)
BWR ONLY:
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LARGER REACTOR VESSEL, PERMITTING INCREASED WATER INVENTORY, LOWER RPV WALL FLUENCE.
SUBSTANTIALLY IMPROVED CONTROL R0D DRIVES (FINE MOTION DRIVE SYSTEM, ELECTRIC MOTOR FOR POSITIONING AND SIMPLER HYDRAULICS FOR SCRAli/ RAPID INSERTION) 9999-18
CHAPTER 5 - POTENTIAL' IMPROVEMENTS IMPROVED STATION BLACK 0UT PERFORMANCE.
UPGRADED PWR EMERGENCY FEED CAPABILITY DIRECT VESSEL INJECTION CAPABILITY (PWR)
HIGHER PRESSURE RHR SYSTEM (PWR) l BALANCED TREATMENT OF ACCIDENT PREVENTION AND ACCIDENT MlTIGAT10N REQUIREMENTS L
CONTAINMENT CAPABILITY TO DEAL WITH DBA (STANDARD L
LICENSING BASIS ANALYSIS) AND SA (REALISTIC ANALYSIS), CONSIDERING l
LEAK TIGHTNESS /lSOLATION HEAT REMOVAL FISSION PRODUCT REMOVAL 9996JCD-4
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ALWR PROGRAM ELEMENT'S (CONT'D) l SMALL PLANT CONCEPTUAL DESIGN SMALL PLANT REQUIREMENTS I
MANY UTILITIES HAVE A SPECIAL INTEREST IN PLANTS WITH SMALLER ELECTRICAL OUTPUT FITS POSSIBLE LOAD GROWTH PROJECTIONS FOR MANY UTILITIES PROJECT COSTS ARE REDUCED: FINANCING POSSIBILITIES ARE ENHANCED COMPETITION WITH SIMILAR SIZE FOSSIL PLANTS POSSIBILITIES FOR DESIGN SIMPLIFICATION, PARTICULARLY THE APPLICATION OF PASSIVE SAFETY SYSTEMS, ARE OUTSTANDING CONCEPTUAL DESIGNS ARE EVOLVING COORDINATED DOE /EPRI DESIGN EFFORT WITH JAPC FOR THE ASBWR TWO DESIGN TEAMS - A PWR AND A BWR REQUIREMENTS FOR THESE SMALL PLANTS ARE TO BE INCLUDED IN THE REQUIREMENTS DOCUMENT 88820AN-15
SMALL PLANT CONCEPTUAL DESIGN SBWR PLANT FEATURES NATURAL CIRCULATION FOR CORE FLOW DURING FULL POWER.
OPERATION ISOLATION CONDENSER, LOCATED IN ELEVATED SUPPRESSION POOL, REMOVES DECAY HEAT BY NATURAL CIRCULATION AT FULL PRESSURE / TEMPERATURE STEAM INJECTOR PROVIDES PASSIVE SOURCE OF' MAKEUP TO RCS GRAVITY DRAIN COOLING SYSTEM DEPRESSURIZATION VALVES OPEN TO REDUCE SYSTEM PRESSURE ELEVATED SUPPRESSION POOL DRAINS TO COOL THE CORE PASSIVE CONTAINMENT COOLING PROVIDED BY WATER-FILLED-WALL l
8882 DAN-16
7 SMALL PLANT CONCEPTUAL DESIGN AP-600 PWR PLANT FEATURES STREAMLINED RCS CONFIGURATION UTILIZING CANNED-MOTOR PUMPS NATURAL CIRCULATION HEAT EXCHANGER REMOVES DECAY HEAT AT FULL PRESSURE / TEMPERATURE GRAVITY DRIVEN ECCS FULL' PRESSURE CORE-MAKEUP TANKS KEEP CORE COVERED J
WHILE SYSTEM DEPRESSURIZES DEPRESSURlZATION VALVES VENT PRESSURIZER TO IN-CONTAINMENT REFUELING WATER STORAGE TANK (IRWST)
STEEL CONTAINMENT WITH NATURAL CONVECTION AND EXTERNAL WETTING PROVIDES PASSIVE' DECAY HEAT REMOVAL t
8882 DAN-17 l
' r-s SIGNIFICANCE OF NRC REVIEW AND CONCURRENCE A PLANT MEETING THE ALWR REQUIREMENTS DOCUMENT'S' SAFETY CRITERIA WOULD BE LICENSED USI's AND GSI's TREATED.IN THE DOCUMENT ARE RESOLVED OPTIMIZATION OF CURRENT REGULATORY CRITERIA ARE-ACCEPTED AGREEMENT WITH THE SAFETY ASPECTS OF THE BASIC DESIGN CONCEPTS IN THE REQUIREMENTS DOCUMENT i
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8882 DAN-11 i
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RECOMMENDATIONS FOR THE REVIEW PROCESS NATURE OF THE REQUIREMENTS DOCUMENT AND THE COMPLETE ALWR PROGRAM LEADING TO NATIONAL STANDARDIZED DESIGNS RAISES A COMPELLING NEED FOR THE HIGH LEVEL NRC MANAGEMENT ROLE IT IS RECOMMENDED THAT THE OVERALL REVIEW OF THE UTILITY REQUIREMENTS DOCUMENT WOULD BE THE DIRECT RESPONSIBILITY OF AN NRC-ALWR REVIEW COMMITTEE THE NRC-ALWR REVIEW COMMITTEE WOULD CONSIST OF:
T. MURLEY - CHAIRMAN E. BECKJORD F. MIRAGLIA R. STAROSTECKI THE NRC-ALWR REVIEW COMMITTEE WOULD PRESENT THE STATUS OF THE REVIEW OF THE ALWR REQUIREMENTS DOCUMENT.lN OVARTERLY MEETINGS WITH BOTH VIC STELLO, NRC EXECUTIVE DIRECTOR OF OPERATIONS, AND THE ALWR UTILITY. STEERING COMMITTEE MINUTES OF THESE MEETINGS WOULD BE.KEPT, ACTION ITEMS ASSIGNED, AND AGREEMENTS RECORDED.
THE CHAIRMAN, T. MURLEY, WOULD SIGN THE MINUTES OF EACH MEETING SIGNIFYING HIS AGREEMENT WITH THE CONTENT 8882 DAN-12 I
PROPOSED REVIEW PROCESS l
i NUREG-1197, " ADVANCED LIGHT WATER REACTOR PROGRAM --- PROGRAM MANAGEMENT AND STAFF REVIEW METHODOLOGY" SET FORTH THE GENERAL FRAMEWORK FOR THE REVIEW 0F THE UTILITY REQUIREMENTS DOCUMENT IT IS RECOMMENDED THAT AN ADDITIONAL NUREG BE ISSUED TO CLARIFY NUREG-1197 CONCERNING THE DETAILS OF THE NRC REVIEW PROCESS THE UTILITY STEERING COMMITTEE WOULD BE PLEASED TO PROVIDE ITS INPUT FOR PROPOSED NUREG-ALWR REQUIREMENTS REVIEW PLAN BY AUGUST 31, 1987 i
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