ML20043G748
| ML20043G748 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/13/1990 |
| From: | Peterson S Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9006210086 | |
| Download: ML20043G748 (27) | |
Text
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.si June 13, 1990 ket Nos. 50-528, 50-529 and 50-530 LICENSEE: Arizona Public Service Company FACILITY:
Palo Verde Nuclear Generating Station
SUBJECT:
MEETING
SUMMARY
- RELOAD TECHNOLOGY TRANSFER On May 31 1990, the staff met in Rockville, Maryland with representatives of andconsultantsforArizonaPublicServiceCompany(APS)todiscussthelicensee's plans to pursue licensing of reload engineering capability for Palo Verde Nuclear Generating Station. A list of attendees is provided in Enclosure 1.
APS focused their discussion on the scope and development of their nuclear fuel management reload technology transfer program.
The purpose of the meeting was to obtain staff feedback and discuss future actions. APS provided an overview oftheCombustionEngineering(CE)designedprogramtoprovidereloadtechnology to APS. The training program and plans involved to obtain qualified staff, develop capability and implement design control procedures were discussed. APS stated that they currently plan on submitting a request to license their reload capability by the second quarter of 1991.
APS informed the staff that it will be seeking NRC approval of their reload design capability by the end of the first quarter of 1992 and that CE methodology would be used. The presentation handouts from APS are provided as Enclosure 2.
The staff indicated that APS's general approach to obtain reload technology was appropriate. The staff emphasized that APS should provide in their submittal a CE/APS comparison of independent reload analysis and the limitations of their license including the computer codes used and identifying CE fuel reloads only.
The staff stated that it is available for further discussions if APS needs further feedback about the effort before it is completed.
/s/
Sheri R. Peterson, Project Manager Project Directorate V Division of Reactor Projects - 111, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
As stated cc:
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June 13, 1990 Docket Nos. 50-528, 50-529 and 50-530 i
LICENSEE: Arizona Public Service Company FACILITY:
Palo Verde Nuclear Generating Station
SUBJECT:
MEETING $UMMARY - RELOAD TECHNOLOGY TRANSFER On May 31, 1990, the staff met in Rockville, Maryland with representatives of and consultants for Arizona Public Service Company (APS) to discuss the licensee's plans to pursue licensing of reload engineering capability for Palo Verde Nuclear Generating Station. A list of attendees is provided in Enclosure 1.
APS focused their discussion on the scope and development of their nuclear fuel management reload technology transfer program. The purpose of the meeting was to obtain staff feedback and discuss future actions. APS provided an overview of the Combustion Engineering (CE) designed program to provide reload technology to APS. The training program and plans involved to obtain qualified staff, develop capability and implement design control procedures were discussed.
APS stated that they currently plan on submitting a request to license their reload capability by the second quarter of 1991. APS informed the staff that it will be seeking NRC approval of their reload design capability by the end of the first quarter of 1992 and that CE methodolony would be used. The presentation handouts from APS are provided as Enclosure 2.
The staff indicated that APS's general approach to obtain reload technology was appropriate. The staff emphasized that APS should provide in their submittal a CE/APS comparison of independent reload analysis and the limitations of their license including the computer codes used and identifying CE fuel reloads only.
The staff stated that it is available for further discussions if APS needs further feedback about the effort before it is completed.
b Sheri R. Peterson, Project Manager Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Enclosures:
As stated cc:
See next page
Mr. William F. Conway Palo Verde Arizona Public Service company cc:
Arthur C. Gehr, Esq.
Mr. Jack R. Newman Snell & Wilmer Newman & Holtzinger P.C.
3100 Valley Center 1615 L Street, NW, Suite 1000 Phoenix, Arizona 85073 Washington, DC 20036 Charles R. Kocher, Esq. Assistant Mr. Jack N. Bailey Council Vice President Nuclear James A. Boeletto, Esq.
Safety and Licensing Southern California Edison Company Arizona Public Service Company P. O. Box 800 P.O. Box 52304 Rosemead, California 91770 Phoenix, Arizona 85072-2034 Senior Resident Inspector Mr. James M. Levine U.S. Nuclear Regulatory Commission Vice President, Nuclear Production HC-03 Box 293-NR Arizona Public Service Company Buckeye, Arizona 85326 P.O. Box 52304 Phoenix, Arizona 85072-2034 Regional Administrator, Region V U. S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Mr. Charles B. Brinkman Washington Nuclear Operations
. Combustion Engineering, Inc.
12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. Charles Tedford, Director Arizona Radiation Regulatory Agency 4814 South 40 Street Phoenix, Arizona 85040 Chairman Maricopa County Board of Supervisors 111 South Third Avenue Phoenix, Arizona 85003 (10)
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ENCLOSURE 1 LIST OF ATTENDEES NRC/APS MEETING ON RELOAD TECHNOLOGY TRANSFER NRC AP,S S
Sheri Peterson Carter Rogers Shih-Liang Wu Paul Crawley
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Terence L. Chan Matthew J. Reid Mark Caruso Ronald Land Larry Phillips Charles Brinkman (CE)
John T. Larkins 8
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ENCLOSURE 2 ARIZONA PUBLIC SERVICE Palo Verde Nuclear Generating Station Presentation to NRC P
RELOAD d
TRANSFER TECHNOLOGY /
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PVNGS N.
CLEA FUEL MA AGEMENT May 31,1990 j
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PURPOSE
- DISCUSS PLAN 8 TO PURSUE LICENSING OF RELOAD ENGINEERING CAPABILITY i
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- OBTAIN NRC FEEDBACK AND PLAN FUTURE ACTIONS l
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PRESENTATION 1
- 1. INTRODUCTION (A. C. ROGERS)
- 2. APS NUCLEAR FUEL MANAGEMENT RELOAD TECHNOLOGY TRANSFER PROGRAM:
HISTORY (P. F. CRAWLEY)
CURRENT STATUS (M. J. REID)
FUTURE PLANS (R. J. LAND)
- 3.
SUMMARY
(A. C. ROGERS)
- 4. NRC FEEDBACK / FUTURE ACTIONS 1
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. OVERVIEW
.t RELOAD ANALYSIS PROCESS I
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PERFORMANCE OBJECT'VES J
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RELOAD ANALYSIS REPORT
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TECNNICAL SPECIFICATIONS
- PROTECTION & 98090870Rt988 SYSTEM SETPetN TS (f.e, CPCS/COLSS#RPS)
GROUNDRULES
- TECNNICAL SPECIFICATIO90 CNANGES AN ALYSIS SASES (FSAR. SRP. CFR) -
PLANT SIRRTUP DATA RELOAD EXPERIENCE r
E NRICN9E E N T SPECIFICATION AS-9UfLT
& FUEL DESIO98 PRRAMETERS PAR AMETE RS FUEL. FABRICATION l
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HISTORY
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i BENEFITS OF APS OBTAINING RELOAD ENGINEERING CAPABILITY:
OPTIMlZED PLANT OPERATING SPACE i
IN-HOUSE CONTROL OF RELOAD DESIGN e
BASIS IMPROVED PLANT ENGINEERING SUPPORT i
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APS PLAN TO OBTAIN RELOAD ENGINEERING CAPABILITY
- OBTAIN QUALIFIED STAFF
- DEVELOP CAPABILITY
- IMPLEMENT DESIGN CONTROL PROCEDURES i
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ARIZONA PUBLIC SERVICE Palo Verde Nuclear Generating Station NUCLEAR FUEi. MANAGEMENT ORGANIZATION
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APS Nuclear Fuel Management Nuclear Analysis Milestones i
UNIT 1 CYCLE 1 BEGAN APS CORE FOLLOW PROGRAM WITH EPRI-SIMULATE MODEL NORMALIZED TO CE-ROCS MODEL
-UNIT 1 CYCLE 2 L
GENERATED FIRST APS CORE DATA BOOK WITH EPRI-SIMULATE MODEL-NORMALIZED TO EPRI-PDQ MODEL UNIT 2 CYCLE 2 VERIFIED CE RELOAD DESIGN WITH STUDSVIK-SIMULATE MODEL PERFORMED CLASSROOM TRAINING ON CE FUEL MANAGEMENT METHODS - AND PHYSICS INPUT TO SAFETY ANALYSIS UNIT 3 CYCLE 2 PERFORMED ON THE JOB TRAINING ON CE PHYSICS INPUT TO SAFETY ANALYSIS UNIT CYCLE 3 PERFORMED ON THE JOB TRAINING ON CE FUEL MANAGEMENT METHODS UNIT 2 CYCLE 3' l
PERFORMED FUEL MANAGEMENT STUDY IN PARALLEL WITH CE (CE PATTERN USED).
UNIT 3 CYCLE 3 PERFORMED FUEL MANAGEMENT STUDY IN PARALLEL WITH E
PERFORMING INDEPENDENT ANALYSIS OF COASTDOWN i
OPTION
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Preparation of the RSB6-1 Natural Circulation Test Report to the NRC Development of a PC based simulator of the - Core Protection Calculators CPC/COLSS Core follow reports Safety Analysis associated with the following significant Palo Verde operational concerns:
- Double drop of control element assemblies
- Loss of shutdown cooling at mid-loop operations
- Fallure of atmospheric dump. valves to open
- Aux, feedwater pump degradation- & Isolation L
valve failure
- MSSV/PSV setpoint tolerance out of t speelfication
- DNB calculations for loose material in the core-L
- Reactor coolant pump shaf t cracking Station -blackout
-Early criticality 1
DEVELOPMENT OF CAPABILITY m
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. OBJECTIVES:
ACQUISITION OF QUALIFIED COMPUTER CODES ACQUISITION OF' QUALIFIED METHODS FOR SPECIFIC EVENTS ANALYSIS H
QUALIFICATION OF METHODS AND STAFF
- HOW:
CE/APS RELOAD TECHNOLOGY TRANSFER PROGRAM 1
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1 RELOAD TECHNOLOGY TRANSFER
. PROGRAM OVERVIEW t
C CE Designed Program to Provide Reload Technology to APS SCOPE All. Reload Engineering Technology Except i
LOCA 1
Fuel Mechanical Design Fuel Fabrication-PROGRAM Three Phases'
- 1. -
Classroom Lecture 2.
On the Job Training (OJT) 3.
Independent Analysis GOAL NRC approval by 1st Quarter of 1992 4
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" RAINING PROGRAM PHASEI l
CLABBROOM LECTURE PROGRAM OBJECTIVE:
.TO. PROVIDE BASIC TRAINING IN THE FUNDAMENTALS
'i OF C-E RELOAD DESIGN METHODS AND SOFTMRE TAUGHT BY QUALIFIED INSTRUCTORS FAMILIAR WITH THE DESIGN AND ANALYSIS OF-PALO VERDE EXAMPLES SPECIFIC TO PALO VERDE TOPICS COVERED INCLUDE:
. THEORY METHODS COMPUTER CODES INTERPRETATION OF RESULTS UNCERTAINTIES i
PERFORMANCE EVALUATION AS MEASURED BY:
STUDENT ASSIGNMENTS TEST RESULTS 1
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CLASSROOM TRAINING ARRANGED BY DISCIPLINE L
COURSE ID Q.QURSE TITLE PHYSICS ANALYST LD100 OVERVIEW OF RELOAD DESIGN PROCESS NA001 OVERVIEW OF SELLER'S PHYSICS METHODS 1'
NA002 CROSS SECTION GENERATION NA003 ENRICHMENT SETTING, FUEL MANAGEMENT L
AND ASBUILT ANALYSIS L
NA004 CORE FOLLOW ANALYSIS NA005 STARTUP TEST PREDICTIONS / TECHNICAL DATA BOOK q
NA006 CECOR COEFFICIENT GENERATION NA007 PHYSICS INPUT TO SAFETY ANALYSES LD001 QUALITY ASSURANCE PROCEDURES CC001 OVERVIEW OF COLSS/CPC/CEAC ANALYSIS CC002 COLSS/CPC POWER-DISTRIBUTIONS THERMAL-HYDRAULIC AND COLSS/CPCS ANALYST LD100 OVERVIEW OF RELOAD DESIGN PROCESS SA001 DESIGN THERMAL HYDRAULICS L
SA002 FUEL - PERFORMANCE ANM.YSES L
SA003 COLSS/CPCS RELATED~ W ANSIENT ANALYSES-CC001 OVERVIEW OF COLSS/CPC CEAC ANALYSES i
CC002 COLSS/CPC POWER DISTRIBUTIONS CC003-ON-LINE THERMAL-HYDRAULICS CC004 OTHER CPCS ALGORITHMS CC005 OTHER COLSS ANALYSES CC006 UNCERTAINTY ANALYSES LD001 QUALITY ASSURANCE PROCEDURES t
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CLASSROOM TRAINING ARRANGED BY DISCIPLINE.
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COURSE ID COURSE TITLE
. PLANT TRANSIENT ANALYST LD100 OVERVIEW OF RELOAD DESIGN PROCESS l
SA001 DESIGN THERMAL-HYDRAULICS SA003 NON-LOCA TRANSIENT ANALYSES L
SA103 COLSS/CPCS RELATED TRANSIENT ANALYSES CC001 OVERVIEW OF-COLSS/CPC/CEAC ANALYSES
- LD001 QUALITY-ASSURANCE PROCEDURES LD002.
TECHNICAL SPECIFICnTION CHANGES
.t LD003 RELOAD ANALYSIS REPORT 1
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TRAINING PROGRAM PHASE ll OJTr ANALYSIS PERFORMED IN PARALLEL WITH CE OBJECTIVE:
TO TRAIN APS ENGINEERS IN THE APPLICATION OF PRINCIPLES LEARNED IN PHASE I TO REAL DESIGN SITUATIONS i
PARTICIPATION BY APS ENGINEERS IN ACTUAL-PALO VERDE DESIGN ANALYSIS C-E ON SITE SUPERVISION EXPERIENCED ENGINEERS ASSIGNED TO ASSIST - APS INDIVIDUAL PERFORMANCE EVALUATION BASED ON KNOWLEDGE OF SUBJECT QUALITY OF RESULTS PRODUCTIVITY
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TRAINING PROGRAM PHASE Ill lNDEPENDENT ANALYSIS
' OBJECTIVE:
TO DEMONSTRATE THAT APS HAS' BEEN ADEQUATELY ll,
TRAINED IN C-E RELOAD ENGINEERING METHODS APS ENGINEERS PERFORM INDEPENDENT RELOAD
' AN ALYSIS
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C-E INDEPENDENTLY REVIEWS AND APPROVES ALL CALCULATIONS AND RESULTS FOR NRC REQUIRED SUBMITTALS ( RAR, TECH ~ SPEC CHANGES. TOPICAL -
REPORTS) y CRITERIA :
RESULTS OF ANALYSIS BASED ON DESIGN OBJECTIVES
' ESSENTIALLY THE SAME AS C-E FINDINGS L
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APS-CE Reload Technology L
Transfer Program Status i
Phase:1 Classroom Training Started 10/87 Completed 3/90 6000 Engineer-hours 1
Phase 2 On the Job Training i
Started 1/88 Est. Completion 12/90 17000 Engineer-hours Phase 3 Independent-Analysis l
i Based on PVNGS. Unit 3 Cycle 3 Started 4/90 Est. Completion 6/91 12000 Engineer-hours j
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I RELOAD TECHNOLOGY TRANSFER 1
OTHER ISSUES:
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- 1. PROCEDURES 1
- 2. FUTURE PLANS t
- 3. TOPICAL REPORTS A
.q APS Design Control Procedures 1
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-Firci Level Procedures-APS Admiti!strative Control Procedures w
P'3 Second Level Procedures Defines responsibilities Assign. work activities
. Detail on how to comply with QA program including:
Calculation' Procedures:
documentation, review, revisions 1
Computer Programs:
authorization, documentation, verifloaticn,.
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Third Level-Procedures Reload. Design Instructions:
Specific. technical procedures that engineers use when performing calculations. for a reload licensing L
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Schedule Name : APS Reload Technology Transfer Program R2tponsible As-of Date
- 30-May-90 '8:00am Schedule File : A:\\ RTE.
87 88 89 90-91 92 I
Start End Jan Task Name Date Date
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3 2
2 2-R21oad Technology Transfer 1-Oct-87 28-Jun-91
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Phase 1 - Classroom Training 1-Oct-87 28-Feb-90 l
Phase 2 - On The Job Training 4-Jan-88 28-Dec-90 Phase 3 - Independent Analysis 2-Apr-90 28-Jun-91 APS Prepare Topical Reports 1-Apr-91 28-Jun-91 l
NP.C Review Topical Reportis 1-Jul-91 5-Mar-92 l
PVNCS Unit 3 Cycle 4 1-Nov-91 22-Jan-93 l
p Fuel Management 1-Nov-91 7-Jan-92 l
7 Reload Analysis 8-Jan-92 22-Jan-93 l
N PVEGS Unit 2 Cycle 5 2-Jan-92 22-Mar-93 l
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Fuel Management 2-Jan-92 4-Mar-92
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EMB Reload Analysis 5-Mar-92 22-Mar-93 l
.m Detail Task
- Su m ry Task a.
. Milestone (Started)
- -(Started)
- Conflict C
(Slack)
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.. " Resource delay Scale: 1 month per character -
TIME LINE Cantt Chart Report, Strip 1 f
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t APS Nuclear Fuel Management
. Topical Report Outline 1.0 Introduction -
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2.0 Description of Basic Models r
3.0
- Application of Models L4.0 Verification of :Models y
5.0 Independent Analysis Verification 6.0 References l
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SUMMARY
l APSL is Entering the Final Phase of Obtaining CE Reload technology 1
APS Currently Plans on Submitting Topical Reports for NRC Review by 2nd-Quarter of 1991 NRC Approval of APS Reload Design Capability Required by end of 1st Quarter of -1992 L
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NRC FEEDBACK i
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APS Proposes a working level meeting with NRd 9/90 to Review Topical Outlines in more detail --
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