ML20055D301
| ML20055D301 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/28/1990 |
| From: | Persinko D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9007060135 | |
| Download: ML20055D301 (106) | |
Text
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June 28, 1990 i
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tccket tio. 50-29 I
LICEllSEE:
Y/l:KEE ATOMIC ELECTRIC COMPAttY FACILITY:
YA!;KEE ROUE i
SUBJECT:
TRIP REPORT /MEETIt;G
SUMMARY
. f:RC MEETil!C WITH YAl;KEE AT0111C ELECTRIC COMPAliY, JUtlE 19-21, 1990.
j i
On June 19, 1990, John Craig, Drew Persinko, P.T. Kuo and Paul Shemanski were given a tour of the Yankee site in P. owe, Massachusetts by Tom Koshy,1:PC Senior Resident inspector at Yankee.
On June 10 21, 1990, men.bers of the };RC staff roet with members of the Yankee Atomic Electric Company (YAEC) staff to discuss license renewal activities concerning the Yankee plant. A list of attendees, the meeting agenda, and slides used during the meeting are attached. During the meeting, flRC questions that were sent to YAEC on June 8, 1990, concerning the Yankee Atomic Pilot EvaluationReport(YAEC-171u)werediscussed. The staff found YAEC responses to be adequate and no additional information necessary for all questions except questions 10, 25, 56 ar.d E8. YAEC will formally respond to all questions and provide additional information for questions 16, 25, 56 and 58.
Original signed by:
Drew Persinko, Senior Project lianager License Renewal Project Directorate Division of Reactor Projects. Ill, IV, Y and Special Projects
Enclosure:
- 1. List of Attendees T. fleeting Agenda
- 3. Slides cc w/ enclosure D.H. Crutchfield W.D. Travers (withoutenclosure)
Distribution s CentraTTlTe e, fiRC & Local PERS LRPO R/F F. Miraglia J. Partlow J. Craig PT Kuo OGC E. Jordan ACRS(10)
J. Caldwell R. Borchardt J. Clifford M. Slosson R. Bosnak W. flinners J. Durr, R1 J. Yora P. Shenanski F. Akstulewicz T. Knshy n
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s YANKEE R0WE Ms. Jane 11. Grant Senior Engineer - License Renewal Yankee Aton.ic Electric Company 580 Main Street Boltch, Massachusetts 01740-1398 cc:
s Dr. Andrew C. Kacak, President and Chief Operating Officer Yankee Atoiaic Electric Con.pany 580 Main Street Bolton, Massachusetts 01740-1396 Thonias Dignan, Esquire Ropes and Gray 225 Frar.klin Street Boston, Massachusetts 02110 Mr. T. K. Henderson Acting Plant Superintendent Yenkee Atoniic Electric Ccmpany Star Route Rcwe, Massachusetts 01367 Resident Inspector Yankee Nuclear Power Stction U.S. t!uclear Reguintory Commission Post Office Box 28 Monroe Bridge, Massachusetts 01350 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 A11encale Road Kir.g of Prussia, Pennsylvania 19406 Robert M. Halliscy, Director Radiation Control Program Massachusetts Department of Public Hecith 150 Treniont Street, 7th Floor Boston, Massachusetts 02111 Mr. George Sterzinger Commissioner Vermont Department of Public Service 120 State Street, 3rd Floor tientpelier, Vermont 05602 Hr. John Haseltine Project Director - Yankee Project Yankee Atomic Electric Company 500 Main Street Bolton, Massachusetts 01740-1398
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NENORANDUM FOR: John W. Craig, Director License Renawal Project Directorate Divisicn of Reactor Projects - Ill, IV, V end Special Projects FROM:
Drew Persinko, Senior Project Manager License Renewal Project Directorate Division of Reactor Projects - Ill, IV, Y and Special Projects
SUBJECT:
FORTHCOMING MEET!!iG WITH YANKEE ATOMIC ELECTRIC COMPAt;Y (YAEC) CONCERNING YAEC ACTIVITIES FOR LICENSE RENEWAL DATE & TIME:
June 20, 1990 9am - Apm June 21, 1990 9am - Apm LOCATION:
Yankee Corporate Office 500 Main Street Bolton, MA 01740 PURPOSE:
To discuss progress of YAEC efforts concerning license renewal f or Yankee Rowe.
PARTICIPANTS *:
NRC YAEC John Craig John DeVincentis Drew Persinko John Haseltine et al.
P.T. Kuo A
Aw Drew Persinko, S&nior Project Manager License Renewal Project D1 rectorate Division of Reactor Projects - 111, IV, Y and Special Projects cc:
See next page
'Peet1ogs between NRC technical steff and dpplicants for licenses are open for intet u,ted membe.t s of the puLlic, petitioners, intervenors, or other parties to atter.c as observers pursuant to "Open Meeting Staterent of NRC Staf f Policy",
43 federei kecister 26058, 6/28/78.
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'i-AGENDA EQB NRC/ YANKEE MEETING QM LICENSE RENEWAL IQB THE YANKEE NUCLEAR POWER STATION EpHR 20-21,1990 BOLTON, KASSACHUSETTS 7.HER 111 1990 9:30 a.m.
Introduction (Haseltine) 9:00-10:00 a.m.
Yankee License Renewal Program 9:30 (Haseltine) 10:00 - 12:00 a.m.
Review & Evaluations (McCumber) 12:00 - 1:00 p.m.
Lunch 2t30 p.m.
Established, Effective Programs -
1:00
- cer.hnical Basis, Documentation, Cmtrol (S:ymczak) 3:00 p.m.
Review of Licensing Documents -
2:30 Exemptions, Reliefs, Time Dependencies (Grant) 3:30 p.m.
Application Overview (Hinkle) 3:00 4:00 p.m.
Yankee Environmental Studies -
3:30 Overview (Snooks) 5:00 p.m.
License Renewal Process (Edwards) 4:00 June alt 1990 12:00 a.m.
NRC Questions on Yankee Pilot Study /
8:30 CoDAT Discussion & Resolution (McCumber, et al) 12:00 - 1:00 p.m.
Lunch
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NRC Review of Yankee's Work To Date 1:00 (Breakout Groups)
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LICENSE RENEWAL FOR YANKEE NUCLEAR POWER STATION i
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YANKEE /NRC MEETING l
JUNE 20-21,1990 i
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YANKEE ATOMIC ELECTRIC COMPANY BOLTON, MASSACHUSETTS l
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l AGENDA EQB NRC/ YANKEE MEETING 1
QE LICENSE BENEWAL EQB THE YANKEE NUCLEAR POWER STATION JUNE 20-27.1990 BOLTON, MASSACHUSETTS i
JUNE 1RA 1990 9:00
- 9:30 a.m.
Introduction (Haseltine) 9:30
- 10:00 a.m.
Yankee License Renewal. Program (Haseltine) 10:00 - 12:00 a.m.
Review & Evaluations (McCumber) 12:00 - 1:00 p.m.
Lunch 1:00
- 2:30 p.m.
Established, Effective Programs -
Technical Basis, Documentation, Control (Szymczak) j 2:30
- 3:00 p.m.
Review of Licensing Documents -
Exemptions, Reliefs, Time Dependencies (Grant) 3:00
- 3:30 p.m.
Application Overview (Hinkle) 3:30
- 4:00 p.m.
Yankee Environmental Studies -
Overview (Snooks) 4:00
- 5:00 p.m.
License Renewal Process (Edwards)
EMDA 112 1990 8:30
- 12:00 a.m.
NRC Questions on Yankee Pilot Study /
CoDAT - Discussion & Resolution (McCumber, et al) 12:00 - 1:00 p.m.
Lunch i
1:00
- 3:00 p.m.
NRC Review of Yankee's Work To Date (Breakout Groups)
LEAD PLANTS YANKEE HAS CONTRACT WITH DOE /EPRI FOR LEAD LICENSE RENEWAL PWR PLANT NORTHERN STATES POWER'S MONTICELLO PLANT IS THE LEAD LICENSE RENEWAL BWR PLANT 9
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<l June 12, 1990 PLEX WORK INSTRUCTION INDEX YR-WI-28 Format and Content of Component Specific Rev. 2 Evaluations YR-V1-30 Fluid System Component Identafication Rev. 3 YR-WI-31 Performing Plant System and Structure Level Rev. 3 Review Rev. 2 YR-WI-32 Performing Component Level Review Rev. 1 YR-WI-33 Information Management YR-WI-34 Plant Procedure (s) Review Rev. 2 YR-WI-35 Structural Component Identification Rev. 2 YR-WI-36 Electrical System Components Identification Rev. 3 YR-WI-37 PerfSrming Component. Level Review Rev. 3 for Structural Components YR-WI-38 Current Licensing Basis Documentation Rev. S' for Structures, Systems and Components of the YNPS YR-WI-39 Evaluating the YNPS Environmental Rev. 1 Qualification Program YR-WI-41 Area Environmental Monituting Rev. 1 YR-WI-42 Action Itea Identification and Status Rev. 0 Rev. 0 YR-WI-49 I&C Component Identification Rev. 0 YR-WI-50 Nameplate Data
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YANKEE /NRC LICENSE RENEWAL MEETING JUNE 20-21,1990 BOLTON, MASSACHUSETTS SCREENING AND EVALUATIONS
~
JOSEPH T. MCCUMBER YANKEE ATOMIC ELECTRIC-COMPANY
t YANKEE LICENSE RENEWAL PROGRAM ALL PLANT SYSTEMS AND W
STRUCTURES (SS) 5 NO NO NO DOCUMENT SAFETY N ON-SAF E T Y APP R SASIS FOR R E L AT E DY REQUIRED TO A
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SCREENING AND EVALUATIONS
- 1. OBJECTIVES
- 2. PILOT REPORT'S PURPOSE AND SCOPE
- 3. METHODOLOGY AND CRITERIA o HISTORY o CHANGES
- 4. SCREENING IMPLEMENTATION l
o SYSTEM LEVEL SCREEN o COMPONENT SCREENING BY DISCIPLINE
- 5. DETAILED EVALUATIONS
- 6. DOCUMENTATION / REFERENCES
- 7. BASIS FOR PROGRAM EFFECTIVENESS o ROLE OF SCREENING o MAINTENANCE REVIEW COMMODITY EVALUATIONS 1
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SCREENING REVIEW OBJECTIVES
- DETERMINE SCOPE OF SSC'S REQUIRING LICENSE RENEWAL REVIEW e DETERMINE COMPONENTS FOR WHICH AGING CAN BEST BE MANAGED BY PLANT PROGRAMS IDENTIFY COMPONENTS REQUIRING DETAILED e
EVALUATION AND/OR SPECIAL ACTIONS FOR LICENSE RENEWAL o
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i SCREEhlNG REVIEW PURPOSE OF PILOT REPORT i
l PURPOSE PROVIDE THE METHODOLOGY, CRITERIA, AND PLANT SPECIFIC EXAMPLE OF THE SYSTEMS / STRUCTURE LEVEL SCREEN PROVIDE A DEMONSTRATION OF THE COMPONENT LEVEL SCREENING PROCESS FOR A REPRESENTATIVE PLANT SYSTEM /
STRUCTURE FOR EACH DISCIPLINE SCOPE ONLY CONSIDERS THE SCREENING PROCESS, DOES NOT INCLUDE DETAILS OF FURTHER EVALUATIONS DETERMINED NECESSARY OR THE FULL BASIS OF PROGRAM EFFECTIVENESS
SCREENING REVIEW METHODOLOGY AND CRITERIA HISTORY
- DEVELOPED BY SANDIA AND NUMARC TECHNICAL SUBCOMMITTEE BEGINNING BACK IN 1988 SUBMITTED TO NRC BY NUMARC IN 10/89
- NRC COMMENTS PROVIDED IN 3/90
- NUMARC RESPONSE AND PROPOSED CRITERIA CHANGES SUBMITTED 4/90
- REVISED METHODOLOGY AND CRITERIA DUE TO NRC IN 7/90 l
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SCREENING REVIEW METHODOLOGY AND CRITERIA CHANGES
- TERMINOLOGY from SCREENING to REVIEW j
to EVALUATION to SCREENING
- DEFINITION FOR SYSTEMS AND STRUCTURES' REQUIRING LICENSE RENEWAL REVIEW ADOPTED SIMilAR TO NRC DRAFT. RULE
- BASIS FOR EFFECTIVE PROGRAM DETERMINATION MUST CONSIDER COMPONENT FUNCTION AND AGE RELATED DEGRADATION, TO THE EXTENT NECESSARY
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SCREENING IMPLEMENTATION SYSTEM AND STRUCTURES A STANDARDIZED SYSTEMS AND STRUCTURES LIST WAS DEVELOPED CLEAR SYSTEMS AND STRUCTURAL BOUNDARIES WERE ESTABLISHED FOR USE IN SCREENING SCREENING PERFORMED USING THE NUMARC METHODOLOGY AND CRITERIA AS. DESCRIBED i
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SCREEhlNG IMPLEMENTATION SYSTEM AND STRUCTURES (CONT)
- RESULTS
- PILOT 35 OF 78 SYSTEMS EXCLUDED 19 OF 46 STRUCTURES EXCLUDED
- CURRENT 35 OF 78 SYSTEMS EXCLUDED 12 OF 46 STRUCTURES EXCLUDED
- CHANGES ARE. PRELIMINARY AND ARE THE RESULT OF THE PROPOSED NUMARC DEFINITION OF SYSTEMS AND STRUCTURES REQUIRING LICENSE RENEWAL REVIEW
- ASSOCIATED WITH STRUCTURE FAILURE CAUSING LOSS OF A COMPONENT'S SAFETY FUNCTION
- . A BASIS WAS PROVIDED FOR ALL SYSTEMS AND STRUCTURES EXCLUDED FROM LICENSE RENEWAL REVIEW
- TO DATE WE HAVE ONLY REVIEWED SYSTEMS AND STRUCTURES TO THE PROPOSED DEFINITIONS TO DETERMINE lF ADDITIONAL SYSTEMS NEED TO L
BE INCLUDED. IT IS ALSO POSSIBLE THAT SYSTEMS AND STRUCTURES CAN BE EXCLUDED i
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4 SYSTEMS AND STRUCTURES IMPORTANT TO LICENSE RENEWAL L
(1) SAFETY RELATED SYSTEMS AND STRUCTURES,
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AND MAINTAIN IT IN A SAFE SHUTDOWN CONDITION, AND THE CAPABILITY TO PREVENT OR MITIGATE THE CONSEQUENCES OF ACCIDENTS P
WHICH COULD RESULT IN POTENTIAL OFF-SITE DOSE CONSEQUENCES COMPARABLE TO THE PART 100 GUIDELINES. DESIGN BASIS EVENTS ARE
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DEFINED THE SAME AS IN 10CFR 50.49 (b)(1).
g (2) NONSAFETY-RELATED SYSTEMS AND STRUCTURES WHOSE FAILURE COULD DIRECTLY PREVENT SATISFACTORY ACCOMPLISHMENT OF THE SAFETY FUNCTIONS SPECIFIED IN PARAGRAPH (1) OF THIS DEFINITION BY THE SAFETY-RELATED SYSTEMS AND STRUCTURES, y
(3) SYSTEMS AND STRUCTURES WHICH ARE NECESSARY TO MEET THE REQUIREMENTS OF:
(a) 10CFR50.48 (FIRE PROTECTION)
(b) 10CFR50.62 ( ATWS)
(c) 10CFR50.63 (STATION BLACKOUT) 1
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SCREENING IMPLEMENTATION l
SYSTEMS AND STRUCTURES (CONT) l l
IT IS RECOGNIZED THAT OTHER PLANT SYSTEMS AND STRUCTURES WARRANT CONSIDERATION OF AGING BEYOND THE l
SCOPE OF LICENSE RENEWAL i
- KEY TRANSIENT INITIATORS
- PERSONNEL SAFETY l
- ECONOMIC YANKEE SPECIFIC RISK STUDIES AND INDUSTRY EXPERIENCE WILL DETERMINE THE FOCUS AND EXTENT OF REVIEW t
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- IDENTIFY COMPONENTS
- INDIVIDUAL AND GENERIC GROUPS
- MARKER:-Vi ORAWINGS
- DATAB/ SE T ;VELOPMENT
- IMPLEMEN. ATION VARIES BY DISCIPLINE
- FLUID SYSTEMS
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l SCREENING IMPLEMENTATION FLUID SYSTEMS DETERMINE COMPONENT FUNCTIONS
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- ACTIVE OPERABILITY DETERMINE COMPONENTS IMPORTANT TO SYSTEM SAFETY FUNCTION PRESSURE BOUNDARY COMPONENTS ARE 3
l REVIEWED USING CODAT TO DETERMINE POTENTIAL DEGRADATION ISSUES BASED ON MATERIALS AND PROCESS CONDITIONL POTENTIAL ISSUES ARE REVIEWED RELATIVE TO CAPABILITY OF ISI AND OTHER PROGRAMS l
l TO DETECT AND MANAGE ISSUES PLANT PROGRAMS WILL PROVIDE THE BASIS FOR MANAGING ACTIVE FUNCTIONS PROGRAM ENHANCEMENTS WILL BE MADE AS NECESSARY l
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Dearacation Mechan'sms Cons cered General or Uniform Corrosion Erosion / Corrosion Two Phase Erosion Microbiologically influenced Corrosion intergranular Stress Corrosion Cracking Transgranular Stress Corrosion Cracking i
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CoDAT HAS IDENTIFIED THE POTENTIAL FOR GENERAL OR UNIFORM CORROSION IN SELECTED SYSTEMS 4
THE EROSION CORROSION PROGRAM DEFINES i
SPECIFIC WALL THICKNESS MEASUREMENT REQUIREMENTS FOR PIPING SUSCEPTIBLE TO EROSION CORROSION AN OPTION FOR MAN AGING POTENTIAL CORROSION IS TO EXPAND THE EROSION CORROSION PROGRAM TO TAKE WALL THICKNESS MEASUREMENTS OF 1
I SELECTED CONTROL LOCATIONS IN SYSTEMS WITH CORROSION CONCERN SPECIFIC DETAILS WILL BE DESCRIBED IN THE COMMODITY REPORTS I
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SCREENING IMPLEMENTATION STRUCTURAL GENERIC ASSESSMENTS WERE DEVELOPED i
TO IDENTIFY AGE RELATED DEGRADATION MECHANISMS APPLICABLE TO STRUCTURAL COMPONENTS i
ASSESSMENTS DESCRIBE WHICH CONDITIONS LEAD TO DEGRADATION AND HOW DEGRADATION IS MANIFESTED ASSESSMENTS PREPARED FOR:
- CONCRETE STRUCTURAL CO'MPONENTS
- STRUCTURAL STEEL COMPONENTS
- SEALANTS, ROOFING, AND WATERPROOFING BARRIERS
- EQUIPMENT SUPPORT COMPONENTS APPROXIMATELY 6 MANWEEKS SPENT STUDYING ASSESSMENTS AND PLANT DRAWINGS IN i
PREPARATION FOR WALKDOWN WALKDOWN TEAM CONSISTED OF:
1 YANKEE I
2 STONE AND WEBSTER 1 BECHTEL l
(OVER 80 YEARS OF CIVIL EXPERIENCE)
SCREEhlNG IMPLEMENTATIOh i
STRUCTURAL (CONT.)
TWO WEEKS ON SITE FOR WALKDOWN
- FOCUSED EXAMINATIONS OF AREAS IDENTIFIED IN ASSESSMENTS
- GENERAL EXAMINATION OF ALL ACCESSIBLE AREAS
- VIDEOTAPED CONDITIONS FOR DOCUMENTATION AND AS A BASELINE FOR ANY TRENDING OF MATERIAL CONDITION WHICH MAY BE NECESSARY AREAS IN-ACCESSIBLE DURING PLANT OPERATION ARE SCHEDULED FOR WALKDOWN THIS OUTAGE l
SCREENING.lMPLEMENTATION STRUCTURAL (CONT.)
- BASED ON WALKDOWN, STRUCTURES ARE IN VERY GOOD CONDITION AND WlLL NOT PRESENT A PROBLEM FOR LICENSE RENEWAL
- WITH SOME CORRECTIVE MAINTENANCE NOW, AND PERIODIC FOLLOW-UP EXAMINATIONS OF SELECTED AREAS
- roofing degradation was noted, with repairs in progress
-initiation of minor corrosion 1
in need of maintenance painting
- minor cracking will be assigned periodic follow-up examinations
- outside equipment foundations with signs of freeze-thaw damage initiation will be further evaluated to determine optimum repair methods l
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- ELECTRICAL COMPONENT FUNCTIONS ARE ACTIVE (MOTOR SHt"'T ROTATION, CONTACTS CLOSING, OR
. SWITCH, BREAKER, OR RELAY MOVEMENT) OR PASSIVE (ENERGY CONVERSION, CONDUCTANCE, OR l
DIELECTRIC STRENGTH)
- I&C COMPONENTS CAN HAVE BOTH AN OPERABILITY AND PRESSURE BOUNDARY FUNCTION
- THE PRESSURE BOUNDARY PORTION OF l&C COMPONENTS ARE REVIEWED WITH THE FLUID SYSTEM
- OPERABILITY CAN BE ELECTRICAL OR MECHANICAL
- THE DEGRADATION MECHANISMS APPLICABLE TO ELECTRICAL EQUIPMENT ARE:
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- RADIATION DAMAGE
- THERMAL EMBRITTLEMENT
- WEAR OF ACTIVE COMPONENTS
- PITTING AND CORROSION e
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SCREENING IMPLEMENTATION l
ELECTRICAL AND I&C (CONT.)
MANY ELECTRICAL AND I&C SYSTEMS AND COMPONENTS HAVE BEEN REPLACED IN RECGNT YEARS, WITH PLANS FOR ADDITIONAL UPGRADES l
examples include:
l
- Containment isolation System
- Feedwater Control System
- Steam Generator Trip System
- EQ Equipment in Containment
- Nuclear Instrumentation System (this outage)
I THE REASON FOR REPLACEMENT WAS NOT A RESULT OF AGE RELATED FAILURE, BUT DUE TO NEW LICENSING REQUIREMENTS OR BECAUSE OBSOLESCENCE MADE ROUTINE MAINTENANCE DIFFICULT (DUE TO LACK OF VENDOR SUPPORT OR UN-AVAILABILITY OF SPARE PARTS)
AGE OF MANY OF THESE COMPONENTS WILL BE LESS THAN 40 AT THE YEAR 2020 e
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ELECTRICAL AND I&C (CONT.)
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- THE EQ PROGRAM PROVIDES THE BASIS FOR AGING MANAGEMENT OF MANY COMPONENTS i
- AN EVALUATION OF THE COMPONENTS COVERED BY THE PROGRAM WAS PERFORMED TO DETERMINE THE ACTUAL QUALIFIED LIFE.
- MOST COMPONENTS WERE SHOWN TO HAVE i
QUALIFIED LIFES EXTENDING TO THE YEAR 2020, OR BEYOND
- EXPECT TO USE QUALIFIED LIFE DATA FOR COMPONENTS IN HARSH ENVIRONMENTS TO DEMONSTRATE LIFE OF SIMILAR i
COMPONENTS IN CONTROLLED ENVIRONMENTS l
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SCREENING IMPLEMENTATION ELECTRICAL AND I&C (CONT.)
)
MANY SMALL ELECTRICAL AND I&C COMPONENTS HAVE BEEN PUT INTO MISC, COMMODITY GROUPINGS (for example, relays, switches, molded case circuit breakers, indicators, terminal blocks, etc.)
1
- these are typically short lived, and readily replaced l
- failures are not generally tied to age
- of ten associated with multiple train l
L redundancy I
- intuitively not a concern for license renewal, however, further bases development needed - possibly by trending failure rates l
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DOCUMENTATION IDENTIFY COMPONENTS IMPORTANT
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COP'PONENT SPECIFIC REACTOR VESSEL MAIN COOLANT SYSTEM REACTOR INTERNALS l
VAPOR CONTAINER REACTOR SUPPORT STRUCTURE L
ISSUE RELATED
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NSSS FATlGUE MICROBIOLOGICAL INDUCED CORROSION L
l l
A EVALUATION OF FATIGUE NSSS COMPONENTS SCOPING REVIEW OF YANKEE SHOWS-
- NOZZLE DESIGNS HAVE INHERENT 2
FATIGUE RESISTANCE
- TRANSIENT CYCLES VERY LOW OPTIONS
- ASME Ill ANALYSES OF SELECTED LOCATIONS
- DEMONSTRATE DESIGN MARGIN BASED ON COMPARISON OF SIMILAR DESIGNS
- AUGMENTED EXAMINATION OTHER PLANT WALKDOWNS TO IDENTIFY HIGH CYCLE FATIGUE CONCERNS Near Vibrating Equipment Pump Suction / Discharge Relief Valve Discharge Poor Configurations l
ACTIVITIES PLANNED FOR OUTAGE WALKDOWNS
- Vapor Container
- Other Previously In-accessible Areas
- General Equipment Condition Assessment
- Potential High Cycle Fatigue Locations SAMPLING AND ANALYSIS FOR MIC POTENTIAL TEMPERATURE MONITORING IN VAPOR j
CONTAINER
- lNFRARED SURVEY FOR HOT SPOTS l
l 4
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l SCREENING AND EVALUATIONS ARE PERFORMED IN ACCORDANCE WITH DETAILED WORK INSTRUCTIONS INFORMATION SUPPORTING THE SCREENING PROCESS ARE MAINTAINED IN SYSTEM NOTEBOOKS A DATABASE HAS BEEN DEVELOPED, TIED TO COMPONENT TAG NUMBERS, TO STORE SCREENING i
AND EVALUATION INFORMATION AND FOR USE IN SUPPORTING MAINTENANCE ACTIVITIES THE BASES FOR CoDAT HAVE BEEN SUBMITTED TO THE NRC AS YAEC REPORT 1727P DATABASE VERIFICATION IS IN PROGRESS THE COMPLETE BASIS FOR DETERMINATION OF PROGRAM EFFECTIVENESS IS PROVIDED BY THE MAINTENANCE COMMODITY EVALUATIONS ALL SUPPORTING INFORMATION WILL BE AVAILABLE AT YANKEE FOR NRC REVIEW 9
e,
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l REFERENCES l
ENGINEERING STAFF REVIEWS AVAILABLE
=
l TECHNICAL INFORMATION TO SUPPORT YANKEE EFFORTS, INCLUDING EPRI, DOE, NPAR, NRC BULLETINS,1NPO, ETC.
DESIGN INFORMATION IS USED AS NEEDED TO MAKE A DETERMINATION THAT A l
COMPONENT WILL CONTINUE TO PERFORM ITS INTENDED SAFETY FUNCTION DURING THE RENEWAL PERIOD.
example:
- PROGRAMS IN PLACE TO FUNCTIONALLY TEST A PUMP PER ASME REQUIREMENTS l
ARE JUDGED ACCEPTABLE BASED ON THE ACTIVITIES PERFORMED. THE ACTUAL PERFORMANCE FIGURES (FLOW, HEAD, ETC.)
GIVEN IN THE PROGRAM PROCEDURES ARE CONSIDERED TO BE CONSISTENT WITH LICENSING REQUIREMENTS DOCUMENTS IDENTIFIED WITH SPECIFIC TIME DEPENDENCIES, EXEMPTIONS, OR RELIEFS WILL BE REVIEWED TO ENSURE THE BASES OF SCREENING AND EVALUATIONS ARE NOT ALTERED 9
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I BASIS FOR PROGRAM EFFECTIVENESS ROLE OF SCREENING SCREENING PROVIDES A PRELIMINARY ASSESSMENT OF THE CAPABILITY OF PLANT PROGRAMS TO PROVIDE THE BASIS FOR MANAGING COMPONENT AGING DURING j
- COMPONENTS ARE BINNED ACCORDINGLY
- THE BASES SUPPORTING THE DETERMINATION OF EFFECTIVENESS WILL BE ESTABLISHED IN COMPONENT SPECIFIC OR COMMODITY REPORTS j
- WHICH CONSIDER FUNCTIONS, DEGRADATION MECHANISMS, MAINTENANCE ACTIVITIES, HISTORY, ETC. - TO THE EXTENT NECESSARY l
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i COMMODITY GROUPS i
CABLES / CONDUCTORS INVERTERS /UPS PUMPS TRANSFORMERS TANKS POWER SUPPLIES MANUAL VALVES ANALYZERS CHECK VALVES CONTROL & PROT EQUIP MOTOR OPERATED VALVES BATTERIES CONTROL VALVES MOTORS l
SOLENOID VALVES SWITCHGEAR/MCOs HVAC EQUIPMENT DIESELS FILTERS MISC ELECTRICAL l
HEAT EXCHANGERS MISC I&C DIESELS SPRING SUPPORTS ROOFING BLOCK WALLS SEALANTS PIPING FIRE DOORS AND SEALS LIFTING EQUIP.
t l
SNUBBERS MISC. STRUCTURAL l
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YANKEE /NRC LICENSE RENEWAL met-IING JUNE 20-21,1990 t
i BOLTON, MASSACHUSETTS ESTABLISHED EFFECTIVE PROGRAMS i
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WILLIAM J. SZYMCZAK YANKEE ATOMIC ELECTRIC COMPANY I
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ESTABLISHED EFFECTIVE PROGRAMS GOAL MANAGE AGE-RELATED DEGRADATION APPROACH BUILD UPON CURRENT PROGRAMS FOR MANAGING AGE-RELATED DEGRADATION t-
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ONGOING AGING MANAGEMENT ACTIVITIES IN SUPPORT OF LICENSE RENEWAL t
EXPANSION OF VIBRATION PURCHASED MOVATS EQUIPMENT MONITORING PROGRAM AND TRAINING f
ROUTINE USE OF THERMOGRAPHY ENHANCED INSERVICE TESTING PROGRAM j
i CONTINUAT!ON OF WATER CHEMISTRY EXPANSION OF LUBE OIL PROGRAM l
PROGRAM (RESULTING IN EXCELLENT TO INCLUDE FERROGRAPHY CONDITION OF STEAM GENERATORS) l EXPANSION OF EDDY CURRENT STRUCTURAL WALKDOWNS FOR AGE-l PROGRAM FOR HEAT EXCHANGERS RELATED DEGRADATION l
EQ PROGRAM CHECK VALVE PROGRAM i
ULTRASONIC ERROSION/ CORROSION AMBIENT TEMPERATURE MONITORING PROGRAM MONITORING PROGRAM J
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FOR PLANT PROGRAMS FOR MANAGING AGE-RELATED i
DEGRADATION BY:
IDENTIFYING LICENSE RENEWAL COMPONENTS IDENTIFYING ACTIVITIES TO MANAGE i
AGE-RELATED DEGRADATION JUSTIFYING SCOPE OF ACTIVITIES (BASES)
IDENTIFYING ENHANCEMENTS AND/OR EXPANSIONS TO EXISTING PLANT PROGRAMS, AS NECESSARY i
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PROCEDURE ENHANCEMENT PROGRAM i
THE PROCEDURE ENHANCEMENT PROGRAM, A SUBSET OF THE OVERALL LICENSE RENEWAL PROGRAM, IMPLEMENTS j
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- ESTABLISHES DOCUMENTATION AND CONTROL REQUIREMENTS 4
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ELEMENTS OF COMPONENT / COMMODITY GROUP EVALUATIONS WILL INCLUDE, TO THE EXTENT NECESSARY, THE FOLLOWING:
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- EVALUATE ACTIVITIES TO DETERMINE IF l
DEGRADATION MECHANISMS ARE BEING PROPERLY j
MANAGED AND COMPONENT FUNCTION MAINTAINED i
l
- IDENTIFY ANY.NECESSARY EXPANSIONS AND/OR ENHANCEMENTS TO ACTIVITIES l
l i
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h STATION BATTERY EXAMPLE STATION BATTERIES ARE FUNCTIONALLY TESTED TO MONITOR PERFORMANCE.
REFURBISHMENT AND/OR REPLACEMENT IS REQUIRED IF ACCEPTANCE l
STANDARDS ARE NOT MET-I
- STATION BATTERY TESTING:
+ WEEKLY - ALL PILOT CELLS-- CHECKED l
+ QUARTERLY ~ - ALL CELLS CHECKED
+ REFUELING - FULL LOAD TEST l
+ 5-YRS - CAPACITY CHECK (80% OR GREATER)
- COMPONENT / COMMODITY GROUP EVALUATION DOCUMENTS JUSTIFICATION FOR SUFFICIENCY OF THE ABOVE ACTIVITIES
- NO FURTHER ACTION REQUIRED f
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Pump inservice testing programs, which are used to verify pump performance, record results, and which require corrective action-if acceptance. criteria are not met, are considered effective for demonstrating the operability safety function.
Such testing, however, would not cover ' degradation mechanisms associated with the pump's. pressure boundary function.
Other programs, such as. inservice inspection, will be necessary to address the pressure boundary function.
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INSTRUMENT TEST AND CALIBRATION PROCEDURES i
l REQUIRE REPLACEMENT ~ OR REFURBISHMENT IF THE l
COMPONENT FAILS TO. MEET. SPECIFIED ACCEPTANCE CRITERIA:
1 A-transmitter which is regularly tested to ensure j
1 setpoints are within specified limits to assure proper' operation, has the results recorded and is calibrated as. necessary, and. requires replacement with abnormal setpoint drift, is considered subject to an effective program.
Knowledge of the specific degradation mechanisms which caused the drift in setpoint is-not necessary to demonstrate program i
effectiveness.
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ENVIRONMENTAL QUALIFICATION EXAMPLE.-
l THE EQ -PROGRAM QUALIFIES COMPONENTS FOR A SPECIFIED LIFE AND REQUIRES EXTENDED QUALIFICATION OR REPLACEMENT AT THE END 'OF THE QUALIFIED LIFE:
- Environmental Qualification (EQ) Programs require l
periodic maintenance and scheduled replacement of items.
These actions are-based on extensive testing and/or i
analyses to. determine. design ' basis environmental I
i conditions which include the effects of aging.
The j
requirements of the EQ Program to maintain component f
4 qualification is considered an existing licensing committment which will continue during the-renewal j
period. Such components. covered by the EQ Program do not j
require further evaluation for license renewal.
The EQ Program mandates. replacement or extended qualification-of governed components when their qualification expires.
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COMPONENT / COMMODITY GROUP EVALUATION RESULTS 1)
ACTIVITIES NECESSARY TO MANAGE AGE-RELATED DEGRADATION ARE IDENTIFIED
- 2) BASIS FOR THE ABOVE ACTIVITIES
- 3) IDENTIFICATION OF ENHANCEMENTS / EXPANSIONS
- 4) IDENTIFICATION OF UNECESSARY ACTIVITIES 5)
IDENTIFICATION OF ANY NEW PROGRAMS
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SUMMARY
l I
4 i
o THE YANKEE LICENSE-RENEWAL PROGRAM i
INTEGRATES SCREENING AND EVALUATION TASKS l
o PROGRAM WILL ADDRESS PROCESS, CONTROL, AND DOCUMENTATION CONCERNS o
PROVIDE BASIS. FOR PROCEDURE ENHANCEMENTS AND PLANT PROGRAM FOR MANAGING AGE-RELATED DEGRADATION i
MONITORS PLANT AND INDUSTRY EXPERIENCE o
O PLANT MAINTENANCE PROGRAM MANUAL WILL PROVIDE FRAMEWORK FOR INTEGRATING LR REQUIREMENTS o
ASSURES CONTINUED COMPLIANCE FOR LR l
l
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e YANKEE /NRC LICENSE. RENEWAL MEETING JUNE 20-21,1990 BOLTON, MASSACHUSETTS i
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EXEMPTIONS, RELIEFS, TIME DEPENDENCIES
=
JANE M. GRANT YANKEE ATOMIC ELECTRIC COMPANY
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REVIEW FOR TIME DEPENDENCIES o
REVIEW ALL YANKEE LICENSING CORRESPONDENCE TO IDENTIFY EXEMPTIONS AND RELIEFS (10 -CFR PART -54) i t
o EVALUATE TIME DEPENDENCY NATURE OF EXEMPTIONS AND RELIEFS jj o
PROVIDE
SUMMARY
JUSTIFICATION IN THE APPLICATION l
FOR CONTINUING -THE -EXEMPTION OR.REllEF THROUGH THE LICENSE RENEWAL TERM OR DESCRIBE OTHER ACTION l
TO BE TAKEN I
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THAN EXEMPTIONS AND RELIEFS, SUCH AS:
FSAR TECH SPECS LICENSING CORRESPONDENCE TIME DEPENDENCIES WILL BE-IDENTIFIED AND THEN o
RESOLVED AS PART OF THE SSC EVALUATIONS l
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STATUS OF REVIEW OF YANKEE LICENSING DOCUMENTS.
(EXCLUDING FSAR/ TECH SPECS)
AS OF JUNE 14, 1990:
13,432 TOTAL NO. OF DOCUMENTS
=
(EXCLUDING FSAR/ TECH SPECS) 9,479 NO. OF DOCUMENTS REVIEWED
=
43 TIME DEPENDENCIES
=
55 EXEMPTIONS
=
20 RELIEFS
=
- *
- N OT E * *
- THE-NUMBERS INDICATED FOR TIME DEPENDENCIES, EXEMPTIONS, AND RELIEFS REPRESENT THE NUMBER OF DOCUMENTS WHICH RELATE TO EACH OF THOSE CATEGORIES.
FOR ~ EXAMPLE, OUT OF 55
- EXEMPTION" DOCUMENTS,.ONLY 15 UNIQUE EXEMPTIONS MAY EXIST.
~
RESULTS OF LICENSING DOCUMENTS REVIEW EXAMPLES --
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EXEMPTIONS IDENTIFIED (TO' DATE):
l 10CFR50, ~ APP. R (MAJORITY) 10CFR50, APP J 10CFR50.44 -
o RELIEFS IDENTIFIED (TO DATE):
INSERVICE INSPECTION-o TIME DEPENDENCIES IDENTIFIED (TO DATE):
EXEMPTIONS (MOST. ARE FOR THE LIFE OF THE PLANT)
OTHER LICENSING DOCUMENTS - REACTOR VESSEL AND FATIGUE 1
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YANKEE /NRC LICENSE RENEWAL MEETING L
JUNE 20-21,1990 BOLTON, MASSACHUSETTS l
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WILLIAM D. HINKLE.
YANKEE ATOMIC ELECTRIC COMPANY im t
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INTRODUCTION
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I
- APPLICATION TO BE SUBMITTED IN JUNE 1991
- NEED TO BEGIN PREPARATION NOW
- NRC REQUIREMENTS STILL UNCERTAIN j
. OUTLINE PRESENTED IS BASED ON YANKEE'S j
CURRENT VIEWS AND ASSUMPTIONS j
=.
APPLICATION CONTENTS i
COVER LETTER l
i REGULATORY
SUMMARY
SAFETY ANALYSIS REPORT i
i ENVIRONMENTAL REPORT i
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REGULATORY
SUMMARY
1.0 INTRODUCTION
2.0 SAFETY ANALYSIS 3.0 ENVIRONMENTAL ANALYSIS
4.0 CONCLUSION
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SAFETY ANALYSIS REPORT
1.0 INTRODUCTION
2.0 METHODOLOGY FOR INTEGRATED PLANT REVIEW 2.1 SELECTION OF SSs IMPORTANT TO LICENSE RENEWAL 2.2 COMPONENT-LEVEL SCREENING AND EVALUATION
- 2. 2.1 FLUID SYSTEMS 2.2.2 ELECTRICAL SYSTEMS 2.2.3 I&C SYSTEMS 2 2.4 STRUCTURES 3.0
SUMMARY
OF COMPONENT-LEVEL EVALUATIONS 3.1 INDIVIDUAL COMPONENT EVALUATIONS
I SAFETY ANALYSIS REPORT (CONTINUED) l i
I 3.1.1 REACTOR VESSEL 3.1.2 REACTOR INTERNALS 3.1.3 MAIN COOLANT SYSTEM COMPONENTS l
3.1.4 STEAM GENERATORS 3.1.5 VAPOR CONTAINER 3.1.6 REACTOR SUPPORT AND NEUTRON SHIELD TANK l
3.2 COMMODITY GROUP EVALUATIONS 1
3.2.1 FLUID SYSTEM COMMODITY GROUPS l
3.2.2 ELECTRICAL SYSTEM COMMODITY GROUPS 3.2,3 I&C SYSTEM COMMODITY GROUPS 3.2.4 STRUCTURAL COMMODITY GROUPS 3.3 DEGRADATION ISSUE EVALUATIONS 3.3.1 NSSS FATIGUE 3.3.2 OTHER ISSUES i
i-SAFETY ANALYSIS REPORT
~
l (CONTINUED) 4.0 PLANT PROGRAM FOR MANAGING AGE-RELATED l
DEGRADATION l
l 4.1 PURPOSE AND SCOPE l
4.2
SUMMARY
DESCRIPTION 1
l 4.3 DOCUMENTATION 4.4 ADMINISTRATION AND CONTROL j
l 5.0 REVIEW OF PLANT-SPECIFIC EXEMPTIONS AND i
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RELIEFS i
i 5.1 IDENTIFICATION OF TIME-DEPENDENCIES l
i l
5.2 ANALYSIS OF TIME-DEPENDENCIES i
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SAFETY ANALYSIS REPORT (continued) i 6.0
SUMMARY
AND CONCLUSIONS j
7.0 REFERENCES
i APPENDICES f
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ENVIRONMENTAL REPORT j
ASSUMPTIONS I
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NOT REQUIRED
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- GENERIC ENVIRONMENTAL DOCUMENT WILL BE USED f
l TO MAXIMUM EXTENT POSSIBLE
- ANALYSES NEED ONLY BE PROSPECTIVE 7
- NO NEED FOR CONSIDERATION OF SEVERE ACCIDENTS, NEED FOR POWER, OR ALTERNATIVES l
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4 ENVIRONMENTAL REPORT i
1.0 INTRODUCTION
2.0 ENVIRONMENTAL INTERFACES i
2.1 GEOGRAPHY AND DEMOGRAPHY i
2.2 ECOLOGY l
i 2.3 METEOROLOGY 2.4 HYDROLOGY l
3.0 ENVIRONMENTAL EFFECTS 1
3.1 EFFECTS OF NEW CONSTRUCTION i
l 3.2 EFFECTS OF HEAT DISCHARGE l
1 i
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ENVIRONMENTAL REPORT (continued) j 3.3 EFFECTS OF ROUTINE RADIOLOGICAL EMISSIONS i
l 3.4 EFFECTS OF LICENSING BASIS ACCIDENTS 3.5 EFFECTS OF URANIUM FUEL CYCLE 3.6 EFFECTS ON DECOMMISSIONING 4.0
SUMMARY
AND CONCLUSIONS
5.0 REFERENCES
^
l APPENDICES 4
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i 1
THE RENEWAL RULE i
Objective is Establishment of a Workable Process i
l CLB - Opportunity and Pitfall 1
Backfit Philosophy Hearing Schedule Treatment of NEPA L
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A SUCCESSFUL PROCESS t
Lead Plants Obtain Renewal:
Timeliness Process Actually Ends With a Decision Opportunities to Upset /?revent Decision Minimum l
Process is Repeatable:
Stability Definitions are Unambiguous and Universal l
Boundary of Review is Clear & Unimpeachable Litigation ' Targets" Reduced Scope is Confined to Age Degradation:
Focus Degradation of Important Equipment is Managed Legitimize Variability (Between Plants) in L. B. Detail Generic Issues Incorporated Only as Resolution Available Note: Success Will Precipitate Participation
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USE OF CLB AS AUTHORITATIVE REFERENCE
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Originally CLB Created as a Concept and a Term Applicant for Renewal is an Existing Facility Unique Combination of Features to Meet Regulations Performance a Matter of History Immersed in " Environment" of Review and Oversight Protection of Public Safety Adequate Rock Bottom Standard of Acceptance CLB Provides Little Information for Screening and/or Evaluation Screening for Equipment Requiring Added Attention-(Repair, Replace, Monitor)
Evaluation:
Ability to Continue to Perform Intended Function Similar to Any Evaluation Done now L
Example of S.I. Tank Replacement j
Aging Degradation - Corrosion of a Component Exactly What Evaluations are About What we do Today for a Ddsign Change
v EXAMPLE OF SI TANK REPLACEMENT CLB INFORMATION DB DOCUMENTS l
FSAR k Codes to Use Materials i
AISC-Supports
(
API-650 (AWS D-1)
Foundation
(
ACI-318-83 Piping Design 4
B.31.1
)
~
4 Plant Piping Specification ]
J FSAR
)
System Parameters Select Value Type
(
Engineering Experience j
(
SI Design Calc.
TECH SPECS k Min Water Volume Tank Volume
(
Plant Design Spec.
TECH SPECS
) Temperature Range Heat / Tracing Insulation (
Plant Insulation Specs Power Source
(
Safety Classifications Classifications 4
of Systems Manual j
I (Elec/ Mech) 1 TSCH SPECS
) Water Level Inst. Location
(
- Plant froiedures
& Experience j
l.
Shipping & Receipt 4
- ANSI Standards I
l SEP-SER p Separate Seismic & LOCA l
Selsniic Design for Seismic Reevaluation 1'
and Retrofit Criteria L
Tank and Supports
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- ~. - - - - - -
)
COMPILATION OF THE CLB Should not be a Prerequisite to the Screen / Evaluation l
Reasons for Compilation for Renewal Invalid Search "old Incomplete Records to Find Forgotten Requirements" r
Uncover Significant Commitments not in FSAR Make it Have " Official Enforceable Status" Determine Whether "[ Licensee] has Effective Programs to Control & Monitor - Aging" l
Enable " Question [ing) Compliance and Accuracy of the CLB" Compilation Unfairly Burdens License Renewal If a Valid Issue -it is Valid Today not Future Cannot - Assume Credit for Programs That " Assure L
Compliance on an Ongoing Basis" and also Require Compilation to see if "Anything Missed" a
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USE OF CLB i
What is the CLB7 -
Documents Body of Docketed Information That Describes the Means by Which Yankee Satisfies Regulations N'RC License Conditions Technical Specifications / Amendments Orders SERs Exemptions / Reliefs Environmental Assessments Yankee FSAR/ Amendments Responses to G.L., Bulletins,50.54(f) Letters, NOVs Environmental Reports What Should be Compiled for Renewal-Information Actually Used to Support Conclusions May or May not Include CLB Information Use Commitment Documents as a Cross-Check Exemptions and Reliefs Non-Hardware Associated Time Dependencies Demography - (Environmental Report)
Re-Evaluation of Appendix I Determination i
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EFFECTIVE PROGRAMS NOT DESCRIBED IN CLB i
4 Effective " program" Documented in Plant Procedures Provides Objective Acceptance Criteria L
Specifically Treats Degradation Mechanism of Concern Existing Relevant " programs" Should be Accepted w/o Change Effective Date - Application Date Many not Specifically Described in CLB 4
New " programs" may be Necessary to Resolve Deficiencies From Analysis Summary of Conclusions in Application Detailed Basis of Conclusions Retained in Renewal Files 4
Control and Administration of all Age-Degradation Management " programs" Should be Incorporated l
Into the Licensing Basis as the Renewal Program
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l TREATMENT OF THE CLB AS DESCRIBED ABOVE
)
Reduces Potential Instances Where Decision to Issue Renewal License can be Overturned or Prevented l
(Extraneous Debate Over Adequacy of CLB Documentation is Avoided)
Licensing Basis Information is Distinguished From j
Underlying Design Information l
l
. Review Focused on Soundness of Technical Decision, as is the Practice Today j
Only Relevant CLB Information is Compiled
,}
l Scope is Management of Age-Degradation of Components Necessary to Maintain Safety Function i
j APPLICABILITY OF BACKFIT PHILOSOPHY SHOULD NOT CHANGE b.
Commission can Exclude Rulemaking from Backfit Analysis Basis Should be That new Requirements are not Being Created.
M Review of Application Should be Controlled by L
Backfit Philosophy Changes Imposed by Staff to Mitigate Aging Degradation Should be Documented but not Necessarily Cost-Justified Changes Imposed by Staff for Reasons Other Than Mitigation of Age-Degradation Should be Documented and l
Cost Justification Provided
(
Creation of a new Category
" Age-Related Requirements l-l That are Needed to Maintain Compliance With the CLB"- Could add Confusion and Delay i-Threshold was Focus of Two Lawsuits Sounds Like the Only Reason to Compile CLB L
Potential Avenue to Gain Change w/o Concommitant Justification I
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5 1
HEARING SCHEDULE i
Hear!"g Schedule Guideline is a Magnificent Tool Used for Maintaining Licensing Process in mid-70's Installed in HLW Proceeding Format Being Dismissed Out-of-Hand Timely Renewal Doctrine not a Substitute Uncertainty on Staff Uncertainty on Capital Progranu Schedule Guidelines Focuses on Getting to the End of the Proceedings Does not Impede Substantive Public Participation Applies Equally to all Parties Disciplines the Process
TREATMENT OF NEPA ISSUES l
1 Shift From Env. Doc. to G.E.I.S. Unexpected Tables S-3 & S-4 B ssed Upon Environmental Survey Base Document G.E.I.S. has Strong Programmatic Overtones Increases Hearing Potential Decreases Certainty of Finishing 1
l Substantially Increases Burden on Lead Plants b
Lead Plants Have a Substantial Problem
+
Pt. 51.20 b.(2) Requires Plant-Specific EIS G.E.I.S. hearings in Parallel With L.P. Filing L.P. " Resolve" all Issues in own Hearing?
Staff Willing - Plant-Specific Decision Before Generic?
l Generic Resolution Determined by L.P.'s?
- Success Means:
l Timely Issuance of Renewal Licenses Stability Focus r
l L.
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