ML20196C709
| ML20196C709 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 02/09/1988 |
| From: | Bettenhausen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| NUDOCS 8802160215 | |
| Download: ML20196C709 (59) | |
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FEB 0 91988 Docket-Nos. 50-245; 50-336; 50-423; 50-213 Northeast Nuclear Energy Company Connecticut Yankee Atomic Power Company ATTN: Mr. E. J. Mroczka Senior Vice President - Nuclear Engineering and Operations Group P. O. Box 270 Hartford, Connecticut 06141-0270 Gentlemen:
Subject:
February 2,1988 Management Meeting This refers to the February 2, 1988 management meeting, held at your request, in the Region I of fice (see Enclosure 1 for Attendees). We appreciate your interest in keeping us informed of your plans and priorities at the Haddam Neck and Mill-stone sites.
Matters discussed during this meeting included your corporate mission statement, individual performance and accountability, procedure improvements, root cause analyses, outage length reduction plans, INPO evaluations and accreditation, rad-waste volume reduction, radiation exposure reduction, water chemistry improvements, the Haddam Neck core barrel thermal shield modification, and plans to convert from stainless steel to Zircalloy fuel cladding at Haddam Neck.
On our part, we outlined national and regional NRC inspection initiatives. Also, we agreed to pursue improving open item closecut at Haddam Neck by arranging to provide closeout documentation packages prepared by you to region-based reviewers for offsite review.
To submit such packages for review, you need only to provide them to the resident inspector.
Thank you for your cooperation and for your information input. We look forward to other meetings of this type.
Sincerely, Orfctnn:;icnedD,3 l'3H Bettanhausen Lee H. Bettenhausen, Chief i
Projects Branch No. 1 Division of Reactor Projects Enclosures.
1.
Meeting Attendees 2.
NU/NNEC0 Viewgraphs 3.
CYAPC0 Slides 4,
Haddam Neck Fuel Conversion 0FFICIAL RECORD COPY 19/MCCABE/2/4/88 - 0001.0.0 02/04/88 8802160215 880209
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i Northeast Nuclear Energy Company 2
FEB 0 91988 Connecticut Yankee Atomic Power Company l
cc w/ encl:
W. D. Romberg, Vice President, Nuclear Operations S. E. Scace, Station Superintendent D. O. Nordquist, Manager of Quality Assurance R. M. Kacich, Manager, Generation Facilities Licensing D. B. Miller, Station Superintendent Gerald Garfield, Esquire Public Document Room (PDR) local Public Document Room (LPOR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspecter State of Connecticut bec W/ encl:
Region 1 Occket Room (with concurrences)
Management Assistant, ORMA (w/o enci)
ORP Section Chief M. Boyle, LPM, NRR D. Jaffe, LPM, NRR R. Ferguson, LPM, NRR A. Wang, LPM, NRR E. McCabe, RI S. Collins, RI W. Kane, RI L. Bettenhausen, RI E. Conner, RI l
S. Peleschak, RI R. Bellamy, RI J. Richardson, RI W. Johnston, RI W. Thomas, RI T. Weadock, RI P. Swetland, RI R. Bores, ORSS RI:0RP RI:0RP R :0RP 25 Conner /meo McCabe ettenhausen 2/$/88 Og 2/6 0FFICIAL RECORD COPY 19/MCCABE/2/4/88 - 0002.0.0 02/04/88
ENCLOSURE 1 REGION I MEETING NORTHEAST NUCLEAR ENERGY COMPANY FEBRUARY 2, 1988 Northeast Nuclear Energy Company Harry F. Haynes, Station Services Superintendent, Millstone-Richard M. Kacich, Licensing Manager Donald B. Miller, Station Superintendent, Haddam Neck Wayne D. Romberg, Vice President, Nuclear Operations Steve E. Scace, Station Superintendent, Millstone John P. Stetz, Unit 1 Superintendent Nuclear Regulatory Commission Ronald R. Bellamy, Chief, Emergency Preparedness and Radiological Protection Branch, Division of Radiation Safety and Safeguards (DRSS), RI*
Lee Bettenhausen, Chief, Projects Branch No. 1, Division of Reactor Projects (DRP)
Michael L. Boyle, Millstone 1 Project Manager, NRR Samuel-J. Collins, Deputy Director, DRP, RI Monte Conner, Project Engineer, Reactor Projects Section IB, DRP, RI William Johnston, Director, Division of Reactor Safety (DRS), RI*
William F. Kane, Director, DRP, RI Ebe C. McCabe, Chief, Reactor Projects Section 18, DRP, RI Susan Peleschak, Reactor Engineer, Reactor Projects Section 1A, DRP, RI*
Jim Richardson, Deputy Director, DRS, RI*
Paul Swetland, Chief, Reactor Projects Section 28, DRP, RI*
Walter V. Thomas, Radiation Specialist, DRSS, RI*
Tony Weadock, Radiation Specialist, DRSS, RI*
- Part time attendees.
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ENCLOSURE 1 REGION I MEETING NORTHEAST NUCLEAR ENERGY COMPANY FEBRUARY 2, 1988 Northeast Nuclear Energy Compeny Harry F. Haynes, Station Services Superintendent, Millstone Richard M. Kacich, Licensing Manager Donald B. Miller, Station Superintendent, Haddam Neck Wayne D. Romberg, Vice President, Nuclear Operations Steve E. Scace, Station Superintendent, Millstone John P. Stetz, Unit 1 Superintendent Nuclear Regulatory Commission Ronald R. Bellamy, Chief, Emergency Preparedness and Radiological Protection Branch, Division of Radiation Safety and Safeguards (DRSS), RI*
Lee Bettenhausen, Chief, Projects Branch No.1, Division of Reactor Projects (ORP)
Michael L. Boyle, Millstone 1 Project Manager, NRR Samuel J. Collins, Deputy Director, DRP, RI Monte Conner, Project Engineer, Reactor Projects Section IB, DRP,- RI William Johnston, Director, Division of Reactor Safety (DRS), RI*
William F. Kane, Director, DRP, RI Ebe C. McCabe, Chief, Reactor Projects Section 18, DRP, RI Susan Peleschak, Reactor Engineer, Reactor Projects Section 1A, DRP, RI*
Jim Richardson, Deputy Director, DRS, RI*
Paul Swetland, Chief, Reactor Projects Section 28, DRP, RI*
Walter V. Thomas, Radiation Specialist, DRSS, RI*
Tony Weadock, Radiation Specialist, DRSS, RI*
- Part time attendees.
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Northeast Utilities I
NRC Region 1
Management Meeting February 2,1988 King of Prussia, Pa s
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NU Attendees Wayne D. Romberg Vice President - Nuclear Ops Stephen E. Scace Station Supt. - Millstone Donald B. Miller Jr.
Station Supt. - Conn Yankee John P. Stetz Unit 1 Supt. - Millstone Harry F. Haynes Station Services Supt. - Millstone J
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r John P. Stetz John P. Stetz is Superintendent of Millstone 1.
Stetz was born in Wilkes Barre, Pennsylvania.
He carned a Bachelor's Degree in Mechanical Engineering l
in 1968 from Polytechnic Institute of Brooklyn.
As a Nuclear Specialist for General Electric Co. from 1968 to 1977,.Stetz worked on startup and refueling activities at Oyster Creek, Millstone, Vermont Yankee, Peach Bottom, Nine Mile Point and Pilgrim Nuclear Power Stations.
In 1977 he joined NU as a Staff Engineer in the Millstone 1 Engineering Department.
He became Assistant Operations Supervisor for the Unit in 1980.
In 1983 Stetz was promoted to I&C Supervisor and was in that position until becoming Unit Superintendent in 1985.
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j Harry F. Haynes I
Harry F. Haynes is Millstone Station Services Superintendent.
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From 1962 to 1968 Haynes served in the U.S. Navy Nuclear Program. In 1968 he was hired by Millstone 1 Operations l
Department and held PEO, RO, and SRO positions. From j
1972 to 1975 Haynes worked for Millstone 2 Operations as an i
SRO and Shift Supervisor.
In 1975 he was promoted to I&C j
Supervisor for Millstone 2.
He transferred to the corporate i
office in 1982 where he served as the Simulator Project Manager of Technical Systems until 1985 when he became Manager fo Operator Training.
He has been in his current Position as Millstone Station Services Superintendent smcc March of 1987.
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Northeast Utilitics' Corporate Mission Statemement i
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n Northeast Utilities is dedicated to providing
- b. -3afc; Dependable, and rea bnably priced
- kne\\'gy a::d related'servigeEas an ethical and financially sound private enterprise l'
commitled-l0 the'eLRcienVuse of resources,
. a 'resonnsivetlo the,, needs of customers and,their l
cor:ims;nities, Isenskive to the well-being of 1
employees,'and yielding a fair return to shareholders
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r Excellence in Operations To provide SAFE, DEPENDABLE energy at ECONOMIC prices requires high performance at ALL levels i
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Several actions are being taken to meet Mil'istone goals and complementary NRC / INPO goals Management's commitment to excellence is the
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foundation of success
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Operator Professionalism At Millstone "Operations" includes all departments that support operation of the plant The Operations department is the focal point of daily activitics Professionalism based on sense of individual accountability Defined roles and responsibilitics Necessary tools to perform Stress individual accountability Procedure compliance Conduct of Maintenance Radiological Work Practices Industrial Safety e
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r Management's Role in Operator Professionalism Set and Maintain Standards - Levels of Expectations Provide Tools for Personnel to Succeed First line Supervisor Initiativess Additional Supervisory training Increased time in field Salary structure enhancements Facilitics Upgrades Accredited Training Procedurc Upgrade Material Management Focus on Areas of Improvement Root Cause Assessment of LER's, Reactor trips, ESF Actuations, Industrial Accidents QSD Reorganization Emphasis on Functional Requirements Vertical Slice Audits
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r Outage Length Reduction Outage Length Goal - 35 to 42 Days (Breaker to Breaker) i Reduced Exposure Reduced Rad Waste Minimize elective plant modifications Increased Cycle Length May require mid cycle outages of limited duration and scope Rely on recognized strength in outage planning Preparation and execution of outages critical i
Extend resources to emphasize non-outage maintenance planning Maintain and Strengthen Operations focus in maintenance activities V
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1987 INPO Evaluation Overall - 14 Findings 7 Appendix 1 Items 4 Good Practices 5 Strengths Rating - High 2 and Improving 1
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"High morale, individual professionalism, teamwork, and a positive attitude are evident throughout the plant staff.
Additionally, there is a strong sense of management direction and accountability" 4
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r 1987 INPO Evaluation Identified Strengths Control of Totai Orpnic Carbon Nitrogen Injection to Reduce Oxygen in Condensate Use of Bar Coding to Track Contaminated Tools Self Assessment Process to Improve HP Program Extensive Chemistry Upgrade Program Safety Intern Program i
Identified Areas for Improvement Human Factors Deficiencies in Procedures Conduct of Maintenance - Work Practices, Procedure Compliance Maintenance of Station Batteries Contamination Control I
r Training Accreditation Technical Training and Technical Staff and Manager Training are now fully accredited U-3 Operations is only program not yet accredited Accreditation is expected in Spring L
Millstone Unit 1
Unit Overview Operations Maintenance Instrumentation and Control Refuel Planning 1987 Major Outage Modifications NRC Performance Indicators I
Inspection Tour Findings, Bill Russell Tour t
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Operations On-site Fire Protection Coordinator LER Thoroughness, Consistency and Quality Appendix R Audit Feedwater and Reactor Coolant Chemistry Control BWR Owners Group Scram Frequency Reduction Committee Influence High Radiation Gates e
r Maintenancc Turbine MPR/EPR System Performance Improvements Formal In-Service Testing of Feedwater Regulating Controls Gas Turbine Reliability Study Live Loaded Packings Condenser Air In-Leakage Reduction Emergency Diesel Generator Overhaul In-Service Testing of BOP Equipment L
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Instrumentation and Controls I
Surveillance Enhancements Subsequent to 1987 Refueling Outage On-the Job Training Color Coded Test Devices APRM Test Protective Covers l
I&C Supervisory Observations Significant Events Training Department Guidelines Revised j
Plant Management Assessment i
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r Refuel Planning 1987 Refueling Outage Success Advanced Planning Operations Department Perceptive Management Attention and Adlierence to the Schedule l
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r Refuel Planning 1989/1991 Refuel Outage Philosophy 35 to 42 day Outage Window Multi-cycle Schedule Development Unit 1. Average Fuel Cycle
~550 Full Power Days e
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1987 Major Outage Modifications Recirc System Decon / GEZIP / Hydrogen Water Chemistry Test B Low Pressure Turbine Rotor Replacement i
Extraction Steam Piping Replacement Process Computer and Safety Parameter Display System MOVATs Program
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Torsional Test i
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NRC Performance Indicators Millstone 1 Selected Participant in Pilot Program Pilot Program to set guidelines for Industry l
BNL visit to NU to Determine Maintenance Performance Indicator Feasibility in 6 Categories:
1.
Automatic Scrams While Critical 2.
Safety Systems Actuations 3.
Significant Events 4.
Safety System Failures 5.
Forced Outage Rate 6.
Equipment Forced Outage Rate /1000 Critical Hours t
l Visit Provided Valuable Exchange for Both Parties NRC Office of Research (Mr. Stern) receptive to NU's Ideas l
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r Inspection Tour Findings
- Unit 1
Summary of Ilill Russell Tour - August 18,1987 NRC Comments
" The overall material condition and cleanliness of plant areas was very good.
Of particular note was the case of accessability to various plant areas due to radiological cleanliness" w
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Unit 2 1987 Operating Highlights Capacity Factor 91.8% - 3rti higliest in 1987 1987 Exposure 159 Man-Rem total 63 Man-Rem normal operations 81 Man-rem S/G outage 15 Man-Rem Appentlix R modifications I
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Unit 2 Operations Shift Schedule 1
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4 5
6 7
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10 11 12 Ililli llII11 111111 111111 111111 111111 111111 111111 1llll1 1I1111 llllll lll111 Days
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Maximizes Effectiveness of Backshifts Fewer Shift Changes e
Maximizes Quality of Operator Time Off Time Off on Weekends / Long Weekends e
Maximizes Operator Control Over Work Environment Schedule Largely Self Designed by Operations Personnel
r Outage Length Reduction Goal - 35 to 42 days breaker to breaker Shortest outage to date 72 days Current outage schedule 52 days Includes 5 day ILRT Outage scope / Designs / Schedule frozen 3 months before outage Upcoming cycle is last 12 month cycle
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Steam Generator Status Chemistry Improvements Chlorides / Sodium reduced 20X's l
Ionic leakage from demins reduced over 100X's l
Dramatic results evolutionary - attributable to perseverance motivation of staff Titanium Condenser Installed - Zero leakage this cycle Degradation rate sufficiently slowed to allow tube plugging
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rather than sleeving i
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Steam Generator Status Current Outage S/G Inspection 100% ECT to first support l
~15% ECT full length L
Approximately 400 repairable defects All will be plugged 2519 tube pulled / sent for analysis
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Fuel Consolidation I
I Pilot Project co-sponsored l>y CE - EPRI - NU - BG&E 2 to 1 increase in storage density Eligible fuel must have 85% burn up,5 years decay Currently licensed for ten assemblies Ammendment anticipated to allow full scale consolidation e
Unit 3 First Cycle Operating Su:nmary Cycle 1 Capacity Factor - 82.4%
1987 Capacity Factor - 67.4%
Longest run 123 days Cycle 2 refueling outage scheduled 55 days On schedule until RCP problem identified i
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r Unit 3 First Refuel Outage Summary Motlifications:
RTD Hypass Loop Reinoval Snubber recluction S/G contlensate pot replacement Feetipump seal water upgra(le Loose parts monitor replacement ISI S/G slutige lancing S/G ECT testing MOVATS Snubber testing e
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r Unit 3 Trip Reduction Effort 18 Reactor Trips in 1986 9 Reactor Trips in 1987 i
Causes:
Plant specific control responses that were unknown before Start-up Operator inexperience with Unit 3 i
Equipment deficiencies Remedies:
Improved training Fine tuning of control circuits Procedure changes Plant modifications -
S/G condensate pot replacement Feedwater pump sealwater supply upgrade Feedwater isolation valve solenoid replacement e
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3 Flux Thimble Thinning i
Thinning identified in Information Notice 87-44 Baseline eddy current testing of all 58 tubes this outage I
Result:
21 Thimbles with no wear 37 Thimbles show wear from 9% to 38% of wall thickness 6 Thimbles had wear greater than 30%
i Corrective Action:
Worst case thimble capped 6 thimbles >30% moved to change wear location Safety assessment performed to ensure justification of l
continued operation j
i Eddy current testing to be repeated at next outage w
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Exposure Reduction luitiatives Short Term Increase ALARA Awareness - All Units Jol) Cancellation / Scope Reduction - All Units Work Practice Review - All Units Construction Work EITiciency - All Units Decontamination - CY, MP1, MP2 Snul> lier Reduction - MP2, MP3 ALARA Installation Reviews - Early Stages - All Units Coljalt Reduction - All Units l'
<wa Exposure Reduction Initiatives N
Long Term 1
Primary Chemistry Controls - CY, MP2, MP3 Robotics - All Units Steam Generator Replacement - MP2 Cobalt Material Alternatives - All Units l
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r Unit 1 Reactor and Feedwater Chemistry Summary Paranneter Limit Cycle 11 Cycle 12 Reactor Water Chloride Less tlian 20 PPB 5
5 Feedwater Oxygen Less than 200 PPB 20 20 Cycle 12 Startup - August 1987 1
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,r Unit 2 Steam Generator Chemistry Summary Cycle Parameter Limit 5
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8 Chloride Less than 20 PPB 57 29 23 1
Sodium Less than 200 PPB 26 15 13 1
Cat. Cond.
Less than 0.8 US 1.5 1.1 0.6 0.1 End of Cycle 8 - January 1988 l
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r Unit 3 Steam Generator Chemistry Summary Parameter Limit Cycle 1 Chloride Less than 20 PPB 5
Sodium Less than 200 PPB 11 Cat. Cond.
Less than 0.8 US 0.4 w
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i Millstone Station l
Solid Radwaste Burial Volumes i
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42,129 35,337 26,005 27,994 Unit 3 -
1602 16,590 Unit 2 -
3274 Unit 1 - 11,714 1
i 1983 1984 1985 1986 1987 i
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d THE CY MISSION To generate safe, reliable and reasonably priced electrical energy. In doing so we must satisfy our customers (The l
I New England Grid) and regulators while co-existing with our neighboring communities.
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Major contributors to that mission are:
I.
Reduce costs and increase capacity factor.
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Improve our regulatory performance and in doing so, be among the top 10 U.S. generating facilities.
III.
Maintain a strong rapport with neighboring towns and communities.
IV.
Make excellence a standard - not a goal.
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1987 SALP REPORT STATUS UPDATE l
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DONALD B. MITJRR, JR.
STATION SUPERINTENDENT
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PLANT OPERATIONS o
PRE WORK PROCEDURE FOR OFF HOURS MAINTENANCE
-PRE JOB CHECKLIST o
OPERATIONS "IN CHARGE" PHILOSOPHY o
INCREASED EMPHASIS ON FIRST LINE SUPERVISORY PRESENCE IN THE FIELD o
"DO IT RIGHT THE FIRST TIME" o
INCREASED EMPHASIS ON CLEANLINESS /
PAINTING o
ONE REACTOR TRIP DURING 1987
-ADDRESSED ROOT CAUSE o
1987 PRE-OUTAGE CAPACITY FACTOR - 94%
o PORC IMPROVEMENTS
-INCREASED ACCESSIBILITY
-REDUCED MEETING LENGTH o
CONTINUED LER PROGRAM IMPROVEMENTS
-INCREASED EMPHASIS ON ROOT CAUSE ANALYSIS o
EOP IMPROVEMENT PROGRAM
-HUMAN FACTORS REVIEW
-TEMPORARY PROCEDURE CHANGES
-TRAINING IMPROVEMENTS o
STRESS PROCEDURAL COMPLIANCE
. MAINTENANCE MODIFICATIONS o
PRE WORK PROCEDURE FOR OFF HOURS MAINTENANCE
- PRE JOB CHECKLIST o
PROCEDURE UPGRADE PROJECT
-INCORPORATE SOUND HUMAN FACTOR PRINCIPLES o
INCREASED EMPHASIS ON FIRST LINE SUPERVISORY PRESENCE IN FIELD o
"DO IT RIGHT THE FIRST TIME" o
PRE-JOB PLANNING o
INCREASED EMPHASIS ON PROCEDURAL COMPLIANCE AND ATTENTION TO DETAIL o
INCREASED INVOLVEMENT BY HPES AND ROOT CAUSE ANALYSIS
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SURVEILLANCE o
-FIRST INSERVICE ILRT AT THIS PRESSURE
-HELD ADDITIONAL 24 HOURS
-EMPHASIS TEST DIRECTOR RESPONSIBILITIES o
CONTAINMENT PENETRATION IMPROVEMENTS
-MODIFIED HISTORICALLY POOR PERFORMERS THROUGH NEW PIPING CONFIGURATIONS AND VALVE REPLACEMENTS o
LOCAL LEAK RATE TESTING IMPROVEMENTS
-PHYSICAL MODIFICATIONS TO INCREASE COMPLIANCE WITH APPENDIX J TEST REQUIREMENTS
-INITIATED UTILIZATION OF VOLUMETRIC TEST EQUIPMENT TO ACHIEVE GREATER ACCURACY
-INSTITUTED LLRT TECHNICAL PROGRAM FOR NU NUCLEAR UNITS TO INCREASE THOROUGHNESS AND ASSURE CONSISTENCY o
ADDED ADDITIONAL SERVICE WATER VALVES
-PREVENTS RIVER WATER CONTAMINATION OF COMPONENT COOLING WATER o
IMPROVED ECT DATA ANALYSIS / REVIEW PROCESS o
INCREASED EMPHASIS ON PROCEDURAL COMPLIANCE AND ATTENTION TO DETAIL
t FIRE PROTECTION o
STATION FIRE PROTECTION ENGINEER
-POSITION FILLED MAY 1987
-ENHANCED SITE EXPERTISE
-INCREASED SITE AWARENESS
-IMPROVED COMMUNICATIONS WITH CORPORATE GROUPS o
FIRE PROTECTION COMMITMENT EVALUATION
-DOCUMENT SEARCH AND COMMITMENT IDENTIFICATION COMPLETE
-COMMITMENT COMPLIANCE REVIEW COMPLETE
-ULTIMATELY DEVEI.OPED INTO APPENDIX R PROGRAM PLAN o
CODE COMPLIANCE REVIEW COMPLETE
-INITIATION OF MAJOR MODIFICATIONS UNDERWAY o
APPRENDIX R TASK GROUP
-OVERSIGHT FUNCTION o
SELF IDENTIFICATION OF FIRE BARRIER CONCERNS o
MODIFIED SWITCHGEAR ROOM HALON SYSTEM o
STRESS TESTING OF FIRE BRIGADE MEMBERS o
APPENDIX R SWITCHGEAR BUILDING
ENGINEERING SUPPORT o
MITIGATE STAFFING CONCERNS
-REDUCE TURNOVER
-INCREASE OVERALL EXPERIENCE LEVEL o
INCREASED COORDINATION BETWEEN SITE AND CORPORATE ORGANIZATIONS o
PDCR TIMELINESS IMPROVEMENTS o
DEVELOPED AND IMPLEMENTED PDCR PREOPERATIONAL TEST PROGRAM o
INPO ACCREDITATION OF TECHNICAL STAFF AND MANAGER TRAINING PROGRAM o
RESOLUTION OF EEQ AUDIT ITEMS o
ADDITIONAL EEQ ITEMS
-RELOCATION OF CONTROL SWITCHES / INDICATING LIGHTS ON MOTOR OPERATORS MOV-1 AND MOV-2
-PAB CABLING QUALIFIED LIFETIME
-ESTABLISHED A SITE EEQ COORDINATOR
-PERMANENT STAFFING IN CORPORATE ORGANIZATION
-MANAGEMENT INVOLVEMENT IN EEQ WORK REVIEW /
AUTHORIZATION
-TRAINING ON SPLICING / RAYCHEM
-PROGRAM DETERMINED TO BE STRONG; "MECHANICS" TO BE IMPROVED
LICENSING ACTIVITIES o
ROUTINE MEETINGS BETWEEN NRC PROJECT MANAGER AND CORPORATE LICENSING
-JOINTLY PRIORITIZE OPEN ITEMS o
ENHANCE COORDINATION BETWEEN CORPORATE LICENSING AND SITE ORGANIZATION
-ISSUANCE OF PERIODIC PRIORITIZED LIST OF OPEN CY LICENSING ISSUES o
INCREASED CORPORATE LICENSING PRESENCE ON SITE
-LICENSING ENGINEER ON SITE PART TIME
-IMPROVED UNDERSTANDING OF ISSUES
-DEVELOPMENT OF POSITIVE RAPPORT o
INCREASED EMPHASIS ON LER QUALITY AND TIMELINESS o
CONVERSION TO STANDARD TECHNICAL SPECIFICATIONS
-COMPREHENSIVE SURVEILLANCE DATA B ASE
-ADVANCE PREPARATION OF PROCEDURES o
CONTINUED EMPHASIS ON ISAP o
INCREASED SITE EMPHASIS ON NRC OPEN ITEMS
REFUELING AND OUTAGE MANAGEMENT o
PDCR TIMELINESS IMPROVEMENTS o
REFULING OUTAGE COORDINATOR
-MORNING AND EVENING MEETINGS BETWEEN COORDINATOR AND KEY DEPARTMENT PERSONNEL
-DAILY CRITICAL PATH ACTIVITY
-2 DAY LOOK AHEAD
-USE OF NON-MANAGEMENT PERSONNEL AS COORDINATORS o
INCREASED SITE PERSONNEL OUTAGE
" AWARENESS"
-DAILY PLANT STATUS SHEETS o
CONTRACTOR CONTROL
-TWO STOP WORK ORDERS ISSUED
-CONSTRAINED MILESTONE TO MINIMIZE CONTRACTORS ON SITE
-TERMINATIONS FOR SLEEPING
RADIOLOGICAL CONTROLS o
CORPORATE / SITE COMMITTEE
-REVIEW AND UPGRADE HEALTH PHYSICS PROCEDURES o
1987 REFUELING OUTAGE
-EXTENSIVE PRE-OUTAGE ALARA REVIEWS
-OVERALL OUTAGE GOAL 827 MAN-REM
-ACTUAL WAS UNDER GOAL DESPITE WORK SCOPE INCREASES
-DETAILED EXPOSURE REPORT
-ROBOTIC TUBE PLUGGING
-COMPREHENSIVE "HOT PARTICLE" MANAGEMENT F A'OGRAM
-USE OF REMOTE READOUT DOSIMETRY
-STRONG MANAGEMENT SUPPORT OF HEALTH PHYSICS AND ALARA INITIATIVES o
CORPORATE AUDIT / APPRAISAL PROCESS
-TECHNICAL RADIOLOGICAL PROGRAM APPRAISAL BY CORPORATE OVERSIGHT TEAMS o
INPO ACCREDITATION OF CHEMISTRY AND HEALTH PHYSICS TRAINING PROGRAMS
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ON-GOING EPIP UPGRADE o
SPDS COMPLETED DURING 1987 REFUELING OUTAGE o
OFIS IN FINAL TEST MODE o
CONTINUE WITH UNANNOUNCED AUGMENTATION DRILLS o
SUCCESSFUL 1987 DRILL o
ENHANCEMENTS BASED ON 1987 DRILL
-RELOCATE MOCK CONTROL ROOM
-ADDITIONAL CONTROLLER TRAINING
-PROCEDURAL MODIFICATION TO ENSURE RADIO PAGINO TIMELINESS
b SECURITY AND SAFEGUARDS l
o INITIATED PROJECT TO REPLACE SECURITY COMPUTER
-UPGRADE HARDWARE
-EXPAND CAPACITY AND CAPABILITIES o
COMPREHENSIVE SELF INITIATED SECURITY REVIEW CONDUCTED
-CONSIDERED MILLSTONE SECURITY FINDINGS
-CLOSED ONE ACCESS POINT
-PHYSICAL IMPROVEMENTS TO PROTECTIVE AREA FENCES
-UPGRADE AREA DOORS (ON-GOING) l
-UPGRADE VENTILATION SYSTEM BARRIERS (ON-GOING) o IMPROVED ACCESS CONTROL TO SOUTH STORAGE YARD
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TRAINING QUALIFICATIONS ASD EFFECTIVENESS o
INPO ACCREDITATION FOR TECHNICAL TRAINING PROGRAMS
-ENGINEERING (TSM)
-HEALTH PHYSICS
-CHEMISTRY
-INSTRUMENT & CONTROL
-MAINTENANCE o
INTERIM EMPLOYEE CERTIFICATIONS o
NEW PROCEDURE ON PRE-OPERATIONAL TESTING OF PLANT MODIFICATIONS o
INCREASED ALARA EMPHASIS IN GENERAL EMPLOYEE TRAINING
I ASSURANCE OF QUALITY o
INCREASED EMPHASIS
-ATTENTION TO DETAIL
-PROCEDURAL COMPLIANCE
- DO IT RIGHT THE FIRST TIME"
-SUPERVISORY PRESENCE IN THE FIELD o
HIGH RADIATION WORK CONTROL
-CLOSED CIRCUIT TV SURVEILLANCE
-ADDITIONAL LOCKED HIGH RAD GATES
-REMOTE READING DOSIMETRY o
IMPROVEMENT IN QUALITY OF LERs
-EMPHASIZED ROLE OF LER COORDINATOR o
4 ITEMS OF NON-COMPLIANCE IN 1987 VS 21 IN 1986
-EEQ AUDIT RESULTS STILL OUTSTANDING o
ONE PLANT TRIP DURING 1987
e.. e E n c los ar e 4 i
l CONVERSION TO ZIRCALOY CLADDING MOTIVES AND BENEFITS i
l 1
0
$7.5 MILLION/ CYCLE SAVINGS IN FUEL COSTS l
i o
MORE RELIABLE FUEL O
ROUTE TO LONGER CYCLES l
i o
UPGRADE FUEL TECHNOLOGY 4
l i
CONVERSION TO ZIRCAL_0Y CLADDING LONG-TERM.
COMPREHENSIVE PLAN o
EXPERIENCE WITH LEAD TEST ASSEMBLIES l
l o
SUBMITTAL TO NRC ON JANUARY 8,
1988 l
o COMPREHENSIVE IN-HOUSE REANALYSIS I
o N0 HARDWARE MODIFICATIONS PLANNED i
.,. i.
l.
j CONVERSION TO ZIRCALOY CLADDING i
MAJOR MILESTONES l
i o
MEETINGS WITH NRC--EARLY 1988 I
o TOPICAL REPORTS--JANUARY TO JULY 1989 o
LICENSE AMENDMENT REQUEST--JULY 1989 o
CYCLE 17 TECHNICAL REPORT--JUNE 1990 l
l 0
CYCLE 17 START-UP WITH ZIRCALOY--JANUARY 1991 l
i l
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