ML18152A237
| ML18152A237 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 10/05/1990 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 9010230187 | |
| Download: ML18152A237 (39) | |
Text
OCT o 5 1990 Docket Nos.
50-280, 50-281, 50-338, 50-339 License Nos. NPF-4, NPF-7, DPR-32, DPR-37 Virginia Electric and Power Company ATTN:
Mr. W. L. Stewart Senior Vice President - Nuclear 5000 Dominion Boulevard Glen Allen, VA 23060 Gentlemen:
SUBJECT:
MANAGEMENT MEETING
SUMMARY
OFFICIAL COPY This letter refers to the Management Meeting held on September 21, 1990, at the Region II Office.
The meeting concerned a status review of your commitment management system and a North Anna presentation on safety assessment and automation enhancements at the station. A list of attendees, a meeting summary, and a copy of your handouts are enclosed.
Iii accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room Should you have any questions concerning this letter, please let us know.
Enclosures:
- 1.
List of Attendees
- 2.
Meeting Summary
- 3.
Handout - Commitment Management Status
- 4.
Handout - Safety Assessment and Automation cc w/encls:
E. W. Harrell Vice President - Nuclear Operations Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 (cc w/encls ~ cont'd page 2) rtft~?i!~,~r ~r!;~~t-:i, 1:-,
Sincerely, Original signed by Ellis W. Merschoff (for)
Luis A. Reyes, Director Division of Reactor Projects
Virginia Electric and Power Company (cc w/encls cont 1d)
J. P. 0 1 Hanlon Vice President - Nuclear Services Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 R. F. Saunders, Manager Nuclear Licensing Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 G. E. Kane, Station Manager North Anna Power Station P. 0. Box 402 Mineral, VA 23117 Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, VA 23683 Executive Vice President Old Dominion Electric Cooperative Innsbrook Corporate Center 4222 Cox Road, Suite 102 Glen Allen, VA 23060 W. T. Lough Virginia Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, VA 23209 William C. Porter, Jr.
County Administrator Louisa County P. 0. Box 160 Louisa, VA 23093 Michael W. Maupin, Esq.
Hunton and Williams P. 0. Box 1535 Richmond, VA 23212 Patrick A. 0 1 Hare Office of the Attorney General Supreme Court Building 101 North 8th Street Richmond, VA 23219 (cc w/encls - cont 1d page 3) 2 OCT o 5 1990
Virginia Electric and Power Company cc w/encls cont'd)
C. M. G. Buttery, M.D., M.P.H.
Department of Health 109 Governor Street Richmond, VA 23219 Attorney General Supreme Court Building 101 North 8th Street Richmond, VA 23219 Commonwealth of Virginia bee w/encls:
Document Control Desk DRP Section Chief NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 78-A Mineral. VA 23117 NRC Resident Inspector U.S. Nuclear Regulatory Commission Routes 1, Box 166 Surry, VA 23883 RI~DRP r
PFr drickson 10/t:;/90 RII~
MSi iul; 10/~/90 3
OCT o 5 hi90
ENCLOSURE 1 MANAGEMENT MEETING LIST OF ATTENDEES Virginia Electric and Power Company (V1rginia Power)
J. O'Hanlon, Vice President, Nu~lear Services G. Kane, Station Manager - North Anna R. Saunders, Manager, Licensing M. Bowling, Assistant Station Manager - North Anna Nuclear Regulatory Commission - Region II L. Reyes, Director, Division of Reactor Projects (DRP), RI!
E. Mersch off, Deputy Di rector, DRP, RI!
T. Peebles, Chief, Operations Branch, Division of Reactor Safety (DRS), RH M. Sinkule, Branch Chief, DRP~ RII T. Decker, Chief, Radiological Effluents a*nd Chemistry Section, Divis"ion of
- Radiatio_n Safety and Safeguards (DRSS), RII P. Fredrickson, Section Chief, DRP, RII F. Jape, Chief,.Quality Performance Section, DRS~. RI!
R. Moore~ Reactor Engineer, DRS, Rll R. Shortridge, Radiation Specialist, ORSS, RI!
Nuclear Regulatory Commission - Hea~guarters L. Engle, Project Manager, North Anna, NRR
ENCLOSURE 2 MEETING
SUMMARY
An NRC and Virginia Power management meeting was conducted at the NRC Region II office on September 21, 1990, to discuss the status of the Virginia Power commitment management system and also to discuss safety assessment and automation enhancements at the North Anna statio~.
The DRP Division Director opened* the meeting* by welcoming. the licensee attendees and noting that the NRC was very interested in the topics at-hand.
The Vice President; Nuclear Services, then introduced the topics for discussion.
The Manager, Licensing, presented the corrmi tment management system update using the handout in Enclosure J.
(This issue had previously been discussed in* a February 1990 NRG/Virginia Power meeting.)
He discussed the self-assessment conducted of the existing system and the recommendations from that study.
He focused on the pi 1 ot programs for both stations and a corporate program to be implemented by the end of March 1991.
Slides were presented to show the samples of actual forms to be used in this system.
Some discussion took place on the use of this system to reschedule resources.when
. large significant corranitments are made unexp~ctedly.
Virginia Power stated that the system would assi.st in -these instances, but up-front management decisions would sti 11 be necessary to reschedul ¢ resources.
Additional discussion took place on the commitment milestones, used to ensure that a project was on-track time-wise.
Based on the recent NRC Regulatory Impact Survey, discussion took place on the need for the NRC to understand the resource impact on 1 i censees for NRC conmi tments ~ to ensure that safety
- significance is the driving force on scheduling plant changes and upgrades.
The North Anna Station and Assistant Manager discussed, using the handout from, the philosophy of safety assessment at North Anna and several of the tools used to ensure good performance in this area.
They also discussed performance indicators for North Anna and further discussed (from the July 1990 self-assessment meeting) the performance windows concept now in-place at North Anna.
In addition, several computer-based devices developed for plant operations use were demonstrated for the NRC staff. The meeting was concluded with the DRP Deput.rDirector thanking Virginia Power for the presentation.
Virginia Power Commitment Management System Update.
September 21, 1990 Mr. J. P. O'Hanlon Mr. R. F. Saunders
Agenda
- Self Assessment of Existing CTS
- Recommendations
- Management Oversight
- Program Plan
- Further Enhancements
Self Assessment of Existing CTS System
- Corporate Nuclear Safety Performed Assessment
- Management Review of Assessment Report Conducted
- Nine recommendations Identified for Implementation
- Information Meeting Held with NRC in February 1990
Recommendations
- 1. Establish single and effective issues management system.
- 2. Upgrade and standardize corporate and station procedures
- 3. Improve information flow and interface between stations and corporate
- 4. Formalize system for evaluating issue 'impact and priority before establishing due dates.
- 5. Establish stringent controls for extensions to due dates
- 6. Flag or restore historical commitments into station documents as necessary
- 7. Evaluate computer hardware and software needs
- 8. Establish accountability through performance indicators, and management goals and objectives.
- 9. Closely monitor commitment implementation and flag delays to management.
Management Oversight Based on implementing the recommendations of the CTS assessment,
.. significant improvements are _expected in:
- Management involvement in establishing due dates
- Management involvement in extending due dates
- Periodic reports to management on CTS trends, workloads, and completion
- User-friendly computer software and common data base
- Single and effective management standard
Program Plan Item
- Update computer hardware and software
- Periodic CTS working level coordination meetings
- Revise nuclear standard and procedures
- Provide interim status reports to management
- Establish routine management report requirements
- Pilot program at Surry
- S_tart pilot program at North Anna
- Total commitment management implementation Status Ongoing Ongoing
- Approval Routing
. Completed
- April / August Ongoing 3rd quarter t990 4th quarter 1990 1st quarter 1991
Further Enhancements
- Add historical commitment data base derived from configuration management effort
- Continue to update* commitments in the historical commitment data base
- Management utilization of performance indicators to monitor and maintain program effectiveness
t.l'H,L.U~Ul,t:. q VIRGINIA POWER G. E. Kane Station Manager
AGENDA SAFETY ASSESSMENT AND QUALITY VERIFICATION G. E. KANE NUCLEAR SAFETY ASSESSMENT M. L. BOWLING PERFORMANCE ANNUNCIATOR WINDOWS M. L. BOWLING PRIORITY CORRECTIVE ACTIONS AUTOMATION G. E. KANE/ M. L. BOWLING
SAFETY ASSESSMENT & 2UALITY VERIFICATION CONSERVATIVE OPERATING AND REPORTING PHILOSOPHY SENSITIVITY TO INDUSTRY EVENTS
- SOER REVALIDATION PROGRAM
- INCREASED MANAGEMENT ATTENTION AND RESOURCES FOR OPERATIONAL EVENT REVIEWS BOTH AT CORPORATE AND STATION LEVEL VERY LOW THRESHOLD FOR IDENTIFICATION OF STATION DEVIATIONS AND TIMELY RESOLUTION THROUGH THE CORRECTIVE ACTION PROGRAM REORGANIZED OFFSITE INDEPENDENT REVIEW FUNCTION.
- CORPORATE NUCLEAR SAFETY
- MANAGEMENT SAFETY REVIEW GROUP SELF ASSESSMENT PROGRAM HAS STRONG MANAGEMENT SUPPORT AND INVOLVEMENT
SAF.~TY ASSESSMENT & QUALITY VERIFICATION QUALITY ASSURANCE PROGRAM HAS BEEN INCORPORATED AS AN INTEGRAL PART OF STATION MANAGEMENT STARTUP ASSESSMENT PROGRAM USED TO ENSURE UNIT IS READY FOR POWER OPERATION NUCLEAR SAFETY ASSESSMENTS ARE BEING PERFORMED AUTOMATION IS BEING USED TO HELP REDUCE PERSONNEL ERRORS AND ENHANCE PROFESSIONALISM
- - - - - - ~ ~ ~
VIRGINIA POWER M. L. Bowling Assistant Station Manager
- NUCLEAR SAFETY ASSESSMENT
I INDICATORS OF NUCLEAR SAFETY
- Past Performance in key safety areas relative to the industry performance.
- Current performance in key safety areas relative to past performance.
- Events which could challenge the operators and the plant.
- Reactor Coolant System and Steam Generator integrity.
- Material condition of key safety systems, safety related equipment, and equipment which if not available, has a direct impact on the operator.
- Precursors of significant industry issues and events.
- Precursors of significant personnel error events.
KEY SAFETY PERFORMANCE PAST PERFORMANCE RELATIVE TO INDUSTRY CURRENT PERFORMANCE REIATIVE TO INDUSTRY
PERFORMANCE IND1CA10RS FOR NORTH ANNA UNIT 1 PAST PERFORMANCE WORSE THAN AVG BETTER THAN AVG (2)
( 1) 0 2
(MEASURED IN STANDARD DEVIATIONS)
DEVIATIONS OF LAST 4 QUARTER AVERAGE FROM CURRENT INDUSTRY AVERAGE (LAST QUARTER IS 90-3)
- -**-----*~-------
AUTO SCRAMS SCRAMS PER 1000 HRS EQUIVALENT AVAILABILITY FORCED OUTAGE RATE THERMAL PERFORMANCE SAFETY SYSTEM ACTUATIONS CHEMISTRY INDEX FUEL RELIABILITY (2)
CURRENT PERFORMANCE DECLINED IMPROVED
-0.24
( 1) 0 (MEASURED IN STANDARD DEVIATIONS)
DEVIATIONS Of LAST QUARTER FROM PREVIOUS 4 QUARTER AVERAGE (LAST QUARTER IS 90-3) 2
PERFORMANCE INDICATORS FOR NORTH ANNA UNIT 2 PAST PERFORMANCE WORSE THAN AVG BETTER THAN AVG (2)
( 1) 0 2
(MEASURED IN STANDARD DEVIATIONS)
DEVIATIONS or LAST 4 QUARTER AVERAGE FROM CURRENT INDUSTRY AVERAGE (LAST QUARTER IS 90-3)
AUTO SCRAMS StRAMS PER 1000 HRS EQUIVALENT AVAILABILITY FORCED OUTAGE RATE THERMAL PERFORMANCE (Cannot be calculated 90-3)
SAFETY SYSTEM ACTUATIONS CHEMISTRY INDEX FUEL RELIABILITY
-14.97
-CX>-
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CURRENT PERFORMANCE (2)
DECLINED IMPROVED
( 1) 0 2
(MEASURED IN STANDARD DEVIATIONS)
DEVIATIONS OF LAST QUARTER FROM PREVIOUS 4 QUARTER AVERAGE (LAST QUARTER IS 90-3)
I
PERFORMANCE INDICATORS FOR NORTH ANNA (COMMON)
PAST PERFORMANCE WORSE THAN AVG BETTER THAN AVG (2)
( 1) 0 (MEASURED IN STANDARD DEVIATIONS)
DEVIATIONS OF LAST 4 QUARTER AVERAGE FROM CURRENT INDUSTRY AVERAGE (LAST QUARTER IS 90-3) 2 MAINT BACKLOG > 3 MONTHS RATIO or PM TO TOTAL* MAINT PM ITEMS OVERDUE LOST TIME ACCIDENTS RADIATION EXPOSURE SKIN & CLOTHING CONTAMINATIONS SOLID RADWASTE SHIPPED (2)
CURRENT PERFORMANCE DECLINED IMPROVED
( 1) 0 (MEASURED IN STANDARD DEVIATIONS)
DEVIATIONS OF LAST QUARTER FROM PREVIOUS 4 QUARTER AVERAGE (LAST QUARTER IS 90-3) 2
CHALLENGES TO OPERATIONS AND PLANT TRANSIENTStrRIPS FORCED.POWER REDUCTIONS REQUIRED SAFETY SYSTEM ACTUATIONS SAFETY SYSTEM ACTUATIONS DUE TO MAINTENANCE AND TEST ACTIVITIES SAFETY SYSTEM FAILURES
Forced Power Reductions & Transients 8
2 2
89-4 90-1 90-2 7 /90-8/)0 Year-Quarter 3
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88-4 89-1 89-2 89-3 89-4 90-1 90-2 7/90-8/90
. Year - Quarter
4-4 Safety Systen1 Actuations Due* to Test & Maintenance Activities I Unit 1 I 2.---------------,
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89-3 89-4 90-1 90-2 7/90-8/90 Year - Quarter
PRIMARY CONTAINMENT INTEGRITY REACTOR COOLANT SYSTEM INTEGRITY STEAM GENERATOR INTEGRITY
RCS LEAKRATE I Unit 1 Unidentified RCS Leakage I QB
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[ RM-121 Air Ejector I 10-89 11-89 12-89 01-90 02-90 03-90 04-90 05-90 06-90 07-90 08-90 Month-Year Unit2 Main Steam Header I 35
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- MATERIAL CONDITION KEY SAFETY EQUIPMENT AVAILABILITY KEY SAFETY EQUIPMENT PERFORMANCE LONG TERM EQUIPMENT PROBLEM
SAFETY SYSTEM AVAILABILITY FOR ~ORTH ANNA UNIT 1 PAST PERFORMANCE WORSE THAN AVG BETTER THAN AVG 0.26 0.64 (2)
( 1) 0 2
(MEASURED IN STANDARD DEVIATIONS)
DEVIATIONS Of LAST 4 QUARTER AVERAGE FROM CURRENT INDUSTRY AVERAGE (LAST QUARTER IS 90-3)
DG AVAILABILITY HHSI AVAILABILITY AFW AVAILABILITY CURRENT PERFORMANCE DECLINED IMPROVED
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SAFETY SYSTEM AVAILABILITY FOR NORTH ANNA UNIT 2 PAST PERFORMANCE WORSE THAN AVG BETTER THAN AVG 0.81 (2)
( 1) 0 2
(MEASURED IN STANDARD DEVIATIONS)
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Long Tern1 Equipnient Probleins I Equipment Problems More Than 3 Months Old I 8
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3/89 6/89 9/89 12/89 3/90 6/90 8/90 Month-Quarter
PRECURSOR EVENTS PRECURSORS OF SIGNIFICANT INDUSTRY ISSUES AND EVENTS PRECURSORS OF SIGNIFICANT PERSONNEL ERROR EVENTS
DR Comparison to SOERS 70 60
" 50
... :, = 40 0
LL. 30 0
- 20 10 0
119-1 SOER 88-1 Instrument Air System Failures 62 119-2 119-3 89-4 90-1 90-2 90-3 SOER 85-3 Excessive Personnel Rodiotion. Exposure 12.----------------------,
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.. 15 0 10 I.&. -
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119-1 119-2 119-3 119-,
90-1 90-2 90-3 SOER 84-5 Bolt Degradation or Failure in Nuclear Power Plants 12.---------------------,
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1 1990 Personnel Errors Operations & Maintenance 2
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