ML18153B410
| ML18153B410 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 12/13/1993 |
| From: | Buckley B, Engle L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9312220260 | |
| Download: ML18153B410 (45) | |
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Docket Nos. 50-280, 50-281 50-338, 50-339 December 13~93 LICENSEE:
Virginia Electric and Power Company (VEPCO)
FACILITIES:
Surry, Units 1 and 2 and North Anna Units 1 and 2 Power Stations
SUBJECT:
SUMMARY
OF NOVEMBER 4, 1993 COUNTERPARTS MEETING On November 4, 1993, NRR and Region II staff met with representatives of VEPCO in VEPCO's Corporate Office in Richmond, Virginia, to discuss a variety of subjects as summarized below.
A list of attendees and meeting handouts are provided as Enclosures 1 and 2, respectively.
Issues that the NRC took the lead on were:
(1) temporary leak repairs, (2) employee concerns, i.e., whistle blowers, and (3) control rods. Topics discussed by VEPCO were: (1) Nuclear Business Unit, (2) Surry core upgrading, (3) storage of Surry, Unit 2 control rod guide tubes, (4) Surry service water self assessment, (5) Maintenance Rule implementation status, (6) North Anna, Unit 2 steam generator replacement plans, (7) NRC/VEPCO Communications/
presentations plans, (8) status of open NRC unresolved items, and (9) radiation work permits, digital alarming dosimeters {DADs) issues and compliance.
VEPCO also requested that we arrange meetings in the near future on (1) ASME relief request process, (2) core upgrade, and (3) cost beneficial licensing actions.
(Original. Signed By)
Leon B. Engle, Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11
Enclosures:
As stated cc w/enclosures:
See next page OFFICE LA: PDII-2 PM:
NAME Elana [f..f (Original Signed By)
Bart C. Buckley, Sr. Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 OFFICIAL RECORD COPY - DOCUMENT NAME: C:\\AUTOS\\WPDOCS\\S RRY\\CPSUM.MTG 9312220260 931213". -~]
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Virginia Electric & Power Company cc:
Mr. William C. Porter, Jr.
County Administrator Louisa County P.O. Box 160 Louisa, Virginia 23093 Michael W. Maupin, Esq.
Hunton and Williams Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, Virginia 23219 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P.O. Box 1197 Richmond, Virginia 23209 Old Dominion Electric Cooperative 4201 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. M. L. Bowling, Manager Nuclear Licensing & Programs Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060 Office of the Attorney General Supreme Court Building IOI North 8th Street Richmond, Virginia 23219 Senior Resident Inspector North Anna Power Station U.S. Nuclear Regulatory Commission Route 2, Box 78 Mineral, Virginia 23117 Senior Vice President Surry Power Station U.S. Nuclear Regulatory Commission Post Office Box 166, Route 1 Surry, Virginia 23883 Robert B. Strobe, M.D., M.P.H.
State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Regional Administrator, RII U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W, #2900 Atlanta, Georgia 30323 Mr. G. E. Kane, Manager North Anna Power Station P.O. Box 402 Mineral, Virginia 23117 Mr. W. L. Stewart Senior Vice President - Nuclear Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. Michael R. Kansler, Manager Surry Power Station Post Office Box 166, Route I Surry, Virginia 23883 Mr. Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683
e Memorandum Dated:
December* 13, 1993 Distribution
.Oocl,rt _f_iJ e*
NRC & Local PDRs PDII-2 RF T. Murley/F. Miraglia, 12-G-18 L. J. Callan, 12-G-18 S. Varga G. Lainas H. Berkow B. Buckley E. Tana OGC E. Jordan M. Branch, RI I S. Tingen, RII/R J. York, RII/R L. Garner, RII/R R. Croteau D. Taylor, RII/R R. McWhorter, RII ACRS (10)
L. Plisco, EDO RII M. Sinkule, RII
1 SURRY/NORTH ANNA POWER STATIONS COUNTERPARTS MEETING November 4, 1993 Name Bart Buckley Morris Branch Stephen Tingen Art Stall John York Larry Garner Richard Croteau Marvin Sinkule Don Taylor Alan Price Rick McWhorter Herb Berkow Leon Engle David Sommers Joe Hegner Bil 1 Benthall Attendance List Office NRR/PDil-2 SRI/Surry {NRC)
RI/Surry {NRC)
VEPCO RI/Surry {NRC)
RII NRR/PDll-2 RII NAPS VEPCO NRC/SRI NA NRR/PDII-2 NRR/PDil-2 VEPCO VEPCO VEPCO
J-NORTH ANNA UNIT 2 NRC COUNTERPARTS MEETING NOVEMBER 4, 1993
STEAM GENERATOR REPLACEMENT NORTH ANNA UNIT 2 PROJECT STRATEGY MANAGEMENT MANAGE AE's AND CONTRACTOR COORDINATE INTERFACE ENGINEERING MANAGE AE's 1 OCFR50.59 APPROACH PURCHASING S/Gs - OEM PERMANENT PLANT MATERIALS BY VA. POWER NON-PERMANENT PLANT MATERIALS BY CONTRACTOR STRATEGY THE SAME AS UNIT 1
Lessons Learned
- Perform walkdowns and as-builts for all systems worked on or replaced ir*
- Clearly identify requirements that are beyond codes or standards (RT Quality)
- Minimize interface with other groups P8081.14
Lessons Learned (Continued)
- Issue Engineering package 6-9 months before outage
- Project Engineering should review construction procedures
- Physically verify all purchased materials and*
equipment P9081.II e
Lessons Learned ( Continued)
- Support contracts needed
- SIG supplier
- NE of record
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- Support areas dedicated to the proj~ct
- NOE
- HP /RP e
1993 I
1994 I
1995 SEPIOCT NOVIDECIJAN IFEBIMAR IAPRIMAYIJUNIJUL IAUG ISEPIOCT INOVIDEC IJANIFEBIMAR IAPRIMAY IJUNIJULIAUGISEPIDCT INDVIDEC 1993 RFO ENG WALKDOWN e
AB AND ELIVER STEAM GENERATORS lROCURE.ONG LEAD MATERIALS
.. NGINEEAING e
1995 RFO AND PRE SGR MODIFICATIONS Plot Date 2BOCT93 r;:mm ~m'i;' Datu -
Shut I of I
Data Date 1NOV93 NORTH ANNA UNIT NO. 2
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- n*rred annrnuon Project Start tSEP93 g//1 I PrOlll'IU Bar Pro ect Fintsh 1MAY95 M1lutone/Fl111 JcU.vltY STEAM GENERATOR REPLACEMENT PROJECT SCHEDULE (cl Pr11111ver11 Svsteaa. Inc.
,i, STEAM GENERATOR REPLACEMENT NORTH ANNA UNIT 2 G PREP ACTIVITIES DURING 1 995 RFO CONCRETE CUTTING AND REMOVAL CUT & SPLICE BIOWALLS CUT & REMOVE FLOOR SECTION AT EH CUT & REMOVE PC WALL SECTION INSPECT POLAR CRANE AND REPAIR AS NEEDED RELOCATE INTERFERENCES SAMPLE SYSTEM ELECTRICAL COMMODITIES ENGINEERING WALKDOWNS e
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CORPORATE NUCLEAR SAFETY SERVICE WATER SELF ASSESSMENT NRC TEAM INSPECTIONS November 4, 1993 I.
INTRODUCTION A.
Basis For Reduced Scope NRC Inspection
- NRC IP 40501, Licensee Self-Assessments Related to Area of Emphasis Inspections
- NRC TI 2515/118, Service Water System Operational Performance Inspection (SWSOPI)
B.
Formal Request to the NRC II.
VIRGINIA POWER SELF ASSESSMENTS A.
Assessment Schedule:
- Surry May-June 1994
- North Anna Fall 1994 B.
Assessment Scope:
- Performance Based
- TI 2515/118 provide the basis for the Assessment
- Team Size, Qualifications & Effort are consistent with TI 2515/118 C.
Assessment Experience:
- NRC SALP 1 in SA/QV
- EDSFA
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III. SERVICE WATER SYSTEM CONSIDERATIONS A.
Service Water System Performance:
- Design Basis Documentation Completed for both
- Surry & North Anna. No significant issues.
- Surveillance Requirements Consistently Met.
B.
Service Water System Improvements:
- Response to Surry 1989 Inspection at Surry
- GL 89-13 Actions
- Surry Potential Flooding Actions
- North Anna Service Water Restoration Project C.
Prior NRC Inspections:
- EDSFis at Surry & North Anna
- MOV Program at Surry & North Anna
- ISI Program at Surry & North Anna
- Engineering Support Activities at Surry & North Anna IV. NRC DISCUSSION & COMMENT
e NRC COUNTERPARTS MEETING NOVEMBER 4, 1993 INNSBROOK TECHNICAL CENTER M. W. HENIG 11/03/93 FILE -> MWH-HG: 7172-PSM
e PROJECT STATUS NRC COUNTERPARTS :MEETING IR 7172 - CRGT STORAGE FACILITY SURRY POWER STATION
1.0 BACKGROUND
-1)(1-1984 - UNIT 1 CRGT REPLACEMENT COMPLETED
-1)(1-1985 - UNIT 1 CRGT's ARE REFURBISHED BY B&W
-1)(1-1986 - REFURBISHED CRGT's ARE PLACE IN STORAGE AT B&W'S APOLLO PA FACILITY 2.0 STRATEGY (ff)
TAKE POSSESSION OF REFURBISHED CRGT's AND MAKE CRGT's AVAILABLE ON-SITE FOR TIMELY REPLACEMENT AS REQUIRED
-1)(1-STORE REFURBISHED CRGT'S IN SURRY STEAM GENERATOR STORAGE FACILITY
-1)(1-CONTINUE TO ASSESS NEED TO REPLACE UNIT 2 CRGT'S FILE-> MWH-LTRS: 93-178
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AUGfMNJ,i11 CONTROL ROD ASSEMBLY GUIDE TUBE ONTROL ROD DRIVE SHAFT CONTROL ROD ASSEMBLY (WITHP_RAWN)
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---BOTIOM NOZZLE GUIDE THD!BLE TYPICAL CONTROL ROD ASSEMBLY
CRGT STORAGE CANISTER M. W. HENIG 11/03/93 FILE -> MWH-HG: 7172-SFC
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DETAIL 2 SECTION A-A BASE SLAR
STEAM GENERATOR STORAGE FACILITY SURRY POWER STATION
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PROJECT SCHEDULE DEC 1993 - COMPLETE CONSTRUCTION JAN 1994 - MOCK UP TRAINING FEB TO JUN 1994 - INSTALL CRGT 1s INTO CONTAINERS e
JUL 1994 - MOVE CONTAINERS INTO SG STORAGE FACILITY.
M. W. HENIG 11/02/93 FILE-> MWH-HG: 7172-PS
VIRGINIA POWER SURRY POWER STATION.
CORE UPRATING
VIRGINIA POWER SURRY POWER STATION CORE UPRATING
Background
- Surry Units originally licensed at 2441 MWt
- Uprated power level is 2546 MWt (4.3°/o greater)
- Much of original equipment capable of 2546 MWt
- NSSS
- BOP
-T/G
- Many accident evals done at 2546 MWt
VIRGINIA POWER SURRY POWER STATION CORE UPRATING Basis
- 1988 evaluation by Va Power, Westinghouse, SWEC
- operation at uprated power acceptable
- certain mods to units necessary (e.g., SIG MCO)
- Project suspended in 1988 due to changing priorities
- Some mods already performed
- SIG MCO on Unit 1 A,B,C
- SIG MCO on Unit 2 A e
VIRGINIA POWER SURRY POWER STATION CORE UPRATING Overview
- Reverify 1988 study
- Identify plant mods performed since initial study
- Determine impact on 1988 study/analyses
- Identify plant mods needed to accomplish uprate
- SIG MCO?
- Containment depressurization?
- Others?
- Licensing submittal
VIRGINIA POWER SURRY POWER STATION CORE UPRATING 0 ve rvi e w (continued)
- Design Change Package(s) to perform mods
- Physical mods
- Setpoint changes
- Licensing approval
- Power ascension e
VIRGINIA POWER I
SURRY. POWER STATION CORE UPRATING Schedule
- Vendors review existing reports - 2/94
- Scope plant mods - 2/94
- VP analysis - 5/94
- Approve plant mod engineering - 5/94
- Licensing report to NRC - 6/94_
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- U2 plant mods complete - 11 /94
VIRGINIA POWER SURRY POWER STATION CORE UPRATING Schedule (continued)
- Requested NRC approval - 12/94
- Approve setpoint engineering -12/94
- U2 power ascension - 1 /95
- . U 1 plant mods complete - 10/95
- U 1 power ascension - 10/95 _
VIRGINIA POWER
- RCA Entries With DADs in the Pause Mode
RCA Entries with DADs in PAUSE MODE During the Unit 2 Refueling Outage, a total of 46, 116 RCA entries were made as part of the Unit 2 Refueling Outage.
During the course of the outage, between September 7, and September 15, 1993, seven individuals entered the RCA with their DADs in the PAUSE Mode. This is a violation of the RWP that controls work activity.
DIGITAL ALARMING DOSIMETER INCIDENTS In every case, the ind.ividual was wearing a TLD and an accurate reading of the individual's exposure was made.
No administrative exposure limits were exceeded in any of the incidents.
After the first week of the outage, an HP technician was stationed at the entry of the RCA to verify proper dosimetry prior to workers entering.
The HP technician prevented three additional cases where individuals tried to enter to the RCA with their DADs in pause. No entries were made into the RCA with DADs* in PAUSE following the posting of the HP technician.
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ROOT CAUSE Personnel did not verify their DAD was in the proper operational mode prior to removing it from the Merlin Gerin (MG) dosimeter reader.
Present operation of the MG dosimeter reader allows the individual to remove the DAD from the reader prior to the completion of processing.
CORRECTIVE ACTIONS Remedial:
- The individuals involved were counseled on the importance of proper issuance of DADs A "Station Alert" was issued depicting the Correct dosimeter display configuration.
Radiological Protection personnel were posted at the entrance to the RCA to check individuals DADs prior to entry.
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CORRECTIVE ACTIONS Long Term:
Long term corrective action includes a modification to the dosimeter reader software program. The modification will cause the DAD to alarm if it is removed in the "PAUSE" mode prior to processing completion. This modification is currently scheduled for completion by March 1994.
Virginia Power e
STATUS OF OPEN NRC UNRESOLVED ITEMS
Status of Open NRC Unresolved Items URI 91-22-02: LHSI Relief Valve lnoperability Safety Concern Corrective Actions:
- 1. An operability assessment was performed on the LHSI relief valves lifting during pump testing.
- 2. O-MCM-0415-01 was revised to provide the proper instructions for adjusting relief valve setpoints and blowdown ring settings.
- 3. Modifications were implemented to install vents on the LHSI system.
- 4. Further testing and evaluations are being conducted by Engineering to resolve this issue.
Status of Open NRC Unresolved Items URI 92-04-03: lndepth Review Of TS Surveillance Procedures Corrective Actions:
- 1. The indepth review of TS surveillance requirements has been completed. This unresolved item is ready for NRC closure.
URI 92-32-01: RS System Design Basis Corrective Actions:
- 1. The specific items discussed as part of the unresolved item have been resolved.
- 2. Additional corrective actions as a result of a Quality Assurance audit finding are progressing. Actions include (1) Categorization of Group 1, Revision 1 DBD open items has been completed.
(2) The resolution of 15% of all currently existing open items by December 1993 is progressing.
Status Of Open NRC Unresolved Items URI 93-23-01: Lack Of Physical Separation For The Unit 1 RCP Underfrequency Reactor Trip Circuits Corrective Actions:
- 1. Modifications were implemented on Unit 2 to re-route the RCP underfrequency trip circuits.
- 2. Operator logs have been revised to routinely check the "DC power available" indication on the Unit 1 underfrequency auxiliary relay panels.
- 3. Modifications will be performed to re-route the Unit 1 RCP underfrequency circuits.
Note: The unresolved item was opened for the NRC to review the issue to determine if our evaluation was correct in that the Unit 1 circuits are operable.
. I
STATUS OF OPEN NRC UNRESOLVED ITEMS
. VIRGINIA POWER
- SURRY POWER STATION NOVEMBER 31993
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Status of Open NRC Unresolved Items URI 92-15-01: Lack of Formal UFSAR Update Process Corrective Actions:
- 1. Reviewed and determined UFSAR adequately addresses potential hazards due to Aircraft.
- 2. Gravel Neck Combustion turbines incorporated into UFSAR via Revision 20 dated 8/93.
- 3. Chapter 2 metrological information was updated via UFSAR Revision 20. Hydrology and seismology reviews have been completed and will be incorporated in the next update.
Assessment of population changes and appropriate UFSAR updates are planned in 1994.
- 4. New UFSAR administrative procedure (VPAP 2803) scheduled for SNSOC in December, 1993.
Status of Open NRC Unresolved Items URI 92-22-03: l&C Maintenance Practices Corrective Actions:
- 1. An Evaluation of past replacement of Rosemount Transmitters in containment was performed. No problem with in place calibration practices was identified.
- 2. A memorandum has been issued by the Station Manager on Tagging Policy for Control of l&C Calibration /
Maintenance Activities.
- 3. This item is ready for NRC closure review.
Status of Open NRC Unresolved Items URI 93-007-01 Evaluation of DBD Program Corrective Actions:
- 1. DBD Project review meetings conducted with Region II Management.
- 2. DBD Open Items resolution enhanced.
(re: Va Power Letter No 93-048 dated April 19, 1993)
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Status of Open NRC Unresolved Items URI 93-08-01 : Review of LHSI Pump Performance Data Corrective Actions:
- 1. The NRC has been supplied with completed copies of 2-PT-18.3C data "Refueling Testing LHSI Check Valve to Hot Leg." A 30 day 10CFR50.46 notification was made.
This item is ready for closure.
URI 93-15-01: Use of Probability Assessment in preparing 1 OCFR50.59 Safety Analysis*
Corrective Actions:
- 1. Meeting held with NRC Residents to discuss Feedwater Regulating Valve Analysis. Nuclear Analysis and Fuels is finalizing an update to the analysis to address resident comments.
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Status of Open NRC Unresolved Items URI 93-22-03: ESW Pump building with Degraded Flood Barrier Corrective Actions:
- 1. Engineering determined that the flood protection devices at the Low Level would have provided adequate protection.
- 2. Engineering improvement recommendations in.eluding PM's for the Low Level hurricane protection equipment are being reviewed for incorporation into work documents.
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