ML18153B788
| ML18153B788 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/19/1989 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8906270342 | |
| Download: ML18153B788 (9) | |
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°!..iN 1 9 1989 Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37 Virginia Electric and Power Company ATTN:
Mr. W. R. Cartwright, Vice President, Nuclear Operations 5000 Dominion Boulevard Glen Allen, VA 23060 Gentlemen:
SUBJECT:
MANAGEMENT MEETING
SUMMARY
This letter refers to the Management Meeting held on May 22, 1989, at the Surry Power Station.
The meeting concerned acti vi ti es authorized for your Surry facility, and involved a status discussion of the Surry restart issues.
A list of attendees, a meeting summary, and a copy of your handout are enclosed.
In accordance with 2.790 of the NRC's 11 Rules of Practice 11
, Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Publi0 Document Room.
Should you have any questions concerning this matter, please contact us.
Enclosures:
- 1.
List of Attendees
- 2.
Meeting Summary
- 3.
Handout cc w/encls:
M. R. Kansler, Station Manager R. F. Saunders, Manager - Nuclear Programs and Licensing Commonwealth of Virginia bee w/encls:
NRC Resident Inspector Document Control Room
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PFredrickson 06/*, /89 Sincerely, 1~1 Stewart D. Ebneter Regional Administrator r/f;I/Jk LReyes 06/ 1
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e ENCLOSURE 1 MANAGEMENT MEETING LIST OF ATTENDEES Virginia Electric and Power Company W. Stewart, Senior Vice President, Nuclear W. Cartwright, Vice President, Nuclear Operations F. Moore, Vice President, Power Engineering Services M. Kansler, Station Manager, Surry E. Grecheck, Assistant Station Manager, Surry R. Saunders~ Manager, Licensing R. Calder, Manager, Nuclear Engineering W. Corbin, Supervisor, Project Engineering J. Price, Manager, Site Quality Assurance D. Sommers, Supervisor, Nuclear Licensing C. Robinson, Manager, Civil Engineering W. Benthal, Supervisor, Licensing W. Thompson, Manager~ Electrical Engineering Stone & Webster Company A. Banerjie, Project Manager Nuclear Regulatory Commission S. Ebneter, Regional Administrator, Region II (RII)
C. Hehl, Deputy Director, Division of Reactor Projects (DRP), RII E. Merschoff, Deputy Director, Division of Reactor Safety (DRS), RII H. Berkow, Director, Project Directorate II-2, NRR P. Fredrickson, Acting Branch Chief, DRP, RII B. Buckley, Project Manager, NRR W. Holland, Senior Resident Inspector, DRP, RII J. York, Resident Inspector, DRP, RII L. Nicholson, Resident Inspector, DRP, RI!
e ENCLOSURE 2 MANAGEMENT MEETING
SUMMARY
An NRC and Virginia.Electric and Power Company (VEPCO) management meeting was conducted at the Surry Power Station on May 22, 1989 to discuss the status of restart issues for the Surry units.
VEPC0 1 s Senior Vice President, Nuclear, opened the meeting by stating that all issues applicable to restart, including those on the March 9, 1989 Confirmation of Action Letter (CAL) are being handled diligently and resolved satisfactorily.
The Surry Station Manager began the formal presentation, using the handout attached as Enclosure 3, and stated that, based.on the current schedule, Unit 1 should leave 200°F on June 8 and be on-line by June 15.
The completed CAL items were then briefly discussed with emphasis on the fact that long-term work
\\vas still scheduled for some of the items, such as the reactor cavity seal.
The Station Manager then began a detailed discussion of the remaining CAL items.
NRC questions arose on the status of grease review as a part of the motor-operated valve (MOV) program.
VEPCO stated that, although acceptance criteria were not completely clear in the past and, thus, are being revised, no problems have been identified to date where grease inadequacy definitely affected MOV operability.
With respect to system walkdowns, VEPCO responded to an NRC question by stating that any walkdown discrepancy will be '
appropriately reflected on station drawings prior to restart.
The NRC stated that the control room habitability issue may not receive a detailed on-site review priqr to restart, but that the effort would receive a documentation review prior to restart, with appropriate on-site implementation inspection conducted subsequent to that review.
To cone l ude the CAL portion of the presentation, the Station Manager stated that the MOV program was the critical path for resolution of CAL issues and that a 11 issues are expected to be completed by June 8, 1989.
The Station Manager using Enclosure 3, discussed those issues identified by VEPCO after issuance of the CAL and which will also be resolved prior to restart.
With respect to the cable separation issue, a discussion ensued involving the number of spare cables to be removed.
Also discussed was the NRC 1s concern that VEPCO should do what is necessary to fix the problem, but should also evaluate the necessity of removing spare cables against the poten-tial damage from that activity.
A lengthy discussion then took place on a recently identified issue involving component cooling water (CCW) inside containment as it relates to a potential primary-to-CCW leak.
The Station Manager stated that, at present, the intent is to install three relief valves on each supply and return CCW line to all three reactor coolant pump thermal barriers.
The discussion revolved around the status of seismic and
~afety-related modifications and also extended to a concern over the status of containment integrity of the CCW system.
VEPCO stated that assembly of the relief valves would be observed by licensee personnel at the manufacturer's location, and that the appropriate system containment isolation valves were being leak tested.
VEPCO stated that this fix was not a final solution; but
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that the intent was to replace a portion of the CCW p1p1ng inside containment with high pressure piping.
This discussion concluded with the NRC stating that, before restart, the modification of the CCW relief valve arrangement and the design adequacy of CCW containment.integrity would be evaluated by the NRC.
VEPCO expressed a concern, and the NRC agreed, that the containment integrity review be conducted _expeditiously.
The Station Manager concluded the presentation with a discussion of the VEPCO management restart assessment.
In addition to the information contained in, discussions were also conducted on specific operator training for restart and timeliness of drawing change implementation.
The NRC stated that all emergency response facilities should receive priority attention on updating plant drawings.
The Vice President, Nuclear Operations, concluded the VEPCO presentation by stating that all VEPCO personnel realize that completing issues satisfactorily prior to restart is important and also by requesting a rapid assessment of NRC
- concerns with respect to restart.
The Regional Administrator closed the meeting by thanking the licensee for the presentation and stating that the NRC staff would continue to review VEPC0 1s restart activities.
e ENCLOSURE 3 SURRY RESTART MEETING.
AGENDA I. Introductions II. Status of Confirmation of Action Letter Items A. Summary of Previously Closed Restart Items
- 1.
Secondary Pipe Thinning
- 2.
Socket Weld Integrity
- 3.
Gas Binding of Charging Pumps
- 4.
Reactor Cavity Seal W. L. Stewart M. R. Kansler B. Remaining Open Restart Activities
- 1. SSFI *
- 2. EDG Load Sequencing
- 3. MCA & ESGR Air Conditioning
- 4. Safety Related Electrical Power Termination Inspections
- 5. Safety Related Motor-Operated Valves
- 6. Operational Readiness Program
- 7. Emergency Power Separation Verification Testing
- 8. Non-Original Equipment Manufacturer Parts
- 10. 4160 Volt Breakers
- 11. Instrument Air
111. Status of Other Items M. R. Kansler
- 1.
Electrical Cable Separation
- 2.
IRSP Flow Testing
- 3.
Component Cooling System Issues
- 4.
Instrument Cable Replacements IV. Management Restart M. R. Kansler Assessment
. (Self Assessment)
V. Concluding Remarks W. R. Cartwright VI. NRC Remarks/Outstanding NRC Actions
SURRY POWER STATION
SUMMARY
OF RESTART ACTIVITIES MAY 22, 1989 UNIT 1 ISSUE ACTIVITY STATUS
- Secondary Pipe Thinning Inspection Complete Replacement Complete Summary Rpt Complete
- Socket Weld Integrity Inspection Complete Summary Rpt Complete
- Gas Binding Modifications Complete
- Reactor Cavity Seal Modifications Complete Leak Testing Complete
- SSFI - Canal Level Modifications Complete Tech Specs Submitted Summary Rpt Complete Testing 5/26/89
- ESW Pumps Refurbishment Complete Flow Upgrades 5/25/89 Testing 5/25/89
6/2/89 Hx Testing 6/2/89
- EOG Load Sequence Modifications Complete Testing 5/29/89 Summary Apt Complete
e
SUMMARY
OF REST ART ACTIVITIES (CONTINUED)
ISSUE
- Power Terminations
- MOV Program
- Operational Readine~
Review
- Emergency Power Separation Verification Testing
- Non-OEM Parts
- Control Room Habitability 0 4160 Breakers 0 Instrument Air Compressors ACTIVITY Inspection Evaluation Maint. & Testing Documentation Walkdowns Document Review Functional Testing Dead Bus Test lnteg. Logic/Funct.
Power Supply Testing Investigation Rebuild Pump Evaluation Modification Testing Refurbish Refurbish UNIT 1 STATUS 5/29/89 Compl_ete 6/5/89 6/8/89 Complete Complete 5/31/89 Complete 5/29/89 6/3/89 Complete Complete Complete 5/25/89 5/30/89 6/1/89 Complete
e SURRY POWER STATION
SUMMARY
OF OTHER ACTIVITIES MAY 22, 1989 UNIT 1 ISSUE ACTIVITY STATUS
- Electrical Cable Cable Tracing 5/26/89 Separation Cable Tray Covers 5/30/89
- IRSP Flow Testing Testing Complete
- Component Cooling Support Mods 5/25/89 System Relief Valves &
Supports
- Instrument Cable Replacement 5/29/89 Replacements
- Procedures 6/2/89
- Training 6/2/89
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