ML18153B887
| ML18153B887 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/31/1989 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 89-188A, CAL, NUDOCS 8909140248 | |
| Download: ML18153B887 (7) | |
Text
. '
ee VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 31, 1989
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- United States Nuclear Regulatory Commission Attention: Mr. Stewart D. Ebneter Regional Administrator, Region II 101 Marietta Street,N.W.
Suite 2900 Atlanta, Georgia 30323
Dear Mr. Ebneter:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 I ;J *.* *.
- Serial No.
NUCGL:vlh Docket No.
license No.
STATUS OF ITEMS IDENTIFIED IN THE MARCH 9, 1989 CONFIRMATION OF ACTION LETTER 89-188A R3 50-281 DPR-37 Per your previous request to formally document resolution of Confirmation of Action Letter (CAL) items prior to Unit 2 restart, attached is a status of those items identified in your March 9, 1989 letter. The status of. each CAL item is further identified into component subparts as previously specified in our May 22, 1989 meeting at Surry and as modified via letter Serial No. 89-0828, dated July 28, 1989. Required procedure revisions, although not identified in the CAL as a subitem, are ongoing and will be completed prior to restart.
Should you have any questions, please contact us.
Very truly yours, LJ~L~9b W. L. Stewart Senior Vice President - Power Attachment cc:
U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station
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ee ATTACHMENT STATUS OF ITEMS IDENTIFIED IN THE* MARCH 9, 1989 CONFIRMATION OF ACTION LETTER FOR SURRY POWER STATION UNIT 2
ee STATUS OF ITEMS IDENTIFIED IN THE CONFIRMATION OF ACTION LETTER ITEMS PREVIOUSLY CLOSED BY NBC
- 1.
Replacement of secondary plant piping due to pipe wall thinning
- 2.
Resolution of Class 1 piping socket weld integrity
- 3.
Modifications to prevent gas binding in both units ECCS systems
- 4.
Resolution of refueling cavity seal deficiencies ITEMS TO BE COMPLETED PRIOR TO RESTART
- 1.
Correction of Safety System Functional Inspection findings involving the Service Water System.
A.
Canal Level Design Basis And Configuration (1)
Canal Inventory Design Basis Accident Calculations (2)
Technical Specification Changes (3)
Service Water/Circulating Water System Modifications B.
Emergency Service Water (ESW) Pumps (1)
ESW Pump and Diesel Refurbishment (2)
ESW Pump Diesel Electrical Enhancements (3)
ESW Pump Flow Capability Upgrade (4)
Special Testing C.
Service Water Heat Exchanger Performance (1). Recirculation Spray Heat Exchanger Surveillance UNIT 2 STATUS Complete Complete Complete Complete Complete Complete Working (1)
Complete Complete Complete Complete Complete
ee (2)
Main Control Room Chiller/Condenser Testing (3)
Heat Exchanger Performance Evaluation Report
- 2.
Completion of emergency diesel generator sequence logic testing (i.e. load sequencing for worst case loading scenario of LOOP subsequent to LOCA).
A.
Load Sequencing Modifications and Testing
- 8.
Final Summary Report to NRC Complete Complete Complete Submitted
- 3.
Completion of modification and testing of control room envelope ventilation system (i.e. air conditioning capacity for Main Control Room and Emergency Switchgear Room).
A.
Special Testing
- 8.
Interim Condition Modifications C.
Technical Specification Changes D.
Final Testing
- 4.
Inspection and repair of deficiencies identified on safety-related motors to include completion of repairs and testing of the inside and outside recirculation spray pumps and motors (i.e. safety-related electrical power termination inspections).
A.
Inside and Outside Recirculation Spray Pumps and Motors
- 8.
Other Inspections and Repairs
- 5.
Resolution of deficiencies identified on safety-related motor operated valves.
A.
Evaluation
- 8.
Comprehensive Maintenance Complete Complete Complete Complete Complete Complete Complete Working (2)
C.
Testing
- 6.
Completion of system walkdowns.
A Walkdowns (1) Common Systems (2) Unit 2 In-containment Systems B.
Document Reviews C.
Additional Special Testing
- 7.
Separation verification of divisional emergency power.
A Electrical Separation Verification Testing (1) "B" Train (2)
"A" Train B.
Integrated Logic/Functional Testing (1)
ESF Actuation, Instantaneous Bus UV (2)
ESF Actuation, Five Minute UV Delay
- 8.
Resolution of deficiencies identified on safety-related components involving replica parts.
A Records Investigation B.
Disposition of Non-OEM Parts
- 9.
Inspection and resolution of any identified operability issues concerning the control room habitability systems (i.e. assessment of North Anna inspection results for applicability).
A Engineering Analysis/Evaluation B.
- Modification of Docketed Dose Calculation C.
Modification for Automatic Initiation Working (2)
Complete Complete (3)
Working (4)
Complete Complete (5)
Next Refueling (5)
Working (6)
Working (6)
Complete Complete Complete Submitted Complete
D.
Testing
- 10. Inspection, cleaning and testing of safety-related 4160 volt breakers,
- 11. Restoration of the foundation and instrument air system compressors to design basis operability.
A.
Foundation Repair
- 8.
Compressor Refurbishment Complete Working (7)
Comptete Complete
- l..
ee Footnotes:
(1)
Item complete pending final closeout and technical review.
(2)
Maintenance and Motor Operated Valve Automatic Testing System (MOVATS) testing is complete on 91 of 98 valves. Maintenance and MOVATS testing on the seven (7) remaining valves are scheduled to be completed prior to criticality. Operability testing and/or final technical review are/is pending on a total of 23 valves.
(3)
Discrepancies identified by the in-containment walkdowns will be dispositioned in accordance with Engineering Work Request (EWR)88-584. The safety related systems outside of containment will be prioritized and walkdowns will be performed under a station procedure and completed by December 31, 1989. (
Reference:
Letter Serial No. 89-0828)
(4)
Temporary Modifications and safety related Work Order reviews will be completed prior to criticality.
(5)
The research phase of a test procedure for "A" train (2H) is complete and testing will be performed at the next refueling outage. Priority drawing changes for both "A" and "8" trains identified during procedure preparation have been completed. Other drawing changes identified during the test procedure research will be completed 90 days after Unit 2 startup. Pump and valve breaker power supply verification testing was conducted on a representative sample selected from both "A" and "B" trains. (
Reference:
Letter Serial No. 89-0828)
(6)
The testing is scheduled to be completed prior to criticality.
(7)
Inspection and refurbishment has been completed on 17 of 19 safety related breakers. The two(2) remaining breakers will be inspected and refurbished prior to criticality.