ML18153B345
| ML18153B345 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/30/1993 |
| From: | BOWLING M L, MASON D, OLSEN C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 93-655, NUDOCS 9310200218 | |
| Download: ML18153B345 (17) | |
Text
e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 12, 1993 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No. NO/RPC:vlh Docket Nos. License Nos.93-655 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of September 1993. Very truly yours, JllA/6~ M. L. Bowling, Manager Nuclear Licensing
& Programs Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station n 0 Q "'I"'),-, ,,. '* ,: I " **. l 'i -~* \./ _., * .. ' t...J V VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 93-09 Approved:
-TABLE OF CONTENTS Section e Surry Monthly Operating Report No. 93-09 Page 2 of 16 Page Operating Data Report -Unit No. 1 .........................................................................................................
3 Operating Data Report -Unit No. 2 .........................................................................................................
4 Unit Shutdowns and Power Reductions
-Unit No. 1 ....................................................................................
5 Unit Shutdowns and Power Reductions
-Unit No. 2 ....................................................................................
6 Average Daily Unit Power Level -Unit No. 1.. ............................................................................................
7 Average Daily Unit Power Level -Unit No. 2 ..............................................................................................
8 Summary of Operating Experience
-Unit No. 1 .........................................................................................
9 Summary of Operating Experience
-Unit No. 2 .......................................................................................
1 O Facility Changes That Did Not Require NRC Approval ...............................................................................
11 Procedure or Method of Operation Changes That Did Not Require NRC Approval ...........................................
12 Tests and Experiments That Did Not Require NRC Approval ......................................................................
13 Chemistry Report .............................................................................................................................
14 Fuel Handling -Unit No. 1 ...................................................................................................................
15 Fuel Handling -Unit No. 2 ...................................................................................................................
15 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications
...................................................................................................
16
.urry Monthly Operating Report No. 93-09 Page 3 of 16 OPERATING DATA REPORT Docket No.: Date: Completed By: 50-280 10-03-93 D. Mason Telephone:
(804) 365-2459 1. Unit Name: .................................................. . 2. Reporting Period: ........................................
.. 3. Licensed Thermal Power (MWt): ...................... . 4. Nameplate Rating (Gross MWe): .....................
.. 5. Design Electrical Rating (Net MWe): ................
.. 6. Maximum Dependable Capacity (Gross MWe): .. .. 7. Maximum Dependable Capacity (Net MWe): ...... .. Surry Unit 1 September, 1993 2441 847.5 788 820 781 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: 9. Power Level To Which Restricted, If Any (Net MWe): 1 O. Reasons For Restrictions, If Any: This Month 1 t. Hours In Reporting Period ..........................
720.0 12. Number of Hours Reactor Was Critical ..........
720.0 13. Reactor Reserve Shutdown Hours ...............
0.0 14. Hours Generator On-Line ...........................
720.0 15. Unit Reserve Shutdown Hours .....................
0.0 16. Gross Thermal Energy Generated (MWH) ...... 1752948.0
- 17. Gross Electrical Energy Generated (MWH) .... 577175.0 18. Net Electrical Energy Generated (MWH) ........ 554622.0 19. Unit Service Factor ...................................
100.0% 20. Unit Availability Factor ...............................
100.0% 21. Unit Capacity Factor (Using MDC Net) ...........
98.6% 22. Unit Capacity Factor (Using DER Net) ...........
97.8% 23. Unit Forced Outage Rate ............................
0.0% YID 6551.0 6223.2 0.0 6194.6 0.0 14810972.4 4923625.0 4699950.0 94.6% 94.6% 91.9% 91.0% 2.0% 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Refueling (1 O Year ISi), February 4, 1994, 70 Days 25. If Shut Down at End of Report Period, Estimated Date of Start-up:
- 26. Unit In Test Status (Prior to Commercial Operation):
Cumulative 182111.0 121598.2 3774.5 119470.0 3736.2 278430251
.5 90941878.0 86297810.0 65.6% 67.7% 61.1% 60.1% 17.7% FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION OPERATING DATA REPORT e Surry Monthly Operating Report No. 93-09 Page 4 of 16 Docket No.: 50-281 10-03-93 D. Mason Date: Completed By: Telephone:
(804) 365-2459 1 . Unit Name: .................................................. . 2. Reporting Period: ........................................
.. 3. Licensed Thermal Power (MWt): ...................... . 4. Nameplate Rating (Gross MWe): ...................... . 5. Design Electrical Rating (Net MWe): ................
.. 6. Maximum Dependable Capacity (Gross MWe): .. .. 7. Maximum Dependable Capacity (Net MWe): ...... .. Surry Unit 2 September, 1993 2441 847.5 788 820 781 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: 9. Power Level To Which Restricted, If Any (Net MWe): 10. Reasons For Restrictions, If Any: This Month YID Cumulative
- 11. Hours In Reporting Period ..........................
720.0 6551.0 178991.0 12. Number of Hours Reactor Was Critical ..........
677.2 4549.6 118236.5 13. Reactor Reserve Shutdown Hours ...............
0.0 0.0 328.1 14. Hours Generator On-Line ...........................
668.7 4453.2 116384.2 15. Unit Reserve Shutdown Hours .....................
0.0 0.0 0.0 16. Gross Thermal Energy Generated (MWH) ...... 1608248.1 10025656.2 271356730.0
- 17. Gross Electrical Energy Generated (MWH) .... 525350.0 3304210.0 88500114.0
- 18. Net Electrical Energy Generated (MWH) ........ 504952.0 3150418.0 83940831.0
- 19. Unit Service Factor ...................................
92.9% 68.0% 65.0% 20. Unit Availability Factor ...............................
92.9% 68.0% 65.0% 21. Unit Capacity Factor (Using MDC Net) ...........
89.8% 61.6% 60.2% 22. Unit Capacity Factor (Using DER Net) ...........
89.0% 61.0% 59.5% 23. Unit Forced Outage Rate ............................
7.1% 12.4% 14.3% 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): None 25. If Shut Down at End of Report Period, Estimated Date of Start-up:
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION (1) -urry Monthly Operating Report No. 93-09 Page 5 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EOUAL To OR GREATER THAN 20%) REPORT MONTH: September, 1993 (2) (3) (4) (5) Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-01-93 Completed by: Craig Olsen Telephone:
(804) 365-2155 Duration Method of Reason Shutting Down Rx LER No. System Component Cause & Corrective Action to Date Type Hours Code Code Prevent Recurrence (1) F: Forced S: Scheduled (4) (2) REASON: None during this reporting period. A -Equipment Failure (Explain)
B Maintenance or Test C Refueling D Regulatory Restriction E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)
Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) (3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)
(5) Exhibit 1 -Same Source.
4'urry Monthly Operating Report No. 93-09 Page 6 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EOUAL To OR GREATER THAN 20%) REPORT MONTH: September, 1993 (1) (2) (3) (4) (5) Method Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-01-93 Completed by: Craig Olsen Telephone:
(804) 365-2155 Duration of LER No. System Component Cause & Corrective Action to Date Type Hours Reason Shutting Code Code Prevent Recurrence (1) F: Forced S: Scheduled (4) (2) REASON: Down Rx None during this reporting period. A -Equipment Failure (Explain)
B Maintenance or Test C Refueling D Regulatory Restriction E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)
Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LEA) File (NUREG 0161) (3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)
(5) Exhibit 1 -Same Source.
e Surry Monthly Operating Report No. 93-09 Page 7 of 16 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-03-93 Completed by: Pat Kessler Telephone:
365-2790 MONTH: September, 1993 Average Daily Power Level Average Daily Power Level Day (MWe -Net) Day (MWe-Net) 1 689 17 769 2 748 18 781 3 759 19 780 4 762 20 783 5 764 21 782 6 765 22 779 7 755 23 780 8 771 24 781 9 772 25 781 10 772 26 780 11 773 27 779 12 766 28 781 13 780 29 782 14 779 30 784 15 771 16 760 INSTRUCTIONS On this format, list the average daily unit power level in MWe -Net for each day in the reporting month. Compute to the nearest whole megawatt.
e Surry Monthly Operating Report No. 93-09 Page 8 of 16 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-03-93 Completed by: Pat Kessler Telephone:
365-2790 MONTH: September, 1993 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 0 17 772 2 0 18 770 3 533 19 772 4 707 20 772 5 725 21 768 6 756 22 766 7 755 23 768 8 751 24 769 9 728 25 778 10 761 26 769 11 754 27 763 12 761 28 763 13 767 29 761 14 765 30 771 15 753 16 763 INSTRUCTIONS On this format, list the average daily unit power level in MWe -Net for each day in the reporting month. Compute to the nearest whole megawatt.
e
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR:
September, 1993 Surry Monthly Operating Report No. 93-09 Page 9 of 16 The following chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.
UNJI ONE: 09/01/93 09/30/93 0000 The reporting period began with the Unit operating at 81 % power, 600 MWe; high pressure heater drain pump level control valve, 1-SD-LCV-106, inoperable.
0737 Started power increase following maintenance on 1-SD-LCV-106.
0930 Unit at 100% power, 775 MWe. 2400 The reporting period ended with the Unit 1 at 100% power, 820 MWe.
UNIT Two: 09/01/93 0000 09/03/93 0316 1519 09/04/93 0648 0650 1624 1706 09/09/93 0630 0635 1610 1635 09/13/93 0945 1009 09/24/93 1055 1100 09/25/93 2133 2138 09/30/93 2400 e Surry Monthly Operating Report No. 93-09 Page 10 of 16
SUMMARY
OF OPERATING EXPERIENCE MONTH/VEAR:
September, 1993 The reporting period began with the Unit heating up in preparation for start-up. (Reactor had tripped due to safety injection relay failure on 08/27/93)
Unit on-line. Started power increase.
Stopped power increase at 97.5%, 760 MWe. Holding for evaluation of Steam Generator "C" level oscillations.
Started power reduction to maintain condenser vacuum while cleaning water boxes. Stopped power reduction at 90%, 715 MWe. Started power increase following water box cleaning.
Stopped power increase at 97.5%, 760 MWe. Started power reduction to maintain condenser vacuum while cleaning water boxes. Stopped power reduction at 95%, 740 MWe. Started power increase following water box cleaning.
Stopped power increase at 99%, 785 MWe. Started slow power increase.
Stopped power increase at 100%, 820 MWe. Started power reduction due to Steam Generator "C" level oscillations.
Stopped power reduction at 99%, 800 MWe. Started power reduction due to Steam Generator "C" level oscillations.
Stopped power reduction at 98%, 792 MWe. The reporting period ended with the Unit at 98% power, 792 MWe, due to Steam Generator "C" level oscillations.
SE 93-184 DCP 86-03 TM S1-93-11 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
September, 1993 Safety Evaluation e Surry Monthly Operating Report No. 93-09 Page 11 of 16 09-09-93 Safety Evaluation 93-184 was performed, following a failure of a Unit 1 "B" Steam Generator
{SG) channel head drain line weld, to assess the impact of a potential failure of other similar SG channel head drain lines. The evaluation concluded that a single high head safety injection pump could effectively provide emergency core cooling to mitigate the effects of a SG channel head drain line failure. This type of failure would result in Reactor Coolant system (RCS) leakage into the Containment and would be identified through routine Technical Specification RCS leakage surveillances and by containment gas and particulate radiation monitors.
Therefore, an unreviewed safety question does not exist. Design Change Package (Safety Evaluation No.90-195) 09-10-93 Design Change Package 86-03 replaced the manual bypass and isolation valves for the Unit 1 and 2 Instrument Air (IA) system dryers, 1/2-IA-D-1, with automatic pneumatic) valves. The new valves were installed to provide for timely automatic isolation of the IA system dryers in the event of a drop in pressure in the IA header downstream of the dryers. Specifically, the new valves are designed to allow automatic bypass and isolation of the IA dryers in the event the dryer's automatic blowdown feature does not function as designed.
This DCP also installed a new battery power supply system, including a charger with a constant voltage transformer to protect the charger from high voltage electrical spikes. These modifications increased the reliability of the nonsafety-related IA system. The automatic valves represent an IA system enhancement and perform the same functions as the manual valves. The new valves do not affect any safety-related system. Therefore, an unreviewed safety question does not exist. Temporary Modification
{Safety Evaluation No.93-185) 09-20-93 Temporary Modification
{TM) S1-93-11 installed electrical jumpers to bypass test switch 1-LC-495-TB on the Unit 1 Safety Injection (SI) system train "B" circuitry to allow its replacement without rendering the circuits inoperable.
This TM continued to allow SI system train "B" actuation on a valid signal and did not affect train "A", thus maintaining the design SI functions.
Double verification of jumper installation/removal and post maintenance testing were performed.
Therefore, an unreviewed safety question did not exist.
FS 93-45 VPAP-0102 e Surry Monthly Operating Report No. 93-09 Page 12 of 16 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
September, 1993 Updated Final Safety Analysis Report Change Station Administrative Procedure (Safety Evaluation No.93-188) 09-27-93 UFSAR Section 12.2.2.8.2, "[Responsibility of the] Supervisor
-Quality", was revised to delete the requirement for the Supervisor of Quality to review and concur with changes to procurement documents and modifications, maintenance, and repair procedures.
Station Administrative Procedure VPAP-0102, "Station Nuclear Safety and Operating Committee", was changed to delete the requirement for a Quality Assurance member on the Procedures Subcommittee.
These changes were administrative in nature and did not modify or affect the operation of the station. Therefore, an unreviewed safety question did not exist.
e Surry Monthly Operating Report No. 93-09 Page 13 of 16 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR:
September, 1993 None during this reporting period.
Primary Coolant Analysis Gross Radioactivity, uCi/ml Susoended Solids, oom Gross Tritium, uCi/ml 1131, uCi/ml 113111133 Hydroqen cc/kq Lithium, oom Boron -10, oom* Oxygen, (DO), ppm Chloride, oom pH at 25 deqree Celsius
None CHEMISTRY REPORT MONTH/VEAR:
September, 1993 Unit No. 1 Max. Min. Avg. 5.12E-1 2.31 E-1 3.39E-1 < 0.1 < 0.1 < 0.1 9.10E-2 3.46E-2 6.50E-2 3.00E-3 7.52E-4 1.10E-3 0.14 0.07 0.09 37.5 26.9 31.5 2.02 1.13 1.55 49.0 19.4 29.7 <0.005 :50.005 .:5.0.005 0.004 <0.001 0.001 7.37 7.00 7.23 4lurry Monthly Operating Report No. 93-09 Page 14 of 16 Unit No. 2 Max. Min. Avq. 2.36E-1 8.29E-4 1.47E-1 < 0.1 < 0.1 < 0.1 3.20E-1 1.04E-1 2.22E-1 1.93E-4 5.46E-5 8.68E-5 0.14 0.07 0.10 47.8 27.5 35.5 2.34 1.45 2.16 361.2 233.0 259.8 .:5.0.005
- 50.005 .:5.0.005 0.013 0.005 0.009 6.45 5.86 6.30 Newer Spent Fuel Shipment Date Stored or Number Received l _________
_ FUEL HANDLING UNITS 1 & 2 MONTH/YEAR:
September, 1993 Number of Assemblies per Shipment Assembly Number ANSI Number e Surry Monthly Operating Report No. 93-09 Page 15 of 16 Initial Enrichment New or Spent Fuel Shipping Cask Activity No fuel received or stored during this reporting period.
~'>
- I
- e Surry Monthly Operating Report No. 93-09 Page 16 of 16 DESCRIPTION OF PERIODIC TEST{S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR:
September, 1993 None during this reporting period.