ML18153B345

Monthly Operating Rept for Sept 1993 for Surry Power Station Units 1 & 2.W/931012 Ltr

ML18153B345
Person / Time
Site:	Surry
Issue date:	09/30/1993
From:	Bowling M, 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 Serial No.93-655 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT 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"'),-,

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 93-09 Approved:

- e Surry Monthly Operating Report No. 93-09 Page 2 of 16 TABLE OF CONTENTS Section 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 ....................................................................................... 1O 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.: 50-280 Date: 10-03-93 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 1

2. Reporting Period: ........................................ .. September, 1993

3. Licensed Thermal Power (MWt): ...................... . 2441

4. Nameplate Rating (Gross MWe): ..................... .. 847.5

5. Design Electrical Rating (Net MWe): ................ .. 788

6. Maximum Dependable Capacity (Gross MWe): .. .. 820

7. Maximum Dependable Capacity (Net MWe): ...... .. 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):

1O. Reasons For Restrictions, If Any:

This Month YID Cumulative 1 t. Hours In Reporting Period .......................... 720.0 6551.0 182111.0

12. Number of Hours Reactor Was Critical .......... 720.0 6223.2 121598.2

13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 3774.5

14. Hours Generator On-Line ........................... 720.0 6194.6 119470.0

15. Unit Reserve Shutdown Hours ..................... 0.0 0.0 3736.2

16. Gross Thermal Energy Generated (MWH) ...... 1752948.0 14810972.4 278430251 .5

17. Gross Electrical Energy Generated (MWH) .... 577175.0 4923625.0 90941878.0

18. Net Electrical Energy Generated (MWH) ........ 554622.0 4699950.0 86297810.0

19. Unit Service Factor ................................... 100.0% 94.6% 65.6%

20. Unit Availability Factor ............................... 100.0% 94.6% 67.7%

21. Unit Capacity Factor (Using MDC Net) ........... 98.6% 91.9% 61.1%

22. Unit Capacity Factor (Using DER Net) ........... 97.8% 91.0% 60.1%

23. Unit Forced Outage Rate ............................ 0.0% 2.0% 17.7%

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):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 93-09 Page 4 of 16 OPERATING DATA REPORT Docket No.: 50-281 Date: 10-03-93 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 2

2. Reporting Period: ........................................ .. September, 1993

3. Licensed Thermal Power (MWt): ...................... . 2441

4. Nameplate Rating (Gross MWe): ...................... . 847.5

5. Design Electrical Rating (Net MWe): ................ .. 788

6. Maximum Dependable Capacity (Gross MWe): .. .. 820

7. Maximum Dependable Capacity (Net MWe): ...... .. 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 ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

-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 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-01-93 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx None during this reporting period.

(1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

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 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-01-93 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx None during this reporting period.

(1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LEA) File (NUREG 0161)

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 Surry Monthly Operating Report No. 93-09 Page 9 of 16

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: September, 1993 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 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.

09/30/93 2400 The reporting period ended with the Unit 1 at 100% power, 820 MWe.

e Surry Monthly Operating Report No. 93-09 Page 10 of 16

SUMMARY

OF OPERATING EXPERIENCE MONTH/VEAR: September, 1993 UNIT Two:

09/01/93 0000 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) 09/03/93 0316 Unit on-line. Started power increase.

1519 Stopped power increase at 97.5%, 760 MWe. Holding for evaluation of Steam Generator "C" level oscillations.

09/04/93 0648 Started power reduction to maintain condenser vacuum while cleaning water boxes.

0650 Stopped power reduction at 90%, 715 MWe.

1624 Started power increase following water box cleaning.

1706 Stopped power increase at 97.5%, 760 MWe.

09/09/93 0630 Started power reduction to maintain condenser vacuum while cleaning water boxes.

0635 Stopped power reduction at 95%, 740 MWe.

1610 Started power increase following water box cleaning.

1635 Stopped power increase at 99%, 785 MWe.

09/13/93 0945 Started slow power increase.

1009 Stopped power increase at 100%, 820 MWe.

09/24/93 1055 Started power reduction due to Steam Generator "C" level oscillations.

1100 Stopped power reduction at 99%, 800 MWe.

09/25/93 2133 Started power reduction due to Steam Generator "C" level oscillations.

2138 Stopped power reduction at 98%, 792 MWe.

09/30/93 2400 The reporting period ended with the Unit at 98% power, 792 MWe, due to Steam Generator "C" level oscillations.

e Surry Monthly Operating Report No. 93-09 Page 11 of 16 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1993 SE 93-184 Safety Evaluation 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.

DCP 86-03 Design Change Package 09-10-93 (Safety Evaluation No.90-195)

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 {electro-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.

TM S1-93-11 Temporary Modification 09-20-93

{Safety Evaluation No.93-185)

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.

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 FS 93-45 Updated Final Safety Analysis Report Change 09-27-93 VPAP- 0102 Station Administrative Procedure (Safety Evaluation No.93-188)

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.

4lurry Monthly Operating Report No. 93-09 Page 14 of 16 CHEMISTRY REPORT MONTH/VEAR: September, 1993 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Avq.

Gross Radioactivity, uCi/ml 5.12E-1 2.31 E-1 3.39E-1 2.36E-1 8.29E-4 1.47E-1 Susoended Solids, oom < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Gross Tritium, uCi/ml 9.10E-2 3.46E-2 6.50E-2 3.20E-1 1.04E-1 2.22E-1 1131, uCi/ml 3.00E-3 7.52E-4 1.10E-3 1.93E-4 5.46E-5 8.68E-5 113111133 0.14 0.07 0.09 0.14 0.07 0.10 Hydroqen cc/kq 37.5 26.9 31.5 47.8 27.5 35.5 Lithium, oom 2.02 1.13 1.55 2.34 1.45 2.16 Boron - 10, oom* 49.0 19.4 29.7 361.2 233.0 259.8 Oxygen, (DO), ppm <0.005 :50.005 .:5.0.005 .:5.0.005 :50.005 .:5.0.005 Chloride, oom 0.004 <0.001 0.001 0.013 0.005 0.009 pH at 25 deqree Celsius 7.37 7.00 7.23 6.45 5.86 6.30

• Boron -10 = Total Boron x 0.196 Comments:

None

e Surry Monthly Operating Report No. 93-09 Page 15 of 16 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: September, 1993 Newer Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity No fuel received or stored during this reporting period.

l_________ _

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• 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.