ML18153A942

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Monthly Operating Repts for Apr 1994 for Surry Power Station Units 1 & 2.W/940511 Ltr
ML18153A942
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/30/1994
From: Bowling M, Mason D, Olsen C
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-304, NUDOCS 9405190099
Download: ML18153A942 (17)
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'\ VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 11, 1994 U. S. Nuclear Regulatory Commission Serial No.94-304 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 April 1994.

Very truly yours,

/f'Y.IJ~J 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

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 94-04 Approved:

e esurry Monthly Operating Report No. 94-04 Page 2of 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. 94-04 Page 3of 16 OPERATING DATA REPORT Docket No.: 50-280 Date: 05-02-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: ..................... .-............................ . Surry Unit 1
2. Reporting Period: ......................................... . April, 1994
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 ......................... . 719.0 2879.0 187199.0
12. Number of Hours Reactor Was Critical ......... . 719.0 1399.8 125207.0
13. Reactor Reserve Shutdown Hours .............. . 0 0 3774.5
14. Hours Generator On-Line ....*.......*.............. 719.0 1366.9 123045.9
15. Unit Reserve Shutdown Hours....*................ 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) *..... 1747887.0 2749615.0 285917360.1
17. Gross Electrical Energy Generated (MWH) ... . 586040.0 921095.0 93460643.0
18. Net Electrical Energy Generated (MWH) ....... . 565227.0 882996.0 88710097.0
19. Unit Service Factor .................................. . 100.0% 47.5% 65.7%
20. Unit Availability Factor.............................. . 100.0% 47.5% 67.7%
21. Unit Capacity Factor (Using MDC Net) .......... . 100.7% 39.3% 61.1%
22. Unit Capacity Factor (Using DER Net) .......... . 99.8% 38.9% 60.1%
23. Unit Forced Outage Rate ...*........................ 0% 0% 17.3%
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

esurry Monthly Operating Report No. 94-04 Page 4of 16 OPERATING DATA REPORT Docket No.: 50-281 Date: 05-02-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ...............................*.......... April, 1994
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 ......................... . 719.0 2879.0 184079.0
12. Number of Hours Reactor Was Critical ......... . 719.0 2879.0 122955.3
13. Reactor Reserve Shutdown Hours .............. . 0 0 328.1
14. Hours Generator On-Line .......................... . 719.0 2879.0 121094.6
15. Unit Reserve Shutdown Hours .................... . 0 0 0
16. Gross Thermal Energy Generated (MWH) ..... . 1592098.8 6775938.9 282451681.3
17. Gross Electrical Energy Generated (MWH) ... . 533150.0 2269735.0 92215359.0
18. Net Electrical Energy Generated (MWH) ....... . 512777.0 2188114.0 87520184.0
19. Unit Service Factor .................................. . 100.0% 100.0% 65.8%
20. Unit Availability Factor.............................. . 100.0% 100.0% 65.8%
21. Unit Capacity Factor (Using MDC Net) ...........
  • 91.3% 97.3% 61.0%
22. Unit Capacity Factor (Using DER Net) .......... . 90.5% 96.4% 60.3%
23. Unit Forced Outage Rate ........................... . 0% 0% 13.8%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Maintenance, June 4, 1994, 22 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

&urry Monthly Operating Report No. 94-04 Page 5 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: April, 1994 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 05-01-94 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LEA System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 940404 F NIA A NIA NIA IG ACT Turbine runback to 65% power occurred when nuclear instrument Nl-42 failed.

(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)

esurry Monthly Operating Report No. 94-04 Page 6 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: April, 1994 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 05-01-94 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 940403 F NIA A NIA NIA EL IPBU Reduced power to 66% to repair "A" and "C" phase isophase bus duct fans.

940411 F NIA A NIA NIA SJ p Reduced power to 60% to repair feedwater pump, 2-FW-P-1 B, seal return line.

(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)

-Surry Monthly Operating Report No. 94-04 Page 7of 16 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 05-04-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: April, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 789 17 793 2 790 18 793 3 758 19 784 4 708 20 781 5 791 21 782 6 792 22 785 7 791 23 793 8 791 24 793 9 791 25 792 10 791 26 791 11 792 27 786 12 786 28 783 13 784 29 782 14 786 30 789 15 793 16 792 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. 94-04 Page 8of 16 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit2 Date: 05-04-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: April, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 755 17 738 2 754 18 737 3 588 19 736 4 515 20 735 5 678 21 730 6 741 22 737 7 741 23 740 8 741 24 727 9 742 25 724 10 740 26 722 11 676 27 721 12 536 28 721 13 739 29 721 14 737 30 719 15 738 16 737 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.

- Surry Monthly Operating Report No. 94-04 Page 9of 16

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: April, 1994 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.

UNIT ONE:

04/01/94 0000 The reporting period began with the Unit at 98% power, 820 MWe, pending Engineering evaluation of reactor core power level.

04/04/94 1342 Turbine runback began when nuclear instrument N-42 failed.

. 1500

  • Turbine runback stopped at 65% power, 485 MWe.

1815 Started power increase.

2127 Stopped power increase at 99%, 810 MWe.

04/05/94 0025 Started power increase.

0036 Stopped power increase at 99.5%.

0928 Started power increase.

1018 Stopped power increase at 100%.

04/30/94 2400 The reporting period ended with the Unit at 100% power, 820 MWe.

e Surry Monthly Operating Report No. 94-04 Page 10 of 16

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: April, 1994 UNIT Two:

04/01/94 0000 The reporting period began with the Unit at 96% power, 785 MWe due to Steam Generator "C" level oscillations.

04/03/94 0425 Started power reduction to stabilize Steam Generator "C" level oscillations.

0430 Stopped power reduction at 94%, 770 MWe.

0955 Started power reduction to repair "A" and "C" phase isophase bus duct fans.

1107 Stopped power reduction at 66%, 565 MWe.

04/05/94 0554 Started power increase after completing repairs to "A" and "C" phase isophase bus duct fans.

091 O Stopped power increase at 94%, 780 MWe.

04/11/94 1648 Started power reduction to repair feedwater pump, 1-FW-P-1 B, seal return line.

1930 Stopped power reduction at 60%, 500 MWe.

04/12/94 1655 Started power increase after completing repair to feedwater pump, 1-FW-P-1 B, seal return line.

2030 Stopped power reduction at 94%, 770 MWe.

04/23/94 2300 Started power reduction to stabilize Steam Generator "C" level oscillations.

2340 Stopped power reduction at 92%, 755 MWe.

04/30/94 2400 The reporting period ended with the Unit operating at 92% power, 755 MWe, due to Steam Generator "C" level oscillations.

e Surry Monthly Operating Report No. 94-04 Page 11 of 16 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1994 DR S-94-0115 Deviation Report 04-18-94 (Safety Evaluation No.94-085)

Safety Evaluation 94-085 assessed the condition reported by Deviation Report S-94-0115 concerning the placement of temporary wind screens over the inside of the louvers in the steam side of the Safeguards Building. The wind screens were installed to protecl instrument lines from freezing during a period of extreme cold weather.

The evaluation concluded that this temporary modification did not affect the operability of the turbine-driven auxiliary feedwater pump and did not reduce the Technical Specifications margin of safety. Therefore, an unreviewed safety question did not exist.

FS 94-13 UFSAR Change 04-28-94 (Safety Evaluation No.94-088)

Updated Final Safety Analysis Report Change 94-13 revised Section 2.1, "[Site]

General Description," to reflect current population data, delete unnecessary land and water use information, and update the discussion of nearby facilities and the reviews of potential accidents associated with these facilities.

This change was administrative in nature. It did not involve any physical modifications and did not affect the margin of safety or the Technical Specifications. Therefore, an unreviewed safety question did not exist.

- Surry Monthly Operating Report No. 94-04 Page 12 of 16 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1994 DR S-94-0638 Deviation Report 04-18-94 (Safety Evaluation No.94-086)

Safety Evaluation 94-086 assessed the condition reported by Deviation Report S-94-0638 concerning the continued operation of Unit 1 with the letdown isolation valve, 1-CH-HCV-1200C fully closed and not available for use.

The evaluation concluded that continued operation for the remainder of the fuel cycle is acceptable since the subject condition does not affect the integrity or increase the severity of the operating conditions of the Reactor Coolant System or Charging/Letdown System. In addition, the subject valve is not required during an accident condition. Therefore, an unreviewed safety question does not exist.

1-NPT-RX-002 Engineering Periodic Test Procedure 4-22-94 (Safety Evaluation No.94-087)

Engineering Periodic Test Procedure 1-NPT-RX-002, "Reactor Core Flux Maps" was revised to provide instructions for installing an electrical jumper around the limit switch for the detector withdrawn position on the Unit 1 "D" incore detector drive motor. This jumper will allow use of the "D" detector 1O path transfer device along with the "C" detector 5 path transfer device and drive motor to perform Technical Specification required full core flux maps. The "D" detector 5 path transfer switch will also be disabled to prevent damaging the detector cable when the detector is inserted into its storage location. This option is being made available due to the failure of the "D" incore detector drive motor clutch mechanism.

This change will facilitate the continued performance of full core flux mapping and will prevent unnecessary radiation hazards. Furthermore, operation of the incore instrumentation system will not be adversely affected and the integrity of the reactor coolant system boundary at the seal table will not be compromised.

Therefore, an unreviewed safety question does not exist.

SE 94-089 Safety Evaluation 04-26-94 Safety Evaluation 94-089 was performed to evaluate the impact on plant systems of isolating the Process Vent and Gaseous Waste (GW) systems to facilitate the tie-in of completed modifications (Design Change Packages93-024, "GW Piping Reroute," and 93-057, "GW Piping Drains").

The evaluation concluded that the temporary change in the mode of operation is within the scope of normal operating capability and limitations, and will be within Technical Specification requirements. Furthermore, the activity will be stringently monitored and controlled. Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report No. 94-04 Page 13 of 16 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April, 1994 None During the Reporting Period
  • Surry Monthly Operating Report No. 94-04 Page 14 of 16 CHEMISTRY REPORT MONTH/YEAR: April, 1994 Unit No. 1 Unit No. 2 Primarv Coolant Analysis Max. Min. Ava. Max. Min. Ava.

Gross Radioactivitv, LLCi/ml 3.20E-1 2.04E-1 2.69E-1 1.91E-1 1.06E-1 1.46E-1 Suspended Solids, oom < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Gross Tritium, µ.Ci/ml 2.11 E-1 7.94E-2 1.48E-1 6.09E-1 4.74E-1 5.27E-1 1131, µ.Ci/ml 3.51E-4 1.50E-4 2.79E-4 3.94E-4 4.56E-5 8.30E-5 113111133 0.07 0.06 0.07 0.11 0.05 0.07 Hvdroaen, cc/kg 44.4 31.9 37.2 48.2 35.2 41.1 Lithium, oom 2.34 2.06 2.18 2.32 2.08 2.19 Boron - 10, oom* 217.0 232.8 222.9 173.1 146.4 155.1 Oxvaen, (DO). onm 0.005 0.005 0.005 0.005 0.005 0.005 Chloride oom 0.009 0.005 0.007 0.008 0.004 0.006 pH at 25 dearee Celsius 6.69 6.20 6.54 6.98 6.45 6.77

None

- Surry Monthly Operating Report No. 94-04 Page 15 of 16 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: April, 1994 New or 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 the Reporting Period.

  • Surry Monthly Operating Report No. 94-04

... Page 16 of 16 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE !NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: April, 1994 None During the Reporting Period.

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