ML18153B098

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Monthly Operating Repts for Sept 1994 for Surry Power Station.W/941012 Ltr
ML18153B098
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/30/1994
From: Bowling M, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-590, NUDOCS 9410170286
Download: ML18153B098 (17)
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Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 12, 1994 U.S. Nuclear Regulatory Commission Serial No.94-590 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 1994.

Very truly yours, M. L. Bowling, Manager Nuclear Licensing and 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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i..~\................ i 9410170286 940930 PDR ADOCK 05000280 R PDR

e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 94-09 Approved:

Station Manager Date

.urry Monthly Operating Report No. 94-09 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 ......................................................................................... 9 Facility Changes That Did Not Require NRG Approval ............................................................................... 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 11 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. 94-09 Page 3 of 16 OPERATING DATA REPORT Docket No.: 50-280 Date: 09-02-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . September, 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 YTD Cumulative

11. Hours In Reporting Period .......................... 720.0 6551.0 190871.0
12. Number of Hours Reactor Was Critical .......... 720.0 5049.7 128856.9
13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5
14. Hours Generator On-Line ........................... 720.0 5012.5 126691.5
15. Unit Reserve Shutdown Hours ..................... 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 1749025.4 11626743.1 294794488.2
17. Gross Electrical Energy Generated (MWH) .... 575820.0 3855860.0 96395408.0
18. Net Electrical Energy Generated (MWH) ........ 554633.0 3707849.0 91534950.0
19. Unit Service Factor ................................... 100.0% 76.5% 66.4%
20. Unit Availability Factor ............................... 100.0% 76.5% 68.3%
21. Unit Capacity Factor (Using MDC Net) ........... 98.6% 72.5% 61.8%
22. Unit Capacity Factor (Using DER Net) ........... 97.8% 71.8% 60.9%
23. Unit Forced Outage Rate ............................ 0.0% 0.5% 16.9%
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. 94-09 Page 4 of 16 OPERATING DATA REPORT Docket No.: 50-281 Date: 09-02-94 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . September, 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 .......................... 720.0 6551.0 187751.0
12. Number of Hours Reactor Was Critical .......... 720.0 6052.2 126128.5
13. Reactor Reserve Shutdown Hours ............... 0 0 328.1
14. Hours Generator On-Line ........................... 720.0 6042.5 124258.1
15. Unit Reserve Shutdown Hours ..................... 0 0 0
16. Gross Thermal Energy Generated (MWH) ...... 1753243.3 14203529.3 289879271.7
17. Gross Electrical Energy Generated (MWH) .... 571955.0 4701255.0 94646879.0
18. Net Electrical Energy Generated (MWH) ........ 551235.0 4528295.0 89860365.0
19. Unit Service Factor ................................... 100.0% 92.2% 66.2%
20. Unit Availability Factor ............................... 100.0% 92.2% 66.2%
21. Unit Capacity Factor (Using MDC Net) ........... 98.0% 88.5% 61.4%
22. Unit Capacity Factor (Using DER Net) ........... 97.2% 87.7% 60.7%
23. Unit Forced Outage Rate ............................ 0% 0% 13.5%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling (10 Year ISi), February 4, 1995, 58 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. 94-09 Page 5 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: September, 1994 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 09-03-94 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 None During the 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)

  • ~urry Monthly Operating Report No. 94-09 Page 6 of 16 UNIT SHUTDOWN AND POWER REDUCTION

{EQUAL To OR GREATER THAN 20%)

REPORT MONTH: September, 1994 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 09-03-94 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 None During the 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)

  • -Surry Monthly Operating Report No. 94-09 Page 7 of 16 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 09-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: September, 1994 Average Daily Power Level Average Daily Power Level Dal (MWe- Net} Dal (MWe- Net}

714 17 722 2 769 18 778 3 773 19 780 4 776 20 781 5 776 21 782 6 772 22 784 7 774 23 784 8 771 24 784 9 772 25 782 10 753 26 782 11 753 27 781 12 779 28 780 13 735 29 780 14 774 30 782 15 764 16 775 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. 94-09 Page 8 of 16 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 09-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: September, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 767 17 762 2 769 18 761 3 773 19 764 4 774 20 765 5 772 21 765 6 770 22 764 7 770 23 738 8 774 24 733 9 773 25 771 10 771 26 770 11 770 27 770 12 769 28 768 13 768 29 773 14 765 30 763 15 766 16 750 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.
  • ~urry Monthly Operating Report No. 94-09 Page 9 of 16

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: September, 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:

09/01/94 0000 The reporting period began with the unit operating at 100% power, 800 MWe.

09/13/94 0749 Started power reduction to maintain condenser vacuum while cleaning waterboxes.

0919 Stopped power reduction at 92%, 71 O MWe.

1250 Started power reduction to maintain condenser vacuum while cleaning waterboxes.

1410 Stopped power reduction at 89%, 675 MWe.

1621 Started power increase.

1722 Stopped power increase at 100%, 800 MWe.

09/17/94 0512 Started power reduction to maintain condenser vacuum while cleaning waterboxes.

0846 Stopped power reduction at 86%, 670 MWe.

1619 Started power increase.

1900 Stopped power increase at 100%, 81 O MWe.

09/30/94 2400 The reporting period ended with the unit operating at 100% power, 810 MWe.

UNIT Two:

09/01/94 0000 The reporting period began with the unit operating at 100% power, 800 MWe.

09/23/94 0547 Started power reduction to maintain condenser vacuum while cleaning waterboxes.

0640 Stopped power reduction at 87%, 680 MWe.

1052 Started power increase.

1150 Stopped power increase at 100%, 800 MWe.

09/24/94 0515 Started power reduction to maintain condenser vacuum while cleaning waterboxes.

0700 Stopped power reduction at 91 %, 720 MWe.

1600 Started power increase.

1715 Stopped power increase at 100%, 805 MWe.

09/30/94 2400 The reporting period ended with the unit operating at 100% power, 805 MWe.

_J

  • 'FACILITY CHANGES THAT DID NOT

.urry Monthly Operating Report No. 94-09 Page 10 of 16 REQUIRE NRC APPROVAL MONTH/YEAR: September, 1994 WO 297836/02 Work Order 09-01-94 (Safety Evaluation No.94-166)

Work Order 297836/02 performed an on-line temporary leak-seal repair of the Unit 1 "C" Steam Generator seconda_ry side.lower handhole cover ..

The leak sealant material was compatible with the materials it contacted and a stress analysis was performed to ensure the bolting materials would not be overstressed by the sealant injection. The leak-seal repair did not alter the performance characteristics of the steam generator, the bolting material, or the handhole flange. Therefore, an unreviewed safety question does not exist.

DCP 93-023 Design Change Package 09-16-94 (Safety Evaluation No.93-167)

Design Change Package 93-023 replaced the overcurrent relays on the 4160 volt circuit breakers supplying the Unit 1 and 2 charging/high head safety injection pump motors and changed the overcurrent setpoints.

The modification was implemented to provide additional margin between the maximum current requirement of the motors and the minimum pick-up (trip) of the relays. The change does not affect the operation of safety-related systems or components and will not prevent systems from performing accident mitigation functions. Therefore, an unreviewed safety question does not exist.

DCP 94-028 Design Change Package 09-16-94 (Safety Evaluation No.94-106)

Design Change Package 94-028 evaluated and made permanent an electrical jumper that had been previously installed to temporarily bypass the failed Unit 1 Consequence Limiting Safeguards (CLS) alarm circuit relay 1BOB and clear Control Room annunciator 1-B-4, "CLS Coil Failure."

The subject Hi CLS System Train "B" relay is a spare that performs no function. The activity did not affect other systems or the Hi CLS System Train "A." The operability of the affected alarms was verified following the installation of the electrical jumper. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES e Surry Monthly Operating Report No. 94-09 Page 11 of 16 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1994 2-TMOP-3027 Temporary Maintenance Operating Procedure 09-01-94 (Safety Evaluation No.94-165)

Temporary Maintenance Operating Procedure 2-TMOP-3027, "Cleaning-Retention Element on 2-CH-1-1 A,"* was revised to provide -instructions -for-cleaning. any. residual~resin. or .....

foreign debris from the retention element of the Unit 2 "A" mixed bed demineralizer.

The subject procedure will be implemented while the demineralizer is isolated from the inservice letdown train and within the ventilation boundaries of the Auxiliary Building filtered exhaust. Therefore, an unreviewed safety question does not exist.

FS94-009 Updated Final Safety Analysis Report Change 09-06-94 (Safety Evaluation No.94-169)

UFSAR Change FS94-009 revised section 9.1.1.3, "[Chemical and Volume Control System] Codes and Classification," to reflect the change in the fabrication codes for the replacement Unit 1 excess letdown heat exchanger tube bundle (1-CH-E-4}.

The original tube bundle was fabricated in accordance with ASME Section Ill Class C 1965 Edition Winter 1966 Addenda. The replacement tube bundle was fabricated in accordance with the 1992 Edition ASME Section VIII. An engineering evaluation of the two fabrication codes concluded that the new code met or exceeded the previous code requirements.

Therefore, an unreviewed safety question does not exist.

1(2}-CPT-CS-001 Chemistry Periodic Test 09-07-94 (Safety Evaluation No. 94-170}

Chemistry Periodic Test procedures 1(2)-CPT-CS-001, "Refueling Water Storage Tank Chemistry," was revised to provide instructions for administratively controlling valves 1(2)-CS-27 while obtaining a sample from the lower part of the refueling water storage tanks (RWST}.

The administrative controls established by the subject procedures verify that the respective RWST recirculation pumps are operating at slow speed when valves 1(2}-CS-27 are open and ensure that these valves are closed within three minutes of the initiation of a safety injection signal. The RWST volume and chemistry requirements specified by the Technical Specifications are not affected by this change. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES

-urry Monthly Operating Report No. 94-09 Page 12 of 16 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1994 FS94-003 Updated Final Safety Analysis Report Change 09-07-94 (Safety Evaluation No. 94-169A)

UFSAR Change*FS 94-003-revised*section 8.4.3, **120-V Alternating Current-Vital Bus System," to be consistent with the design specifications for the station's Uninterruptible Power Supply (UPS) and to reflect the implementation of design changes that upgraded the UPS.

Specifically, the revision changed the reference voltage used to determine whether the voltage tolerance is within specification from the inverter output voltage to the UPS system output voltage. These changes did not affect the vital buses and did not reduce the margin of safety as described by the Technical Specifications. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 94-09 Page 13 of 16 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: September, 1994 2-ST-313 Special Test 08-08-94 (Safety Evaluation 94-138)

Special Test 2-ST-313, "Steam Generator Moisture Carryover Measurement Using Chemical Tracer Method," was conducted to determine the moisture carryover for the Unit 2 steam gen_erators (SG), evaluate the effectiveness of moisture separator modifications to the "A" SG, and to estimate the moisture carryover expected following core uprate. . .

The test results indicated that the average moisture carryover of the Unit 2 SGs is approximately 0.4%, which is greater than the design value of 0.25%. Safety Evaluation 94-173 was performed to assess these results and concluded that the increased steam moisture content does not affect the margin of safety as described by the Technical Specifications. The collected data is being further evaluated to determine why the moisture carryover is above the design value.

The testing procedure employed controls to prevent any impact on feedwater system performance or the reactor protection function of the SG level circuitry. Therefore, an unreviewed safety question does not exist.

&urry Monthly Operating Report No. 94-09 Page 14 of 16 CHEMISTRY REPORT MONTH/YEAR: September, 1994 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max: Min. Ava. *** *Max: 'Min.**- 'Ava:

Gross Radioactivity, µCi/ml 2.95E-1 2.38E-1 2.72E-1 1.74E-1 1.15E-1 1.37E-1 Suspended Solids, ppm <0.1 <0.1 <0.1 <0.1 <0.1 .:,;0.1 Gross Tritium, µCi/ml 2.67E-1 2.12E-1 2.43E-1 2.67E-1 2.13E-1 2.48E 0 1 1131, µCi/ml 4.66E-4 3.24E-4 4.07E-4 1.85E-4 1.03E-4 1.40E-4 113111133 0.08 0.06 0.07 0.09 0.06 0.08 Hydrogen, *cc/kg 34.3 26.6 30.7 41.6 29.4 36.2 Lithium, oom 2.33 2.05 2.23 2.31 1.99 2.19 Boron - 10, oom* 175.0 155.4 163.0 81.7 63.5 72.5 Oxygen, (DO), ppm .:,;0.005 .:,;0.005 .:,;0.005 .:,;0.005 .:,;0.005 .:,;0.005 Chloride, ppm .:,;0.050 0.003 0.008 .:,;0.050 0.002 0.006 pH at 25 degree Celsius 6.89 6.76 6.82 7.35 7.18 725 Boron - 1O = Total Boron x 0.196 Comments:

None

e Surry Monthly Operating Report No. 94-09 Page 15 of 16 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: September, 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

.eSurry Monthly Operating Report No. 94-09 Page 16 of 16 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: September, 1994 None During the Reporting Period

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