ML18153B098

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Monthly Operating Repts for Sept 1994 for Surry Power Station
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)
v • d • e


Text

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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 12, 1994 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.94-590 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 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

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

Station Manager Date

TABLE OF CONTENTS Section

.urry Monthly Operating Report No. 94-09 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......................................................................................... 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

OPERATING DATA REPORT

-urry Monthly Operating Report No. 94-09 Page 3 of 16 Docket No.:

50-280 09-02-94 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 1 September, 1994 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 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.:

Date:

Completed By:

50-281 09-02-94 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 2 September, 1994 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 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 INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION

(1)

Date Type (1)

F:

Forced S:

Scheduled (4)

-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 (2)

(3)

(4)

Method (5)

Docket No.: 50-280 Unit Name:

Surry Unit 1 Date: 09-03-94 Completed by: Craig Olsen Telephone:

(804) 365-2155 Duration

  • of *
      • *LER --*System*** Component** Cause*&*Corrective*Action to Hours Reason Shutting No.

Code Code Prevent Recurrence (2)

REASON:

Down Rx None During the 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)

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Exhibit 1 - Same Source.

(1)

Date Type (1)

F:

Forced S:

Scheduled (4)

~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 (2)

(3)

(4)

(5)

Method Docket No.:

50-281 Unit Name: Surry Unit 2 Date:

09-03-94 Completed by:

Craig Olsen Telephone:

(804) 365-2155 Duration

  • of
          • LER * ---System * *Component * *Cause & Corrective*Action to Hours Reason Shutting No.

Code Code Prevent Recurrence (2)

REASON:

Down Rx None During the 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)

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Exhibit 1 - Same Source.

-Surry Monthly Operating Report No. 94-09 Page 7 of 16 AVERAGE DAILY UNIT POWER LEVEL MONTH:

September, 1994 Average Daily Power Level Dal (MWe-Net}

714 2

769 3

773 4

776 5

776 6

772 7

774 8

771 9

772 10 753 11 753 12 779 13 735 14 774 15 764 16 775 INSTRUCTIONS Dal 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 09-02-94 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level (MWe-Net}

722 778 780 781 782 784 784 784 782 782 781 780 780 782 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 MONTH:

September, 1994 Average Daily Power Level Day (MWe-Net) 767 2

769 3

773 4

774 5

772 6

770 7

770 8

774 9

773 10 771 11 770 12 769 13 768 14 765 15 766 16 750 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 09-02-94 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level (MWe-Net) 762 761 764 765 765 764 738 733 771 770 770 768 773 763 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 09/13/94 09/17/94 09/30/94 UNIT Two:

09/01/94 09/23/94 09/24/94 09/30/94 0000 0749 0919 1250 1410 1621 1722 0512 0846 1619 1900 2400 0000 0547 0640 1052 1150 0515 0700 1600 1715 2400 The reporting period began with the unit operating at 100% power, 800 MWe.

Started power reduction to maintain condenser vacuum while cleaning waterboxes.

Stopped power reduction at 92%, 71 O MWe.

Started power reduction to maintain condenser vacuum while cleaning waterboxes.

Stopped power reduction at 89%, 675 MWe.

Started power increase.

Stopped power increase at 100%, 800 MWe.

Started power reduction to maintain condenser vacuum while cleaning waterboxes.

Stopped power reduction at 86%, 670 MWe.

Started power increase.

Stopped power increase at 100%, 81 O MWe.

The reporting period ended with the unit operating at 100% power, 810 MWe.

The reporting period began with the unit operating at 100% power, 800 MWe.

Started power reduction to maintain condenser vacuum while cleaning waterboxes.

Stopped power reduction at 87%, 680 MWe.

Started power increase.

Stopped power increase at 100%, 800 MWe.

Started power reduction to maintain condenser vacuum while cleaning waterboxes.

Stopped power reduction at 91 %, 720 MWe.

Started power increase.

Stopped power increase at 100%, 805 MWe.

The reporting period ended with the unit operating at 100% power, 805 MWe.

_J

WO 297836/02 DCP 93-023 DCP 94-028

'FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1994 Work Order (Safety Evaluation No.94-166)

.urry Monthly Operating Report No. 94-09 Page 10 of 16 09-01-94 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.

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

Design Change Package (Safety Evaluation No.94-106) 09-16-94 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 1 BOB 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.

2-TMOP-3027 FS94-009 1 (2}-CPT-CS-001 e

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

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

Chemistry Periodic Test (Safety Evaluation No. 94-170}

09-07-94 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.

FS94-003

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

2-ST-313 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 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.

CHEMISTRY REPORT MONTH/YEAR: September, 1994 Unit No. 1 Primary Coolant Analysis Max:

Min.

Ava.

Gross Radioactivity, µCi/ml 2.95E-1 2.38E-1 2.72E-1 Suspended Solids, ppm

<0.1

<0.1

<0.1 Gross Tritium, µCi/ml 2.67E-1 2.12E-1 2.43E-1 1131, µCi/ml 4.66E-4 3.24E-4 4.07E-4 113111133 0.08 0.06 0.07 Hydrogen, *cc/kg 34.3 26.6 30.7 Lithium, oom 2.33 2.05 2.23 Boron - 10, oom*

175.0 155.4 163.0 Oxygen, (DO), ppm

.:,;0.005

.:,;0.005

.:,;0.005 Chloride, ppm

.:,;0.050 0.003 0.008 pH at 25 degree Celsius 6.89 6.76 6.82 Boron - 1 O = Total Boron x 0.196 Comments:

None

&urry Monthly Operating Report No. 94-09 Page 14 of 16 Unit No. 2

      • *Max:

... 'Min.**-

'Ava:

1.74E-1 1.15E-1 1.37E-1

<0.1

<0.1

.:,;0.1 2.67E-1 2.13E-1 2.48E01 1.85E-4 1.03E-4 1.40E-4 0.09 0.06 0.08 41.6 29.4 36.2 2.31 1.99 2.19 81.7 63.5 72.5

.:,;0.005

.:,;0.005

.:,;0.005

.:,;0.050 0.002 0.006 7.35 7.18 725

New or Spent Fuel Shipment Date Stored or Number Received FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: September, 1994 Number of Assemblies per Shipment Assembly Number ANSI Number e

Surry Monthly Operating Report No. 94-09 Page 15 of 16 Initial Enrichment New or Spent Fuel Shipping Cask Activity No Fuel Received or Stored During the Reporting Period

.e Surry 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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