ML18153A814

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Monthly Operating Repts for Apr 1995 for Surry Power Station Units 1 & 2.W/950511 Ltr
ML18153A814
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/30/1995
From: Mason D, Olsen C
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-233, NUDOCS 9505190304
Download: ML18153A814 (18)
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 11, 1995 U. S. Nuclear Regulatory Commission Serial No.95-233 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 1995.

Very truly yours, 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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e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 95-04 Approved:

/\Ju-CL Station Manager

e Surry Monthly Operating Report No. 95-04 Page 2 of 17 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 NRC Approval ............................................................................... 1O Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 13 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 14 Chemistry Report ............................................................................................................................. 15 Fuel Handling - Unit No. 1 ................................................................................................................... 16 Fuel Handling - Unit No. 2 ................................................................................................................... 16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications********************************************************:****************************************** 17

. .urry Monthly Operating Report No. 95-04 Page 3,of 17 OPERATING DATA REPORT Docket No.: 50-280 Date: 05-01-95 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . April, 1995
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 ......................... . 719.0 2879.0 195959.0
12. Number of Hours Reactor Was Critical ......... . 683.8 2699.7 133169.4
13. Reactor Reserve Shutdown Hours .............. . 0 0 3774.5
14. Hours Generator On-Line .......................... . 678.1 2665.2 130906.2
15. Unit Reserve Shutdown Hours .................... . 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... . 1621917.1 6436291.5 304890030. 7
17. Gross Electrical Energy Generated (MWH) ... . 546160.0 2168705.0 99782538.0
18. Net Electrical Energy Generated (MWH) ....... . 526082.0 2092946.0 94801969.0
19. Unit Service Factor .... : ............................. . 94.3% 92.6% 66.8%
20. Unit Availability Factor .............................. . 94.3% 92.6% 68.7%
21. Unit Capacity Factor (Using MDC Net) .......... . 93.7% 93.1% 62.4%
22. Unit Capacity Factor (Using DER Net) .......... . 92.9% 92.3% 61.4%
23. Unit Forced Outage Rate ........................... . 5.7% 7.4% 16.5%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, August 31, 1995, 37 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. 95-04 Page 4 of 17 OPERATING DATA REPORT Docket No.: 50-281 Date: 05-01-95 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . April, 1995
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 YfD Cumulative

11. Hours In Reporting Period .......................... 719.0 2879.0 192839.0
12. Number of Hours Reactor Was Critical .......... 719.0 1803.3 130140.8
13. Reactor Reserve Shutdown Hours ............... 0 0 328.1
14. Hours Generator On-Line ........................... 719.0 1771.3 128238.4
15. Unit Reserve Shutdown Hours ..................... 0 0 0
16. Gross Thermal Energy Generated (MWH) ...... 1754903.3 4118826.1 299387290.4
17. Gross Electrical Energy Generated (MWH) .... 586980.0 1378390.0 97820684.0
18. Net Electrical Energy Generated (MWH) ........ 566892.0 1.328575.0 92921611.0
19. Unit Service Factor ................................... 100.0% 61.5% 66.5%
20. Unit Availability Factor ............................... 100.0% 61.5% 66.5%
21. Unit Capacity Factor (Using MDC Net) ........... 101.0% 59.1% 61.8%
22. Unit Capacity Factor (Using DER Net) ........... 100.1% 58.6% 61.1%
23. Unit Forced Outage Rate ............................ 0% 0% 13.2%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
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. 95-04 Page 5 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: April, 1995 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 05-04-95 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 950412 F N/A A N/A N/A AA ROD Control rod J-7 dropped, resulting in unit runback from 100% to 70% power.

950412 F N/A A N/A N/A AA ROD Flux deviation resulting from dropped control rod J-7.

Reduced power to 49%.

950412 F 40.9 A 1 AA ROD Increasing delta flux resulting 003-00 from dropped control rod J-7.

Manually tripped reactor.

(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)

e Surry Monthly Operating Report No. 95-04 Page 6 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: April, 1995 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 05-04-95 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 (NU REG 0161)

e Surry Monthly Operating Report No. 95-04 Page 7 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 05-03-95 Completed by: Barry C. Bryant Telephone: 365-2786 MONTH: April, 1995 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe- Net) 791 17 784 2 795 18 782 3 795 19 782 4 795 20 782 5 795 21 781 6 795 22 782 7 789 23 782 8 792 24 783 9 796 25 781 10 797 26 782 11 796 27 782 12 443 28 735 13 0 29 782 14 308 30 783 15 784 16 783 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. 95-04 Page 8 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 05-04-95 Completed by: Barry C. Bryant Telephone: 365-2786 MONTH: April, 1995 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day , (MWe - Net) 1 791 17 789 2 793 18 789 3 790 19 787 4 790 20 787 5 791 21 787 6 790 22 785 7 791 23 787 8 790 24 788 9 790 25 788 10 789 26 788 11 787 27 787 12 788 28 787 13 788 29 786 14 788 30 786 15 789 16 788 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. 95-04 Page 9 of 17

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: April, 1995 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:

04/01/95 0000 The reporting period began with the unit operating at 100% power, 825 MWe.

04/12/95 0818 Control rod J-7 dropped, resulting in a unit run back from 100%.

0833 Unit runback stopped at 70% power, 575 MWe.

1254 Started power reduction due to flux deviation resulting from dropped control rod J-7.

1259 Stopped power reduction at 49% power, 401 MWe.

1756 Manually tripped reactor due to increasing delta flux resulting from dropped control rod J-7. This conservative decision was made to ensure that the unit response would remain bounded by existing accident analyses in the event an additional transient was to occur.

04/14/95 0509 Reactor critical.

1051 Generator on line. Started power increase.

2349 Stopped power increase at 99% due to high steam flow on steam generator "C."

04/30/95 2400 The reporting period ended with the unit operating at 99% power, 810 MWe.

UNIT Two:

04/01/95 0000 The reporting period began with the unit operating at 100% power, 825 MWe.

04/30/95 2400 The reporting period ended with the unit operating at 100% power, 820 MWe.

e Surry Monthly Operating Report No. 95-04 Page 10 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1995 DCP 92-077-3 Design Change Package 3-04-95 (Safety Evaluation No.93-077)

Design Change Package 92°077-3 removed main -steam trip valve *bypass lirie check valves 1[2]-MS-85, 1[2]-MS-117, and 1[2]-MS-156. Piping was installed in place of the valves.

The subject valves, which were required in the original plant design, do not have a design basis function and are no longer required due to subsequent piping modifications. The replacement piping meets the design standards of the Main Steam System. Therefore, an unreviewed safety question does not exist.

DCP 93-054-3 Design Change Package 3-05-95 (Safety Evaluation No.93-203)

Design Change Package 93-054-3 implemented various outage related modifications to correct control room design deficiencies identified by the Control Room Design Review Reassessment Report including: 1) engraving and grouping some annunciator windows, 2) rescaling charging line flow indicators, 3) separating safety injection "A" and "B" alarms, 4) relocating annunciator pushbutton controls away from reactor trip pushbuttons, 5) installing digital auxiliary feedwater flow indicators, 6) adding engineering units to indicator scales, 7) changing the scale on the chemical addition tank level indicator, and 8) labeling emergency diesel generator No. 3 watts and Vars indicators.

These modifications, which enhance operator response capability, affect indication and annunciator control only. The operation of safety-related equipment or availability of safety-related power sources is not affected. Therefore, an unreviewed safety question does not exist.

DCP 89-010-3 Design Change Package 3-31-95 (Safety Evaluation No.90-006)

Design Change Package 89-010-3 installed additional fire detectors in the Cable Vaults and Tunnels, Main Steam Valve House Basements, and Computer Rooms.

This nonsafety-related modification was implemented to comply with the requirements of NFPA-72E, as required by Generic Letter 86-10. The change did not impact the operation of safety-related equipment and did not affect the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 95-04 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1995 DCP 94-008-3 Design Change Package 4-06-95 (Safety Evaluation No.94-052)

Design Change Package 94-008-3 replaced the Radiation Monitoring System recorders in the Control Room.

The modification enhances radiological monitoring capabilities by providing increased recorder reliability and visual resolution. Compensatory measures were instituted while each recorder was being replaced and the automatic control functions that impact potential release paths to the environment remained in service. Therefore, an unreviewed safety question does not exist.

FS 95-11 Updated Final Safety Analysis Report Change 4-13-95 (Safety Evaluation No.95-048)

UFSAR Change 95-11 revised Section 9.10.4.18, "[Fire Protection Evaluation of] Turbine Building," to clarify 1) that the carbon dioxide fire suppression systems which protect the turbine generator bearings can be manually initiated by local controls only, and 2) that the main and station service transformers are separated from each other by concrete fire walls and from the Turbine Building by a spatial distance of 35 feet (not by a concrete wall).

This change was made to clearly reflect the original plant design. The change did not involve any physical modifications to the plant and did not affect continued compliance with the Technical Specifications or Appendix R requirements. Therefore, an unreviewed safety question does not exist.

WO 315357 Work Order 4-18-95 (Safety Evaluation No.95-050)

Work Order 315357 removed breaker 2-EP-BKR-2481-5 from service to perform corrective maintenance on the breaker while Unit 2 was at power. This activity de-energized the 480 volt motor control center (MCC) 281-2, which de-energized the "B" incore flux detector, the motor operator for the "B" main steam (MS) non-return valve (NRV), and containment dome cooling fan 2-VS-F-101.

The activity was evaluated to determine its effect on the main steam line break (MSLB) and steam generator tube rupture (SGTR) accident analyses. The evaluation concluded that de-energizing the "B" MS NRV will not increase the consequences or probability of occurrence of a MSLB or a SGTR. The lncore Flux Detector System and the containment dome cooling fan are not considered in these two accident analyses. Furthermore, the loads associated with MCC 281-2 are nonsafety-related and do not affect the station's ability to achieve and maintain safe shutdown. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 95-04 Page 12 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April, 1995 DCP 93-005-3 Design Change Package 4-25-95 (Safety Evaluation No.93-186)

Design Change Package 93-005-3 replaced the Unit 1 and 2 pressurizer-pressure transmitters and changed the safety injection (SI) low-low trip setpoint from 1715 psig to 1775 psig.

The replacement transmitters are similar in design to the existing transmitters and are better able to resist post design basis event environmental conditions. The change in the SI trip setpoint provides additional conservatism to ensure the function will occur above the current Technical Specification limit of 1700 psig. Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report No. 95-04 Page 13 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1995 VPAP-2104 Station Administrative Procedure 4-04-95 (Safety Evaluation No.95-047)

Station Administrative Procedure VPAP-2104, "Radioactive Waste Process Control Program (PCP),"was revised to reflect a change in the bitumen solidification operation.

This change_ to the PCP involves the addition of an increased quantity of a different type of surfactant to the process waste stream to improve the processing of boric acid and sodium sulfate concentrates. The change does not modify Radwaste Facility operation as described in the UFSAR and does not affect the margin of safety as described in the Technical Specifications. Therefore, an unreviewed safety question does not exist.

eSurry Monthly Operating Report No. 95-04 Page 14 of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1995 None During the Reporting Period

e Surry Monthly Operating Report No. 95-04 Page 15 of 17 CHEMISTRY REPORT MONTHNEAR: April, 1995 Unit No. 1 Unit No. 2 Primarv Coolant Analysis Max. Min. Ava. Max. Min. Avg.

Gross Radioactivity, µCi/ml 4.07E-1 2.55E-2 3.40E-1 2.20E-1 1.50E-1 1.84E-1 Suspended Solids, ppm 50.010 50.010 50.010 50.010 50.010 50.010 Gross Tritium, µCi/ml 2.08E-1 7.82E-2 1.49E-1 2.75E-1 1.35E-1 2.20E-1 11 3 1, µCi/ml 2.24E-3 2.46E-4 7.49E-4 1.60E-4 8.94E-5 1.17E-4 113111133 0.10 0.06 0.07 0.10 0.05 0.08 Hvdroaen, cc/kq 40.9 30.2 35.8 42.3 25.5 33.9 Lithium, ppm 2.40 2.00 2.20 2.58 2.06 2.23 Boron - 1O, oom* 161.1 58.8 83.9 210.3 203.1 206.0 Oxygen, (DO), ppm 50.005 50.005 50.005 50.005 50.005 50.005 Chloride, ppm 5.0.050 50.001 0.005 50.050 50.001 0.007 pH at 25 deqree Celsius 7.34 6.74 7.24 6.71 6.50 6.62 Boron - 10 = Total Boron x 0.196 Comments:

None

'f' e Surry Monthly Operating Report No. 95-04 Page 16 of 17 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: April, 1995 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. 95-04 Page 17 of 17 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: April, 1995 None During the Reporting Period I

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