ML18153A494

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Monthly Operating Repts for Jan 1997 for Surry Power Station,Units 1 & 2.W/970213 Ltr
ML18153A494
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/31/1997
From: Fanguy M, Kilmer J, Sarver S
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
97-094, 97-94, NUDOCS 9702260351
Download: ML18153A494 (17)
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 13, 1997 United States Nuclear Regulatory Commission Serial No.97-094 Attention: Document Control Desk NURPC 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 M,~mthly Operating Report for Surry Power Station Units 1 and 2 for the month of January 1997.

If you have any questions or require additional information, please contact us.

Very truly yours, S. P. Sarver, Acting Manager Nuclear Licensing and Operations Support Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323

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Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station r--

1 9702260351 970131 PDR -' ADOCK 05000280 R .. POil i

e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 97-01 Approved:

b¥*Q~~tation Manager ZI 1'3/t/7 Date

e e Surry Monthly Operating Report No. 97-01 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 ............................................................................................ 1O Procedure or Method of Operation Changes That Did Not Require NRG Approval ................................................. 12 Tests and Experiments That Did Not Require NRG 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

e e Surry Monthly Operating Report No. 97-01 Page 3 of 16 OPERATING DATA REPORT Docket No.: 50-280 Date: 02/05/97 Completed By: D. K. Mason Telephone: (804) 365-2459

1. Unit Name: ........................................................... . Surry Unit 1
2. Reporting Period: ................................................. . January, 1997
3. Licensed Thermal Power (MWt): ......................... . 2546
4. ** Nameplate Rating (Gross MWe): ......................... . 847.5
5. Design Electrical Rating (Net MWe): ................... . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 840
7. Maximum Dependable Capacity (Net MWe): ...... . 801
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 ............................... 744.0 744.0 211368.0
12. Number of Hours Reactor Was Critical. ........... 559.9 559.9 147394.6
13. Reactor Reserve Shutdown Hours .................. 0.0 0.0 3774.5
14. Hours Generator On-Line ................................ 559.4 559.4 145090.4
15. Unit Reserve Shutdown Hours ........................ 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 1413488.3 1413488.3 340048932.1
17. Gross Electrical Energy Generated (MWH) ..... 473435.0 473435.0 111446253.0
18. Net Electrical Energy Generated (MWH) ......... 457791.0 457791.0 106051540.0
19. Unit Service Factor .......................................... 75.2% 75.2% 68.6%
20. Unit Availability Factor ..................................... 75.2% 75.2% 70.4%
21. Unit Capacity Factor (Using MDC Net) ............ 76.8% 76.8% 64.6%
22. Unit Capacity Factor (Using DER Net) ............ 78.1% 78.1% 63.7%
23. Unit Forced Outage Rate ................................. 24.8% 24.8% 15.3%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, March 6, 1997, 37 Days

25. If Shut Down at End of Report Period, Estimated Date of Start-up: 2/2/97
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

J..

e e Surry Monthly Operating Report No. 97-01 Page 4 of 16 OPERATING DATA REPORT Docket No.: 50-281 Date: 02-05-97 Completed By: D. K. Mason Telephone: (804) 365-2459

1. Unit Name: ........................................................... . Surry Unit 2
2. Reporting Period: ................................................. .
  • January, 1997
3. Licensed Thermal Power (MWt): ......................... . 2546
4. Nameplate Rating (Gross MWe): ......................... . 847.5
5. Design Electrical Rating (Net MWe): ................... . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 840
7. Maximum Dependable Capacity (Net MWe): ...... . 801
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 ............................... 744.0 744.0 208248.0
12. Number of Hours Reactor Was Critical. ........... 744.0 744.0 143819.6
13. Reactor Reserve Shutdown Hours .................. 0.0 0.0 328.1
14. Hours Generator On-Line ................................ 744.0 744.0 141841.8
15. Unit Reserve Shutdown Hours ........................ 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ...... 1893331.9 1893331.9 333367588.7
17. Gross Electrical Energy Generated (MWH) ..... 635530.0 635530.0 109086329.0
18. Net Electrical Energy Generated (MWH) ......... 614218.0 614218.0 103806097. 0
19. Unit Service Factor .......................................... 100.0% 100.0% 68.1%
20. Unit Availability Factor ..................................... 100.0% 100.0% 68.1%
21. Unit Capacity Factor (Using MDC Net) ............ 103.1% 103.1% 63.8%
22. Unit Capacity Factor (Using DER Net) ............ 104.8% 104.8% 63.3%
23. Unit Forced Outage Rate ................................. 0.0% 0.0% 12.4%
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: N/A
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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e e Surry Monthly Operating Report No. 97-01 Page 5 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: January, 1997 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02-05-97 Completed by: M. J. Fanguy Teleehone: (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 Power reduction in preparation 1-7-97 s NA B NA NA TA V for the Turbine Inlet Valve Freedom Test.

1-24-97 F 184.6 A 97-001 SB V Shutdown in accordance with Tech Spec 4.15.C.1 to repair a pinhole leak on two inch main steam piping. The line goes to 1-MS-TD-4 from the "B" main steam 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 (LEA) File (NU REG 0161)

e Surry Monthly Operating Report No. 97-01 Page 6 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: January, 1997 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 02-05-97 Completed by: M. J. Fanguy Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action to Date Type Hours Reason Shutting 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)

  • AVERAGE DAILY UNIT POWER LEVEL e Surry Monthly Operating Report No. 97-01 Page 7 of 16 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02-03-97 Completed by: J. D. Kilmer Telephone: (804) 365-2792 MONTH: January, 1997 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 824 17 827 2 824 18 827 3 824 19 827 4 825 20 827 5 824 21 827 6 824 22 827 7 763 23 827 8 823 24 151 9 823 25 0 10 823 26 0 11 823 27 0 12 823 28 0 13 826 29 0 14 827 30 0 15 827 31 0 16 827 INSTRUCTIONS On this format, list the average daily unit power level in MWe - Net tor each day in the reporting month. Compute to the nearest whole megawatt.

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e e Surry Monthly Operating Report No. 97-01 Page 8 of 16 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 02-03-97 Completed by: John D. Kilmer Telephone: (804) 365-2792 MONTH: January, 1997 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 825 17 828 2 825 18 828 3 824 19 828 4 824 20 828 5 824 21 827 6 823 22 829 7 821 23 829 8 822 24 815 9 824 25 828 10 822 26 828 11 823 27 827 12 825 28 827 13 826 29 827 14 824 30 827 15 826 31 827 16 829 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. 97-01 Page 9 of 16

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: January, 1997 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:

01/01/97 0000 Unit starts month at 100% power, 855 MWe.

01/07/97 0513 Start power reduction to perform 1-0SP-TM-001, Turbine Inlet Valve Freedom Test.

1200 Stop power reduction at 77%, 660 MWe.

1444 Started power increase.

1850 Unit at 100%, 850 MWe.

01/24/97 0124 Start power reduction in accordance with Tech Spec 4.15.C.1 to repair a pinhole leak on two inch main steam piping. The line goes to 1-MS-TD-4 from the "B" main steam line.

0721 Tripped turbine locally with power <15% on all Nls.

01/31/97 2400 Unit finishes month off-line.

UNITTwo:

01/01/97 0000 Unit starts month at 100% power, 855 MWe.

01/31/97 2400 Unit finishes month at 100% power, 860 MWe.

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e e Surry Monthly Operating Report No. 97-01 Page 10 of 16 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January, 1997 DCP 95-020 Design Change Package 11-26-96 (Safety Evaluation 95-152)

Design Change Package 95-020 adds biometric access capability to the plant security system. This system provides an alternate means of positively identifying personnel requesting access to the plant protected area. This system replaces the personal information number (PIN) system.

This design is an enhancement to the existing station security computer system. The station security system does not perform any safety-related functions nor does it support any safety-related equipment. No activities associated with this design change have a potential to affect any safety-related equipment. Therefore, an unreviewed safety question does not exist.

SE 95-154, Rev. 2 Safety Evaluation 1-06-97 Safety Evaluation 95-154 Rev. 2 was performed to delete Unit 2 operation with pressurizer spray control valve 2-RC-PCV-2455A maintained in a fully closed position.

The valve was repaired during the Unit 2 maintenance outage.

The Safety Evaluation and Operations Standing Order 95-001 were updated to reflect the change in status of the Unit 2 pressurizer spray control valve. The pressurizer spray control valve 2-RC-PCV-2455A is now operable. Therefore, an unreviewed safety question does not exist.

JCO 82-97-001 Justification For Continued Operation 1-10-97 (Safety Evaluation No.97-002)

Justification For Continued Operation S2-97-001 assessed the acceptability of placing the Unit 2 Letdown System in service to collect data on letdown line vibrations. Data collection was performed to determine the service life/limits of the letdown piping. The analysis of previous vibration data indicates that operation with the 'A' and 'C' letdown orifices in service with a 350 psig backpressure ensures the combined stress is within allowable limits for all operating and design basis conditions. The 'B' orifice shall not be placed in service because letdown pressure must be maintained above 350 psig to ensure the combined stress remains within allowable limits.

Based on the vibration data collected, it has been concluded that the socket welded joints downstream of the letdown lines have been stressed above yield stress. However, there is assurance of pressure boundary integrity during the period required for taking vibration data. Should a through wall or weld defect occur, it will result in a leak before break. A leak on this system will be sensed by the containment radiation monitoring system and can be quantified by performance of a Primary System Leak Rate calculation.

Additionally, the Letdown System can be isolated from the Reactor Coolant System.

Therefore, an unreviewed safety question does not exist.

DCP 95-003 Design Change Package 1-16-97 (Safety Evaluation 95-063)

Design Change Package 95-003 installed new fuel oil piping for the Emergency Diesel Generators and the Auxiliary Boiler with 2 1/2 inch seamless schedule 160 carbon steel pipes.

This design change only installed new fuel oil lines in the yard from the Fuel Oil House to the north of the Unit 2 alleyway. These new lines were not connected to the current Fuel Oil Transfer System. Therefore, an unreviewed safety question does not exist.

e e Surry Monthly Operating Report No. 97-01 Page 11 of 16 FACILITY CHANGES THAT DID Nor REQUIRE NRC APPROVAL MONTH/YEAR: January, 1997 FS 97-02 Updated Final Safety Analysis Report Change 1-23-97 (Safety Evaluation 97-006)

UFSAR Change Request 97-02 revises section 9.12.4, "Refueling Equipment," and Appendix 9B.1, "Heavy Loads Over Spent Fuel." Several sections of Appendix 9B.1 have been moved to Section 9.12.4 because they describe equipment that did not meet the definition of a heavy load. Other sections in Appendix 9B.1 have been updated to provide a better description of the equipment and its handling.

This UFSAR change is administrative and does not involve changes to equipment or software at the station. Therefore, an unreviewed safety question does not exist.

SE 97-009 Safety Evaluation 1-27-97 (Safety Evaluation No.97-009)

This Safety Evaluation assesses one train of the reactor vent system being out of service for greater than 30 days. The purpose of the reactor vent system is to remove gases or steam inside the reactor vessel following an accident, if required to prevent interruption of heat transfer. Only one train is required for venting in accordance with the Emergency Operating Procedures. The redundant train remains operable and capable of performing its safety function.

This condition meets the requirements of Technical Specifications and no additional surveillances are required. Therefore, an unreviewed safety question does not exist.

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e Surry Monthly Operating Report No. 97-01 Page 12 of 16 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January, 1997 GMP-001 General Maintenance Procedure 1-15-97 OP-4.18 Operating Procedure (Safety Evaluation No.97-005)

General Maintenance Procedure GMP-001, "Heavy Loads Rigging and Movement" and Operating Procedure OP-4.18, "Moving the Fuel Transfer Canal Door," provides instructions for the movement of the Surry Fuel Transfer Canal Door over the Spent Fuel Pool. Steps were added to restrict the height that the door may be lifted above the fuel and to specify that mounted insert components not be installed in any fuel assemblies in the load path.

With these restrictions in place, the current licensing basis as previously documented remains valid. Therefore, an unreviewed safety question does not exist.

O-TOP-CT-4078 Temporary Operating Procedure 1-23-97 (Safety Evaluation No.97-007)

Temporary Operating Procedure O-TOP-CT-4078, "Draining Containment Penetrations,"

was developed to provide instructions for partially draining six containment penetrations.

These penetrations have closed isolation valves on both sides. The draining of the penetrations was done as a precautionary measure due to the potential for overpressurizing an isolated containment penetration boundary. The overpressurization would result from expanding fluid due to rapid temperature increases during a Design Basis Accident.

Draining containment penetrations will be controlled by the Temporary Operating Procedure. This procedure addresses requirements for administrative control and control of radioactive fluids as outlined in Technical Specification 3.8 and Section 5.3 of SUADM-0-26. The penetrations are tested during Type C testing using gas (air) as a test medium.

Draining of the penetrations will place them in a condition similar to the tested condition.

Therefore, an unreviewed safety question does not exist.

1-AP-4.00 Abnormal Procedure 1-24-97 (Safety Evaluation No.97-008)

Abnormal Procedure 1-AP-4.00, "Nuclear Instrumentation Malfunction," was temporarily changed to allow repair of the source range nuclear instruments. This change provided compensatory actions to verify any personnel safety concerns associated with access to the containment are met. This is accomplished by eliminating precursors to accidents associated with positive reactivity additions during subcritical conditions.

Additionally, the count rate will be monitored by control room personnel using the Gamma-Metrics channel. If the count rate on both narrow range channels increases by 1/2 decade above its current reading, the personnel in containment will be notified to evacuate. With these compensatory actions in place, an unreviewed safety question does not exist.

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e e Surry Monthly Operating Report No. 97-01 Page 13 of 16 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January, 1997 1-ST-317 Special Tests 1-28-97 (Safety Evaluation 95-144)

Special Test 1-ST-317, Calibration of Steam and Feedwater Flow Transmitters At Power, will verify the initial scaling applied to the Main Feedwater flow transmitters as a result of replacement of the feedwater flow elements under DCP 94-55-1 and the current scaling of the Main Steam flow transmitters.

The performance of this special test does not impose any operation on the plant that has not been previously analyzed. The special test collects plant data from control room, P250 computer, local and reactor protection rack test points during normal power escalation. Therefore, an unreviewed safety question does not exist.

2-ST-315 Special Tests 1-28-97 (Safety Evaluation 95-088)

Special Test 2-ST-0315, Feedwater Flowrate Determination Using Chemical Tracer Method, will collect Main Steam and Feedwater System data for final verification of the scaling of these loops following core uprate. The scaling will be based on feedwater flowrate determination using a lithium nitrate chemical tracer. The CHEMTRAC flow test injects this tracer into the feedwater line drain valves and then samples down stream to determine the concentration.

The injection of the tracer will not severely impact secondary chemistry or affect the ability of operators to control and monitor the plant. The test procedure provides adequate verification of the temporary modification installation and removal. Therefore, an unreviewed safety question does not exist.

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e Surry Monthly Operating Report No. 97-01 Page 14 of 16 CHEMISTRY REPORT MONTH/YEAR: January, 1997 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avq. Max. Min. Avq.

Gross Radioactivity, µCi/ml 2.96E+O 9.37E-2 7.87E-1 4.30E-1 1.85E-1 2.55E-1 Suspended Solids, ppm Gross Tritium, µCi/ml 2.19E-1 1.15E-1 1.56E-1 2.78E-1 1.74E-1 2.27E-1 1131, µCi/ml 2.07E+O 5.44E-3 3.51E-1 3.31E4 3.58E-5 9.45E-5 1131;1133 0.26 0.23 0.25 0.13 0.06 0.09 Hydroqen, cc/kq 38.7 33.7 36.4 33.5 16.1 24.1 Lithium, ppm 1.30 0.93 1.11 2.34 1.85 2.18 Boron - 10, Porn* 124.3 12.7 61.3 191.3 176.0 184.1 Oxygen, (DO), ppm ~0.005 ~0.005 ~0.005 ~0.005 ~0.005 ~0.005 Chloride, ppm 0.002 <0.001 <0.001 0.009 0.003 0.004 pH at 25 degree Celsius 7.56 6.09 6.96 6.60 6.05 6.33 Boron - 10 = Total Boron x 0.196 Comments:

None

e e Surry Monthly Operating Report No. 97-01 Page 15 of 16 FUEL HANDLING UNITS1 &2 MONTH/YEAR: January, 1997 New or Spent New Fuel Number of New or Spent Fuel Shipment Shipment or Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Cask No. Received per Shipment Number Number Enrichment Cask Activity No Fuel Received or Stored During the Reporting Period

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  • Surry Monthly Operating Report No. 97-01 Page 16 of 16 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHIYEAR:JANUARY, 1997 None During the Reporting Period
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