ML18153C936

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Monthly Operating Repts for Feb 1992 for Surry Power Station Units 1 & 2.W/920313 Ltr
ML18153C936
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/29/1992
From: Negron M, Stwart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-169, NUDOCS 9203180243
Download: ML18153C936 (19)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261

  • March l3, 1992 U. S. Nuclear Regulatory Commission Serial No.92-169 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 February 1992.

Very truly yours,

,¢~~

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W . Stewart ~

Senior Vice President - Nuclear 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. 92-02 Approved:

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  • Surry Monthly Operating Report No. 92-02 Page 2 of 18 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 ........................................... 13 Tests and Experiments That Did Not Require NRG Approval ...................................................................... 15 Chemistry Report ............................................................................................................................. 16 Fuel Handling - Unit No. 1 ............................................................................................................: ...... 17 Fuel Handling - Unit No. 2 ................................................................................................................... 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 18

,,

- OPERATING DATA REPORT

  • Surry Monthly Operating Report No. 92-02 Page 3 of 18 Docket No.: 50-280 Date: 03-06-92 Completed By: M.A. Negron Telephone: (804) 365-2795
1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . February 1992
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 ................................... . 696.0 1440.0 168216.0
12. Number of Hours Reactor Was Critical ......... . 694.6 1288.0 109522.2
13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 3774.5
14. Hours Generator On-Line .......................... . 694.1 1271.8 107512.0
15. Unit Reserve Shutdown Hours.................... . 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... . 1475556.0 2727607.2 249844283.9
17. Gross Electrical Energy Generated (MWH) ... . 500535.0 919665.0 81434853.0
18. Net Electrical Energy Generated (MWH) ....... . 474146.0 871153.0 77245219.0
19. Unit Service Factor .................................. . 99.7% 88.3% 63.9%
20. Unit Availability Factor .............................. . 99.7% 88.3% 66.1%
21. Unit Capacity Factor (Using MDC Net).......... . 87.2% 77.5% 59.3%
22. Unit Capacity Factor (Using DER Net) .......... . 86.5% 76.8% 58.3%
23. Unit Forced Outage Rate ........................... . 0.0% 11.6% 19.2%
24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each):

Refueling - February 29, 1992, 64 days.

25. If Shut Down at End of Report Period Estimated Date of Start-up: May 3, 1992
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 92-02 Page 4of 1~

OPERATING DATA REPORT Docket No.: 50-281 Date: 03-06-92 Completed By: M.A. Negron Telephone: (804) 365-2795

1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . February 1992
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 .................................... 696.0 1440.0 165096.0
12. Number of Hours Reactor Was Critical .......... 696.0 1440.0 106648.1
13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 328.1
14. Hours Generator On-Line ........................... 696.0 1440.0 104900.9
15. Unit Reserve Shutdown Hours ..................... 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ...... 1640351.4 3451123.8 244329805.9
17. Gross Electrical Energy Generated (MWH) .... 548675.0 1155645.0 79589494.0
18. Net Electrical Energy Generated (MWH) ........ 521919.0 1099913.0 75463851.0
19. Unit Service Factor ................................... 100.0% 100.0% 63.5%
20. Unit Availability Factor ............................... 100.0% 100.0% 63.5%
21. Unit Capacity Factor (Using MDC Net) ........... 96.0% 97.8% 58.6%
22. Unit Capacity Factor (Using DER Net) ........... 95.2% 96.9% 58.0%
23. Unit Forced Outage Rate ............................ 0.0% 0.0% 15.2%
24. Shutdowns Schedule 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 e Surry Monthly Operating Report No. 92-02 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February 1992 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 03-06-92 Completed by: M. A. Negron Telephone: (804) 365-2795 (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 92-02-29 S 1.4 C 2 NIA NIA NIA Shutdown for scheduled refueling outage.

(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. 92-02 Page 6 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February 1992 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 03-06-92 Completed by: M. A. Negron Telephone: (804) 365-2795 (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 92-02-14 S 0 B 4 NIA SJ p Reduced unit power from 100%

to 59.5% to repair "B" Main Feedwater Pump Seals.

(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. 92-02 Page ?of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 03-06-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: February 1992 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 762 17 687 2 756 18 681 3 751 19 677 4 744 20 673 5 741 21 666 6 738 22 663 7 736 23 659 8 735 24 653 9 728 25 651 10 723 26 642 11 717 27 611 12 711 28 561 13 712 29 282 14 707 30 15 698 31 16 691 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 e Surry Monthly Operating Report No. 92-02 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 03-06-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: February 1992 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 777 17 683 2 778 18 684 3 778 19 683 4 777 20 703 5 777 21 779 6 777 22 778 7 776 23 777 8 778 24 780 9 779 25 777 10 779 26 778 11 780 27 779 12 779 28 779 13 779 29 779 14 776 30 15 458 31 16 641 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.

SUMMARY

OF OPERATING EXPERIENCE

  • Surry Monthly Operating Report No. 92-02 Page 9 of 18 MONTH/YEAR: February 1992 Listed below in 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 02-01-92 0000 This reporting period started with the Unit coasting down due to fuel depletion; 96.5%

power, 800 MWe.

02-27-92 1756 Started ramp down for scheduled Refueling Outage and performance of ST-300 (Feedwater Flow Measurement Testing); 81% power, 670 MWe.

02-29-92 2204 Unit off line.

2235 This reporting period ended with the Reactor manually tripped; Unit at Hot Shutdown.

UNIT TWO 02-01-92 0000 This reporting period started with the Unit operating at 100% power, 815 MWe.

02-14-92 2252 Started ramp down to repair "B" Main Feedwater Pump and to repair tube leaks on First Point Feedwater Heaters; 100% power, 815 MWe.

02-15-92 0913 Stopped ramp; 59.5% power, 480 MWe.

02-16-92 0230 Started ramp up after Feedwater Pump repairs were completed; 58% power, 470 MWe.

1218 Stopped ramp at 90% power, 730 MWe to continue with First Point Feedwater Heater repairs.

02-20-92 1933 Started ramp up after returning First Point Feedwater Heaters to service; 90% power, 740 MWe.

2020 Stopped ramp; 100% power, 820 MWe.

02-29-92 2400 This reporting period ended with the Unit operating at 100% power, 815 MWe.

e

  • Surry Monthly Operating Report No. 92-02 Page10of18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1992 DR S-92-0191 Deviation Report 02-07-92 (Safety Evaluation No.92-021)

This Deviation Report addresses a degraded flow condition between the Unit 2 charging pump 2-CH-P-1A and the charging pump seal coolers 2-CH-E-7A and 2-CH-E-78 resulting from a flow restriction caused by a deposit of a foreign substance in the cooler shell and the inlet and outlet lines.

An evaluation of this condition concluded that the charging pump seal design limits will not Ibe exceeded provided that the interruption of component cooling water to the normal letdown heat exchanger would not go undetected and prompt corrective action would be taken. Since the volume control tank high temperature annunciation provides early detection capability and the applicable response procedures ensure corrective actions are taken, the degraded flow condition is considered to have no adverse effect on the performance and reliability of the charging pumps. Therefore, an unreviewed safety question is not created.

JCO C-92-001 Justification For Continued Operation 02-13-92 (Safety Evaluation No.92-023)

This Justification For Continued Operation (JCO) assessed Appendix "R" compliance relative to nonfunctional fire barrier walls located between the Unit 1 and 2 cable vaults and the auxiliary building and the wall separating the service building from the auxiliary building.

The JCO implemented compensatory measures in accordance with the Technical Specifications by posting a fire watch. In the event of a fire, this action ensures early detection and initiation of additional fire suppression efforts to supplement the automatic suppression and detection systems in these areas.

Therefore, an unreviewed safety question is not created.

FS 90-45 UFSAR Change 02-20-92 (Safety Evaluation 92-026)

The Updated Final Safety Analysis Report (UFSAR) Section 1.2.4, ':Reactor And Station Controls," was revised to be consistent with the automatic control system setpoint value specified in WCAP-7649, "Setpoint Study for Virginia Electric and Power Company Surry Units 1 and 2."

This change was editorial in nature. No physical changes to the station were made. Therefore, an unreviewed safety question was not created.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

  • Surry Monthly Operating Report No. 92-02 Page 11 of 18 MONTH/YEAR: February 1992

[continued]

FS 90-39 UFSAR Change 02-20-92 (Safety Evaluation 92-027)

The Updated Final Safety Analysis Report (UFSAR) Section 1.2.3, "Nuclear Steam Supply System," was revised to reflect the change from an "out-in" to a low leakage type of fuel management.

An evaluation of this change was performed and it was determined that the reload design meets the criteria and limits for the accidents in the UFSAR.

Therefore, an unreviewed safety question was not created.

TSR 92-011 Temporary Shielding Request 02-20-92 (Safety Evaluation 92-028)

This Temporary Shielding Request installs temporary lead shielding on the aerated drains system and reactor purification system lines in the Unit 1 containment basement to reduce the radiation dose received by personnel while performing work in the area during a refueling outage.

Installation of the shielding while the subject lines remain operable was determined to be acceptable through the performance of a seismic piping analysis. The shielding will not adversely affect the design functions of the affected systems and will be removed prior to leaving cold shutdown.

Therefore, an unreviewed safety question is not created.

EWR 90-148 Engineering Work Request 02-24-92 (Safety Evaluation No.90-182)

This Engineering Work Request added a power supply interlock between radiation monitor sample pump VG-109 and the health physics (HP) accountability sample pump for the Victoreen normal range radiation monitors 1-RM-VG-109 and 1-RM-VG-110.

The interlock will ensure that the HP sample pump will stop whenever sample pump VG-109 stops, thereby ensuring an isokinetic effluent sample at the alternate Kaman radiation monitors, 1-RM-VG-131-1 and 1-RM-VG-131-2.

This nonsafety-related modification enhances the availability of radiation monitoring during normal and accident conditions. Safety-related systems are not affected. Therefore, an unreviewed safety question is not created.

e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

  • Surry Monthly Operating Report No. 92-02 Page 12 of 18 MONTH/YEAR: February 1992

[continued]

TSR 92-029 Temporary Shielding Request 02-25-92 TSR 92-030 (Safety Evaluation 92-031)

TSR 92-031 These Temporary Shielding Requests install temporary lead shielding on the Unit 1 reactor coolant loop piping and valves (including the loop stop valve by-pass line and valve) to reduce the radiation dose received by personnel while removing the resistance temperature device by-pass lines and performing other work in the area.

Installation of the shielding while the subject lines remain "operable" was determined to be acceptable through the performance of a seismic piping analysis, provided the pressure and temperature do not exceed 385 psi and 140° F. The shielding will not adversely affect the design functions of the affected systems and will be removed prior to unit heat-up. Therefore, an unreviewed safety question is not created.

TM S1-92-07 Temporary Modification 02-26-92 (Safety Evaluation No.92-032)

This Temporary Modification (TM) provides an auxiliary security diesel generator to supply back-up security lighting while the the normal security diesel generator is removed from service for periodic maintenance.

The auxiliary diesel generator will be tested prior to being placed in service and fuel supply provisions will be made. The normal security diesel generator will also be tested prior to returning it to service. Therefore, an unreviewed safety question is not created.

  • Surry Monthly Operating Report No. 92-02 Page 13 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1992 0/1 /2-0PT-EG-002 - Operations Periodic Test Procedures 12-02-91 0/1 /2-0PT-EG-004 (Safety Evaluation No.91-254) 0/1 /2-0PT-EG-6.3 Operations Periodic Test Procedures 0/1/2-0PT-EG-002, "Emergency Diesel Generator Monthly Fast Start Exercise Test," 0/1 /2-0PT-EG-004, "Emergency Diesel Generator Quarterly Fast Start Exercise Test," and 0/1/2-0PT-EG-6.3, "Emergency Diesel Generator Starting Sequence Test," were revised to install temporary electrical jumpers to enable the initiation/simulation of automatic start signals to the emergency diesel generators (EOG).

The jumpers will be installed only long enough to initiate a manual fast start of the EOG, as required by the Technical Specifications. The EOG will be considered inoperable upon initiation of the "jacking over" sequence and appropriate TS limiting conditions for operation will be entered. Once started, the EOG can be loaded to the bus, as required. Therefore, an unreviewed safety question is not created.

1-PT-18.1 Operations Periodic Test Procedure 02-25-92 (Safety Evaluation No.92-029)

Unit 1 Operations Periodic Test Procedure 1-PT-18.1, "Low Head Safety Injection Pump Test," was revised (temporary change) to permit the use of temporary transmitters to enable the measurement of low head safety injection pump pressure during the few seconds following pump start.

The temporary transmitters are safety-related and will not affect the operation of the subject pump. Therefore, an unreviewed safety question is not created.

2-PT-18.1 Operations Periodic Test Procedure 02-25-92 (Safety Evaluation No.92-030)

Unit 2 Operations Periodic Test Procedure 2-PT-18.1, "Low Head Safety Injection Pump Test," was revised (temporary change) to permit the use of temporary transmitters to enable the measurement of low head safety injection pump pressure during the few seconds following pump start.

The temporary transmitters are safety-related and will not affect the operation of the subject pump. Therefore, an unreviewed safety question is not created.

-

  • Surry Monthly Operating Report No. 92-02 Page 14 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1992

[continued]

1-0PT-22-001 Operations Periodic Test Procedures 02-27-92 1-0PT-22-002 (Safety Evaluation No.92-033)

Unit 1 Operations Periodic Test Procedures 1-0PT-22-001, "ESF Actuation With Delayed Undervoltage 1H Bus," and 1-0PT-22-002, "ESF Actuation With Delayed Undervoltage 1J Bus," were revised to temporarily lift electrical leads to allow verification of safety injection (SI) and trip breaker signals that trip the turbine and to allow testing of the SI signals which initiate feedwater isolation.

The unit will be at cold shutdown during the performance of this testing. The temporary modifications will be controlled by the subject procedures (which require double verification for installation and removal) and do not affect the operation of the residual heat removal system. Therefore, an unreviewed safety question is not created.

GMP-M-161 General Maintenance Procedure 02-28-92 (Safety Evaluation No.92-035)

General Maintenance Procedure GMP-M-161, "Installation Of Recirculation Spray Heat Exchanger Service Water Flow Test Equipment," was developed to provide instructions for installing temporary flow venturis and loop manifold root valves on the service water system to support the performance of special test 1-ST-299, "Recirculation Spray Heat Exchanger Service Water Flow Test."

The temporary test equipment will be installed while the unit is in a condition during which service flow to the recirculation spray heat exchangers is not required and will be removed prior to unit startup. This change will not adversely affect the piping and the pressure boundary integrity and will .be verified prior to conducting the test. Therefore, an unreviewed safety question is not created.

  • Surry Monthly Operating Report No. 92-02 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February 1992 None During This Reporting Period.

CHEMISTRY REPORT

  • Surry Monthly Operating Report No. 92-02 Page 16 of 18 MONTH/YEAR: February 1992 Unit No. 1 Unit No. 2 Primarv Coolant Analysis Max. Min. Avg. Max. Min. Avg.

Gross Radioact., µCi/ml 1.04E+O 4.20E-1 7.02E-1 2.87E-1 1.06E-1 1.88E-1 Suspended Solids, oom 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, µCi/ml 1.24E-1 9.84E-2 1.08E-1 4.16E-1 3.49E-1 3.84E-1 1131, LLCi/ml 2.90E-3 1.53E-3 2.18E-3 4.93E-4 1.90E-4 3.20E-4 113111133 0.16 0.07 0.10 0.18 0.06 0.10 Hvdroaen, cc/ka 34.7 21.7 26.9 41.4 25.3 30.9 Lithium, oom 1.28 0.61 0.78 2.35 2.05 2.20 Boron - 10, oom* 10.8 0.2 0.8 218.7 190.1 199.8 OxvQen, (DO), oom <0.005 <0.005 <0.005 <0.005 <0.005 <0.005 Chloride, oom 0.004 <0.001 0.001 0.003 <0.001 0.002 pH at 25 demees Celsius 9.70 8.37 9.22 6.58 6.43 6.51 Boron - 10 = Total Boron x 0.196 No Comments.

  • FUEL HANDLING
  • Surry Monthly Operating Report No. 92-02 Page 17of 18 UNITS 1 & 2 MONTH/YEAR: February 1992 New or Spent Number for 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 Stored or Received in February, 1992
  • Surry Monthly Operating Report No. 92-02 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: February 1992 None During This Reporting Period.
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