ML18153A847

Monthly Operating Repts for May 1995 for Surry Power Station Units 1 & 2.W/950612 Ltr

ML18153A847
Person / Time
Site:	Surry
Issue date:	05/31/1995
From:	Bowling M, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-289, NUDOCS 9506210207
Download: ML18153A847 (18)

Text

... e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 12, 1995 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.95-289 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 May 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 9506210207 950531 PDR ADOCK 05000280 R PDR

• VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 95-05 Approved:

Station Manager f,-l"L"" j£ Date TABLE OF CONTENTS Section tlurry Monthly Operating Report No. 95-05 Page 2 of 17 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 N RC Approval ...............................................................................

10 Procedure or Method of Operation Changes That Did Not Require N RC Approval ...........................................

13 Tests and Experiments That Did Not Require NRG 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 OPERATING DATA REPORT -urry Monthly Operating Report No. 95-05 Page 3 of 17 Docket No.: Date: Completed By: 50-280 06-01-95 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 1 May, 1995 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 ..........................

744.0 3623.0 196703.0 12. Number of Hours Reactor Was Critical ..........

744.8 3443.7 133913.4 13. Reactor Reserve Shutdown Hours ...............

0 0 3774.5 14. Hours Generator On-Line ...........................

744.0 3409.2 131650.2 15. Unit Reserve Shutdown Hours .....................

0 0 3736.2 16, Gross Thermal Energy Generated (MWH) ...... 1802571.0 8238862.5 306692601.

7 17. Gross Electrical Energy Generated (MWH) .... 604865.0 2773570.0 100387 403. 0 18. Net Electrical Energy Generated (MWH) ........ 582138.0 2675084.0 95384107.0

19. Unit Service Factor ...................................

100.0% 94.1% 66.9% 20. Unit Availability Factor ...............................

100.0% 94.1% 68.8% 21. Unit Capacity Factor (Using MDC Net) ...........

100.2% 94.5% 62.5% 22. Unit Capacity Factor (Using DER Net) ...........

99.3% 93.7% 61.5% 23. Unit Forced Outage Rate ............................

0.0% 5.9% 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):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED

• -urry Monthly Operating Report No. 95-05 Page 4 of 17 OPERATING DATA REPORT 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 May, 1995 2441 847.5 788 820 781 Docket No.: Date: Completed By: Telephone:

50-281 06-01-95 D. Mason (804) 365-2459 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 3623.0 193583.0 12. Number of Hours Reactor Was Critical ..........

629.9 2433.2 130770.0 13. Reactor Reserve Shutdown Hours ...............

0 0 328.1 14. Hours Generator On-Line ...........................

597.5 2368.8 128835.9 15. Unit Reserve Shutdown Hours .....................

0 0 0 16. Gross Thermal Energy Generated (MWH) ...... 1443568.4 5562394.5 300830858.8

17. Gross Electrical Energy Generated (MWH) .... 478845.0 1857235.0 98299529.0

18. Net Electrical Energy Generated (MWH) ........ 461814.0 1790389.0 93383425.0

19. Unit Service Factor ...................................

80.3% 65.4% 66.6% 20. Unit Availability Factor ...............................

80.3% 65.4% 66.6% 21. Unit Capacity Factor (Using MDC Net) ...........

79.5% 63.3% 61.9% 22. Unit Capacity Factor (Using DER Net) ...........

78.8% 62.7% 61.2% 23. Unit Forced Outage Rate ............................

19.7% 5.8% 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):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED

• -urry Monthly Operating Report No. 95-05 Page 5 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) REPORT MONTH: May, 1995 (1) (2) (3) (4) (5) Method Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 06-01-95 Completed by: Craig Olsen Telephone:

(804)365-2155 Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence (1) F: Forced S: Scheduled (4) (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)

Exhibit G -Instructions for Preparation of Data Entry-Sheets for Licensee Event Report (LER) File (NUREG 0161) (3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)

(5) Exhibit 1 -Same Source.

• -urry Monthly Operating Report No. 95-05 Page 6 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) (1) Duration Date Type Hours 950511 F 36.7 950521 F 109.9 (1) F: Forced REPORT MONTH: May, 1995 (2) (3) (4) Method of LER System Reason Shutting No. Code Down Rx A 2 2-95-AA 004-00 A (2) REASON: 2 2-95-005-00 AA S: Scheduled A -Equipment Failure (Explain)

B Maintenance or Test C Refueling D Regulatory Restriction (5) Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 06-01-95 Completed by: Craig Olsen Telephone:

(804) 365-2155 Component Cause & Corrective Action to Code Prevent Recurrence RCT Manual reactor trip due to control bank 8, group 2 control rods dropping into core. RCT Manual reactor trip due to control bank A, group 2 control rods dropping into core. (3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NU REG 0161) (5) Exhibit 1 -Same Source.

• e Surry Monthly Operating Report No. 95-05 Page 7 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 06-06-95 Completed by: Steve Hall Telephone:

365-2793 MONTH: May, 1995 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 782 17 789 2 784 18 788 3 784 19 788 4 783 20 788 5 778 21 788 6 790 22 788 7 794 23 787 8 796 24 787 9 794 25 785 10 794 26 786 11 792 27 788 12 770 28 770 13 780 29 662 14 791 30 785 15 790 31 787 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.

MONTH: May, 1995 Day 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS

~urry Monthly Operating Report No. 95-05 Page 8 of 17 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe-Net) Day 787 17 788 18 788 19 787 20 786 21 786 22 785 23 785 24 785 25 785 26 734 '27 0 28 305 29 783 30 781 31 781 Docket No.: 50-281 Unit.Name:

Surry Unit 2 Date: 06-06-95 Completed by: Steve Hall Telephone:

365-2793 Average Daily Power Level (MWe-Net) 781 778 779 773 390 0 0 0 0 610 777 779 779 776 773 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 -. Surry Monthly Operating Report

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR:

May, 1995 No. 95-05 Page 9 of 17 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: 05/01/95 05/06/95 05/28/95 05/29/95 05/31/95 UNIT Two: 05/01/95 05/11/95 05/12/95 05/13/95 05/21/95 05/25/95 05/26/95 05/31/95 0000 The reporting period began with the unit operating at 99% power, 810 MWe. 1012 Started power increase.

1136 Unit operating at 100% power, 825 MWe. 2007 Started power reduction for removal of the high pressure heater drain pump 1A for maintenance.

2213 Stopped power reduction at 84% power, 650 MWe. 1829 Started power increase.

2016 Unit operating at 100% power, 825 MWe. 2400 The reporting period_ ended with the unit operating at 100% power, 825 MWe. 0000 The reporting period began with the unit operating at 100% power, 820 MWe. 2231 Manually tripped reactor due to control bank B, group 2 control rods dropping into the reactor core. 2248 Reactor Critical.

1108 Generator on line. Started power increase.

2206 Unit operating at 100% power, 810 MWe. 1223 Manually tripped reactor due to control bank A, group 2 control rods dropping into the reactor core. 0611 Reactor Critical.

0219 Generator on line. Stated power increase.

1136 Unit operating at 100% power, 800 MWe 2400 The reporting period ended with the unit operating at 100% power, 810 MWe.

DC-85-07-3 DC-88-23-1 DCP 90-12-2 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

May, 1995 Design Change Package e Surry Monthly Operating Report No. 95-05 Page 10 of 17 5-04-95 Design Change Package DC-85-07-3 installed a comprehensive on-line steam generator secondary side water chemistry monitoring system. The system will provide continuous analytical information from four main sample locations in the secondary system (final feedwater, steam generator blowdown -each steam generator, and condensate) and from two supplemental locations (make-up effluent and heater/moisture separator reheater drains). These modifications do not change the operation or capability of equipment important to safety. The new piping and tubing installation does not affect operations of existing equipment.

This design change does not modify the basis of any Technical Specification.

Therefore, an unreviewed safety question was not created. Design Change Package (Safety Evaluation No.90-158) 5-24-95 Design Change Package DC-88-23-1 installed new indicator and recorder scales on the main control boards and auxiliary shutdown panel. Three pressure transmitters and two flow indicators were replaced.

Labels and tactile changes were installed on reverse acting controllers.

Magnetic amplifiers in a non-safety related process rack were replaced with comparators and relays to perform the same control functions.

These Unit 1 modifications, which enhance operator ability to read and interpret data, affect indication and control only. The operation or performance of safety-related equipment or availability of safety-related power sources is not affected.

Therefore, an unreviewed safety question does not exist. Design Change Package (Safety Evaluation No.92-211) 5-17-95 Design Change Package 90-12-2 replaced service water flow transmitters, associated power supplies, and temperature elements in the discharge lines from the recirculation spray heat exchangers.

These changes were made for compliance with the requirements of RG-1.97 for Type D Category 2 variables.

This Design Change Package also replaced inlet service water flow transmitters and degraded cable. This modification was implemented to enhance the operators' ability to perform accident monitoring, assess the status of the plant, and take appropriate mitigating actions following an event. The change does not impact the operation or performance of safety-related equipment and does not affect the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

DC-85-16-3 SE 95-052 TM S2-95-08 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

May, 1995 Design Change Package ~urry Monthly Operating Report No. 95-05 Page 11 of 17 5-30-95 Design Change Package 85-16-3 performed the demolition of the existing spent resin catch tank system. A newly designed replacement system was also installed.

The new system will permit flexibility in handling of spent radioactive resins in preparation for shipment to a burial facility.

These non-safety related modifications do not affect the safe operation of either unit. The spent resin system is not required to prevent or mitigate the consequences of an accident.

The Technical Specifications do not provide any limiting conditions for operation or surveillance requirements for the spent resin systems. Therefore, an unreviewed safety question does not exist. Safety Evaluation 5-04-95 Safety Evaluation 95-052 evaluated the substitution of manual operator actions for the inoperable automatic safety functions of the field forcing and over excitation protection features for the Main Generator.

All other automatic safety functions remained operable.

These controls were temporary and in effect until repairs were completed.

The evaluation determined that Main Generator malfunctions are not initiating events for any of the accident functions described in the Safety Analysis Report. The evaluation also concluded that failure of the generator or its protective features will not prevent any other system's protective features from being actuated.

Therefore, an unreviewed safety question does not exist. Temporary Modification (Safety Evaluation No. 95-055A) 5-25-95 Temporary Modification (TM) S2-95-08 installed a temporary strainer and piping in the generator air side Hydrogen Seal Oil system to perform a partial flush of the system in order to remove debris and restore pressure control function reliability of the seal oil pump. The Hydrogen Seal Oil system is non-safety related and has no interface with related systems. This system continues to operate within existing design parameters.

Therefore, an unreviewed safety question did not exist.

TM 81-95-05 FS 95-13 TM 82-95-09 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

May, 1995 Temporary Modification (Safety Evaluation No.95-056) tlurry Monthly Operating Report No. 95-05 Page 12 of 17 5-25-95 Temporary Modification

{TM) 81-95-05 installed stand alone spot coolers to provide air cooling for each of the eight rod control power cabinets.

Additional cooling will prolong the life of the printed circuit boards and decrease the probability of equipment malfunction.

Should the temporary spot coolers fail, the cabinet cooling would revert to the previously existing natural circulation.

The operation of the rod control system is not affected and the control rod remain trippable.

Therefore, an unreviewed safety question does not exist. Updated Final Safety Analysis Report Change (Safety Evaluation No.95-057) 5-25-95 UFSAR Change 95-13 deleted incorrect statements in Chapter 6, Engineering Safeguards, Section 6.2, Safety Injection, Subsection 6.2.4.1.4, regarding the application of the lnservice Inspection

{ISi) and lnservice Testing (1ST) Programs for the Safety Injection and Recirculation Spray Systems. The change also added paragraphs in Subsections 6.2.4.2, 6.3.1.5.1, and 6.3.1.5.2 to correctly describe the ISi and 1ST Program requirements for the Safety Injection System, Containment Spray System, and Recirculation Spray System. This change was made to remove statements in UFSAR Chapter 6 that are incomplete or inaccurate regarding the ASME Section XI 181/IST Program and add statements that accurately reflect the implementation of this program. This change involves administrative corrections and has no material impact on plant equipment, operation, inspection, or testing. Therefore, an unreviewed safety question does not exist. Temporary Modification (Safety Evaluation No.95-058) 5-30-95 Temporary Modification (TM) 82-95-09 installed a jumper to defeat the high bearing temperature protective trip for the chilled water refrigeration unit, 2-CD-REF-1.

This action was taken to prevent unnecessary trippng of the chiller due to a defective bearing temperature detector.

Chiller bearing temperatures will be monitored.

This mechanical chiller is not a related component.

It neither impacts the operation of equipment important to safety nor is it used to mitigate the consequences of an accident.

Containment temperature and pressure limits will continue to be adhered to according to the provisions of Technical Specification 3.8. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

May, 1995 None During the Reporting Period No. 95-05 Page 13 of 17 e Surry Monthly Operating Report No. 95-05 Page 14 of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

May, 1995 None During the Reporting Period CHEMISTRY REPORT MONTH/YEAR:

May, 1995 Unit No. 1 Primarv Coolant Analysis Max. Min. Ava. Gross Radioactivity, µ.Ci/ml 3.48E-1 2.18E-1 2.82E-1 Suspended Solids, ppm 50.10 50.10 50.10 Gross Tritium, µ.Ci/ml 1.53E-1 1.02E-1 1.27E-1 1131, µ.Ci/ml 7.11 E-4 4.30E-4 6.10E-4 113111133 0.08 0.06 0.07 Hydroi:ien, cc/kg 42.4 32.1 35.6 Lithium, ppm 2.23 1.69 1.92 Boron -10, oom* 59.0 38.4 47.9 Oxygen, (DO), ppm 50.005 50.005 50.005 Chloride, ppm 0.003 50.001 0.002 pH at 25 dei:iree Celsius 7.44 7.28 7.34

• Boron -1 O = Total Boron x 0.196 Comments:

None e . Surry Monthly Operating Report Unit No. 2 Max. Min. 1.99E-1 5.80E-3 50.10 50.10 4.04E-1 2.14E-1 1.60E-4 3.00E-5 0.09 0.05 44.1 33.7 2.60 1.74 308.3 196.4 50.005 50.005 0.009 0.003 6.72 6.30 No. 95-05 Page 15 of 17 Ava. 1.35E-2 50.10 3.09E-1 1.03E-4 0.07 36.8 2.17 235.1 50.005 0.005 6.59 New or Spent Fuel Shipment Date Stored or Number Received FUEL HANDLING UNITS 1 & 2 MONTH/YEAR:

May, 1995 Number of Assemblies per Shipment Assembly Number ANSI Number e Surry Monthly Operating Report Initial Enrichment No. 95-05 Page 16 of 17 New or Spent Fuel Shipping Cask Activity No Fuel Received or Stored During the Reporting Period

.,. ,. e Surry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR:

May, 1995 None During the Reporting Period No. 95-05 Page 17 of 17