ML18153B073

Monthly Operating Repts for Aug 1993 for Surry Power Station Units 1 & 2.W/940912 Ltr

ML18153B073
Person / Time
Site:	Surry
Issue date:	08/31/1994
From:	Bowling M, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-543, NUDOCS 9409220130
Download: ML18153B073 (18)

Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 12, 1994 U. S. Nuclear Regulatory Commission Serial No.94-543 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 August 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 (r. ("*, n -.J t, I*')

(~ t.> (j ..J~ '-.1: fS 9409220130 940831

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 94-08 Approved:

~JG(LpStation Manager "i'-'1-~4-Date

e Surry Monthly Operating Report No. 94-08 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 ............................................................................... 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 12 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

e Surry Monthly Operating Report No. 94-08 Page 3 of 17 OPERATIN~ DATA REPORT Docket No.: 50-280 Date: 08-02-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 1

2. Reporting Period: ......................................... . August, 1994

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 Period .......................... 744.0 5831.0 190151.0

12. Number of Hours Reactor Was Critical .......... 744.0 4329.7 128136.9

13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5

14. Hours Generator On-Line ........................... 744.0 4292.5 125971.5

15. Unit Reserve Shutdown Hours..................... 0 0 3736.2

16. Gross Thermal Energy Generated (MWH) ...... 1810187.0 9877717.7 293045462.8

17. Gross Electrical Energy Generated (MWH) .... 592400.0 3280040.0 95819588.0

18. Net Electrical Energy Generated (MWH) ........ 570048.0 3153216.0 90980317.0

19. Unit Service Factor ................................... 100.0% 73.6% 66.2%

20. Unit Availability Factor ............................... 100.0% 73.6% 68.2%

21. Unit Capacity Factor (Using MDC Net) ........... 98.1% 69.2% 61.7%

22. Unit Capacity Factor (Using DER Net) ........... 97.2% 68.6% 60.7%

23. Unit Forced Outage Rate ............................ 0.0% 0.6% 17.0%

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

- e Surry Monthly Operating Report No. 94-08 Page 4of 17 OPERATING DATA REPORT Docket No.: 50-281 Date: 08-02-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 2

2. Reporting Period: ........................................ .. August, 1994

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 .......................... 744.0 5831.0 187031.0

12. Number of Hours Reactor Was Critical .......... 744.0 5332.2 125408.5

13. Reactor Reserve Shutdown Hours ............... 0 0 328.1

14. Hours Generator On-Line ........................... 744.0 5322.5 123538.1

15. Unit Reserve Shutdown Hours ..................... 0 0 0

16. Gross Thermal Energy Generated (MWH) ...... 1804211.4 12450286.0 288126028.4

17. Gross Electrical Energy Generated (MWH) .... 582250.0 4129300.0 94074924.0

18. Net Electrical Energy Generated (MWH) ........ 561030.0 3977060.0 89309130.0

19. Unit Service Factor ................................... 100.0% 91.3% 66.1%

20. Unit Availability Factor ............................... 100.0% 91.3% 66.1%

21. Unit Capacity Factor (Using MDC Net) ........... 96.6% 87.3% 61.2%

22. Unit Capacity Factor (Using DER Net) ........... 95.7% 86.6% 60.6%

23. Unit Forced Outage Rate ............................ 0% 0% 13.6%

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 ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 94-08 Page 5 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: August, 1994 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-03-94 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 - Oth~r (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. 94-08 Page 6 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: August, 1994 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-03-94 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 8128194 S NIA B NIA NIA SI COND Unit power reduced to 75% to maintain condenser vacuum while cleaning water boxes.

(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. 94-08 Page ?of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: August, 1994 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe-Net) 769 17 772 2 768 18 770 3 765 19 770 4 763 20 768 5 765 21 769 6 772 22 771 7 702 23 773 8 768 24 775 9 774 25 773 10 772 26 772 11 771 27 769 12 766 28 767 13 750 29 767 14 759 30 767 15 767 31 767 16 772 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 .

Surry Monthly Operating Report No. 94-08 Page 8 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: August, 1994 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 761 17 759 2 760 18 755 3 756 19 753 4 755 20 756 5 758 21 752 6 740 22 754 7 773 23 761 8 769 24 762 9 768 25 746 10 768 26 744 11 765 27 762 12 763 28 700 13 765 29 678 14 763 30 751 15 760 31 756 16 761 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. 94-08 Page 9 of 17

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: August, 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.

UNJI ONE:

08/01/94 0000 The reporting period began with the unit operating at 100% power, 820 MWe.

08/07/94 0331 Started power reduction to maintain condenser vacuum while cleaning water boxes.

0350 Stopped power reduction at 95%, 715 MWe.

1459 Started power reduction to perform Operations Surveillance Test, 1-0SP-TM-001, "Turbine Inlet Valve Freedom Test."

1714 Stopped power reduction at 85%, 685 MWe.

2253 Started power increase following completion of 1-0SP-TM-001.

2335 Stopped power increase at 95%, 760 MWe.

08/08/94 0330 Started power increase.

0350 Stopped power increase at 100%, 800 MWe.

08/13/94 0851 Started power reduction to perform 1-0SP-TM-001.

0952 Stopped power reduction at 85%, 680 MWe.

1110 Started power increase following completion of 1-0SP-TM-001.

1213 Stopped power increase at 100%, 800 MWe.

08/31/94 2400 The reporting period ended with the unit operating at 100% power, 800 MWe.

UNJTTwo:

08/01/94 0000 The reporting period began with the unit operating at 100% power, 815 MWe 08/28/94 0528 Started power reduction to maintain condenser vacuum while cleaning water boxes.

0700 Stopped power reduction at 75%, 585 MWe.

1143 Started power increase.

1315 Stopped power increase at 100%, 800 MWe.

08/31/94 2400 The reporting period ended with the unit operating at 100% power, 800 MWe.

e Surry Monthly Operating Report No. 94-08 Page 10 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1994 SE 94-147 Safety Evaluation 08-01-94 Safety Evaluation 94-147 was performed to evaluate the installation of a temporary piping and hose system to transfer liquid waste from temporary storage tanks at the Radiological Controlled Area yard to the Surry Radwaste Facility Liquid Waste System. The liquid waste was generated during the June, 1994 Unit 2 Steam Generator Chemical Cleaning outage.

A spill control plan and procedures, in conjunction with dikes and berms to contain non-isolable leaks from the temporary storage tanks and piping, are in place to ensure compliance with effluent Technical Specifications. Therefore, an unreviewed safety question does not exist.

WO 295441/01 Work Order 08-10-94 (Safety Evaluation No.94-153)

Work Order 295441/01 performed an on-line temporary leak-seal repair of Unit 1 auxiliary feedwater pump steam header drain valve, 1-MS-181. The repair was implemented in accordance with Mechanical Corrective Maintenance procedure O-MCM-1918-01, "On-line Leak Repairs."

. The subject valve, which is normally closed, was sealed in the closed position. The leak-seal repair did not affect the structural integrity of the valve or the operation of the main steam system. Therefore, an unreviewed safety question does not exist.

DCP 93-052 Design Change Package 08-12-94 (Safety Evaluation No.93-194)

Design Change Package 93-052 installed structural reinforcement to the safety-related Unit 1 and 2 equipment hatch platforms and added a protective coating to the below ground portions of the platforms.

The modifications were implemented to enhance the ability of the platforms and missile shields to perform their safety-related functions. The Technical Specifications margin of safety was not reduced. Therefore, an unreviewed safety question does not exist.

TM S2-94-14 Temporary Modification 08-23-94 (Safety Evaluation No.94-161)

Temporary Modification S2-94-14 installed electrical jumpers to bypass test switch 2-SI-CS-LC-484-TB on the Unit 2 Safety Injection (SI) System Train "B" circuitry to allow the switch to be replaced without rendering the circuits inoperable.

SI System Train "A" was not affected by this activity and both trains remained capable of operating as designed. Double verification of jumper installation/removal and post-maintenance testing were performed. Therefore, an unreviewed safety question did not exist.

e Surry Monthly Operating Report No. 94-08 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1994 EWR 91-108 Engineering Work Request 08-24-94 (Safety Evaluation No.92-049)

Engineering Work Request 91-108 replaced the existing emergency diesel generator (EOG) canister type fuel oil filter assemblies and associated piping/tubing with spin-on filter assemblies and tubing.

The modification was implemented to facilitate the performance of maintenance, improve spare parts acquisition, and increase the reliability of the fuel oil system and the availability of the EOGs. The functional requirements and performance of the EOG fuel oil system were not changed. Therefore, an unreviewed safety question does not exist.

• TM S1-94-34 Temporary Modification 08-24-94 (Safety Evaluation No.94-163)

Temporary Modification (TM) S1-94-34 provided an alternate source of cooling water to the Unit 1 condensate polishing compressor cooling towers to permit continued cooling tower operation while maintenance was being performed.

The modification was made to nonsafety-related equipment and did not affect accident analyses or the margin of safety as defined by the Technical Specifications and Updated Final Safety Analysis Report (UFSAR). Therefore, an unreviewed safety question did not exist.

e Surry Monthly Operating Report No. 94-08 Page 12 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1994 FS94-014 Updated Final Safety Analysis Report Change 08-02-94 (Safety Evaluation No.94-148)

UFSAR Change 94-014 incorporated the Operational Quality Assurance (QA) Program into Chapter 17 of the UFSAR and deleted the sections describing the QA programs during the construction and preoperational phases.

The Operational QA Program has been approved by the NRG and does not impact the margin of safety as described in the Safety Analysis documents. The changes were administrative in nature and did not involve any physical changes to plant equipment.

Therefore, an unreviewed safety question does not exist.

SE 94-149 Safety Evaluation 08-02-94 Safety Evaluation 94-149 was performed to support the application of the Statistical DNBR Evaluation Methodology to the Locked Rotor Accident analysis and to implement the resulting revised analysis into Surry's design basis. This change was implemented to acquire reload core design and analysis margin.

The Statistical DNBR Evaluation Methodology is an NRC approved methodology for considering the impact of key DNBR analysis parameter uncertainties under thermal/hydraulic conditions such as those experienced during a Locked Rotor accident.

The evaluation concluded that the margin of safety is not reduced by the application of the Statistical DNBR Evaluation Methodology. Therefore, an unreviewed safety question does not exist.

2-CAL-504 Calibration Procedure 08-15-94 (Safety Evaluation No.93-182, Revision 1)

Calibration Procedure 2-CAL-504, "T-2-433-2 RCS Hot Leg Temperature - Fire Protection Cabinet," was revised to provide instructions for calibrating the Unit 2 reactor coolant system (RCS) "C" loop wide range temperature indication Appendix R element, 2-RC-TE-2433-2. The procedure revision was implemented to reflect the installation of a temporary modification on 2-RC-TE-2433-2.

Implementation of the revised procedure ensured the accuracy of the subject temperature indicator, providing control room operators with the correct RCS temperature. Therefore, an unreviewed safety question does not exist.

O-ECM-1404-03 Electrical Corrective Maintenance Procedure 08-17-94 (Safety Evaluation No.94-158)

Electrical Corrective Maintenance Procedure O-ECM-1404-03, "4160 Volt Motor Maintenance," was developed to provide instructions for the installation of temporary modifications to facilitate an uncoupled test run of the low pressure heater drain pump motor during post-maintenance testing.

Implementation of this procedure will not negatively impact the nonsafety-related low pressure heater drain pumps and will not affect the operation of the Feedwater System.

Therefore, an unreviewed safety question does not exist.

e .

Surry Monthly Operating Report No. 94-08 Page 13 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1994 1-TOP-4044 Temporary Operating Procedure 08-17-94 (Safety Evaluation No.94-152, Revision 1)

Temporary Operating Procedure 1-TOP-4044, "Number 1 Seal Leakoff 'Bucket Check' 1-RC-P-1 C," was developed to provide instructions for verifying the accuracy of the low range flow instrumentation for Unit 1 reactor coolant pump (RCP) "C" seal leak-off flow.

Implementation of this procedure, which involves the measurement and collection of RCP seal leak-off flow, will not affect the reactor coolant system pressure boundary and will not reduce the margin of safety as described by the Technical Specifications. Therefore, an unreviewed safety question does not exist.

O-MPM-1403-03 Mechanical Preventive Maintenance Procedure 08-31-94 (Safety Evaluation No.94-164)

Mechanical Preventive Maintenance Procedure O-MPM-1403-03, "Terry Turbine Governor Valve Stem Movement Check," was revised to provide instructions for performing additional preventive maintenance to ensure Terry turbine governor valve freedom of movement.

The Terry turbine will be removed from service during the performance of the subject procedure and the appropriate Technical Specification Limiting Condition for Operation will be entered. The additional maintenance activities will not affect the governor control function following the equipment's return to service. Therefore, an unreviewed safety question doe~ not exist.

• Surry Monthly Operating Report TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL No. 94-08 Page 14 of 17 MONTH/YEAR: August, 1994 None During the Reporting Period

• Surry Monthly Operating Report No. 94-08 Page 15 of 17 CHEMISTRY REPORT MONTHNEAR: August, 1994 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Ava. Max. Min. Ava.

Gross Radioactivity, µCi/ml 2.96E-1 2.28E-1 2.63E-1 1.56E-1 8.72E-2 1.29E-1 Suspended Solids, ppm <0.1 <0.1 <0.1 5.0.1 <0.1 <0.1 Gross Tritium, uCi/ml 3.07E-1 2.56E-1 2.86E-1 2.61E-1 2.09E-1 2.36E-1 1131, µCi/ml 4.68E-4 2.87E-4 3.98E-4 1.66E-4 1.12E-4 1.31 E-4 113111133 0.08 0.06 0.07 0.09 0.06 0.07 Hydroaen, cc/ka 40.6 26.8 32.8 40.1 31.9 34.3 Lithium, oom 2.33 2.08 2.21 2.33 2.05 2.20 Boron - 10, oom* 185.6 170.7 178.5 99.6 82.3 90.9 Oxygen, (DO), ppm 5.0.005 5.0.005 <0.005 <0.005 <0.005 <0.005 Chloride, oom 0.006 0.003 0.004 0.004 0.002 0.003 pH at 25 degree Celsius 6.87 6.69 6.77 7.24 7.01 7.14 Boron - 1O = Total Boron x 0.196 Comments:

None

- FUEL HANDLING

.Surry Monthly Operating Report No. 94-08 Page 16 of 17 UNITS 1 & 2 MONTH/YEAR: August, 1994 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

.Surry Monthly Operating Report f'

No. 94-08 Page 17 of 17 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: August, 1994 None During the Reporting Period