ML18152B816

Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr

ML18152B816
Person / Time
Site:	Surry
Issue date:	04/30/1998
From:	Christian D, Marshall G, Slade D, Steinert J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
98-267, NUDOCS 9805200179
Download: ML18152B816 (18)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 8, 1998 United States Nuclear Regulatory Commission Serial No.98-267 Attention: Document Control Desk SPS Lie/JCS RO 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 OPERA TING REPORT The Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of April 1998, is provided in the attachment.

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

Very truly yours, D. A. Christian, Site Vice President Surry Power Station Attachment Commitments made by this letter: None cc: U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, S. W.

Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station 9805200179 980430 PDR ADOCK 05000280 R PDR

VIRGINIA ELECTRIC AND POWER COMPANY SURREY POWER STATION MONTHLY OPERATING REPORT REPORT No. 98-04 Approved: ~JC~-S-~B Site Vice President Date

• TABLE OF CONTENTS

.urry Monthly Operating Report No. 98-04 Page 2 of 17 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 - u*nit 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 Nos. 1 and 2 ............................................................................................. 9 Facility Changes That Did Not Require NRG Approval ............................................................................................ 10 Procedure or Method of Operation Changes That Did Not Require NRG Approval. ................................................ 13 Tests and Experiments That Did Not Require NRG Approval .................................................................................. 14 Chemistry Report ..................................................................................................................................................... 15 Fuel Handling - Unit Nos. 1 and 2 ............................................................................................................................ 16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ....................................................................................................................... 17

• • OPERATING DATA REPORT

.Surry Monthly Operating Report No. 98-04 Page 3 of 17 Docket No.: 50-280 Date: 05/02/98 Completed By: D. L. Slade Telephone: (757) 365-2246

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

2. Reporting Period: ................................................. . April, 1998

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 Year-To-Date Cumulative

11. Hours in Reporting Period 719.0 2879.0 222263.0

12. Hours Reactor Was Critical 719.0 2578.3 156604.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 3774.5

14. Hours Generator On-Line 719.0 2558.5 154158.0

15. Unit Reserve Shutdown Hours 0.0 0.0 3736.2

16. Gross Thermal Energy Generated (MWH) 1825258.0 6479659.7 362724675.3

17. Gross Electrical Energy Generated (MWH) 611038.0 2171032.0 118986786.0

18. Net Electrical Energy Generated (MWH) 590808.0 2099351.0 113333572.0

19. Unit Service Factor 100.0% 88.9% 69.4%

20. Unit Availability Factor 100.0% 88.9% 71.0%

21. Unit Capacity Factor (Using MDC Net) 102.6% 91.0% 65.5%

22. Unit Capacity Factor (Using DER Net) 104.3% 92.5% 64.7%

23. Unit Forced Outage Rate 0.0% 2.2% 14.6%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, October 19, 1998, 35 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

• OPERATING DATA REPORT

. u r r y Monthly Operating Report No. 98-04 Page 4 of 17 Docket No.: 50-281 Date: 05/02/98 Completed By: D. L. Slade Telephone: (757) 365-2246

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

2. Reporting Period: ................................................. . April, 1998

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 Year-To-Date Cumulative

11. Hours in Reporting Period 719.0 2879.0 219144.0

12. Hours Reactor Was Critical 719.0 2879.0 154029.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 328.1

14. Hours Generator On-Line 719.0 2879.0 152012.5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1830451.8 7326206.7 358859774.0

17. Gross Electrical Energy Generated (MWH) 612145.0 2454460.0 117580068.0

18. Net Electrical Energy Generated (MWH) 591897.0 2375392.0 112018543.0

19. Unit Service Factor 100.0% 100.0% 69.4%

20. Unit Availability Factor 100.0% 100.0% 69.4%

21. Unit Capacity Factor (Using MDC Net) 102.8% 103.0% 65.4%

22. Unit Capacity Factor (Using DER Net) 104.5% 104.7% 64.9%

23. Unit Forced Outage Rate 0.0% 0.0% 11.7%

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

• UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

&urry Monthly Operating Report No. 98-04 Page 5 of 17 REPORT MONTH: April, 1998 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 05/03/98 Completed by: G. N. Marshall Telephone: (757) 365-2465 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to 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 (NUREG 0161)

&urry Monthly Operating Report No. 98-04 Page 6 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL TO OR GREATER THAN 20%)

REPORT MONTH: April, 1998 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 05/03/98 Completed by: G. N. Marshall Telephone: (757) 365-2465 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to 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 (NUREG 0161)

• • AVERAGE DAILY UNIT POWER LEVEL

.Surry Monthly Operating Report No. 98-04 Page 7 of 17

/

Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 05/03/98 Completed by: J. C. Steinert Telephone: (757) 365-2834 MONTH: April, 1998 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (Mwe - Net) 1 753 17 824 2 826 18 824 3 825 19 824 4 ~24 20 824 5 790 21 824 6 827 22 824 7 824 23 825 8 824 24 824 9 824 25 824 10 824 26 824 11 823 27 824 12 823 28 822 13 824 29 822 14 824 30 824 15 825 31 16 824 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.

• AVERAGE DAILY UNIT POWER LEVEL

.Surry Monthly Operating Report Docket No.: 50-281 No. 98-04 Page 8 of 17 Unit Name: Surry Unit 2 Date: 05/03/98 Completed by: John C. Steinert Telephone: (757) 365-2837 MONTH: April, 1998 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (Mwe - Net) 1 822 17 816 2 824 18 820 3 826 19 822 4 828 20. 820 5 793 21 820 6 824 22 824 7 827 23 824 8 825 24 825 9 823 25 824 10 824 26 824 11 825 27 823 12 825 28 823 13 824 29 822 14 824 30 818 15 823 31 16 822 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. 98-04 Page 9 of 17 MONTHNEAR: April, 1998 The following chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT ONE:

04/01/98 0000 Unit 1 operating at 50%, 414 MWe.

04/01/98 1002 Unit 1 at 100%, 855 MWe 04/30/98 2400 Unit 1 operating at 100% , 855 MWe.

UNITTWO:

04/01/98 0000 Unit 2 operating at 100%, 855 MWe.

04/30/98 2400 Unit 2 operating at 100%, 855 MWe.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

• Surry Monthly Operating Report No. 98-04 Page 10 of 17 MONTHNEAR: April, 1998 DCP 90-08-03 Design Change Package 09/29/92 (SE 92-201)

The purpose of this Design Change Package was to upgrade the safety related Control Room envelope air conditioning system to provide additional capacity for removal of increased heat loads, improve equipment reliability and performance, and to address Appendix R concerns. Electrical equipment added to the Emergency Switchgear Rooms since original construction has increased heat loads and reduced original design margin for the air conditioning system equipment. Additionally, the original equipment has physically degraded and, consequently, the frequency of maintenance has increased.

DCP 90-08-03 Design Change Package 01/24/94 (SE 94-015)

The purpose of this change to the Design Change Package was to install a one hour fire barrier on conduits for the Mechanical Equipment Room (MER) No. 5 feeders in the Unit 2 emergency Switchgear Room in lieu of the three hour fire barrier originally required. The purpose of this change was to facilitate the installation of the fire barrier in an area with limited space that will not allow installation of a three hour barrier so that compensatory measures in place could be eliminated ..

DCP 90-08-03 Design Change Package 08/03/95 (SE 95-089)

The purpose of this change to the Design Change package was to provide instructions for coating chiller condenser tubes. The chiller condenser tubes were experiencing flow accelerated corrosion on the tube ends. A coating was applied to four inches of the tube ends to resist the corrosion.

DCP 90-08-03 Design Change Package 09/13/95 (SE 95-104, Rev. 1)

The purpose of this change to the Design Change package was to provide supplemental work instructions for the plugging of tubes in a chiller condenser to maintain the refrigerant pressure boundary. The tube plugging will not reduce the loss of heat transfer below the design basis capacity. The design basis capacity continues to be exceeded by a margin of six to seventeen percent for completely fouled and clean conditions, respectively.

DCP 91-09-03 Design Change Package 03/05/92 (SE 92-048)

The purpose of this Design Change package was to construct MER 5 in the Turbine Building Basement. The room is a safety related, concrete structure for housing two new chillers and their auxiliaries being installed by another Design Change Package.

DCP 94-018 Design Change Package 08/08/96 (SE 95-183, Rev. 1)

The purpose of this Design Change Package was to replace the Vital Bus panel main breakers with non-automatic switches and to modify the uninterruptable power supplies (UPS) by the installation of fuses on the Vital Bus panel feeders. The change makes the Vital Bus System more reliable by improving electrical coordination. The installation of the fuses in the UPS panels provides a means to isolate the Control Room panels in the event

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

• Surry Monthly Operating Report No. 98-04 Page 11 of 17 MONTHNEAR: April, 1998 of a Control Room fire and provides circuit protection in light of removal of the non-automatic circuit breakers from the distribution panels.

DCP 94-018 Design Change Package 10/01/97 (SE 97-128)

The purpose of this safety evaluation was to address the implementation and post implementation of the design change to the Vital Bus panel feeder breakers and UPSs for Unit 2. The implementation maintained power to the individual vital bus circuits, by the use of procedurally controlled jumpers to cross tie vital buses buses to maintain vital indications and controls, with the exception of the dead bus transfer performed with fuel removed from the core. Equipment fed from each vital bus was evaluated for consequence of failure and compensatory measures were addressed as required.

DCP 94-018 Design Change Package 03/18/98 (SE 98-032)

The purpose of this safety evaluation was to address the implementation and post implementation of the design change to the Vital Bus panel feeder breakers and UPSs for Unit 1. The modification took place at cold shutdown, with compensatory measures in place. The implementation maintained power to the individual vital bus circuits, by the use of procedurally controlled jumpers to cross tie vital buses to maintain vital indications and controls. Equipment fed from each vital bus was evaluated for consequence of failure and compensatory measures were addressed as required.

DCP 96-024 Design Change Package 08/29/97 FS 97-28 (SE 97-115)

The purpose of this Design Change Package and UFSAR Change Request FS 97-28 was to provide an alternate, non-safety, power supply to the chillers in MER 5 to be used in the event of a fire in the Unit 2 Emergency Switchgear Room that would interrupt normal safety-related power supplies. The alternate power supply will be supplied from the AAC Diesel Generator, which will be designated Appendix R, fulfilling the Appendix R assumption that includes the loss of offsite power concurrent with such a fire.

TM 81-98-08 Temporary Modification 04/07/98 (SE 98-0044)

The purpose of this Temporary Modification (TM) was to remove two jumpers in the non-protection portion of First Stage Turbine Protection Channels. The removal of the jumpers was needed to restore the full instrumentation loop function for the First Stage Turbine Pressure to normal. The jumpers currently serve as second ground to the circuit downstream of a selector switch. The second ground was causing abnormal readings for the computer input channel for impulse pressure and steam dump demand.

TM 81-98-09 Temporary Modification 04/28/98 TM 82-98-01 (SE 98-0045 Rev. 2)

The purpose of this TM was to install temporary blowers in the Main Steam Valve House to increase the flow of cooler air to the Main Steam Radiation Monitors. The Main Steam Radiation Monitors require additional cooling to increase reliability due to failures associated with the ambient temperature in the area.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL Surry Monthly Operating Report No. 98-04 Page 12 of 17 MONTH/YEAR: April, 1998 TM S1-98-10 Temporary Modification 04/20/98 (Safety Evaluation No. 98~0046)

The purpose of this TM was to maintain makeup capability to the Low-Level Vacuum Priming System while modifications are being performed to the Instrument Air System in accordance with a design change package.

SE 98-0047 Safety Evaluation 04/23/98 Safety Evaluation 98-0047 was performed to implement a revised Post-Loss Of Coolant Accident (LOCA) Containment Sump Boron Concentration for the Reload Safety Analysis Checklist. The new methodology and calculation statistically combine probability distributions which conservatively describe key analysis parameters and uncertainties, such as tank volumes and solution concentrations, to determine the minimum predicted Post-LOCA sump boron concentrations. The methodology provides a small amount of additional margin in the allowable critical boron concentration at Post-LOCA sump conditions for future reload core designs and addresses the presence of unborated water in the containment sump during normal operation.

FS 98-07 UFSAR Change Request 04/23/98 (Safety Evaluation No. 98-0048)

UFSAR Change Request FS 98-07 documents a revised containment spray and Post-LOCA sump pH analysis as described in UFSAR Section 6.2.3.3. The new methodology and calculation statistically combine probability distributions which conservatively describe key analysis parameters and uncertainties, such as tank volumes and solution concentrations, to determine the minimum and maximum predicted containment spray and Post-LOCA sump pH. The revised containment spray and Post-LOCA sump pH analysis implements the analysis methodology and addresses the presence of unborated water in the containment sump during normal operation.

FS 98-09 UFSAR Change Request 04/23/98 (Safety Evaluation No. 98-0049)

UFSAR Change Request FS 98-05 documents the revision of the Post-LOCA containment hydrogen concentration calculation. The change includes an initial hydrogen concentration of 0.8% in the Post-LOCA containment hydrogen concentration analysis.

Adherence to this limit is ensured by analysis of containment concentration in accordance with controlled procedures.

• PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID Nor REQUIRE NRC APPROVAL

• Surry Monthly Operating Report No. 98-04 Page 13 of 17 MONTHNEAR: April, 1998 None during the reporting period.

• .urry Monthly Operating Report No. 98-04 Page 14 of 17 TESTS AND EXPERIMENTS THAT DID Nor REQUIRE NRC APPROVAL MONTHNEAR: April, 1998 None During the Reporting Period

• .urry Monthly Operating Report No. 98-04 Page 15 of 17 CHEMISTRY REPORT MONTHNEAR: March, 1998 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Avg.

Gross Radioactivity, µCi/ml 4.60E-1 2.75E-1 3.50E71 2.20E-1 1.34E-1 1.80E-1 Suspended Solids, ppm - - - - - -

Gross Tritium, µCi/ml 1.39E-1 7.79E-2 1.10E-1 9.17E-1 8.35E-1 8.88E-1 1131, µCi/ml 6.91E-3 1.09E-3 2.90E-3 6.00E-5 2.81 E-5 4.66E-5 113111133 0.57 0.16 0.32 0.10 0.05 0.08 Hydrogen, cc/kg 39.1 19.4 30.6 40.6 33.7 36.4 Lithium, ppm 2.34 1.83 2.20 2.32 2.06 2.21 Boron - 10, ppm* 170.5 86.8 101.2 199.5 185.8 193.5 Oxygen, (DO), ppm s0.005 s0.005 s0.005 s0.005 s0.005 s0.005 Chloride, ppm 0.005 0.002 0.002 0.005 0.004 0.004 pH at 25 degree Celsius 7.13 6.65 7.01 6.69 6.53 6.61

• Boron -10 = Total Boron x 0.196 Comments:

None

• FUEL HANDLING

.urry Monthly Operating Report No. 98-04 Page 16 of 17 UNITS 1 & 2 MONTH/YEAR: April, 1998 New Fuel Number of New or Spent Shipment or Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Cask No. Received per Shipment Number Number Enrichment Cask Activity None During the Reporting Period

• .urry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED No. 98-04 Page 17 of 17 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: April, 1998 None During the Reporting Period