ML18152B379
ML18152B379 | |
Person / Time | |
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Site: | Surry ![]() |
Issue date: | 07/31/1999 |
From: | Ashley J, Pincus J, Stief R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
99-410, NUDOCS 9908170159 | |
Download: ML18152B379 (19) | |
Text
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e e VIRGINIA ELECTRIC AND PowER CoMPANY RICHMOND, VIRGINIA 23261 August 11, 1999 United States Nuclear Regulatory Commission Serial No.99-410 Attention: Document Control Desk ' SPS Lic/JSA 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 OPERATING REPORT The Monthly Operatjng Report for Surry Power Station Units 1 and 2 for the month of July 1999 is provided in the attachment.
Ii you have any questions or require additional information, please contact us.
Very truly yours, 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 NRG Senior Resident Inspector Surry Power Station 9908170159 990731 PDR- ADOCK 05000280 R PDR
e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 99-07 Approved:
e e Surry Monthly Operating Report No. 99-07 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 Nos. 1 and 2 ............................................................................................. 9 Facility Changes That Did Not Require NRC Approval ............................................................................................ 11 Procedure or Method of Operation Changes That Did Not Require NRC Approval. ................................................ 14 Tests and Experiments That Did Not Require NRC Approval. ................................................................................. 15 Chemistry Report ..................................................................................................................................................... 16 Fuel Handling - Unit Nos. 1 and 2 ............................................................................................................................ 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ....................................................................................................................... 18
e Surry Monthly Operating Report No. 99-07 Page3of18 OPERATING DATA REPORT Docket No.: 50-280 Date: 08/02/99 Completed By: R. Stief Telephone: (757) 365-2486
- 1. Unit Name: .......................................................... . Surry Unit 1
- 2. Reporting Period: ................................................ . July 1999
- 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 744.0 5087.0 233231.0
- 12. Hours Reactor Was Critical 744.0 5087.0 166403.5
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 3774.5
- 14. Hours Generator On-Line 744.0 5087.0 163858.4
- 15. Unit Reserve Shutdown Hours 0.0 0.0 3736.2
- 16. Gross Thermal Energy Generated (MWH) 1883592.0 12937305.7 387128263.2
- 17. Gross Electrical Energy Generated (MWH) 617382.0 4290648.0 127060804.0
- 18. Net Electrical Energy Generated (MWH) 592823.0 4137950.0 121124554.0
- 19. Unit Service Factor 100.0% 100.0% 70.3%
- 20. Unit Availability Factor 100.0% 100.0% 71.9%
- 21. Unit Capacity Factor (Using MDC Net) 99.5% 101.6% 66.6%
- 22. Unit Capacity Factor (Using DER Net) 101.1 % 103.2% 65.9%
- 23. Unit Forced Outage Rate 0.0% 0.0% 14.0%
- 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):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
e Surry Monthly Operating Report No. 99-07 Page 4 of 18 OPERATING DATA REPORT Docket No.: 50-281 Date: 08/02/99 Completed By: R. Stief Telephone: (757) 365-2486
- 1. Unit Name: .......................................................... . Surry Unit 2
- 2. Reporting Period: ................................................ . July 1999
- 3. Licensed Thermal Power (MW!): ......................... . 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 744.0 5087.0 230112.0
- 12. Hours Reactor Was Critical 502.3 3945.8 163856.1
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 328.1
- 14. Hours Generator On-Line 496.4 3821.9 161715.4
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1238455.9 8989590.1 382785239.1
- 17. Gross Electrical Energy Generated (MWH) 405470.0 3004950.0 125552843.0
- 18. Net Electrical Energy Generated (MWH) 391158.0 2897467.0 119719494.0
- 19. Unit Service Factor 66.7% 75.1% 70.3%
- 20. Unit Availability Factor 66.7% 75.1% 70.3%
- 21. Unit Capacity Factor (Using MDC Net) 65.6% 71.1% 66.5%
- 22. Unit Capacity Factor (Using DER Net) 66.7% 72.3% 66.0%
- 23. Unit Forced Outage Rate 33.3% 6.1% 11.2%
- 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):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
e Surry Monthly Operating Report No. 99-07 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: July 1999 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08/02/99 Completed by: J. R. Pincus Telephone: (757) 365-2863 (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 07/10/99 s 19H 32M B N/A N/A SG COND Clean condenser waterbox (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)
e Surry Monthly Operating Report No. 99-07 Page 6 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: July 1999 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08/02/99 Completed by: J. R. Pincus Telephone: (757) 365-2863 (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 07/05/99 F 247H 33M A 3 82-1999-003 AB ISV 2-RC-MOV-2591 disc separated from stem 07/31/99 s 18H 48M B N/A N/A SG COND Clean condenser waterbox (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)
e Surry Monthly Operating Report No. 99-07 Page 7 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08/02/99 Completed by: J. S. Ashley Telephone: (757) 365-2161 MONTH: July 1999 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 808 17
- 812 2 808 18 811 3 806 19 809 4 804 20 809 5 793 21 809 6 786 22 806 7 790 23 806 8 792 24 807 9 792 25 808 10 756 26 806 11 679 27 806 12 805 28 806 13 788 29 804 14 790 30 805 15 789 31 803 16 810 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. 99-07 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08/06/99 Completed by: J. S. Ashley Telephone: (757) 365-2161 MONTH: July 1999 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 812 17 810 2 813 18 810 3 810 19 811 4 808 20 809 5 382 21 809 6 0 22 807 7 0 23 805 8 0 24 807 9 0 25 807 10 0 26 805 11 0 27 803 12 0 28 801 13 0 29 799 14 0 30 800 15 50 31 656 16 684 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. 99-07 Page 9 of 18
SUMMARY
OF OPERATING EXPERIENCE MONTHNEAR: July 1999 The following chronological sequence by unit is a summary of operating experiences for this month that required load reductions or resulted in significant non-load related incidents.
UNIT ONE:
07/01/99 0000 Unit started the month at 100% / 844 MWe.
07/10/99 1855 Commenced ramp down to maintain condenser vacuum, Unit at 100% / 822 MWe.
07/10/99 2152 Stopped ramp, Unit at 75% / 586 MWe.
07/11/99 1115 Commenced ramp to 100%, Unit at 76% / 630 MWe.
07/11/99 1247 Stopped ramp for IRPI adjustment, Unit at 98% / 805 MWe.
07/11/99 1325 Recommenced ramp to 100%.
07/11/99 1422 Unit at 100% / 825 MWe.
07/31/99 2400 Unit finished the month at 100% / 837 MWe.
UNIT Two:
07/01/99 0000 Unit started the month at 100% / 845 MWe.
07/05/99 1121 Unit trip due to "A" loop stop valve disc separation from stem.
07/15/99 1213 Commenced Reactor startup.
07/15/99 1303 Reactor critical.
07/15/99 1854 Unit on-line, commenced ramp up.
07/15/99 1950 Stopped ramp, Unit at 30% / 205 MWe.
07/15/99 2106 Recommenced ramp, Unit at 30% / 205 MWe.
07/16/99 0211 Stopped ramp, Unit at 53% / 400 MWe.
07/16/99 0251 Recommenced ramp, Unit at 53% / 400 MWe.
07/16/99 0434 Stopped ramp, Unit at 75% / 640 MWe.
07/16/99 0604 Recommenced ramp to 91 %.
07/16/99 0702 Stopped ramp, Unit at 90% / 760 MWe.
07/16/99 1426 Recommenced ramp to 96%.
07/16/99 1445 Unit at 96% / 815 MWe.
07/16/99 1955 Commenced ramp to 100%, Unit at 96.5% / 815 MWe.
07/16/99 2208 Unit at 100% / 840 MWe.
07/31/99 0407 Commenced ramp down for waterbox scraping. Unit at 100% / 820 MWe.
07/31/99 0441 Stopped ramp, Unit at 94% / 765 MWe.
07/31/99 0627 Recommenced ramp, Unit at 94% / 765 MWe.
07/31/99 0754 Unit at 81 % / 655 MWe.
07/31/99 2040 Commenced ramp up, Unit at 72% / 590 MWe.
e Surry Monthly Operating Report No. 99-07 Page 10 of 18 UNIT Two (CONT):
07/31/99 2140 Stopped ramp, Unit at 88% / 740 MWe.
07/31/99 2204 Recommenced ramp, Unit at 88% / 740 MWe.
07/31/99 2255 Unit at 100% I 832 MWe.
07/31/99 2400 Unit finished the month at 99% / 825 MWe.
e - Surry Monthly Operating Report No. 99-07 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July 1999 DCP 92-028-3 Design Change Package 10/25/97 (Safety Evaluation 97-010, Rev. 1)
Design Change Package 92-028-3, "Replacement of Radiation Monitoring Recorders and Ratemeters", replaced remaining Radiation Monitoring (RM) equipment and re-arranged RM cabinets to conform to human performance criteria. Revision 1 of Safety Evaluation 97-010 added "Fail Safe" control logic under loss of power conditions or other failures detected by the ratemeter.
DCP 99-031 Design Change Package 07/01/99 (Safety Evaluation 99-047, Rev. 1)
Design Change Package 99-031, "Trial Chemical Injection of Gire Water System", evaluates the effectiveness of chemically treating the Circulating Water (CW) system to control biofouling of the Unit 1 condensers. Revision 1 of Safety Evaluation 99-047 expanded the chemical treatment to both Unit 1 condensers.
FS99-020 UFSAR Change Request 07/01/99 (Safety Evaluation 99-060)
UFSAR Change Request FS99-020 allows the use of a portable Passive Autocatalytic Recombiner system to maintain the Hydrogen concentration in the containment structure below 0.8% volume during non-accident conditions.
TM S2-99-005 Temporary Modification 07/01/99 (Safety Evaluation 99-061)
Temporary Modification S2-99-005 was used to bypass the bearing lift oil pressure anti-start interlock in the Main Turbine Turning Gear motor circuitry to allow periodic rotation of the turbine rotor using the turning gear.
FS99-001 UFSAR Change Request 07/01/99 (Safety Evaluation 99-062)
As a result of the Integrated Configuration Management Project review, UFSAR Change Request FS99-001 contains corrections and clarifications to the UFSAR sections that discuss Surry's Reactor Coolant System. These changes are to enhance accuracy and do not affect any reactor coolant system or structure, or any of its component's operation or performance.
FS99-018 UFSAR Change Request 07/01/99 TS 346 (Basis Only) Technical Specification Change Request (Safety Evaluation 99-063)
As a result of the Integrated Configuration Management Project review, UFSAR Change Request FS99-018 updates Tables 4.1-14 and 4.1-15 to match the latest information provided to the NRC. Technical Specification Change Request TS 346 (Basis Only) deletes two tables from TS basis and changes the basis to reference the UFSAR tables.
e Surry Monthly Operating Report No. 99-07 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July 1999 TRM Rev. 0 Technical Requirements Manual 07/01/99 FS99-023 UFSAR Change Request (Safety Evaluation 99-064)
This initial issuance of the Surry Technical Requirements Manual (TRM) is considered an administrative change and will relocate existing Fire Protection System technical requirements from the UFSAR to the TRM. The TRM will provide operational convenience by placing, and later consolidating, certain technical requirements in this licensee controlled document.
FS98-036 UFSAR Change Request 07/08/99 (Safety Evaluation 99-066)
UFSAR Change Request FS98-036 permits the addition of a dilute ammonium chloride solution either in place of, or in conjunction with, selective anion resin regenerations to maintain the steam generator sodium to chloride molar ratio within the recommended operating range to minimize the potential for corrosion.
TM S1-99-006 Temporary Modification 07/09/99 (Safety Evaluation 99-067)
Failure of one or both of the cooling fans for the power controller of the Pressurizer proportional heaters causes a switch to actuate that reduces the heaters to "minimum" output and could lead to an unplanned pressure transient and/or Unit 1 shutdown.
Temporary Modification S1-99-006 defeats the over temperature protection circuit in the power controller for the Pressurizer proportional heaters and installs a temporary cooling fan.
TM S2-99-007 Temporary Modification 07/09/99 (Safety Evaluation 99-068 Rev. 0, Rev. 1)
Temporary Modification S2-99-007 allows operation of Unit 2 reactor with the internals of T-cold loop stop valve removed. Revision 1, of the Safety Evaluation dated July 12, 1999, addresses the valve being left fully open by motor and limit switch position.
TM S2-99-008 Temporary Modification 07/19/99 (Safety Evaluation 99-070)
During the Spring, 1999 Unit 2 refueling outage, the manipulator crane gripper and the spent fuel long handling tool were modified to allow movement of fuel assemblies with damaged top nozzle guide holes. Temporary Modification S2-99-008 allows the moving of one of the damaged fuel assemblies that is having its top nozzle replaced using the modified tool.
e Surry Monthly Operating Report No. 99-07 Page 13 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July 1999 FS99-012 UFSAR Change Request 07/22/99 (Safety Evaluation 99-071)
As a result of the Integrated Configuration Management Project review, UFSAR Change Request FS99-012 contains corrections and clarifications to the UFSAR sections that discuss Surry's Main Steam System. These changes are to enhance accuracy and do not affect any main steam system or structure, or any of its component's operation or performance.
FS99-032 UFSAR Change Request 07/29/99 (Safety Evaluation 99-072)
UFSAR Change Request FS99-032 describes the transient analysis, including required operator actions, assumptions, method of analysis, results and conclusions of the high-energy line break (HELB) in the main steam valve house (MSVH) accident in the Surry UFSAR. Emergency Operating procedures 1&2-FR-H.1 were changed to support the analysis.
e e Surry Monthly Operating Report No. 99-07 Page 14 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July 1999 2B-62/H-6 Annunciator Response Procedure 07/07/99 2-0P-RC-005 Operating Procedure (Safety Evaluation 99-065)
Annunciator Response Procedure 2B-62/H6, "RHR HX OUT HI Temp" and Operating Procedure 2-0P-RC-005, "Draining the RCS From Flange Level to Mid-Nozzle (Reduced Inventory)", were temporarily modified to lower the RHR Heat Exchanger Outlet High Temperature Alarm Setpoint to provide the operator with prompt indication of RCS heatup during reduced inventory.
O-MOP-BR-001 Maintenance Operating Procedure 07/29/99 (Safety Evaluation 99-073)
Maintenance Operating Procedure O-MOP-BR-001, "Replacing 1-BR-RV-109 and 1-BR-RV-108", was revised to allow the directing of primary grade water into the Boron Recovery system's tanks to help evacuate hydrogen gas. The combustible hydrogen gas must be purged in order to replace two relief valves.
e Surry Monthly Operating Report No. 99-07 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July 1999 None during the Reporting Period
e e Surry Monthly Operating Report No. 99-07 Page 16 of 18 CHEMISTRY REPORT MONTHNEAR: July 1999 Unit No. 1 Unit No. 2 Primarv Coolant Analysis Max. Min. Ava. Max. Min. Ava.
Gross Radioactivity, µCi/ml 3.30E-1 1.92E-1 2.56E-1 2.20E-1 3.19E-3 1.25E-1 Suspended Solids, oom - - - 0.25 0.01 0.13 Gross Tritium, µCi/ml 1.04E+O 9.15E-1 9.69E-1 3.31E-1 6.38E-2 1.55E-1 11 3 1, µCi/ml 5.78E-4 2.14E-4 3.96E-4 :;; 1.62E-4 :;; 5.93E-5 :;; 8.73E-5 113111133 0.1 0.05 0.07 :;; 0.37 :;; 0.16 :;; 0.26 Hydroaen, cc/ka 38.9 35.8 36.9 35 2.6 17.4 Lithium, oom 2.33 2.08 2.2 3.15 0.21 2.01 Boron - 10, ppm* 168.86 145.43 154.01 454.92 226.58 322.16 Oxygen, (DO), ppm :;;0.005 :;; 0.005 :;;0.005 0.35 :;;0.005 ::; 0.022 Chloride, ppm 0.022 0.01 0.017 0.01 0.003 0.007 pH @ 25 degree Celsius 6.78 6.68 6.74 6.53 5.09 5.94 Boron - 10 = Total Boron x 0.196 Comments:
None
eSurry Monthly Operating Report No. 99-07 Page17of18 FUEL HANDLING UNITS 1 &2 MONTHNEAR: July 1999 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
e Surry Monthly Operating Report No. 99-07 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: July 1999 None during the Reporting Period