ML18152B601
ML18152B601 | |
Person / Time | |
---|---|
Site: | Surry |
Issue date: | 12/31/1998 |
From: | Ashley J, Pincus J, Stief R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
99-014, 99-14, NUDOCS 9901220273 | |
Download: ML18152B601 (20) | |
Text
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., e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 15, 1999 United States Nuclear Regulatory Commission Serial No.99-014 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 Operating Report for Surr1 Power Station Units 1 and 2 for the month of 09cember 1998 is provided in the attachment.
!t you hctve any questions or require additional information, please contact us.
Very truly yours, E. S. Grecheck, 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 NRG Senior Resident Inspector Surry Power Station
- - - - - -- - - - - - - - - - - - - -*---- - --------- -- ---~-,
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. PDR*. ADOCK 050.00280 - ,:I, R .. - - . . PDR
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 98-12 Approved:
Date
e Surry Monthly Operating Report No. 98-12 Page 2 of 19 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 ............................................................................................ 1O Procedure or Method of Operation Changes That Did Not Require NRC Approval. ................................................ 12 Tests and Experiments That Did Not Require NRC Approval. ................................................................................. 13 Chemistry Report ..................................................................................................................................................... 14 Fuel Handling - Unit Nos. 1 and 2 ............................................................................................................................ 15 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ....................................................................................................................... 19
e
- Surry Monthly Operating Report No. 98-12 Page3of19 OPERATING DATA REPORT Docket No.: 50-280 Date: 01/05/99 Completed By: R. Stief Telephone: (757) 365-2486
- 1. Unit Name: .......................................................... . Surry Unit 1
- 2. Reporting Period: ................................................ . December 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 744.0 8760.0 228144.0
- 12. Hours Reactor Was Critical 744.0 7290.7 161316.5
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 3774.5
- 14. Hours Generator On-Line 744.0 7171.9 158771.4
- 15. Unit Reserve Shutdown Hours 0.0 0.0 3736.2
- 16. Gross Thermal Energy Generated (MWH) 1886586.2 17945941.9 37 4190957 .5
- 17. Gross Electrical Energy Generated (MWH) 630011.0 5954402.0 122770156.0
- 18. Net Electrical Energy Generated (MWH) 608849.0 5752383.0 116986604.0
- 19. Unit Service Factor 100.0% 81.9% 69.6%
- 20. Unit Availability Factor 100.0% 81.9% 71.2%
- 21. Unit Capacity Factor (Using MDC Net) 102.2% 82.0% 65.8%
- 22. Unit Capacity Factor (Using DER Net) 103.9% 83.3% 65.1%
- 23. Unit Forced Outage Rate 0.0% 6.9% 14.4%
- 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 e Surry Monthly Operating Report No. 98-12 Page 4 of 19 OPERATING DATA REPORT Docket No.: 50-281 Date: 01/05/99 Completed By: R. Stief Telephone: (757) 365-2486
- 1. Unit Name: ........................................................... Surry Unit 2
- 2. Reporting Period: ................................................. December 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 744.0 8760.0 225025.0
- 12. Hours Reactor Was Critical 744.0 8760.0 159910.3
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 328.1
- 14. Hours Generator On-Line 744.0 8760.0 157893.5
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1891963.2 22262081.7 373795649.0
- 17. Gross Electrical Energy Generated (MWH) 635040.0 7422285.0 122547893.0
- 18. Net Electrical Energy Generated (MWH) 613951.0 7178876.0 116822027.0
- 19. Unit Service Factor 100.0% 100.0% 70.2%
- 20. Unit Availability Factor 100.0% 100.0% 70.2%
- 21. Unit Capacity Factor (Using MDC Net) 103.0% 102.3% 66.3%
- 22. Unit Capacity Factor (Using DER Net) 104.7% 104.0% 65.9%
- 23. Unit Forced Outage Rate 0.0% 0.0% 11.4%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling, April 19, 1999, 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
- Surry Monthly Operating Report No. 98-12 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: December 1998 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 01/01/99 Completed by: J. R. Pincus Telephone: (757) 365-2863 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 (NU REG 0161)
e Surry Monthly Operating Report No. 98-12 Page 6 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: December 1998 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 01/04/99 Completed by: J. R. Pincus Telephone: (757) 365-2863 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 (NU REG 0161)
- Surry Monthly Operating Report No. 98-12 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 01/07/99 Completed by: J. S. Ashley Telephone: (757) 365-2161 MONTH: December 1998 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (Mwe - Net) 807 17 823 2 812 18 822 3 810 19 819 4 813 20 823 5 812 21 823 6 813 22 822 7 813 23 822 8 812 24 822 9 812 25 823 10 812 26 822 11 820 27 822 12 820 28 822 13 820 29 822 14 823 30 822 15 823 31 822 16 819 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. 98-12 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 01/07/99 Completed by: J. S. Ashley Telephone: (757) 365-2161 MONTH: December 1998 Average Daily Power Level Average Daily Power Level Day (Mwe - Net) Day (Mwe - Net) 1 826 17 826 2 826 18 828 3 827 19 827 4 827 20 827 5 822 21 826 6 819 22 825 7 825 23 827 8 824 24 826 9 826 25 827 10 799 26 826 11 827 27 827 12 829 28 826 13 829 29 826 14 827 30 826 15 826 31 827 16 826 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. 98-12 Page 9 of 19
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: December 1998 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:
12/01/98 0000 Unit starts the month at 98.5% / 837 MWe.
12/11/98 0240 Commenced ramp up to 100%.
12/11/98 0313 Unit at 100% / 854 MWe.
12/31/98 2400 Unit finishes the month at 100% / 855 MWe.
UNIT Two:
12/01/98 0000 Unit starts the month at 100% / 855 MWe.
12/31/98 2400 Unit finishes the month at 100% / 855 MWe.
e Surry Monthly Operating Report No. 98-12 Page 10 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: December 1998 DCP 91-003 Design Change Package 12/16/98 (Safety Evaluation 91-035)
Design Change Package 91-003, "Chemical Injection of Service Water 48" Headers", allows for the injection of sodium hypochlorite (chlorine) into the standby 48" Service Water (SW) headers to eliminate biofouling.
DCP 93-089 Design Change Package 12/07/98 (Safety Evaluation 94-160)
Design Change Package 93-089, "High Level Intake Structure Seal Plate Modifications",
installs casters on the corners of the seal plates located at the High Level Intake Structure making the seal plates less prone to binding during High Level isolation.
DCP 96-009 Design Change Package 12/16/98 (Safety Evaluation 96-030)
Design Change Package 96-009, "Emergency Service Water Pump Modification", replaces Emergency Service Water (ESW) pump 1-SW-P-1A with a spare pump that will require several modifications to accommodate differences in drive shaft diameter, angle drive lube oil cooler, and motor drive.
DCP 97-003 Design Change Package 12/16/98 (Safety Evaluation 97-033)
Design Change Package 97-003, RCP Motor Upper Bearing Oil Level Alarm Modifications",
modifies reactor coolant pump (RCP) motor (serial number 2S-76P049) bearing oil system to help prevent erroneous oil level indications in the oil sightglass and from the oil level alarm assemblies.
FS98-046 UFSAR Change Request 12/03/98 (Safety Evaluation 98-127)
UFSAR Change Request FS98-046 revises section 14.4.2.1 and table 9.1-6 to reflect the new volume control tank (VCT) rupture radiological analysis. The UFSAR VCT rupture radiological analysis assumed a letdown flow rate of 60 gallons per minute with delay of 5 minutes before the VCT is assumed to be isolated. The VCT rupture was re-evaluated using an assumed letdown flow rate of 160 gallons per minute with a delay of 25 minutes. The new analysis is consistent with actual plant operation.
FS98-050 UFSAR Change Request 12/08/98 (Safety Evaluation 98-128)
UFSAR Change Request FS98-050 changes the test frequency for the Intercept and Reheat Stop Valves from quarterly to every 18 months to eliminate part of the transient placed on the unit when performing the turbine inlet valve freedom test. The changing of the test interval from three months to eighteen months is based on a report provided by Westinghouse dated December 1998 (Evaluation of Turbine Missile Ejection Probability Resulting From Extending The Test Interval of Interceptor and Reheat Stop Valves at Surry Units 1 & 2).
e e Surry Monthly Operating Report No. 98-12 Page 11 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: December 1998 TM S1-98-026 Temporary Modification 12/09/98 (Safety Evaluation 98-129)
Temporary Modification S1-98-026 was used to remove the isolation valve manifold for the "A" Steam Generator Channel IV Main Steam Transmitter, 1-MS-FT-1475, and install a temporary equalizing valve in place of the isolation valve manifold.
TM S1-98-026 Temporary Modification 12/10/98 (Safety Evaluation 98-129, Rev. 1)
Temporary Modification S1-98-026 was used to remove the isolation valve manifold for the "A" Steam Generator Channel IV Main Steam Transmitter, 1-MS-FT-1475, and install a temporary equalizing valve in place of the isolation valve manifold. The new temporary valve was to be relabeled with a new mark number. Revision 1 of Safety Evaluation 98-129 eliminated the change to station labeling.
FS98-026 UFSAR Change Request 12/10/98 (Safety Evaluation 98-130)
UFSAR Change Request FS98-026 corrects the description of initial testing performed to verify the performance of the Recirculation Spray (RS) system. UFSAR Section 6.3.1.5.2 currently states that the initial test for the recirculation spray subsystem is identical to that for the containment spray subsystem". Based on the results of the RS system integration review performed as part of the Integrated Configuration Management project, the pre-operational testing of the RS system was determined not to be identical to the description of the Containment Spray system. This UFSAR change reflects the actual initial start-up testing performed for the RS system.
FS98-027 UFSAR Change Request 12/10/98 (Safety Evaluation 98-131)
UFSAR Change Request FS98-027 contains corrections and clarifications to the UFSAR sections that discuss Surry's Containment Spray (CS) system as a result of the Integrated Configuration Management project review of the CS system. These changes are to enhance accuracy and do not affect any CS system or structure, or any of its component's operation or performance.
SE 98-132 Safety Evaluation 12/17/98 Safety Evaluation 98-132 evaluates the approximately 200 irradiated fuel assembly insert components (burnable poison rod assemblies, thimble plug assemblies and rod control cluster assemblies) being consolidated and placed in 2 disposable cask liners. Each liner will then be placed in a TN-RAM shipping container and prepared for shipment to Barnwell, S. C. for burial.
e e Surry Monthly Operating Report No. 98-12 Page 12 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December 1998 1-IPT-CC-MS-F-475 Instrument Periodic Test Procedure 12/03/98 (Safety Evaluation 98-126)
Instrument Periodic Test Procedure, 1-IPT-CC-MS-F-475, "Steam Line Flow Protection Loop F-1-475 Channel Calibration", was changed to contain steps for installation and removal of a Temporary Modification (TM) to bypass inoperable Channel 4 Steam Flow to allow surveillance testing to be performed on channels 1,2,3 and 4 of Unit 1. Technical Specifications compliance will be maintained during this evolution.
O-MOP-BS-001 Maintenance Operating Procedure 12/21/98 (Safety Evaluation 98-133)
Maintenance Operating Procedure, O-MOP-BS-001, "Establishing Administrative Control of the Control Room Pressure Boundary", ensures administrative control will be established when Control Room Pressure Boundary doors are open for maintenance or inspection.
1-0P-CN-013 Operating Procedure 12/22/98 (Safety Evaluation 98-134)
Operating Procedure, 1-0P-CN-013, "Manual Regeneration of Condensate Polishing Resin", was revised for installation of a Temporary Modification (TM) to close valve 1-CP-AOV-141 which will allow the anion resin to be transferred from the anion tank to the cation tank to be regenerated with sulfuric acid to remove chloride impurities which were loaded onto the resin during the recent Unit 1 startup.
0-1 PM-RM-G-004&005 Instrument Preventive Maintenance Procedures 12/22/98 CAL-817 Calibration Procedure (Safety Evaluation 98-135)
Procedures, O-IPM-RM-G-004, "Laundry Radiation Monitor RIC-4 Channel Calibration" and O-IPM-RM-G-005, "Laundry Radiation Monitor RIC-3 Ratemeter Calibration", were developed and procedure Cal-817, "Model 942 Log Ratemeter Scintillation Detector Source Calibration", was revised to install a Temporary Modification (TM) to allow for the calibration, repair and testing of the digital ratemeters without causing their control function to occur.
e Surry Monthly Operating Report No. 98-12 Page 13 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: December 1998 None during the Reporting Period
e Surry Monthly Operating Report No. 98-12 Page 14 of 19 CHEMISTRY REPORT MONTHNEAR: December 1998 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avq. Max. Min. AvQ.
Gross Radioactivity, µCi/ml 3.50E-1 1.46E-1 2.60E-1 1.69E-1 1.07E-1 1.29E-1 Suspended Solids, ppm 0.010 0.010 0.010 0.010 0.010 0.010 Gross Tritium, µCi/ml 3.13E-1 8.33E-2 2.15E-1 3.78E-1 3.21 E-1 3.49E-1 1131, µCi/ml 4.42E-4 2.40E-4 3.03E-4 1.07E-4 5.69E-5 8.13E-5 113111133 0.09 0.04 0.06 0.14 0.07 0.10 HydroQen, cc/kQ 37.1 31.4 34.2 39.5 36.6 37.5 Lithium, ppm 2.54 2.17 2.37 1.96 1.49 1.77 Boron - 10, ppm* 268.5 249.7 257.6 58.0 37.2 47.4 Oxygen, (DO), ppm :s;0.005 :s;0.005 :::; 0.005 :s;0.005 :s;0.005 :s;0.005 Chloride, ppm 0.025 0.012 0.019 0.002 :::; 0.001 0.001 pH @ 25 degree Celsius 6.47 6.05 6.35 7.39 6.90 7.22 Boron - 10 == Total Boron x 0.196 Comments:
None
e Surry Monthly Operating Report No. 98-12 Page 15 of 19 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: December 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 Unit 2 Batch 18 Shipment #1 12/01/98 12 17N LM170E 4.0939 15.80 Ci 39N LM1712 4.2600 14N LM170B 4.0999 21N LM170J 4.1056 47N LM171A 4.2591 49N LM171C 4.2688 16N LM170D 4.0967 19N LM170G 4.1087 57N LM171L 4.2497 56N LM171K 4.2463 13N LM170A 4.1015 55N LM171J 4.2448 Unit 2 Batch 18 Shipment #2 12/03/98 12 32N LM170V 4.2632 15.76 Ci 50N LM171D 4.2663 30N LM170T 4.2614 26N LM170P 4.1196 18N LM170F 4.1089
e Surry Monthly Operating Report No. 98-12 Page 16 of 19 FUEL HANDLING UNITS1 &2 MONTHNEAR: December 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 12N LM1709 4.0918 25N LM170N 4.1154 22N LM170K 4.1086 44N LM1717 4.2600 04N LM1701 4.0977 34N LM170X 4.2494 11 N LM1708 4.1039 Unit 2 Batch 18 Shipment #3 12/08/98 12 38N LM1711 4.2582 15.83 Ci 08N LM1705 4.0939 24N LM170M 4.1019 36N LM170Z 4.2498 48N LM171B 4.2583 53N LM171G 4.2421 51N LM171E 4.2600 52N LM171F 4.2684 31N LM170U 4.2636 28N LM170R 4.1012
e Surry Monthly Operating Report No. 98-12 Page17of19 FUEL HANDLING UNITS 1&2 MONTHNEAR: December 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 23N LM170L 4.1012 06N LM1703 4.1019 Unit 2 Batch 18 Shipment #4 12/10/98 12 27N LM1700 4.1169 15.79 Ci 15N LM170C 4.0993 40N LM1713 4.2494 29N LM170S 4.0935 05N LM1702 4.1020 10N LM1707 4.0922 37N LM1710 4.2510 02N LM16ZZ 4.0978 33N LM170W 4.2498 54N LM171H 4.2413 45N LM1718 4.2603 43N LM1716 4.2576 Unit 2 Batch 18 Shipment #5 12/15/98 9 07N LM1704 4.1004 11.73 Ci 03N LM1700 4.0987
- eSurry Monthly Operating Report No. 98-12 Page 18 of 19 FUEL HANDLING UNITS 1&2 MONTHNEAR: December 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 35N LM170Y 4.2506 46N LM1719 4.2600 09N LM17006 4.0942 41N LM1714 4.2590 01N LM16ZY 3.8272 20N LM170H 4.0939 42N LM1715 4.2601
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e e Surry Monthly Operating Report No. 98-12 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: December 1998 None during the Reporting Period