ML18152B379
| ML18152B379 | |
| Person / Time | |
|---|---|
| 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) | |
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VIRGINIA ELECTRIC AND PowER CoMPANY RICHMOND, VIRGINIA 23261 August 11, 1999 United States 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.
SPS Lic/JSA Docket Nos.
License Nos.99-410 RO 50-280 50-281 DPR-32 DPR-37 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
e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 99-07 Approved:
e TABLE OF CONTENTS Section e
Surry Monthly Operating Report No. 99-07 Page 2 of 18 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
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
OPERATING DATA REPORT e
Surry Monthly Operating Report Docket No.:
Date:
No. 99-07 Page3of18 Completed By:
50-280 08/02/99 R. Stief Unit Name:...........................................................
Reporting Period:.................................................
Licensed Thermal Power (MWt):..........................
Nameplate Rating (Gross MWe):.........................
Design Electrical Rating (Net MWe):....................
Maximum Dependable Capacity (Gross MWe):...
Maximum Dependable Capacity (Net MWe):.......
Surry Unit 1 July 1999 2546 847.5 788 840 801 Telephone:
(757) 365-2486
- 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):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
OPERATING DATA REPORT e
Surry Monthly Operating Report No. 99-07 Page 4 of 18 Docket No.:
Date:
Completed By:
50-281 08/02/99 R. Stief Unit Name:...........................................................
Reporting Period:.................................................
Licensed Thermal Power (MW!):..........................
Nameplate Rating (Gross MWe):.........................
Design Electrical Rating (Net MWe):....................
Maximum Dependable Capacity (Gross MWe):...
Maximum Dependable Capacity (Net MWe):.......
Surry Unit 2 July 1999 2546 847.5 788 840 801 Telephone:
(757) 365-2486
- 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
- 11.
Hours in Reporting Period 744.0 5087.0
- 12.
Hours Reactor Was Critical 502.3 3945.8
- 13.
Reactor Reserve Shutdown Hours 0.0 0.0
- 14.
Hours Generator On-Line 496.4 3821.9
- 15.
Unit Reserve Shutdown Hours 0.0 0.0
- 16.
Gross Thermal Energy Generated (MWH) 1238455.9 8989590.1
- 17.
Gross Electrical Energy Generated (MWH) 405470.0 3004950.0
- 18.
Net Electrical Energy Generated (MWH) 391158.0 2897467.0
- 19.
Unit Service Factor 66.7%
75.1%
- 20.
Unit Availability Factor 66.7%
75.1%
- 21.
Unit Capacity Factor (Using MDC Net) 65.6%
71.1%
- 22.
Unit Capacity Factor (Using DER Net) 66.7%
72.3%
- 23.
Unit Forced Outage Rate 33.3%
6.1%
- 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 Cumulative 230112.0 163856.1 328.1 161715.4 0.0 382785239.1 125552843.0 119719494.0 70.3%
70.3%
66.5%
66.0%
11.2%
e Surry Monthly Operating Report No. 99-07 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
(1)
Date Type 07/10/99 s
(1)
F:
Forced S:
Scheduled (4)
REPORT MONTH: July 1999 (2)
Duration Hours Reason 19H 32M B
(2)
REASON:
(3)
Method of LER No.
Shutting Down Rx N/A N/A A
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction (4)
System Code SG 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 (NU REG 0161)
Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
08/02/99 Completed by:
J. R. Pincus Telephone:
(757) 365-2863 (5)
Component Code COND (3)
METHOD:
Cause & Corrective Action to Prevent Recurrence Clean condenser waterbox 1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit 1 - Same Source
e Surry Monthly Operating Report No. 99-07 Page 6 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
(1)
Date Type 07/05/99 F
07/31/99 s
(1)
F:
Forced S:
Scheduled (4)
REPORT MONTH: July 1999 (2)
Duration Hours Reason 247H 33M A
18H 48M B
(2)
REASON:
(3)
Method of LER No.
Shutting Down Rx 3
82-1999-003 N/A N/A A
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction (4)
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 (NU REG 0161)
Docket No.:
50-281 Unit Name:
Surry Unit 2 Date:
08/02/99 Completed by:
J. R. Pincus Telephone:
(757) 365-2863 (5)
Component Code ISV COND (3)
METHOD:
Cause & Corrective Action to Prevent Recurrence 2-RC-MOV-2591 disc separated from stem Clean condenser waterbox 1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit 1 - Same Source
MONTH:
July 1999 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS e
Surry Monthly Operating Report No. 99-07 Page 7 of 18 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)
Day 808 17 808 18 806 19 804 20 793 21 786 22 790 23 792 24 792 25 756 26 679 27 805 28 788 29 790 30 789 31 810 Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
08/02/99 Completed by:
J. S. Ashley Telephone:
(757) 365-2161 Average Daily Power Level (MWe - Net)
- 812 811 809 809 809 806 806 807 808 806 806 806 804 805 803 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:
July 1999 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS e
e Surry Monthly Operating Report No. 99-07 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)
Day 812 17 813 18 810 19 808 20 382 21 0
22 0
23 0
24 0
25 0
26 0
27 0
28 0
29 0
30 50 31 684 Docket No.: 50-281 Unit Name:
Surry Unit 2 Date: 08/06/99 Completed by:
J. S. Ashley Telephone: (757) 365-2161 Average Daily Power Level (MWe - Net) 810 810 811 809 809 807 805 807 807 805 803 801 799 800 656 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
SUMMARY
OF OPERATING EXPERIENCE MONTHNEAR: July 1999 e
Surry Monthly Operating Report No. 99-07 Page 9 of 18 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 07/10/99 1855 07/10/99 2152 07/11/99 1115 07/11/99 1247 07/11/99 1325 07/11/99 1422 07/31/99 2400 UNIT Two:
07/01/99 0000 07/05/99 1121 07/15/99 1213 07/15/99 1303 07/15/99 1854 07/15/99 1950 07/15/99 2106 07/16/99 0211 07/16/99 0251 07/16/99 0434 07/16/99 0604 07/16/99 0702 07/16/99 1426 07/16/99 1445 07/16/99 1955 07/16/99 2208 07/31/99 0407 07/31/99 0441 07/31/99 0627 07/31/99 0754 07/31/99 2040 Unit started the month at 100% / 844 MWe.
Commenced ramp down to maintain condenser vacuum, Unit at 100% / 822 MWe.
Stopped ramp, Unit at 75% / 586 MWe.
Commenced ramp to 100%, Unit at 76% / 630 MWe.
Stopped ramp for IRPI adjustment, Unit at 98% / 805 MWe.
Recommenced ramp to 100%.
Unit at 100% / 825 MWe.
Unit finished the month at 100% / 837 MWe.
Unit started the month at 100% / 845 MWe.
Unit trip due to "A" loop stop valve disc separation from stem.
Commenced Reactor startup.
Reactor critical.
Unit on-line, commenced ramp up.
Stopped ramp, Unit at 30% / 205 MWe.
Recommenced ramp, Unit at 30% / 205 MWe.
Stopped ramp, Unit at 53% / 400 MWe.
Recommenced ramp, Unit at 53% / 400 MWe.
Stopped ramp, Unit at 75% / 640 MWe.
Recommenced ramp to 91 %.
Stopped ramp, Unit at 90% / 760 MWe.
Recommenced ramp to 96%.
Unit at 96% / 815 MWe.
Commenced ramp to 100%, Unit at 96.5% / 815 MWe.
Unit at 100% / 840 MWe.
Commenced ramp down for waterbox scraping. Unit at 100% / 820 MWe.
Stopped ramp, Unit at 94% / 765 MWe.
Recommenced ramp, Unit at 94% / 765 MWe.
Unit at 81 % / 655 MWe.
Commenced ramp up, Unit at 72% / 590 MWe.
UNIT Two (CONT):
07/31/99 07/31/99 07/31/99 07/31/99 2140 2204 2255 2400 Stopped ramp, Unit at 88% / 740 MWe.
Recommenced ramp, Unit at 88% / 740 MWe.
Unit at 100% I 832 MWe.
Unit finished the month at 99% / 825 MWe.
e Surry Monthly Operating Report No. 99-07 Page 10 of 18
DCP 92-028-3 DCP 99-031 FS99-020 TM S2-99-005 FS99-001 FS99-018 TS 346 (Basis Only) e
-Surry Monthly Operating Report No. 99-07 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July 1999 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.
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.
UFSAR Change Request (Safety Evaluation 99-060) 07/01/99 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.
Temporary Modification (Safety Evaluation 99-061) 07/01/99 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.
UFSAR Change Request (Safety Evaluation 99-062) 07/01/99 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.
UFSAR Change Request Technical Specification Change Request (Safety Evaluation 99-063) 07/01/99 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.
TRM Rev. 0 FS99-023 FS98-036 TM S1-99-006 TM S2-99-007 TM S2-99-008 e
Surry Monthly Operating Report No. 99-07 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July 1999 Technical Requirements Manual UFSAR Change Request (Safety Evaluation 99-064) 07/01/99 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.
UFSAR Change Request (Safety Evaluation 99-066) 07/08/99 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.
Temporary Modification (Safety Evaluation 99-067) 07/09/99 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.
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.
Temporary Modification (Safety Evaluation 99-070) 07/19/99 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.
Surry Monthly Operating Report No. 99-07 Page 13 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July 1999 UFSAR Change Request (Safety Evaluation 99-071) 07/22/99 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.
UFSAR Change Request (Safety Evaluation 99-072) 07/29/99 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.
2B-62/H-6 2-0P-RC-005 O-MOP-BR-001 e
e PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July 1999 Annunciator Response Procedure Operating Procedure (Safety Evaluation 99-065)
Surry Monthly Operating Report No. 99-07 Page 14 of 18 07/07/99 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.
Maintenance Operating Procedure (Safety Evaluation 99-073) 07/29/99 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 CHEMISTRY REPORT MONTHNEAR: July 1999 Unit No. 1 Primarv Coolant Analysis Max.
Min.
Ava.
Gross Radioactivity, µCi/ml 3.30E-1 1.92E-1 2.56E-1 Suspended Solids, oom Gross Tritium, µCi/ml 1.04E+O 9.15E-1 9.69E-1 11 31, µCi/ml 5.78E-4 2.14E-4 3.96E-4 113111133 0.1 0.05 0.07 Hydroaen, cc/ka 38.9 35.8 36.9 Lithium, oom 2.33 2.08 2.2 Boron - 10, ppm*
168.86 145.43 154.01 Oxygen, (DO), ppm
- 0.005
- 0.005
None e
Surry Monthly Operating Report No. 99-07 Page 16 of 18 Unit No. 2 Max.
Min.
Ava.
2.20E-1 3.19E-3 1.25E-1 0.25 0.01 0.13 3.31E-1 6.38E-2 1.55E-1
- 1.62E-4
- 5.93E-5
- 8.73E-5
- 0.37
- 0.16
- 0.26 35 2.6 17.4 3.15 0.21 2.01 454.92 226.58 322.16 0.35
- 0.005
- 0.022 0.01 0.003 0.007 6.53 5.09 5.94
New Fuel Shipment or
- Cask No, FUEL HANDLING UNITS 1 & 2 MONTHNEAR: July 1999 Number of Date Stored or Assemblies Received per Shipment Assembly Number ANSI Number None during the Reporting Period e
Surry Monthly Operating Report No. 99-07 Page17of18 Initial Enrichment New or Spent Fuel Shipping Cask Activity
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