ML18152B434
| ML18152B434 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 05/31/1999 |
| From: | Ashley J, Pincus J, Stief R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 99-325, NUDOCS 9906180101 | |
| Download: ML18152B434 (18) | |
Text
j VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 14,1999 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.99-325 RO 50-280 50-281 DPR-32 DPR-37 The rvlonthly Operating Report for Surry Power Station Units 1 and 2 for the month of May 1999 is provided in the attachment.
If you have any questions or require additional information, pleas~ 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 NRC Senior Resident Inspector Surry Power Station
- 9906180101-990531 ---- -
PDR ADOCK 05000280 R
-- ~------
I
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 99-05 Approved:
Date
TABLE OF CONTENTS Section Surry Monthly Operating Report No. 99-05 Page 2 of 17 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............................................................................................ 1 O 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 Nos. 1 and 2............................................................................................................................ 16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications....................................................................................................................... 17
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
OPERATING DATA REPORT
- Surry Monthly Operating Report No. 99-05 Page3of17 Docket No.:
Date:
Completed By:
50-280 06/01/99 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 May 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 3623.0 231767.0
- 12.
Hours Reactor Was Critical 744.0 3623.0 164939.5
- 13.
Reactor Reserve Shutdown Hours 0.0 0.0 3774.5
- 14.
Hours Generator On-Line 744.0 3623.0 162394.4
- 15.
Unit Reserve Shutdown Hours 0.0 0.0 3736.2
- 16.
Gross Thermal Energy Generated (MWH) 1894224.0 9221999.1 383412956.6
- 17.
Gross Electrical Energy Generated (MWH) 627876.0 3067468.0 125837624.0
- 18.
Net Electrical Energy Generated (MWH) 603769.0 2960850.0 119947454.0
- 19.
Unit Service Factor 100.0%
100.0%
70.1%
- 20.
Unit Availability Factor 100.0%
100.0%
71.7%
- 21.
Unit Capacity Factor (Using MDC Net) 101.3%
102.0%
66.4%
- 22.
Unit Capacity Factor (Using DER Net) 103.0%
103.7%
65.7%
- 23.
Unit Forced Outage Rate 0.0%
0.0%
14.1%
- 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
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
OPERATING DATA REPORT
- Surry Monthly Operating Report No. 99-05 Page 4 of 17 Docket No.:
Date:
Completed By:
50-281 06/01/99 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 2 May 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 3623.0
- 12.
Hours Reactor Was Critical 155.4 2723.5
- 13.
Reactor Reserve Shutdown Hours 0.0 0.0
- 14.
Hours Generator On-Line 37.6 2605.5
- 15.
Unit Reserve Shutdown Hours 0.0 0.0
- 16.
Gross Thermal Energy Generated (MWH) 42497.9 5979790.2
- 17.
Gross Electrical Energy Generated (MWH) 11435.0 2010955.0
- 18.
Net Electrical Energy Generated (MWH) 10512.0 1938265.0
- 19.
Unit Service Factor 5.1%
71.9%
- 20.
Unit Availability Factor 5.1%
71.9%
- 21.
Unit Capacity Factor (Using MDC Net) 1.8%
66.8%
- 22.
Unit Capacity Factor (Using DER Net) 1.8%
67.9%
- 23.
Unit Forced Outage Rate 0.0%
0.0%
- 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 Cumulative 228648.0 162633.8 328.1 160499.0 0.0 379775439.2 124558848.0 118760292.0 70.2%
70.2%
66.4%
65.9%
11.2%
Surry Monthly Operating Report No. 99-05 Page 5 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
(1)
F:
Forced S:
Scheduled (4)
REPORT MONTH: May 1999 None during the Reporting Period (2)
REASON:
A Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction 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:
06/02/99 Completed by: J. R. Pincus Telephone:
(757) 365-2863 (3)
METHOD:
1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit 1 - Same Source
(1)
Date Type 05/01/99 s
(1)
F:
Forced S:
Scheduled (4)
(2)
Surry Monthly Operating Report No. 99-05 Page6of17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: May 1999 (3)
(4)
Method Docket No.:
50-281 Unit Name:
Surry Unit 2 Date:
06/02/99 Completed by: J. R. Pincus Telephone:
(757) 365-2863 (5)
Duration of LER No.
System Component Cause & Corrective Action Hours 706.4 Reason C
(2)
REASON:
Shutting Down Rx 1
N/A A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction Code N/A E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
Code to Prevent Recurrence N/A (3)
METHOD:
Refueling Outage 1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NU REG 0161)
Exhibit 1 - Same Source
MONTH:
May 1999 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS Surry Monthly Operating Report No. 99-05 Page7of17 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)
Day 822 17 822 18 822 19 821 20 820 21 819 22 818 23 816 24 816 25 815 26 815 27 815 28 814 29 816 30 816 31 816 Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
06/01/99 Completed by: J. S. Ashley Telephone:
(757) 365-2161 Average Daily Power Level (Mwe - Net) 818 817 816 816 809 800 800 794 793 800 797 794 806 802 810 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:
May 1999 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS AVERAGE DAILY UNIT POWER LEVEL
- Surry Monthly Operating Report Docket No.:
50-281 No. 99-05 Page 8 of 17 Unit Name:
Surry Unit 2 Date:
06/01/99 Completed by: J. S. Ashley Telephone:
(757) 365-2161 Average Daily Power Level Average Daily Power Level (Mwe - Net)
Day (Mwe - Net) 0 17 0
0 18 0
0 19 0
0 20 0
0 21 0
0 22 0
0 23 0
0 24 0
0 25 0
0 26 0
0 27 0
0 28 0
0 29 0
0 30 85 0
31 353 0
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 MONTHNEAR: May 1999 Surry Monthly Operating Report No. 99-05 Page9of17 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:
05/01/99 05/31/99 UNIT TWO:
05/01/99 05/25/99 05/25/99 05/30/99 05/31/99 0000 2400 0000 1052 1221 1025 2400 Unit started the month at 100% / 850 MWe.
Unit finished the month at 100% / 841 MWe.
Unit started the month at 0% / O MWe for refueling outage.
Commenced reactor startup.
Reactor critical.
Unit on-line.
Unit finished the month at 65% / 532 MWe.
DCP 95-038 DCP 98-053 FS99-005 NE-1190 NE-1190, Rev. 1 NE-1190, Rev. 2 SE 99-026, Rev. 1 ET CME 99-0017 Surry Monthly Operating Report No. 99-05 Page 10 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: May 1999 Design Change Package (Safety Evaluation 95-167) 05/14/99 Unit 2 Individual Control Rod Position Indicator (!RPI) M-10 indicated a position of 20 to 30 steps following a Unit trip. Design Change Package 95-038, "RD Rod Position Indicators Search Coils (RPI-M-1 O)", implemented the actions for correcting the !RPI to provide a more accurate indication of the position of rod M-10.
Design Change Package UFSAR Change Request (Safety Evaluation 99-009, Rev. 1) 05/15/99 Design Change Package 98-053, "LHSI Recirculation Line Relocation/Surry/Unit 2", located the recirculation line for the Unit 2 Low Head Safety Injection (LHSI) pumps to originate at the upstream side of each pump's discharge side check valve. This reduces the potential for pump damage when the pumps operate in a parallel operating configuration and are recirculating back to the Refueling Water Storage Tank (RWST). The predicted recirculation flow rates were not achieved during post modification testing. Revision 1 of Safety Evaluation 99-009 discusses how the lower flow rates are acceptable and do not place the pumps in danger of malfunction or failure.
Reload Safety Evaluation Technical Report (Safety Evaluations99-015, Rev. 0, Rev. 1, Rev. 2) 03/11/99 Technical Report NE-1190, Rev. 0, "Reload Safety Evaluation Surry 2 Cycle 16 Pattern 00", March 1999, examines operation of Surry Unit 2 Cycle 16 using fuel of higher enrichment and modified burnable poison (BP) rods with a slightly increased poison stack length. Revision 1, of the Safety Evaluation dated May 4, 1999, accommodates the re-evaluation performed for a redesign of S2C16, designated as Pattern AP. Revision 2, of the Safety Evaluation dated May 15, 1999, accommodates the re-evaluation performed for a redesign of S2C16, designated as Pattern AG. Both revisions addressed top nozzle replacements on some fuel assemblies and the core reconfiguration for other assemblies that were replaced with suitable substitutes from the spent fuel pool.
Safety Evaluation 05/09/99 Safety Evaluation 99-026 evaluated the 1999 Unit 2 Refueling Outage against current industry guidelines and Virginia Power administrative requirements for shutdown risk management including NUMARC 91-06 and NE Technical Report 865, Rev. 3. The schedule provided a plan for safely and efficiently accomplishing refueling, maintenance, modification, and testing activities. Revision 1 addresses the prevention of hydrogen gas while freshening charges are performed on the 2A and 28 Station Batteries.
Engineering Transmittal (Safety Evaluation 99-040) 05/04/99 Based on the review of the dose consequences of post-LOCA Emergency Core Cooling System (ECCS) leakage in the Auxiliary Building, the allowable total leakage in some areas is being reduced to more easily demonstrate compliance with GDC 19 and 10CFR100.
Affected Periodic Test procedures have been updated and the UFSAR will be updated to reflect the new allowable ECCS leakage.
TM S2-99-001 FS99-010 DCP 99-047 DCP 99-031 FS99-017 TM S2-99-004 DCP 99-053 Surry Monthly Operating Report No. 99-05 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: May 1999 Temporary Modification (Safety Evaluation 99-042) 05/12/99 Temporary Modification S2-99-001 modified the Manipulator Crane Gripper and Fuel Building Long Handling Tool to allow removal of fuel assemblies with damaged top nozzle guide holes.
UFSAR Change Request (Safety Evaluation 99-043) 05/13/99 As a result of the Integrated Configuration Management Project review, UFSAR Change Request FS99-010 contains corrections and clarifications to the UFSAR sections that discuss Surry's Emergency Power System. These changes are to enhance accuracy and do not affect any emergency power system or structure, or any of its component's operation or performance.
Design Change Package (Safety Evaluation 99-045) 05/15/99 Design Change Package 99-047, "2-SI-MOV-2869A Replacement/Surry/Unit 2", documents the replacement of valve 2-S1-MOV-2869A with different materials than documented in UFSAR 6.2.2.2.4, "Motor Operated Valves".
Design Change Package (Safety Evaluation 99-047) 05/17/99 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 one condenser.
UFSAR Change Request (Safety Evaluation 99-049) 05/27/99 UFSAR Change Request FS99-017 removes some details and corrects some design data from section 11.2.3.1.8 describing the operation of the reverse osmosis and demineralization systems at the Surry Radwaste Facility.
Temporary Modification (Safety Evaluation 99-050) 05/28/99 Temporary Modification 82-99-004 plugged the broken inner gland supply sensing line for the high-pressure turbine cylinder heating pressure control valve 2-MS-PCV-223 to prevent steam leakage.
Design Change Package (Safety Evaluation 99-052) 05/28/99 Design Change Package 99-053, "RC Loop 1 Delta-T and T-ave/Surry/Unit 2", enhances the Reactor Protection System performance by reducing the potential for spurious rod block and turbine runback signals from process noise.
2-0PT-Sl-007 OT0-1 O-OP-FH-004 O-ECM-1511-01 2-0PT-Sl-008 OT0-1 2-IPT-CC-RC-T-412 2-IPT-FT-RC-T-412 TM S2-99-002 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: May 1999 Operations Periodic Test Procedure (Safety Evaluation 99-041)
Surry Monthly Operating Report No. 99-05 Page 12 of 17 05/06/99 Operations Periodic Test Procedure 2-0PT-Sl-007, "Refueling Test of the HHSI Check Valves to Cold Leg", was changed to provide a Temporary Modification to install pressure gages and transducers on the High High Safety Injection (HHSI) lines upstream and downstream of several Safety Injection (SI) valves to monitor valve differential pressures to satisfy the requirements of GL 96-05.
Operating Procedure 05/15/99 (Safety Evaluation 99-044, Rev. 0, Rev. 1)
Operating Procedure O-OP-FH-004, "Operation of the Fuel Assembly Cruciform Handling Tool", was the procedure to be used when the Special Fuel Assembly Cruciform Handling Tool (SFACHT) was proposed as an alternative method to latch onto a damaged fuel assembly that the Manipulator Crane Gripper could not engage. Revision 1 documented the changing of the rigging method that ensured the fuel assembly remained properly submerged.
Electrical Corrective Maintenance Procedure (Safety Evaluation 99-044A) 05/13/99 Electrical Corrective Maintenance Procedure O-ECM-1511-01, "Emergency Operation of Main Steam Non-Return Valves", was written to provide guidance for opening the Main Steam Non-Return Valves at the Motor Control Center after fire damage in the Main Control Room to facilitate cool down.
Operations Periodic Test Procedure (Safety Evaluation 99-046) 05/17/99 Operations Periodic Test Procedure 2-0PT-Sl-008, "Refueling Test of the HHSI Check Valves to Hot Leg", was changed to provide a Temporary Modification to install pressure gages and transducers on the High High Safety Injection (HHSI) lines upstream and downstream of several Safety Injection (SI) valves to monitor valve differential pressures to satisfy the requirements of GL 96-05.
Instrument Periodic Test Procedures Temporary Modification (Safety Evaluation 99-048) 05/24/99 Instrument Periodic Test Procedures 2-IPT-CC-RC-T-412, "Delta-T and Tavg Protection Set 1, Loop T-412 Channel Calibration", 2-IPT-FT-RC-T-412, "Delta-T and Tavg Protection Set 1, Loop T-412 Functional Test", and Temporary Modification S2-99-002 address the removal from service of one inoperable Resistance Temperature Detector (RTD) from the Unit 2 Reactor Coolant System (RCS) "A" loop. In order to declare the loop "A" temperature indicating system operable, the RCS temperature protection and control system has been re-programmed to calculate T-hot-avg with 2 of 3 RTDs in service.
2-TOP-CN-4090 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: May 1999 Temporary Operating Procedure (Safety Evaluation 99-051)
Surry Monthly Operating Report No. 99-05 Page 13 of 17 05/28/99 A temporary vacuum pump was connected to the Unit 2 condenser to assist in establishing the desired vacuum. This temporary pump would be a possible unmonitored path for the release of radiation in the event of a steam generator tube rupture. Temporary Operating Procedure 2-TOP-CN-4090, "Administrative Control and Operation of the Temporary Condenser Vacuum System", was written to administratively control the vacuum breaker if a condition occurs that requires flow path isolation.
Surry Monthly Operating Report No. 99-05 Page 14 of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May 1999 None during the Reporting Period
Primary Coolant Analysis Gross Radioactivity, µCi/ml Suspended Solids, oom Gross Tritium, µCi/ml 1131, µCi/ml 113111133 Hydroqen, cc/kq Lithium, ppm Boron - 10, ppm*
Oxygen, (DO), ppm Chloride, ppm pH @ 25 deqree Celsius Boron - 1 O = Total Boron x 0.196 Comments:
None Max.
3.53E-1 CHEMISTRY REPORT MONTH/YEAR: May 1999 Unit No. 1 Min.
Ava.
1.64E-1 2.68E-1 1.03E+O 8.50E-1 9.82E-1 4.35E-4 2.26E-4 3.15E-4 0.08 0.04 0.06 38.3 36.4 37.5 2.35 2.06 2.2 196.98 178.75 188.86
< 0.005
< 0.005
< 0.005 0.02 0.017 0.018 6.8 6.51 6.59 Surry Monthly Operating Report Unit No. 2 Max.
Min.
7.07E-2 1.05E-3 0.5 0.01 3.21 E-2 2.90E-2
- c:;1.19E-4
- ,; 2.41 E-5 29.4 12.5 3.48 0.01 485.3 300.86 8
< 0.005 0.007 0.001 6.33 4.67 No. 99-05 Page15of17 Avq.
7.22E-3 0.142 3.06E-2
- ,; 5.78E-5 23.9 1.5 408.55 4.09 0.003 4.49 l
New Fuel Shipment or Cask No.
Number of Date Stored or Assemblies FUEL HANDLING UNITS 1 & 2 MONTHNEAR: May 1999 Received per Shipment Assembly Number ANSI Number None during the Reporting Period Surry Monthly Operating Report Initial Enrichment No. 99-05 Page16of17 New or Spent Fuel Shipping Cask Activity
Surry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: May 1999 None during the Reporting Period
- No. 99-05 Page 17 of 17