ML18153C404
| ML18153C404 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/30/1990 |
| From: | Stewart W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 90-634, NUDOCS 9010250289 | |
| Download: ML18153C404 (19) | |
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 15, 1990 U. S. 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.
NO/RPC:vlh Docket Nos.
License Nos.90-634 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of September 1990.
Very truly yours, JJL~
W. L. Stewart Senior Vice President - Nuclear Enclosure cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRG Senior Resident Inspector Surry Power Station
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a VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT # 90-10 APPROVED:
e POW 34-04
TABLE OF CONTENTS SECTION Operating Data Report - Unit No. 1 Operating Data Report - Unit No. 2 Unit Shutdowns and Power Reductions - Unit No. 1 Unit Shutdowns and Power Reductions - Unit No. 2 Average Daily Unit Power Level
- Unit No. 1 Average Daily Unit Power Level
- Unit No. 2 e
1 2
3 4
5 6
Summary of Operating Experience - Unit No. 1 7
Summary of Operating Experience - Unit No. 2 8
Facility Changes That Did Not Require NRC Approval 10 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 No. 1 15 Fue 1 Handling - Unit No. 2 15 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications 16 PAGE
OPERATING DATA REPORT DOCKET NO.:
50-280 DATE: -1:-:0,-,/~08~/=9=-o -----
COMPLETED BY:
L.A. Warren TELEPHONE:......,..,(8=0....... 4).... 3'"""5=-7_"""'3....... 18=4,---x3=-=5=5~
OPERATING STATUS NOTES
- 1. Unit Name:
Surry Unit 1
- 2. Reporting Period: SEPT. 01-30, 1990
- 3. Licensed Thermal Power (MWt):2441
- 4. Nameplate Rating (Gross MWe):847.5
- 5. Design Electrical Rating (Net MWe):
788
- 6. Maximum Dependable Capacity (Gross MWe):
820
- 7. Maximum Dependable Capacity (Net MWe):
781
- 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. Reason For Restrictions, If Any: -------------------
THIS MONTH YTD CUMULATIVE
- 11. Hours In Reporting Period 720.0 6551.0 155807.0
- 12. Number of Hours Reactor Was Critical 720.0 6260.7 99011. 5
- 13. Reactor Reserve Shutdown Hours 0
0 3774.5
- 14. Hours Generator On-Line 720.0 6247.0 97070.2
- 15. Unit Reserve Shutdown Hours 0
0 3736.2
- 16. Gross Thermal Energy Generated (MWH) 1192102.0 14318200.5 225435003.5
- 17. Gross Electrical Energy Generated (MWH) 387400.0 4772625.0 73318028.0
- 18. Net Electrical Energy Generated (MWH) 360026.0 4528067.0 69538997.0
- 19. Unit Service Factor 100%
95.4%
62.3%
- 20. Unit Availability Factor 100%
95.4%
64.7%
- 21. Unit Capacity Factor (Using MDC Net) 64%
88.5%
57.6%
- 22. Unit Capacity Factor (Using DER Net) 63.5%
87.7%
56.6%
- 23. Unit Forced Outage Rate 0
4.6%
20.7%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling/Snubber Outage started 10/06/90, 60 days
- 25. If Shut Down at End of Report Period Estimated Date of Startup:
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1
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OPERATING DATA REPORT DOCKET NO.:
50-281 DATE:
10/08/90 COMPLETED BY:
L.A. Warren TELEPHONE: -(.,..,,8=o-:-4)..-::3=5==-7_--=3,-a--18=4a---x3~5=5~
OPERATING STATUS NOTES
- 1. Unit Name:
Surry Unit 2
- 2. Reporting Period: SEPT. 01-30, 1990
- 3. Licensed Thermal Power (MWt):2441
- 4. Nameplate Rating (Gross MWe):847.5
- 5. Design Electrical Rating (Net MWe):
788
- 6. Maximum Dependable Capacity (Gross MWe):
820
- 7. Maximum Dependable Capacity (Net MWe):
781
- 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. Reason For Restrictions, If Any:
-~~~~~~~~~~
THIS MONTH YTD CUMULATIVE
- 11. Hours In Reporting Period 720.0 6551.0 152687.0
- 12. Number of Hours Reactor Was Critical 720.0 6375.2 97573.8
- 13. Reactor Reserve Shutdown Hours 0
0 328.1
- 14. Hours Generator On-Line 720.0 6357.7 96006.6
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1740079.1 15169617.4 224779952.2
- 17. Gross Electrical Energy Generated (MWH) 575170.0 5035235.0 73115834.0
- 18. Net Electrical Energy Generated (MWH) 546251. 0 4783722.0 69324681.0
- 19. Unit Service Factor 100%
97%
62.9%
- 20. Unit Availability Factor 100%
97%
62.9%
- 21. Unit Capacity Factor (Using MDC Net) 97.1%
93.5%
58.3%
- 22. Unit Capacity Factor (Using DER Net) 96.3%
92.7%
57.6%
- 23. Unit Forced Outage Rate 0
3%
15%
- 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 Startup:
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST~---,,.A=cH""""I=E.,...,.VE=o=---
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 2
UNIT SHUTDOWN AND POWER REDUCTION (Equal To or Greater Than 20%)
REPORT MONTH:
SEPTEMBER 1990 METHOD OF LICENSEE DOCKET NO.:
50-280 UNIT NAME:
Surry Unit (
DATE:
10/08/90 COMPLETED BY:
L.A. Warren TELEPHONE:
804-357-3184 x355 DURATION SHUTTING EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO DATE TYPE(l)
(HOURS)
REASON(2) DONN REACTOR(3)
REPORT#
CODE(4)
CODE(5)
PREVENT RECURRENCE 09/19/90 F (1)
F:
Forced S: Scheduled 0
( 2)
REASON:
A 4
A - Equipment Failure (Explain)
B ~ Maintenance or Test C - Refueling D - Regulatory Restriction*
N/A E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain)
TA (3)
METHOD:
1 - Manual V
2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain) 3 As a result of the failure of the #3 governor valve positioning arm.
the associated linear varia e differential transformer (LVDT),
several load swings occurred.
These swings began occurring with the Unit operating at 66%
power.
The Unit was stabilized at a power level of 39%.
The turbine control status at that time was as follows:
- 1) valve position limiter in use;
- 2) turbine was in 11 Imp Out" and "Turbine Manual".
(4)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)
File (NUREG 0161)
(5)
Exhibit 1 - Same Source e
UNIT SHUTDOWN AND POWER REDUCTION
{Equal To or Greater Than 20%)
REPORT MONTH:
SEPTEMBER 1990 METHOD OF LICENSEE DOCKET NO.:
50-281 UNIT NAME:
Surry Unit 2 DATE:
10/08/90 COMPLETED BY:
L.A. Warren TELEPHONE:
804-357-3184 x355 DURATION SHUTTING EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO DATE TYPE(!)
{HOURS)
REASON{2) DOWN REACTOR{J)
REPORT#
CODE{4)
CODE{5)
PREVENT RECURRENCE 09/04/90 S 09/27/90 S (I)
F:
Forced S: Scheduled 0
0 (2)
REASON:
B 4
B 4
A - Equipment Failure (Explain)
B - Maintenance or Test C - Refueling D - Regulatory Restriction N/A N/A E - Operator Training & License Examination F - Administrative G - Operational Error {Explain)
H - Other {Explain)
SG TA (3)
METHOD:
1 - Manual HX V
2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain) 4 Reduced power from 100% to 69%~
order to maintain condenser vacu during waterbox cleaning operations.
Reduced power from 100% to 77%
inorder to perform 2-PT-29.1 turbine valves freedom test.
(4)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)
File {NUREG 0161)
{5)
Exhibit 1 - Same Source e
~
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:
50-280 UNIT NAME:
Surry Unit 1 DATE:
10/08/90 COMPLETED BY:
L.A. Warren TELEPHONE:(804)357-3184 x355 MONTH:
SEPTEMBER 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 577 17 501 2
575 18 502 3
570 19 378 4
568 20 446 5
562 21 486 6
552 22 481 7
540 23 459 8
546 24 464 9
550 25 459 10 541 26 455 11 528 27 449 12 521 28 422 13 521 29 406 14 517 30 403 15 512 31 16 510 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.
5
AVERAGE DAILY UNIT POWER LEVEL MONTH:
SEPTEMBER 1990 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 709 2
760 3
756 4
749 5
714 6
763 7
759 8
713 9
759 10 770 11 759 12 766 13 752 14 768 15 768 16 765 INSTRUCTIONS DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 DOCKET NO.:
50-281
-.,,..-~,--,..~--
UNIT NAME:
Surry Unit 2 DATE:
10/08/90 COMPLETED BY:
L.A. Warren TELEPHONE:(804)357-3184 x355 AVERAGE DAILY POWER LEVEL (MWe-Net) 770 769 771 772 769 747 770 769 772 776 732 774 771 771 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.
6
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SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR:
SEPTEMBER 1990 Listed below in 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 09/01/90 0000 This reporting period started with the Unit coasting at 77.8%
power and 620 MWe due to fuel depletion.
09/19/90 1305 The Unit began experiencing load swings of approximately 10 - 15 MWe.
Operators promptly took action to stabilize the unit.
However, the magnitude of the swings increased and an instantaneously load decrease. from 550 MWe to 250 MWe occurred.
The turbine was placed under manual control.
Investigation revealed that a failure of the #3 governor valve positioning arm had occurred.
2244 Following repairs, a slow power increase was initiated as conditions permitted (Xenon Burnout); 39% power, 260 MWe.
09/20/90 0730 Stopped ramp; 65.5% power, 490 MWe.
09/30/90 2400 This reporting period ended with the Unit coasting; 57% power, 440 MWe.
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SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR:
SEPTEMBER 1990 Listed below in 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 TWO 09/01/90 0000 This reporting period started with the Unit operating at 96.1%
power, 775 MWe.
09/02/90 09/04/90 09/05/90 09/08/90 09/11/90 1856 2003 2249 0105 2147 0045 0333 0648 0917 1100 1644 1857 0126 0230 0400 0500 Started ramp down to place moisture separators/reheaters in service; 96.1% power, 775 MWe.
Stopped ramp; 80.5% power, 650 MWe.
Started ramp up; 80% power, 650 MWe.
Stopped ramp; 100% power, 805 MWe.
Started ramp down to clean waterboxes; 100% power, 795 MWe.
Stopped ramp; 69% power, 560 MWe.
Started ramp up; 69% power, 560 MWe.
Stopped ramp; 100% power, 815 MWe.
Started ramp down to clean waterboxes; 100% power, 800 MWe.
Stopped ramp; 84% power, 660 MWe.
Started ramp up; 83% power, 660 MWe.
Stopped ramp 100% power, 810 MWe.
Started ramp down to clean waterboxes; 100% power, 810 MWe.
Stopped ramp; 95% power, 740 MWe.
Started ramp up; 95% power, 775 MWe.
Stopped ramp; 100% power, 810 MWe.
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SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR:
SEPTEMBER 1990 Listed below in 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 TWO 09/13/90 0220 Started ramp down to clean waterboxes; 100% power, 790 MWe.
0310 Stopped ramp; 89.3% power, 700 MWe.
0535 Started ramp up; 89.3% power, 690 MWe.
0705 Stopped ramp; 100% power, 805 MWe.
09/22/90 0320 Started ramp down to clean waterboxes; 100% power, 785 MWe.
0430 Stopped ramp; 90% power, 700 MWe.
0505 Started ramp up; 90% power, 700 MWe.
0550 Stopped ramp; 100% power, 810 MWe.
1237 Started ramp down to clean waterboxes; 100% power, 800 MWe.
1335 Stopped ramp; 90% power, 710 MWe.
1517 Started ramp up; 90.5% power, 730 MWe.
1645 Stopped ramp; 100% power, 805 MWe.
09/27/90 1006 Started ramp down to perform 2-PT-29.1; 100% power, 815 MWe.
1140 Stopped ramp; 77% power, 660 MWe.
1631 Started ramp up; 78.9% power, 655 MWe.
1822 Stopped ramp; 100% power, 820 MWe.
09/30/90 2400 This reporting period ended with the Unit operating at 100%
power, 815 MWe.
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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
SEPTEMBER 1990 JC0-90-1-003 JUSTIFICATION FOR CONTINUED OPERATION (Safety Evaluation #90-0218)
UNIT 1 09/02/90 AC-90-0912 AC-90-0925 Test switch #3 on the flood control panel is to be put in the test position, defeating the close signal from the flood control panel to two 96 inch circulating water valves 1-CW-MOV-106A & C.
Operations will provide a flood watch in the turbine building.
The flood control signal is not safety
- related, and a
compensatory flood watch will be established to notify the control room immediately of flooding so that the affected valves can be closed.
Normal flood protection alarms still function and are not being altered. Therefore, an unreviewed safety question does not exist.
ADMINISTRATIVE CONTROL UNIT 1 09/12/90 (Safety Evaluation #90-0221)
The missile plug above an emergency service water pump (1-SW-P-lC) will be removed to allow removal of 1-SW-P-lC for inspection.
Administrative control actions require that the missile plug be replaced if missile generating weather is threatening. Necessary equipment and personnel will remain available to replace the missile plug as necessary.
Therefore, an unreviewed safety question is not created.
ADMINISTRATIVE CONTROL UNIT 2 09/25/90 (Safety Evaluation #90-0226)
Administrative control to allow a service water rotating strainer (1-VS-S-lA) to be removed from service for maintenance without interrupting service water (SW) flow to the control room chillers and charging pump service water pumps.
This administrative control is necessary to maintain compliance with 10CFR50 Appendix R analyses.
Operation of the normally closed manual valve 1-SW-265 will allow for uninterrupted service water flow to the control room chillers and charging pump SW pumps while 1-VS-S-lA is taken out of service for maintenance.
The ease of access to 1-SW-265, located in Mechanical Equipment Room #3, allows sufficient time for operator action to close the valve in case of an Appendix R fire.
Consequently, utilizing the existing bypass line around 1-VS-S-lA by opening normally closed 1-SW-265 and maintaining administrative control of 1-SW-265 while in the open position, will not create an unreviewed safety question.
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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
SEPTEMBER 1990 AC-90-0924A ADMINISTRATIVE CONTROL UNIT 1 09/27/90 (Safety Evaluation #90-0229)
Administrative control of certain flood protection dikes to facilitate moving heavy equipment into or out of the emergency switchgear room (ESGR).
The removal of the flood dike at the entrance to the ESGR increases the consequence of a flood unless administrative controls are placed to reinstall the dike promptly in case of flooding indications in the turbine building basement.
The removal of the dike will not adversely affect safety related equipment or create an unanalyzed accident condition because the administrative controls adequately compensate for the worst case consequences of a flood.
Operations notification prior to disassembly, the roving flood watch in the turbine building, and reinstallation personnel present during the period of removal provide compensatory measures assuring that the dike section can be reinstalled prior to the flood damage in the ESGR.
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i PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
SEPTEMBER 1990 NONE DURING THIS REPORTING PERIOD 12
j.,...
TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
SEPTEMBER 1990 NONE DURING THIS REPORTING PERIOD 13
e VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT MONTH/YEAR:
SEPTEMBER 1990 PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAX.
MIN.
AVG.
MAX.
MIN.
AVG.
Gross Radioact., µCi/ml 8.75E-1 5.69E-1 7.22E-1 3.07E-1 1.47E-1 2.27E-1 Suspended Solids, ppm 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, µCi/ml 8.31E-2 6.81E-2 7.72E-2
- 1. 37E-1 9.80E-2 1.13E-1 Iodine-131, µCi/ml 8.21E-3 4.12E-3 6.17E-3 1.25E-3 3.79E-4
- 8. lOE-4 Iodine-131/Iodine-133 0.18 0.13 0.16 0.15 0.06E 0.11 Hydrogen, cc/kg 33.8 25.7 29.8 34.4 26.8 30.6 Lithium, ppm 0.82 0.70 0.76 2.34 2.04 2.19 Boron - 10, ppm**
0.392 0.196 0.294 74.284 54.684 64.484 Oxygen, (DO), ppm
~0.005
~0.005
~0.005
~0.005
~0.005
~0.005 Chloride, ppm 0.002 0.001 0.002 0.006 0.002 0.004 pH@ 25 degree Celsius 9.32 8.83 9.10 7.17 6.93 7.05
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UNIT 1&2 NEW OR SPENT FUEL SHIPMENT fl DATE SHIPPED OR RECEIVED e
FUEL HANDLING NUMBER OF ASSEMBLIES ASSEMBLY ANSI PER SHIPMENT NUMBER NUMBER NONE DURING THIS REPORTING PERIOD 15 e
DATE:
SEPT.1990 NEW OR SPENT INITIAL FUEL SHIPPING ENRICHMENT CASK ACTIVITY LEVEL
DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR:
SEPTEMBER 1990 NONE DURING THIS REPORTING PERIOD 16