ML18153B207
| ML18153B207 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1994 |
| From: | Bowling M, Kessler P, Olsen C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 95-015, 95-15, NUDOCS 9501230301 | |
| Download: ML18153B207 (20) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 12, 1995 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.95-015 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 December 1994.
Very truly yours,
- -Id~
M. L. Bowling, Manager Nuclear Licensing and Programs Enclosure cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station
. 9501230301
- --- ---- ---- -*-C",'i PDR ADOCK 941231 ti i 05000280 j
R,.,.,.:. :._'*:. :. *.
..*.. ~PDB_ - -
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERA TING REPORT REPORT No. 94-12 Approved:
Station Manager Date
TABLE OF CONTENTS Section e
Surry Monthly Operating Report No. 94-12 Page 2of 19 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 No. 1 *.......................................................*..........................***... 9 Summary of Operating Experience - Unit No. 2 **...............*********..........*****.....*........................................ 10 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 No. 1..*........*.......*.........................*.*.*******......*..**........*......................*..*..***........ 17 Fuel Handling - Unit No. 2......................................................................*....*...*.*.........................*....... 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications.........*..**.................*...*........................................**..................... 19
e Surry Monthly Operating Report OPERATING DATA RIEPORT Docket No.:
Date:
Completed By:
50-280 01-05-95 D. Mason No. 94-12 Page 3of 19 Telephone:
(804) 365-2459 1. Unit Name:...................................................
- 2.
Reporting Period:..........................................
- 3. Licensed Thermal Power (MWt):.......................
- 4. Nameplate Rating (Gross MWe):.......................
- 5. Design Electrical Rating (Net MWe):..................
- 6. Maximum Dependable Capacity (Gross MWe): *.*.
- 7. Maximum Dependable Capacity (Net MWe):........
Surry Unit 1 December, 1994 2441 847.5 788 820 781
- 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. Reasons For Restrictions, If Any:
This Month
- 11. Hours In Reporting Period..........................
- 12. Number of Hours Reactor Was Critical..........
- 13. Reactor Reserve Shutdown Hours...............
- 14. Hours Generator On-Line...........................
- 15. Unit Reserve Shutdown Hours.....................
- 16. Gross Thermal Energy Generated (MWH)......
- 17. Gross Electrical Energy Generated (MWH)....
- 18. Net Electrical Energy Generated (MWH)........
- 19. Unit Service Factor...................................
- 20. Unit Availability Factor...............................
- 21. Unit Capacity Factor (Using MDC Net)...........
- 22. Unit Capacity Factor (Using DER Net)...........
- 23. Unit Forced Outage Rate............................
744.0 215.4 0
152.3 0
331175.4 110500.0 106379.0 20.5%
20.5%
18.3%
18.1%
0.0%
YID 8760.0 6662.5 0
6562.0 0
15285994.1 5074285.0 4881922.0 74.9%
74.9%
71.4%
70.7%
0.4%
- 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):
Cumulative 193080.0 130469.7 3774.5 128241.0 3736.2 298453739.2 97613833.0 92709023.0 66.4%
68.4%
61.9%
60.9%
16.7%
FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION
e Surry Monthly Operating Report OPERATING DATA REPORT Docket No.:
Date:
Completed By:
50-281 01-05-95 D. Mason No. 94-12 Page 4of 19 Telephone:
(804) 365-2459
- 1. Unit Name:...................................................
- 2. Reporting Period:..........................................
- 3. Licensed Thermal Power (MWt):.......................
- 4. Nameplate Rating (Gross MWe):.......................
- 5. Design Electrical Rating (Net MWe):..................
- 6. Maximum Dependable Capacity (Gross MWe):....
- 7.
Maximum Dependable Capacity (Net MWe):........
Surry Unit 2 December, 1994 2441 847.5 788 820 781
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, H Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month
- 11. Hours In Reporting Period..........................
- 12. Number of Hours Reactor Was Critical..........
- 13. Reactor Reserve Shutdown Hours...............
- 14. Hours Generator On-Line...........................
- 15. Unit Reserve Shutdown Hours.....................
- 16. Gross Thermal Energy Generated (MWH)......
- 17. Gross Electrical Energy Generated (MWH)....
- 18. Net Electrical Energy Generated (MWH)........
- 19. Unit Service Factor...................................
- 20. Unit Availability Factor...............................
- 21. Unit Capacity Factor (Using MDC Net)...........
- 22. Unit Capacity Factor (Using DER Net)...........
- 23. Unit Forced Outage Rate............................
744.0 744.0 0
744.0 0
1814475.4 605405.0 584305.0 100.0%
100.0%
100.6%
99.7%
0%
YTD 8760.0 8261.2 0
8251.5 0
19592721.9 6496670.0 6260966.0 94.2%
94.2%
91.5%
90.7%
0%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling (1 O Year ISi), February 2, 1995, 53 Days
- 25. If Shut Down at End of Report Period, Estimated Date of Start-up:
- 26. Unit In Test Status (Prior to Commercial Operation):
Cumulative 189960.0 128337.5 328.1 126467.1 0
295268464.3 96442294.0 91593036.0 66.6%
66.6%
61.8%
61.2%
13.3%
FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION
~urry Monthly Operating Report No. 94-12 Page 5of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MoNTH: December, 1994 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 01-05-95 Completed by: Craig Olsen Telephone: (804) 365-2155 (1)
(2)
(3).
(4)
(5)
Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No.
Code Code Prevent Recurrence 941229 F
NIA (1)
F:
Forced S: Scheduled A
(2)
REASON:
Down Rx NIA NIA A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction JD RCT E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
(4)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Turbine runback initiated when IRPI K-02 failed. IRPI K-02 instrumentation cable was replaced.
(3)
METI-IOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
(5)
Exhibit 1 - Same Source.
(1)
~urry Monthly Operating Report No. 94-12 Page 6of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MoNTH: December, 1994 (2)
(3)
(4)
(5)
Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 01-05-95 Completed by: Craig Olsen Telephone: (804) 365-2155 Duration Method of Reason Shutting Down Rx LER No.
System Component Cause & Corrective Action to Date Type Hours Code Code Prevent Recurrence (1)
F:
Forced S: Scheduled (4)
(2)
REASON:
None During the Reporting Period 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 (NUREG 0161)
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
(5)
Exhibit 1 - Same Source.
~urry Monthly Operating Report No. 94-12 Page 7of 19 AVERAGE DAILY UNIT POWER LEVEL MONTH:
December, 1994 Average Daily Power Level Day (MWe-Net) 1 0
2 0
3 0
4 0
5 0
6 0
7 0
8 0
9 0
10 0
11 0
12 0
13 0
14 0
15 0
16 0
INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 01-04-95 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level (MWe-Net) 0 0
0 0
0 0
0 0
70 488 767 775 742 795 795 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. 94-12 Page 8of 19 AVERAGE DAILY UNIT POWER LEVEL MONTH:
December, 1994 Average Daily Power Level Day (MWe-Net) 1 787 2
787 3
789 4
790 5
783 6
783 7
789 8
790 9
790 10 789 11 790 12 785 13 782 14 786 15 786 16 787 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: 01-04-95 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level (MWe-Net) 786 786 786 785 784 784 784 785 785 785 782 763 785 786 787 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.
~urry Monthly Operating Report No. 94-12 Page 9 of 19
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: December, 1994 The following 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.
UNIIQNE:
12/01/94 12/23/94 12/25/94 12/26/94 12/28/94 12/29/94 12/31/94 0000 0039 1544 1629 0344 0500 0834 0910 1847 2235 1115 1230 1433 1448 2217 2300 1626 1628 1650 1658 1944 2258 2400 The reporting period began with the unit shutdown for a maintenance outage (steam generator chemical cleaning).
Reactor critical.
Generator on line. Started power increase.
Stopped power increase at 33%, 210 MWe.
Started power increase.
Stopped power increase at 57%, 400 MWe.
Started power increase.
Stopped power increase at 70"/o, 510 MWe.
Started power increase.
Stopped power increase at 97%, 795 MWe.
Started power increase.
Stopped power increase at 99%, 820 MWe.
Started power reduction to perform Delta T calibration.
Stopped power reduction at 98%, 810 MWe.
Started power increase.
Stopped power increase at 100%, 825 MWe.
Turbine runback initiated due to failed IRPI K-02.
Runback stopped at 46% power, 370 MWe.
Started power increase to close the main steam dump valves.
Stopped power increase at 68%, 510 MWe.
Started power increase.
Stopped power increase at 100%, 825 MWe.
The reporting period ended with the unit operating at 100% power, 825 MWe.
UNIJJwo:
12/01/94 12/28/94 12/31/94 0000 0935 1010 1226 1323 1417 1700 2400 e
Surry Monthly Operating Report
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: December, 1994,
No. 94-12 Page 10 of 19 The reporting period began with the unit operating at 1 OOo/o power, 820 MWe.
Started power reduction to perform Operations Surveillance Test, 2-0SP-TM-001,
Turbine Inlet Valve Freedom Test."
Stopped power reduction at 94%, 775 MWe.
Started power reduction.
Stopped power reduction at 85%, 700 MWe.
Started power increase.
Stopped power increase at 100%, 825 MWe.
The reporting period ended with the unit operating at 1 OOo/o power, 825 MWe.
DR S-94-2132 DR S-94-2138 TM S1-94-038 DR S-94-2248 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1994 Deviation Reports (Safety Evaluation No.94-208) tlurry Monthly Operating Report No. 94-12 Page 11 of 19 12-06-94 Safety Evaluation 94-208 assessed the condition addressed by Deviation Reports S 2132 and S-94-2138 concerning the operation of Unit 1 with hot leg loop stop valve 1-RC-MOV-1594 fixed on its backseat with the disc assembly wedged between the seat ring and the backseat.
A UT examination was performed on the hot leg loop stop valve to ensure the stem' was free of cracks. The valve manufacturer was contacted and concurred that no additional valve damage would result from leaving the valve in the fixed position during unit heat-up and operation. The subject configuration was determined to be acceptable since the loop stop valves are used for maintenance isolation and are not required for accident mitigation. Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.94-210) 12-06-94 Temporary Modification (TM) S1-94-038 failed Primary Drains Transfer Tank (POTT) pressure control valve, 1-DG-PCV-100, in the open position to eliminate spurious High Flux at Shutdown alarms caused from electrical noise generated when 1-DG-SOV-100 energizes to open 1-DG-PCV-100.
The TM was in place while the unit was at Cold Shutdown (CSD) with the containment at atmospheric conditions. At these conditions, the Primary Drains System functioned normally. Containment isolation capability was maintained and unaffected by this TM.
Therefore, an unreviewed safety question did not exist.
Deviation Report 12-16-94 (Safety Evaluation No.94-211)
Safety Evaluation 94-211 assessed the condition identified by Deviation Report S 2248 concerning the induction of pieces of 1.5 inch rubber hose ~ six inches per steam generator) into the secondary side of the Unit 1 steam generators (SG) during the SG chemical cleaning process.
An evaluation of Unit 1 operation with the SGs containing the foreign objects was performed by Westinghouse Nuclear Safety. The evaluation concluded that the presence of the objects is not expected to have an adverse effect on the primary pressure boundary integrity of the SGs. Therefore, an unreviewed safety question does not exist.
FS 94-01 DCP94-56 DCP88-24 DCP93-53 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1994 tlurry Monthly Operating Report No. 94-12 Page 12 of 19 Updated Flnal Safety Analysls Report Change (Safety Evaluation No.93-212) 12-19-94 UFSAR Change 94-01 revised Section 6.3, "Consequence-Limiting Safeguards,n to identify the types of fibrous material used inside containment and added a section to discuss how the containment design reduces the potential for significant debris buildup on the containment sump screens during a loss of coolant accident or high energy line break.
This change was administrative in nature and did not involve any physical changes to the plant. Therefore, an unreviewed safety question does not exist.
Design Change Package (Safety Evaluation No.93-182) 12-23-94 Design Change Package 94-56 connected the compensating lead to one of the two normal leads for Unit 2 Reactor Coolant System (RCS) "Cn hot leg wide range temperature indication spare element, 2-RC-TE-2433-2. This configuration allows the compensating lead to be used in lieu of a failed normal lead, enabling 2-RC-TE-2433-2 to be returned to service.
The associated transmitter was adjusted, based on previous measurements, to offset the change in lead resistance and ensure the accuracy of the subject temperature indicator.
This modification did not affect other RCS temperature indication.
Therefore, an unreviewed safety question does not exist.
Design Change Package 12-30-94 Design Change Package 88-24 modified or replaced various indicators, recorders, and controllers in the Main Control Room and Emergency Switchgear Room to correct Human Engineering Deficiencies (HED).
These modifications correct HEDs identified during the Control Room Design Review that was required by NUREG-0737. Implementation of these modifications did not affect the operation of safety-related equipment or systems or the availability of safety-related power sources. Therefore, an unreviewed safety question does not exist.
Design Change Package (Safety Evaluation No.94-142) 12-30-94 Design Change Package 93-53 corrected Human Engineering Deficiencies (HED) including the labeling of the auxiliary shutdown panel, certain heat tracing, and emergency diesel generator switches and indicators and respective panels. The titles of certain control room status tiles were also changed to improve clarity.
These modifications correct HEDs identified in the Control Room Design Review Reassessment Report that was required by NUREG-0737. Implementation of these modifications did not affect the operation of safety-related equipment or systems or the availability of safety-related power sources. Therefore, an unreviewed safety question does not exist.
TM S1-94-39 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1994 Temporary Modification (Safety Evaluation No.94-214) e Surry Monthly Operating Report No. 94-12 Page 13 of 19 12-31-94 Temporary Modification (TM) S1-94-39 installed an individual rod position indication (IRPI) rod bottom bistable module with a soldered jumper which defeats the IRPI dropped control rod turbine runback and rod stop for Unit 1 control rod K-2. This modification will prevent a spurious turbine runback and allow continued operation of Unit 1.
Other IRPI turbine runback and rod stop circuits, as well as nuclear instrument, over-pressure delta temperature and over-temperature delta temperature turbine runback and rod stop circuitry remain operable while this modification is installed. Therefore, an unreviewed safety question does not exist.
1-0PT-Sl-005 2-0PT-Sl-005
.urry Monthly Operating Report No. 94-12 Page 14of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1994 Operations Periodic Test Procedures (Safety Evaluation No.94-209) 12-06-94 Operations Periodic Test Procedures 1-0PT-Sl-005 and 2-0PT-Sl-005, "LHSI Pump Test" were temporarily revised to permit the use of temporary transmitters to enable the measurement of low head safety injection pump discharge pressure during the few seconds following pump start.
The use of the temporary safety-related transmitters does not affect the operation of the subject pumps or the ability of the safety injection system to perform its required safety function. Therefore, an unreviewed safety question does not exist.
~urry Monthly Operating Report No. 94-12 Page 15 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1994 None During the Reporting Period
CHEMISTRY REPORT MONTH/YEAR: December, 1994 Unit No.1 Primary Coolant Analysis Max.
Min.
Ava.
Gross Radioactivity, J.LCi/ml 4.01E-1 4.18E-3 9.09E-2 Suspended Solids, ppm
_s0.1
_s0.1
_s0.1 Gross Tritium uCi/ml 1.94E-2 1.94E-2 1.94E-2 1131, J.LCilml 4.55E-4 5.28E-5 2.66E-4 113111133 0.06 0.06 0.06 Hydroaen, cc/ka 43.7 3.2 28.1 Lithium oom 2.33 0.57 1.50 Boron - 10, oom*
332.6 122.7 278.1 Oxygen, (DO), ppm 8.0
_s0.005 1.2 Chloride, ppm s0.050 so.001 0.006 oH at 25 dearee Celsius 7.08 5.76 6.24 Boron - 10 = Total Boron x 0.196 Comments:
None
-Surry Monthly Operating Report No. 94-12 Page 16 of 19 Unit No. 2 Max.
Min.
Ava.
1.54E-1 8.89E-2 1.17E-1
_s0.1
_s0.1
_s0.1 1.52E-1 8.49E-2 1.23E-1 1.35E-4 6.00E-5 9.83E-5 0.10 0.05 0.07 45.4 36.5 41.5 1.41 0.89 1.14 25.3 5.9 15.6 s0.005 s0.005 s0.005
<0.050 so.001 0.003 7.96 7.51 7.65
New or Spent Fuel Shipment Date Stored or Number Received ISFSI CASTORX/33 12/14/94 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: December, 1994 Number of Assemblies Assembly ANSI eer Shiement Number Number 33 B01 NOANSI B06 NOANSI 807 NOANSI B09 NOANSI B14 NOANSI B15 NOANSI B17 NOANSI B19 NOANSI B21 NOANSI 822 NOANSI B25 NOANSI B26 NOANSI B27 NOANSI B29 NOANSI B30 NOANSI B33 NOANSI B34 NOANSI B35 NOANSI B36 NOANSI B38 NOANSI B39 NOANSI B42 NOANSI B43 NOANSI Surry Monthly Operating Report Initial Enrichment 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 2.573 No. 94-12 Page 17 of 19 New or Spent Fuel Shipping Cask Activi~
New or Spent Fuel Shipment Date Stored or Number Received ISFSI CASTORX/33 (Continued) 12/14/94 e
FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: December, 1994 Numberof
- Assemblies Assembly ANSI e!r Shiement Number Number 33 845 NOANSI 848 NOANSI 849 NOANSI 852 NOANSI S02 LMOOTG S04 LMOOTJ sos LMOOlZ S07 LMOOTP sos LMOOlX S09 LMOOTT
-urry Monthly Operating Report No. 94-12 Page 18 of 19 New or Spent Initial Fuel Shipping Enrichment Cask Activi!X 2.573 NIA 2.573 2.573 2.573 2.606 2.606 2.606 2.606 2.606 2.606
-Surry Monthly Operating Report No. 94-12 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: December, 1994 None During the Reporting Period