ML18153B073
| ML18153B073 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/31/1994 |
| From: | Bowling M, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 94-543, NUDOCS 9409220130 | |
| Download: ML18153B073 (18) | |
Text
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 12, 1994 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.94-543 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 August 1994.
Very truly yours, 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 (r. ("*, n -.J t, I*')
(~ t.> (j..J~ '-.1:
fS 9409220130 940831 J
~DR ADD CK 0500~fi~O- _ _..
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 94-08 Approved:
~JG(Lp Station Manager "i'-'1-~4-Date
TABLE OF CONTENTS Section e
Surry Monthly Operating Report No. 94-08 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 No. 1......................................................................................... 9 Summary of Operating Experience - Unit No. 2......................................................................................... 9 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...................................................................... 14 Chemistry Report............................................................................................................................. 15 Fuel Handling - Unit No. 1................................................................................................................... 16 Fuel Handling - Unit No. 2................................................................................................................... 16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications................................................................................................... 17
e Surry Monthly Operating Report OPERATIN~ DATA REPORT Docket No.:
Date:
Completed By:
50-280 08-02-94 D. Mason No. 94-08 Page 3 of 17 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 August, 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 YID Cumulative
- 11. Hours In Reporting Period..........................
744.0 5831.0 190151.0
- 12. Number of Hours Reactor Was Critical..........
744.0 4329.7 128136.9
- 13. Reactor Reserve Shutdown Hours...............
0 0
3774.5
- 14. Hours Generator On-Line...........................
744.0 4292.5 125971.5
- 15. Unit Reserve Shutdown Hours.....................
0 0
3736.2
- 16. Gross Thermal Energy Generated (MWH)......
1810187.0 9877717.7 293045462.8
- 17. Gross Electrical Energy Generated (MWH)....
592400.0 3280040.0 95819588.0
- 18. Net Electrical Energy Generated (MWH)........
570048.0 3153216.0 90980317.0
- 19. Unit Service Factor...................................
100.0%
73.6%
66.2%
- 20. Unit Availability Factor...............................
100.0%
73.6%
68.2%
- 21.
Unit Capacity Factor (Using MDC Net)...........
98.1%
69.2%
61.7%
- 22.
Unit Capacity Factor (Using DER Net)...........
97.2%
68.6%
60.7%
- 23.
Unit Forced Outage Rate............................
0.0%
0.6%
17.0%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None
- 25. If Shut Down at End of Report Period, Estimated Date of Start-up:
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED
e Surry Monthly Operating Report No. 94-08 Page 4of 17 OPERATING DATA REPORT Docket No.:
Date:
Completed By:
50-281 08-02-94 D. Mason 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 August, 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 YTD Cumulative
- 11. Hours In Reporting Period..........................
744.0 5831.0 187031.0
- 12. Number of Hours Reactor Was Critical..........
744.0 5332.2 125408.5
- 13. Reactor Reserve Shutdown Hours...............
0 0
328.1
- 14. Hours Generator On-Line...........................
744.0 5322.5 123538.1
- 15.
Unit Reserve Shutdown Hours.....................
0 0
0
- 16. Gross Thermal Energy Generated (MWH)......
1804211.4 12450286.0 288126028.4
- 17. Gross Electrical Energy Generated (MWH)....
582250.0 4129300.0 94074924.0
- 18. Net Electrical Energy Generated (MWH)........
561030.0 3977060.0 89309130.0
- 19. Unit Service Factor...................................
100.0%
91.3%
66.1%
- 20.
Unit Availability Factor...............................
100.0%
91.3%
66.1%
- 21.
Unit Capacity Factor (Using MDC Net)...........
96.6%
87.3%
61.2%
- 22.
Unit Capacity Factor (Using DER Net)...........
95.7%
86.6%
60.6%
- 23.
Unit Forced Outage Rate............................
0%
0%
13.6%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling (10 Year ISi), February 4, 1995, 58 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 INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION
e Surry Monthly Operating Report No. 94-08 Page 5 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: August, 1994 (1)
(2)
(3)
(4)
(5)
Method Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-03-94 Completed by: Craig Olsen Telephone:
(804) 365-2155 Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No.
Code Code Prevent Recurrence (1)
F:
Forced S: Scheduled (4)
(2)
REASON:
Down Rx 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 -
Oth~r (Explain)
(5)
Exhibit 1 - Same Source.
(1) e Surry Monthly Operating Report No. 94-08 Page 6 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: August, 1994 (2)
(3)
(5)
Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-03-94 Completed by: Craig Olsen Telephone: (804) 365-2155 Duration Method of Reason Shutting Down Rx LER No.
(4)
System Code Component Cause & Corrective Action to Date Type Hours 8128194 S
NI A (1)
F:
Forced S: Scheduled B
NIA (2)
REASON:
NIA A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction SI Code Prevent Recurrence COND Unit power reduced to 75% to maintain condenser vacuum while cleaning water boxes.
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
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)
(5)
Exhibit 1 - Same Source.
MONTH:
August, 1994 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS e
Surry Monthly Operating Report No. 94-08 Page ?of 17 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe-Net)
Day 769 17 768 18 765 19 763 20 765 21 772 22 702 23 768 24 774 25 772 26 771 27 766 28 750 29 759 30 767 31 772 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-02-94 Completed by:
Pat Kessler Telephone: 365-2790 Average Daily Power Level (MWe-Net) 772 770 770 768 769 771 773 775 773 772 769 767 767 767 767 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:
August, 1994 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS e
Surry Monthly Operating Report No. 94-08 Page 8 of 17 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe-Net)
Day 761 17 760 18 756 19 755 20 758 21 740 22 773 23 769 24 768 25 768 26 765 27 763 28 765 29 763 30 760 31 761 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-02-94 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level (MWe-Net) 759 755 753 756 752 754 761 762 746 744 762 700 678 751 756 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. 94-08 Page 9 of 17
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: August, 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.
UNJI ONE:
08/01/94 08/07/94 08/08/94 08/13/94 08/31/94 UNJTTwo:
08/01/94 08/28/94 08/31/94 0000 0331 0350 1459 1714 2253 2335 0330 0350 0851 0952 1110 1213 2400 0000 0528 0700 1143 1315 2400 The reporting period began with the unit operating at 100% power, 820 MWe.
Started power reduction to maintain condenser vacuum while cleaning water boxes.
Stopped power reduction at 95%, 715 MWe.
Started power reduction to perform Operations Surveillance Test, 1-0SP-TM-001, "Turbine Inlet Valve Freedom Test."
Stopped power reduction at 85%, 685 MWe.
Started power increase following completion of 1-0SP-TM-001.
Stopped power increase at 95%, 760 MWe.
Started power increase.
Stopped power increase at 100%, 800 MWe.
Started power reduction to perform 1-0SP-TM-001.
Stopped power reduction at 85%, 680 MWe.
Started power increase following completion of 1-0SP-TM-001.
Stopped power increase at 100%, 800 MWe.
The reporting period ended with the unit operating at 100% power, 800 MWe.
The reporting period began with the unit operating at 100% power, 815 MWe Started power reduction to maintain condenser vacuum while cleaning water boxes.
Stopped power reduction at 75%, 585 MWe.
Started power increase.
Stopped power increase at 100%, 800 MWe.
The reporting period ended with the unit operating at 100% power, 800 MWe.
SE 94-147 WO 295441/01 DCP 93-052 TM S2-94-14 e
Surry Monthly Operating Report No. 94-08 Page 10 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1994 Safety Evaluation 08-01-94 Safety Evaluation 94-147 was performed to evaluate the installation of a temporary piping and hose system to transfer liquid waste from temporary storage tanks at the Radiological Controlled Area yard to the Surry Radwaste Facility Liquid Waste System. The liquid waste was generated during the June, 1994 Unit 2 Steam Generator Chemical Cleaning outage.
A spill control plan and procedures, in conjunction with dikes and berms to contain non-isolable leaks from the temporary storage tanks and piping, are in place to ensure compliance with effluent Technical Specifications. Therefore, an unreviewed safety question does not exist.
Work Order 08-10-94 (Safety Evaluation No.94-153)
Work Order 295441/01 performed an on-line temporary leak-seal repair of Unit 1 auxiliary feedwater pump steam header drain valve, 1-MS-181. The repair was implemented in accordance with Mechanical Corrective Maintenance procedure O-MCM-1918-01, "On-line Leak Repairs."
. The subject valve, which is normally closed, was sealed in the closed position. The leak-seal repair did not affect the structural integrity of the valve or the operation of the main steam system. Therefore, an unreviewed safety question does not exist.
Design Change Package (Safety Evaluation No.93-194) 08-12-94 Design Change Package 93-052 installed structural reinforcement to the safety-related Unit 1 and 2 equipment hatch platforms and added a protective coating to the below ground portions of the platforms.
The modifications were implemented to enhance the ability of the platforms and missile shields to perform their safety-related functions. The Technical Specifications margin of safety was not reduced. Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.94-161) 08-23-94 Temporary Modification S2-94-14 installed electrical jumpers to bypass test switch 2-SI-CS-LC-484-TB on the Unit 2 Safety Injection (SI) System Train "B" circuitry to allow the switch to be replaced without rendering the circuits inoperable.
SI System Train "A" was not affected by this activity and both trains remained capable of operating as designed. Double verification of jumper installation/removal and post-maintenance testing were performed. Therefore, an unreviewed safety question did not exist.
EWR 91-108
- TM S1-94-34 e
Surry Monthly Operating Report No. 94-08 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1994 Engineering Work Request (Safety Evaluation No.92-049) 08-24-94 Engineering Work Request 91-108 replaced the existing emergency diesel generator (EOG) canister type fuel oil filter assemblies and associated piping/tubing with spin-on filter assemblies and tubing.
The modification was implemented to facilitate the performance of maintenance, improve spare parts acquisition, and increase the reliability of the fuel oil system and the availability of the EOGs. The functional requirements and performance of the EOG fuel oil system were not changed. Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.94-163) 08-24-94 Temporary Modification (TM) S1-94-34 provided an alternate source of cooling water to the Unit 1 condensate polishing compressor cooling towers to permit continued cooling tower operation while maintenance was being performed.
The modification was made to nonsafety-related equipment and did not affect accident analyses or the margin of safety as defined by the Technical Specifications and Updated Final Safety Analysis Report (UFSAR). Therefore, an unreviewed safety question did not exist.
FS94-014 SE 94-149 2-CAL-504 O-ECM-1404-03 e
Surry Monthly Operating Report No. 94-08 Page 12 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1994 Updated Final Safety Analysis Report Change (Safety Evaluation No.94-148) 08-02-94 UFSAR Change 94-014 incorporated the Operational Quality Assurance (QA) Program into Chapter 17 of the UFSAR and deleted the sections describing the QA programs during the construction and preoperational phases.
The Operational QA Program has been approved by the NRG and does not impact the margin of safety as described in the Safety Analysis documents. The changes were administrative in nature and did not involve any physical changes to plant equipment.
Therefore, an unreviewed safety question does not exist.
Safety Evaluation 08-02-94 Safety Evaluation 94-149 was performed to support the application of the Statistical DNBR Evaluation Methodology to the Locked Rotor Accident analysis and to implement the resulting revised analysis into Surry's design basis. This change was implemented to acquire reload core design and analysis margin.
The Statistical DNBR Evaluation Methodology is an NRC approved methodology for considering the impact of key DNBR analysis parameter uncertainties under thermal/hydraulic conditions such as those experienced during a Locked Rotor accident.
The evaluation concluded that the margin of safety is not reduced by the application of the Statistical DNBR Evaluation Methodology. Therefore, an unreviewed safety question does not exist.
Calibration Procedure 08-15-94 (Safety Evaluation No.93-182, Revision 1)
Calibration Procedure 2-CAL-504, "T-2-433-2 RCS Hot Leg Temperature - Fire Protection Cabinet," was revised to provide instructions for calibrating the Unit 2 reactor coolant system (RCS) "C" loop wide range temperature indication Appendix R element, 2-RC-TE-2433-2. The procedure revision was implemented to reflect the installation of a temporary modification on 2-RC-TE-2433-2.
Implementation of the revised procedure ensured the accuracy of the subject temperature indicator, providing control room operators with the correct RCS temperature. Therefore, an unreviewed safety question does not exist.
Electrical Corrective Maintenance Procedure (Safety Evaluation No.94-158) 08-17-94 Electrical Corrective Maintenance Procedure O-ECM-1404-03, "4160 Volt Motor Maintenance," was developed to provide instructions for the installation of temporary modifications to facilitate an uncoupled test run of the low pressure heater drain pump motor during post-maintenance testing.
Implementation of this procedure will not negatively impact the nonsafety-related low pressure heater drain pumps and will not affect the operation of the Feedwater System.
Therefore, an unreviewed safety question does not exist.
1-TOP-4044 O-MPM-1403-03 e
. R Surry Monthly Operating eport PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1994 Temporary Operating Procedure (Safety Evaluation No.94-152, Revision 1)
No. 94-08 Page 13 of 17 08-17-94 Temporary Operating Procedure 1-TOP-4044, "Number 1 Seal Leakoff 'Bucket Check' 1-RC-P-1 C," was developed to provide instructions for verifying the accuracy of the low range flow instrumentation for Unit 1 reactor coolant pump (RCP) "C" seal leak-off flow.
Implementation of this procedure, which involves the measurement and collection of RCP seal leak-off flow, will not affect the reactor coolant system pressure boundary and will not reduce the margin of safety as described by the Technical Specifications. Therefore, an unreviewed safety question does not exist.
Mechanical Preventive Maintenance Procedure (Safety Evaluation No.94-164) 08-31-94 Mechanical Preventive Maintenance Procedure O-MPM-1403-03, "Terry Turbine Governor Valve Stem Movement Check," was revised to provide instructions for performing additional preventive maintenance to ensure Terry turbine governor valve freedom of movement.
The Terry turbine will be removed from service during the performance of the subject procedure and the appropriate Technical Specification Limiting Condition for Operation will be entered. The additional maintenance activities will not affect the governor control function following the equipment's return to service. Therefore, an unreviewed safety question doe~ not exist.
Surry Monthly Operating Report No. 94-08 Page 14 of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1994 None During the Reporting Period
Primary Coolant Analysis Gross Radioactivity, µCi/ml Suspended Solids, ppm Gross Tritium, uCi/ml 1131, µCi/ml 113111133 Hydroaen, cc/ka Lithium, oom Boron - 10, oom*
Oxygen, (DO), ppm Chloride, oom pH at 25 degree Celsius Boron - 1 O = Total Boron x 0.196 Comments:
None CHEMISTRY REPORT MONTHNEAR: August, 1994 Unit No. 1 Max.
Min.
Ava.
2.96E-1 2.28E-1 2.63E-1
<0.1
<0.1
<0.1 3.07E-1 2.56E-1 2.86E-1 4.68E-4 2.87E-4 3.98E-4 0.08 0.06 0.07 40.6 26.8 32.8 2.33 2.08 2.21 185.6 170.7 178.5 5.0.005 5.0.005
<0.005 0.006 0.003 0.004 6.87 6.69 6.77 Surry Monthly Operating Report Unit No. 2 Max.
Min.
1.56E-1 8.72E-2 5.0.1
<0.1 2.61E-1 2.09E-1 1.66E-4 1.12E-4 0.09 0.06 40.1 31.9 2.33 2.05 99.6 82.3
<0.005
<0.005 0.004 0.002 7.24 7.01 No. 94-08 Page 15 of 17 Ava.
1.29E-1
<0.1 2.36E-1 1.31 E-4 0.07 34.3 2.20 90.9
<0.005 0.003 7.14
New or Spent Fuel Shipment Date Stored or Number Received FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: August, 1994 Number of Assemblies per Shipment Assembly Number ANSI Number
.Surry Monthly Operating Report No. 94-08 Page 16 of 17 Initial Enrichment New or Spent Fuel Shipping Cask Activity No Fuel Received or Stored During the Reporting Period
f'
.Surry Monthly Operating Report No. 94-08 Page 17 of 17 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: August, 1994 None During the Reporting Period