ML18153A042
| ML18153A042 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/31/1996 |
| From: | Bryant B, Fanguy M, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 96-410, NUDOCS 9608200045 | |
| Download: ML18153A042 (17) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 14, 1996 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.
NL&OS/GDM Docket Nos.
License Nos.96-410 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 July 1996.
If you have any questions or require additional information, please contact us.
Very truly yours,
- If/~
M. L. Bowling, Manager Nuclear Licensing and Operations Support Enclosure cc:
U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station 960820004-5 960731 PDR ADOCK 05000280 R
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 96-07 Approved:
e TABLE OF CONTENTS Section e
Surry Monthly Operating Report No. 96-07 Page 2 of 16 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 NRG Approval............................................................................................ 10 Procedure or Method of Operation Changes That Did Not Require NRG Approval................................................. 12 Tests and Experiments That Did Not Require NRG Approval.................................................................................. 13 Chemistry Report..................................................................................................................................................... 14 Fuel Handling - Unit No. 1........................................................................................................................................ 15 Fuel Handling - Unit No. 2........................................................................................................................................ 15 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications....................................................................................................................... 16
OPERATING DATA REPORT
- 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 July, 1996 2546 847.5 788 840 801 e
Surry Monthly Operating Report No. 96-07 Page 3 of 16 Docket No.:
Date:
Completed By:
Telephone:
50-280 8-01-96 D. K. Mason (804) 365-2459
- 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 5111.0 206951.0
- 12.
Number of Hours Reactor Was Critical...........
744.0 5111.0 143161.7
- 13.
Reactor Reserve Shutdown Hours..................
0.0 0.0 3774.5
- 14.
Hours Generator On-Line................................
744.0 5111.0 140858.0
- 15.
Unit Reserve Shutdown Hours........................
0.0 0.0 3736.2
- 16.
Gross Thermal Energy Generated (MWH)......
1853907.5 12916196.1 329313988.6
- 17.
Gross Electrical Energy Generated (MWH).....
608950.0 4295525.0 107872708.0
- 18.
Net Electrical Energy Generated (MWH).........
586242.0 4147938.0 102603911.0
- 19.
Unit Service Factor..........................................
100.0%
100.0%
68.1%
- 20.
Unit Availability Factor.....................................
100.0%
100.0%
69.9%
- 21.
Unit Capacity Factor (Using MDC Net)............
98.4%
101.3%
63.8%
- 22.
Unit Capacity Factor (Using DER Net)............
100.0%
103.0%
62.9%
- 23.
Unit Forced Outage Rate................................
0.0%
0.0%
15.6%
- 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:
N/A
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
e OPERATING DATA REPORT
- 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 July, 1996 2546 847.5 788 840 801 e
Surry Monthly Operating Report No. 96-07 Page 4 of 16 Docket No.:
Date:
Completed By:
Telephone:
50-281 8-01-96 D. K. Mason
{804) 365-2459
- 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 5111.0 203831.0
- 12.
Number of Hours Reactor Was Critical...........
744.0 4175.6 139678.5
- 13.
Reactor Reserve Shutdown Hours..................
0.0 0.0 328.1
- 14.
Hours Generator On-Line................................
744.0 4157.7 137713.8
- 15.
Unit Reserve Shutdown Hours........................
0.0 0.0 0.0
- 16.
Gross Thermal Energy Generated (MWH)......
1893594.7 10443567.0 322978624.0
- 17.
Gross Electrical Energy Generated (MWH).....
620595.0 3463690.0 105619334.0
- 18.
Net Electrical Energy Generated (MWH).........
598624.0 3349368.0 100459783.0
- 19.
Unit Service Factor..........................................
100.0%
81.3%
. 67.6%
- 20.
Unit Availability Factor.....................................
100.0%
81.3%
67.6%
- 21.
Unit Capacity Factor (Using MDC Net)............
100.4%
81.8%
63.1%
- 22.
Unit Capacity Factor (Using DER Net)............
102.1%
83.2%
62.5%
- 23.
Unit Forced Outage Rate................................
0.0%
2.2%
12.7%
- 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:
N/A
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
(1)
(2)
Duration e
Surry Monthly Operating Report No. 96-07 Page 5 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: July, 1996 (3)
(4)
Method of LER (5)
Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
8-01-96 Completed by:
M. J. Fanguy Telephone:
(804) 365-2155 Component Cause & Corrective Action to Date Type Hours Reason Shutting No.
System Code Code Prevent Recurrence 960717 s
N/A (1)
F:
Forced S:
Scheduled B
(2)
REASON:
Down Rx N/A N/A A
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction SB 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 (NU REG 0161)
V Reactor power was reduced to perform Operations Surveillance Procedure 1-0SP-TM-001, Turbine Inlet Valve Freedom Test.
(3)
METHOD:
1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit 1 - Same Source
(1)
Date Type (1)
F:
Forced S:
Scheduled (4) e e
Surry Monthly Operating Report No. 96-07 Page 6 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL TO OR GREATER THAN 20%)
Duration Hours REPORT MONTH: July, 1996 (2)
(3)
Method of LER No.
Reason Shutting Down Rx (4)
System Code Docket No.:
50-281 Unit Name:
Surry Unit 2 Date:
8-01-96 Completed by:
M. J. Fanguy Telephone:
(804) 365-2155 (5)
Component Cause & Corrective Action to Code Prevent Recurrence 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)
(3)
METHOD:
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
e Surry Monthly Operating Report No. 96-07 Page 7 of 16 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name:
Surry Unit 1 Date: 8-07-96 Completed by:
B. C. Bryant Telephone: (804) 365-2786 MONTH:
July, 1996 Average Daily Power Level Average Daily Power Level Day (MWe - Net)
Day (MWe - Net) 806 17 593 2
803 18 503 3
805 19 805 4
806 20 802 5
806 21 805 6
806 22 814 7
803 23 815 8
802 24 815 9
800 25 815 10 800 26 815 11 802 27 814 12 803 28 814 13 770 29 814 14 751 30 813 15 809 31 813 16 805 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.
MONTH:
July, 1996 Day 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 INSTRUCTIONS e
e Surry Monthly Operating Report No. 96-07 Page 8 of 16 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)
Day 810 17 807 18 809 19 815 20 815 21 814 22 811 23 811 24 806 25 809 26 811 27 813 28 812 29 809 30 809 31 807 Docket No.: 50-281 Unit Name:
Surry Unit 2 Date: 8-07-96 Completed by:
Barry C. Bryant Telephone: (804) 365-2786 Average Daily Power Level (MWe - Net) 805 805 806 807 806 801 799 798 797 795 793 790 793 791 789 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 MONTH/YEAR: July, 1996 e
Surry Monthly Operating Report No. 96-07 Page 9 of 16 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.
UNIT ONE:
7/01/96 7/13/96 7/14/96 7/17/96 7/18/96 7/31/96 UNIT Two:
7/01/96 7/03/96 7/31/96 0000 0725 The reporting period began with the unit operating at 100% power, 850 MWe.
Started power reduction to maintain condenser vacuum while "C" waterbox was removed from service for cleaning.
0739 Stopped power reduction at 99%, 805 MWe.
0134 Started power increase following the completion of "C" waterbox cleaning.
0200 Stopped power increase at 100%, 840 MWe.
0722 Started power reduction to maintain condenser vacuum while "B" waterbox was removed from service for cleaning.
0815 Stopped power reduction at 92%, 750 MWe.
1230 Reduced power to 89%, 725 MWe to maintain condenser vacuum.
1857 Started power increase following the completion of "B" waterbox cleaning.
1940 0844 Stopped power increase at 100%, 839 MWe.
Started power reduction to perform Operations Surveillance Procedure 1-0SP-TM-001, Turbine Inlet Valve Freedom Test.
1125 Stopped power reduction at 84%, 700 MWe.
1200 Started power reduction.
1225 Stopped power reduction at 75%, 620MWe.
1312 Started power reduction in accordance with 1-0SP-TM-001 after the "C" reheat stop valve failed to reopen.
1446 Stopped power reduction at 49%, 370 MWe.
1500 Started power increase following the completion of 1-0SP-TM-001.
2026 Stopped power increase at 100%, 840 MWe.
2400 The reporting period ended with the unit operating at 100% power, 840 MWe.
0000 The reporting period began with the unit operating at 100% power, 850 MWe.
1241 Started power reduction based on the results of Operation Periodic Test 2-0PT-RX-004, Reactor Power Calorimetric Using Feed Flow with P-250 Out of Service (Manual).
1300 Stopped power reduction at 99.5%, 845 MWe.
1527 1538 2400 Started power increase.
Stopped power increase at 100%, 847 MWe.
The reporting period ended with the unit operating at 100% power, 825 MWe.
TM 82-96-020 TM 82-96-019 TM 81-96-013 FS 96-07 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July, 1996 Temporary Modification (Safety Evaluation No.96-092) e Surry Monthly Operating Report No. 96-07 Page 10 of 16 01-96 Temporary Modification (TM) 82-96-020 temporarily removed the main control room annunciator card for annunciator C-F-2, RCP BRG HI TEMP. The TM was implemented to stop a continuous alarm condition associated with the reactor coolant pump temperature recorder, TE-2-448, until the recorder setpoints were changed.
Annunciators C-F-2 and C-F-1, RCP 1C CC RETURN HI TEMP were disabled while the annunciator card was removed. Indication of the affected parameters remained available and monitoring was increased.
The instrument channels associated with the subject annunciators remained operable since control and protection functions were not affected.
Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.96-095) 7-02-96 Temporary Modification (TM) 82-96-019 installed a mechanical jumper to provide a continuous vent path from the Unit 2 pressurizer relief tank (PRT) through the primary drains tank (PDT) to the overhead gas system.
This TM is necessary to maintain acceptable PRT pressure until pressurizer safety valve leakage could be corrected. The procedures associated with chemistry sampling evolutions that are affected by this TM were revised appropriately.
The mechanical jumper is rated for system pressure and allows PRT gases to vent to the overhead gas system which is designed for processing, holding, and monitoring radioactive gases. The TM did not impact the reactor protection system, safety injection system, consequence limiting safeguards system, or containment integrity. Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.96-096) 7-03-96 Temporary Modification 81-96-013 installed a blank flange on the 1-CP-DM-1A condensate polisher resin transfer line to facilitate the repair of valve 1-CP-AOV-5A.
The 1-CP-DM-1 A condensate polisher will be removed from service while the blank flange is installed. The TM will not adversely affect the operation of condensate polishing system or the operation of any safety-related system or component. Therefore, an unreviewed safety question does not exist.
Updated Final Safety Analysis Report Change (Safety Evaluation 96-098) 7-22-96 Updated Final Safety Analysis Report Change 96-07 revised Section 11.3.4.3, "Containment Gas Monitors," to correct the count rate values for isotopes Xe, 33 and Kr 85.
These changes were administrative in nature and will not result in any unmonitored release or cause the limits of GDC 19 or 1 O CFR 100 to be exceeded. Therefore, an unreviewed safety question does not exist.
FS 96-25 SE 96-099 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1996 Updated Final Safety Analysis Report Change (Safety Evaluation 96-097) e Surry Monthly Operating Report No. 96-07 Page 11 of 16 7-22-96 Updated Final Safety Analysis Report Change 96-25 revised Section 9.4.4.1, "Component Cooling Water System Availability and Reliability," to delete the reference to the automatic closure function of the primary drain coolers component cooling (CC) return line hand control valves 1[2]-CC-HCV-114[214].
This change was administrative in nature and was made to accurately reflect the current plant condition.
The automatic closure function of the subject valves was originally installed to isolate the CC system (to prevent an overpressure condition) in the event of a primary drain cooler tube rupture.
This closure function was subsequently removed during the initial startup of each unit since the potential for the CC system to become overpressurized from the primary drain cooler was not considered to be a credible event.
Therefore, an unreviewed safety question does not exist.
Safety Evaluation 7-22-96 Safety Evaluation 96-099 assessed the continued operation of Units 1 and 2 while the Unit 2 power supply to the common radiation monitor cabinet, 1-RM-CAB-0-0, is out of service.
The subject power supply was tagged out to facilitate the replacement of associated power supply cables.
The evaluation concluded that the affected radiation monitors, indications, alarms, and control functions continue to be capable of performing their required functions since they remain powered from an operable emergency backed power source.
Therefore, an unreviewed safety question does not exist.
1 [2]-0P-CS-002 1 [2]-0P-CS-006 1 [2]-MOP-36.5 FLOWCALC CALCALC CALCCHK FLOWPRNT 1 [2]-0PT-RX-001 1 [2]-0PT-RX-002 1 [2]-0PT-RX-003 1 [2]-0PT-RX-004 e
Surry Monthly Operating Report No. 96-07 Page 12 of 16 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July, 1996 Operating Procedures (Safety Evaluation No.96-094) 7-02-96 Operating Procedures 1 [2]-0P-CS-002, "Refueling Water Chemical Addition Tank Operations," and 1 [2]-0P-CS-006, "Draining the RWST," were revised to provide instructions for administratively controlling Containment Spray (CS) system valves 1-CS-112 and 1-CS-120 or 2-CS-97 and 2-CS-100 when performing the subject procedures.
Appropriate administrative controls are provided in the procedures to ensure that the subject valves are closed within six minutes of the initiation of a Hi Hi Consequence Limiting Safeguards signal.
Closure of the valves within this time limit ensures that sufficient CS flow and Chemical Addition Tank (CAT) inventory is maintained for accident mitigation. Therefore, an unreviewed safety question does not exist.
Maintenance Operating Procedures (Safety Evaluation No.96-065, Revision 1) 7-22-96 Maintenance Operating Procedures 1 [2]-MOP-36.5, "Secondary Plant Air lnleakage Inspection," were revised to provide instructions for the installation and removal of an Orbisphere oxygen monitor, in-line flow indicator, and a temporary sample header at the condensate pump discharge drain lines. The data obtained will be used to verify that the existing on-line oxygen monitor is operating properly.
The procedurally controlled temporary modifications do not adversely affect the operation of any component or system. Therefore, an unreviewed safety question does not exist.
P-250 Computer Programs Operations Periodic Test Procedures (Safety Evaluation No.96-102) 7-29-96 Plant computer (P-250) programs FLOWCALC, CALCALC, CALCCHK, and FLOWPRNT and Operations Periodic Test Procedures 1 [2]-0PT-RX-001, "Reactor Power Calorimetric Using CALCALC Computer Program," 1 [2]-0PT-RX-002, "Reactor Power Calorimetric Using Steam Flow and P-250 Computer Points (Manual)," 1 [2]-0PT-RX-003, "Reactor Power Calorimetric Using Feed Flow and P-250 Computer Points (Manual)," and 1 [2]-
0PT-RX-004, "Reactor Power Calorimetric Using Feed Flow with P-250 Out of Service (Manual)," were revised to improve the accuracy and stability of calorimetric calculations.
The subject changes did not involve any hardware modifications and did not affect methods of operation or surveillance criteria.
The accuracy of the calorimetric calculations remains within that assumed by the safety analysis.
Therefore, an unreviewed safety question does not exist.
L e
Surry Monthly Operating Report No. 96-07 Page 13 of 16 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July, 1996 None During the Reporting Period
Primary Coolant Analysis Gross Radioactivity, µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml 1131, µCi/ml 113111133 Hydrogen, cc/kq Lithium, oom Boron - 10, ppm*
Oxygen, (DO), ppm Chloride, ppm pH at 25 deqree Celsius Boron - 10 = Total Boron x 0.196 Comments:
None CHEMISTRY REPORT MONTHNEAR: July, 1996 Unit No. 1 Max.
Min.
AvQ.
1.06E+O 5.08E-1 8.04E-1 so.010 so.010 so.010 6.48E-1 4.98E-1 5.82E-1 9.80E-2 3.55E-3 1.42E-2 0.73 0.37 0.52 39.0 33.1 36.1 2.30 1.95 2.16 146.4 118.4 128.3 s0.005 s0.005 s0.005 s0.050 0.001 0.005 6.71 6.35 6.57 e
Surry Monthly Operating Report No. 96-07 Page 14 of 16 Unit No. 2 Max.
Min.
AVQ.
1.85E-1 9.56E-2 1.39E-1 so.010 so.010 so.010 5.59E-1 3.11 E-1 4.40E-1 9.80E-5 2.18E-5 4.47E-5 0.24 0.05 0.10 34.1 29.6 32.1 2.49 2.19 2.33 261.7 252.8 257.3 s0.005 s0.005 s0.005 s0.050 0.004 0.006 6.31 5.86 6.12
New or Spent Fuel Shipment Date Stored or Number Received FUEL HANDLING UNITS 1 & 2 MONTHNEAR: July, 1996 Number of Assemblies per Shipment Assembly Number ANSI Number e
Surry Monthly Operating Report No. 96-07 Page 15 of 16 Initial Enrichment New or Spent Fuel Shipping Cask Activity No Fuel Received or Stored During the Reporting Period
New or Spent Fuel Shipment Date Stored or Number Received e
FUEL HANDLING UNITS 1 & 2 MONTHNEAR: July, 1996 Number of Assemblies per Shipment Assembly Number ANSI Number e
Surry Monthly Operating Report No. 96-07 Page 16 of 16 Initial Enrichment New or Spent Fuel Shipping Cask Activity DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: July, 1996 None During the Reporting Period