ML18153A969
| ML18153A969 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/31/1994 |
| From: | Bowling M, Mason D, Olsen C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 94-349, NUDOCS 9406210332 | |
| Download: ML18153A969 (20) | |
Text
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
June 13, 1994 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.
NO/RPC:vlh Docket Nos.
License Nos.94-349 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 May 1994.
Very truly yours,
,N/J~
M. L. Bowling, Manager Nuclear Licensing & 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 9406210332 940531
~DR ADOCK 05000280
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 94-05 Approved:
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Surry Monthly Operating Report TABLE OF CONTENTS Section No. 94-05 Page 2 of 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....................................................................................................................................... 9 Facility Changes That Did Not Require NRC Approval....................................................................................................................... 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval............................................................... 13 Tests and Experiments That Did Not Require NRC Approval.......................................................................................................... 16 Chemistry Report.... _.......................................................................................................................................................................................... 17 Fuel Handling - Unit No. l............................................................................................................................................................................ 18 Fuel Handling-Unit No. 2.............................................................. :............................................................................................................. 18 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications....................................................................................................................................................... 19
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Surry Monthly Operating Report No. 94-05 Page 3 of 19 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 May,1994 2441 847.S 788 820 781 Docket No.:
Date:
Completed By:
Telephone:
50-280 06-02-94 D. 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:
- 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..........................................
This Month 744.0 721.9 0
717.6 0
1744526.1 585445.0 564221.0 96.5%
96.5%
97.1%
96.2%
3.5%
YTD 3623.0 2121.7 0
2084.S 0
4494141.1 1506540.0 1447217.0 57.5%
57.5%
51.1%
50.7%
1.3%
Cumulative 187943.0 125928.9 3774.S 123763.S 3736.2 287661886.2 94046088.0 89274318.0 65.9%
67.8%
61.2%
60.3%
17.2%
- 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):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED
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Surry Monthly Operating Report No. 94-05 Page 4 of 19 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 May, 1994 2441 847.5 788 820 781 Docket No.:
Date:
Completed By:
Telephone:
50-281 06-02-94 D. 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:
- 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..........................................
This Month 744.0 744.0 0
744.0 0
1622484.4 542680.0 521550.0 100.0%
100.0%
89.8%
89.0%
0%
YTD 3623.0 3623.0 0
3623.0 0
8398423.3 2812415.0 2709664.0 100.0%
100.0%
95.8%
94.9%
0%
Cumulative 184823.0 123699.3 328.1 121838.6 0
284074165.7 92758039.0 88041734.0 65.9%
65.9%
61.1%
60.5%
13.7%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Maintenance, June 4, 1994, 22 Days
- 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
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Surry Monthly Operating Report No. 94-05 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: May, 1994 (1)
(2)
(3)
Method Duration of Date Type Hours Reason Shutting LER No.
940511 F
26.4 (1)
F:
Forced S:
Scheduled B
(2)
REASON:
Down Rx 2
94-005-00 A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction (4)
System Code SJ (5)
Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
06-01-94 Completed by:
Craig Olsen Telephone:
(804) 365-2155 Component Cause & Corrective Action to Code Prevent Recurrence SG Reactor manually tripped due to unrecoverable loss of steam generator level resulting from feedwater pump motor trip.
(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.
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Surry Monthly Operating Report No. 94-05 Page 6 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: May, 1994 (1)
(2)
(3)
(4)
(5)
Method Docket No.:
Unit Name:
Date:
Completed by:
Telephone:
50-281 Surry Unit 2 06-01-94 Craig Olsen (804) 365-2155 Duration of LER No.
System Code Component Cause & Corrective Action to Date Type Hours Reason Shutting 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 -
Other (Explain)
(S)
Exhibit 1 - Same Source.
MONTH:
May, 1994 Day 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 INSTRUCTIONS e
Surry Monthly Operating Report No. 94-05 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe-Net)
Day 789 17 790 18 791 19 791 20 792 21 791 22 791 23 792 24 792 25 792 26 697 27 0
28 677 29 791 30 791 31 789 Docket No.: 50-280 Unit Name: Surry Unit 1 Date:
06-02-94 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level (MWe-Net) 791 791 792 792 792 792 790 790 790 789 790 790 790 788 787 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.
MONTH:
May, 1994 Day 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 INSTRUCTIONS e
Surry Monthly Operating Report No. 94-05 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level CMWe-Net)
Day 720 17 722 18 724 19 726 20 724 21 727 22 712 23 710 24 710 25 701 26 703 27 708 28 709 29 707 30 700 31 698 Docket No.:
50-281 Unit Name: Surry Unit 2 Date:
06-02-94 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level CMWe-Net) 700 701 702 699 705 703 701 698 697 692 668 667 666 666 665 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.
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Surry Monthly Operating Report
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR:
May, 1994 No. 94-05 Page 9 of 19 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.
05/01/94 05/11/94 05/12/94 05/13/94 05/31/94 UNrrTwo:
05/01/94 05/07/94 05/14/94 05/26/94 05/31/94 0000 2109 1916 The reporting period began with the unit operating at 100% power, 820 MWe.
Reactor manually tripped due to unrecoverable loss of steam generator level resulting from feedwater pump motor trip.
Reactor critical.
2333 Unit on line; started power increase.
0009 Stopped power increase at 30%, 180 MWe, for chemistry hold.
0147 Started power increase.
0740 Stopped power increase at 100%.
2400 0000 0110 The reporting period ended with the unit operating at 100% power, 820 MWe.
The reporting period began with the unit operating at 92% power, 755 MWe due to Steam Generator "C" level oscillations.
Started power reduction to stabilize Steam Generator "C" level oscillations.
0117 Stopped power reduction at 90%, 750 MWe.
2000 Started power reduction to stabilize Steam Generator "C" level oscillations.
2015 Stopped power reduction at 89%, 735 MWe.
1953 Started power red~ction to stabilize Steam Generator "C" level oscillations and to remove feedwater heater, 2-FW-E-2A, from service.
2054 Stopped power reduction at 86.5%, 700 MWe 2400 The reporting period ended with the unit operating at 86.5% power, 700 MWe, due to Steam Generator "C" level oscillations.
TM Sl-94-31 TM Sl-94-32 TM S2-94-0S TM Sl-94-33 e
e Surry Monthly Operating Report FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
May, 1994 Temporary Modification (Safety Evaluation No.94-095)
No. 94-05 Page 10 of 19 05-09-94 Temporary Modification (TM) Sl-94-31 installed an electrical jumper to bypass the Unit 1 Lubricating Oil (LO) System pump (l-LO-P-3) motor variable speed controller to allow the controller to be repaired.
The TM did not prevent the nonsafety-related LO System from performing its intended function and did not impact safety-related systems. Double verification of jumper installation/removal and post-maintenance testing were performed. Therefore, an unreviewed safety question did not exist.
Temporary Modification (Safety Evaluation No.94-097) 05-10-94 Temporary Modification Sl-94-32 installed electrical jumpers to bypass test switch 1-LC-495-TB on the Unit 1 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.
Temporary Modification (Safety Evaluation No.94-100) 05-12-94 Temporary Modification S2-94-0S installed mechanical jumpers to establish a flow path between fuel oil pump 1-EE-P-lE and the EDG No. 2 fuel oil tank 2-EE-TK-3 due to a leak in the existing piping.
The mechanical jumpers were the same size and class of material as the existing piping and were seismically installed. The TM did not impact the design flow requirements of the system and did not alter the operation or function of the emergency diesel generators.
Therefore, an unreviewed safety question did not exist.
Temporary Modification (Safety Evaluation No.94-101) 05-13-94 Temporary Modification Sl-94-33 installed an electrical jumper to maintain power to certain Unit 1 Reactor Protection System Train "B" circuits during the replacement of relay RT7-YB.
The activity was performed while Unit 1 was at power with the Train "B" main reactor trip breaker open and the "B" bypass breaker closed. The operation of RPS Train "A" and other systems was not affected. Double verification of jumper installation/removal was performed. Therefore, an unreviewed safety question did not exist.
DCP 90-35 WO 00290056 FS 93-05 DCP 93-57 e
e Surry Monthly Operating Report FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
May, 1994 Design Change Package (Safety Evaluation No.92-200)
No. 94-05 Page 11 of 19 05-16-94 Design Change Package 90-35 installed an independent back-up compressed air supply system on each of the two Instrument Air (IA) System lines leading to the two spent fuel pool fuel transfer canal door seals.
The DCP was implemented to ensure that a positive watertight seal is maintained between the spent fuel pool and the fuel transfer canal. The modification was consistent with the original design basis criteria of the existing IA System lines and decreased the probability of spent fuel pool canal door leakage. Therefore, an unreviewed safety question did not exist.
Work Order 05-20-94 (Safety Evaluation No.94-108)
Safety Evaluation 94-108 assessed Work Order 00290056 activities, which included the inspection and repair of the local float type level indicator for the Unit 1 Emergency Condensate Storage Tank. The activities required a diver to enter the tank while the auxiliary feedwater pumps (which take a suction from this tank) remained operable.
The evaluation concluded that the safety precautions and strict foreign material exclusion controls established for this activity would ensure the safety of the diver and the continued operability of the auxiliary feedwater pumps. Therefore, an unreviewed safety question did not exist.
Updated Final Safety Analysis Report Change (Safety Evaluation 94-111) 05-25-94 Updated Final Safety Analysis Report Change 93-05 revised Sections 9.9.3, "[Service Water System] Design Evaluation," 10.3.4.1, "[Circulating Water System] Design Basis," 10.3.4.2,
"[Circulating Water] Description," and 10.3.6.4, "[Condenser] Tests and Inspections," to accurately reflect current station operational practices and to correct some erroneous information.
The changes were administrative in nature. No physical changes were made to the station. Therefore, an unreviewed safety question does not exist.
Design Change Package (Safety Evaluation No.93-172) 05-27-94 Design Change Package 93-57 installed two low point drain valves on the Gaseous Waste (GW) System discharge header. The modification was implemented to help remove moisture from the GW System and prevent associated problems with the Kaman radiation monitors.
The modification did not affect the operation or design function of safety-related equipment. The quantity and monitoring of radioactive gas through the Process Vent System was not impacted. Therefore, an unreviewed safety question did not exist.
DCP 93-24 e
e Surry Monthly Operating Report FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
May, 1994 Design Change Package (Safety Evaluation No.93-171)
No. 94-05 Page 12 of 19 05-28-94 Design Change Package 93-24 relocated the Gaseous Waste (GW) System discharge header upstream of the Process Vent System knockout drums and waste gas charcoal filters. The modification was implemented to help remove moisture from the GW System and prevent associated problems with the Kaman radiation monitors.
The modification did not affect the operation or design function of safety-related equipment. The quantity and monitoring of radioactive gas through the Process Vent System was not impacted. Therefore, an unreviewed safety question did not exist.
O-AP-13.00 O-FCA-6.01 0-FCA-7.02 O-MOP-SW-012 O-MOP-SW-013 1-0P-RC-002 2-0P-RC-002 e
e Surry Monthly Operating Report PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
May, 1994 Abnormal Procedure Fire Contingency Action Procedure (Safety Evaluation No.94-090)
No. 94-05 Page 13 of 19 05-02-94 Abnormal Procedure O-AP-13.00, "Turbine Building or MER 3 Flooding," and Fire Contingency Action Procedure O-FCA-6.01, "Uncontrollable Turbine Building Flooding,"
were developed to provide guidance in the event of uncontrollable Turbine Building flooding.
The procedures provide guidance, based on 10 CFR 50.54x, on how to respond to an accident scenario that is outside the plant design basis. Therefore, an unreviewed safety question does not exist.
Fire Contingency Action Procedure (Safety Evaluation No.94-091) 05-02-94 Fire Contingency Action Procedure O-FCA-7.02, "Loss of ESGR Cooling," was developed to provide guidance to mitigate the loss of Emergency Switchgear Room cooling from normal equipment failures and Individual Plant Examination (IPE) events.
The procedure provides guidance, based on 10 CFR 50.54x, on how to respond to an accident scenario that is outside the plant design basis. Therefore, an unreviewed safety question does not exist.
Maintenance Operating Procedures (Safety Evaluation No.94-099) 05-10-94 Maintenance Operating Procedures O-MOP-SW-012, "Removal From Service of the Unit 2 Service Water Supply Header," and O-MOP-SW-013, "Return to Service of the Unit 2 Service Water Supply Header," were revised to provide instructions for replacing Ventilation System strainer 1-VS-S-lB and Service Water System isolation valves 2-SW-305 and 2-SW-306.
Implementation of these procedures, which requires that one of the two operable charging pump service water flowpaths be removed from service, will be performed within the Technical Specification limiting conditions for operation. Therefore, an unreviewed safety question does not exist.
Operating Procedures 05-10-94 (Safety Evaluation No.94-098)
Operating Procedures 1-0P-RC-002 and 2-0P-RC-002, "Reactor Coolant System Fill," were revised to provide instructions for defeating the interlocks for the hot and cold leg loop isolation valves when filling the Reactor Coolant System loops.
The revision does not affect the basis of the Technical Specifications or the margin of safety since the procedures will be performed when the unit is at refueling or cold shutdown. Therefore, an unreviewed safety question does not exist.
SE 94-103 DR S-94-1075 2-TOP-4039 2-TOP-4040 2-TOP-4041 2-TOP-4042 2-TOP-4045 e
e Surry Monthly Operating Report PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
May, 1994 Safety Evaluation No. 94-05 Page 14 of 19 05-16-94 Safety Evaluation 94-103 assessed the continued operation of Units 1 and 2 while several Primary Sampling System lines are out of service. The subject lines were isolated due to associated inoperable equipment.
The evaluation concluded that the Primary Sampling and High Radiation Sampling Systems continue to be capable of performing their required functions. In addition, the Technical Specification requirements regarding containment integrity continue to be satisfied. Therefore, an unreviewed safety question does not exist.
Deviation Report 05-17-94 (Safety Evaluation No.94-104)
Safety Evaluation 94-104 assessed Deviation Report S-94-1075 concerning the loss and subsequent restoration of level indication for the Unit 1 Emergency Condensate Storage Tank (ECST).
The evaluation addressed the implementation of interim measures including the installation of a local level indication gauge and the use of a dedicated operator to locally monitor the gauge for post-accident monitoring purposes.
In addition, the tank was overflowed every two hours to verify that it was full.
The evaluation concluded that the continued operation of Units 1 and 2 was acceptable since the inoperable level indication or the interim measures established did not affect system automatic functions. Furthermore, the level indication instrumentation is not required during an accident for the ECST to operate to meet its design safety functions.
Therefore, an unreviewed safety question did not exist.
Temporary Operating Procedures (Safety Evaluation No.94-107) 05-20-94 Temporary Operating Procedures 2-TOP-4039, "Installation of Temporary Connections for Unit 2 Steam Generator Chemical Cleaning Outage," 2-TOP-4040, "Removal of Temporary Connections for Unit 2 Steam Generator Chemical Cleaning Outage," 2-TOP-4041, "Placing In Service and Removing From Service Aux Steam TM," 2-TOP-4042, "Placing In Service and Removing From Service Condensate TM," and 2-TOP-4045, "Installation, Operation and Removal of Chilled Water TM," were developed to provide instructions for the installation and operation of temporary connections to the Chilled Water, Auxiliary Steam, and Condensate Make-up Systems to facilitate the Unit 2 steam generator chemical cleaning processes.
The implementation of the subject procedures will not affect safety-related equipment, equipment important to safety, or the Technical Specifications margin of safety.
Therefore, an unreviewed safety question does not exist.
O-ECM-1408-01 1-0P-RT-003 2-0P-RT-003 e
e Surry Monthly Operating Report PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
May, 1994 Electrical Corrective Maintenance Procedure (Safety Evaluation No.94-112)
No. 94-05 Page 15 of 19 05-25-94 Electrical Corrective Maintenance Procedure O-ECM-1408-01, "Low Pressure Heater Drain Pump 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.
Operating Procedures 05-26-94 (Safety Evaluation No.94-113)
Operating Procedures 1(2)-0P-RT-003, "Pumping Steam Generators to WNS Using the Blowdown Lines," were developed to provide instructions for the installation of a temporary drain hose to permit pumping either one of the steam generators to the waste neutralization sumps.
These procedures will be performed when the unit is at cold shutdown and SG water conditions are not acceptable for release to the James River. The draining will be monitored to ensure any SG tube leakage is identified so that the evolution can be terminated. Therefore, an unreviewed safety question does not exist.
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Surry Monthly Operating Report No. 94-05
, Page 16 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
May, 1994 None During the Reporting Period
e Primary Coolant Analysis Gross Radioactivity, µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml r131, µCi/ml 1131;1133 Hydrogen, cc/kg Lithium, ppm Boron - 10, ppm" Oxygen, (DO), ppm Chloride, ppm pH at 25 degree Celsius Boron - 10 = Total Boron x 0.196 Comments:
None CHEMISTRY REPORT Mmmr/YEAR: May, 1994 Unit No. 1 Max.
Min.
Avg.
3.14E-1 3.18E-2 2.40E-1
<0.1
<0.1
<0.1 2.63E-1 2.22E-1 2.47E-1 3.96E-4 9.62E-5 2.91E-4 0.08 0.05 0.06 46.1 34.6 40.3 2.32 2.07 2.21 257.0 209.5 221.2
<0.005
<0.005
<0.005 0.008 0.003 0.006 6.74 6.56 6.64 e
Surry Monthly Operating Report Max.
l.90E-1
<0.1 6.05E-1 l.28E-4 0.11 47.2 2.34 146.4
<0.005 0.007 7.01 No. 94-05 Page 17 of 19 Unit No. 2 Min.
Avg.
7.36E-2 l.29E-1
<0.1
<0.1 5.70E-1 5.83E-1 4.88E-5 7.88E-5 0.05 0.07 35.6 41.6 2.06 2.21 135.4 140.5
<0.005
<0.005 0.003 0.005 6.82 6.92
New or Spent Fuel Shipment Number FUEL HANDLING UNITS 1 & 2 MONTH/YEAR:
May, 1994 Number of Date Stored Assemblies or Received per Shipment Assembly Number ANSI Number Surry Monthly Operating Report Initial Enrichment No. 94-05 Page 18 of 19 New or Spent Fuel Shipping.
Cask Activit No Fuel Received or Stored During the Reporting Period.
Surry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: May, 1994 None During the Reporting Period.
No. 94-05 Page 19 of,19