ML18153A969

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Monthly Operating Repts for May 1994 for Surry Power Stations,Unit 1 & 2.W/940613 Ltr
ML18153A969
Person / Time
Site: Surry  Dominion icon.png
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)
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Text

' I e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 13, 1994 U.S. Nuclear Regulatory Commission Serial No.94-349 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT 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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  • e e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 94-05 Approved:

' . e e Surry Monthly Operating Report No. 94-05 Page 2 of 19 TABLE OF CONTENTS Section 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

e e Surry Monthly Operating Report No. 94-05 Page 3 of 19 OPERATING DATA REPORT Docket No.: 50-280 Date: 06-02-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: ........................................................................... . Surry Unit 1
2. Reporting Period: .............................................................. . May,1994
3. Licensed Thermal Power (MWt): ................................ .. 2441
4. Nameplate Rating (Gross MWe): .................................. . 847.S
5. Design Electrical Rating (Net MWe): .......................... . 788
6. Maximum Dependable Capacity (Gross MWe): ..... . 820
7. Maximum Dependable Capacity (Net MWe): .......... . 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .................................... .. 744.0 3623.0 187943.0
12. Number of Hours Reactor Was Critical ............... . 721.9 2121.7 125928.9
13. Reactor Reserve Shutdown Hours....................... . 0 0 3774.S
14. Hours Generator On-Line ...................................... .. 717.6 2084.S 123763.S
15. Unit Reserve Shutdown Hours ............................. .. 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ......... . 1744526.1 4494141.1 287661886.2
17. Gross Electrical Energy Generated (MWH)....... . 585445.0 1506540.0 94046088.0
18. Net Electrical Energy Generated (MWH) ............. . 564221.0 1447217.0 89274318.0
19. Unit Service Factor.................................................... .. 96.5% 57.5% 65.9%
20. Unit Availability Factor ............................................ .. 96.5% 57.5% 67.8%
21. Unit Capacity Factor (Using MDC Net)............... . 97.1% 51.1% 61.2%
22. Unit Capacity Factor (Using DER Net) ................ . 96.2% 50.7% 60.3%
23. Unit Forced Outage Rate ......................................... . 3.5% 1.3% 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):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e e Surry Monthly Operating Report No. 94-05 Page 4 of 19 OPERATING DATA REPORT Docket No.: 50-281 Date: 06-02-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: ........................................................................... . Surry Unit 2 2 Reporting Period: .............................................................. . May, 1994
3. Licensed Thermal Power (MWt): ................................. . 2441
4. Nameplate Rating (Gross MWe): .................................. . 847.5
5. Design Electrical Rating (Net MWe): .......................... . 788
6. Maximum Dependable Capacity (Gross MWe): ..... . 820
7. Maximum Dependable Capacity (Net MWe): .......... . 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period..................................... . 744.0 3623.0 184823.0
12. Number of Hours Reactor Was Critical.. ............. . 744.0 3623.0 123699.3
13. Reactor Reserve Shutdown Hours ....................... . 0 0 328.1
14. Hours Generator On-Line ....................................... . 744.0 3623.0 121838.6
15. Unit Reserve Shutdown Hours .............................. . 0 0 0
16. Gross Thermal Energy Generated (MWH) ......... . 1622484.4 8398423.3 284074165.7
17. Gross Electrical Energy Generated (MWH) ....... . 542680.0 2812415.0 92758039.0
18. Net Electrical Energy Generated (MWH) ............. . 521550.0 2709664.0 88041734.0
19. Unit Service Factor ..................................................... . 100.0% 100.0% 65.9%
20. Unit Availability Factor ............................................. . 100.0% 100.0% 65.9%
21. Unit Capacity Factor (Using MDC Net). .............. . 89.8% 95.8% 61.1%
22. Unit Capacity Factor (Using DER Net). ............... . 89.0% 94.9% 60.5%
23. Unit Forced Outage Rate ......................................... . 0% 0% 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):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e e 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 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 06-01-94 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 Down Rx 940511 F 26.4 B 2 94-005- SJ SG Reactor manually tripped due 00 to unrecoverable loss of steam generator level resulting from feedwater pump motor trip.

(1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

e e 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 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 06-01-94 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 Down Rx None During the Reporting Period (1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (S)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

e -

S urry Monthly Operating Report No. 94-05 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 06-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: May, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 789 17 791 2 790 18 791 3 791 19 792 4 791 20 792 5 792 21 792 6 791 22 792 7 791 23 790 8 792 24 790 9 792 25 790 10 792 26 789 11 697 27 790 12 0 28 790 13 677 29 790 14 791 30 788 15 791 31 787 16 789 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.

  • e Surry Monthly Operating Report No. 94-05 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 06-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: May, 1994 Average Daily Power Level Average Daily Power Level Day CMWe-Net) Day CMWe-Net) 1 720 17 700 2 722 18 701 3 724 19 702 4 726 20 699 5 724 21 705 6 727 22 703 7 712 23 701 8 710 24 698 9 710 25 697 10 701 26 692 11 703 27 668 12 708 28 667 13 709 29 666 14 707 30 666 15 700 31 665 16 698 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.

e e Surry Monthly Operating Report No. 94-05 Page 9 of 19

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: May, 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.

05/01/94 0000 The reporting period began with the unit operating at 100% power, 820 MWe.

05/11/94 2109 Reactor manually tripped due to unrecoverable loss of steam generator level resulting from feedwater pump motor trip.

05/12/94 1916 Reactor critical.

2333 Unit on line; started power increase.

05/13/94 0009 Stopped power increase at 30%, 180 MWe, for chemistry hold.

0147 Started power increase.

0740 Stopped power increase at 100%.

05/31/94 2400 The reporting period ended with the unit operating at 100% power, 820 MWe.

UNrrTwo:

05/01/94 0000 The reporting period began with the unit operating at 92% power, 755 MWe due to Steam Generator "C" level oscillations.

05/07/94 0110 Started power reduction to stabilize Steam Generator "C" level oscillations.

0117 Stopped power reduction at 90%, 750 MWe.

05/14/94 2000 Started power reduction to stabilize Steam Generator "C" level oscillations.

2015 Stopped power reduction at 89%, 735 MWe.

05/26/94 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 05/31/94 2400 The reporting period ended with the unit operating at 86.5% power, 700 MWe, due to Steam Generator "C" level oscillations.

e e Surry Monthly Operating Report No. 94-05 Page 10 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1994 TM Sl-94-31 Temporary Modification 05-09-94 (Safety Evaluation No.94-095)

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.

TM Sl-94-32 Temporary Modification 05-10-94 (Safety Evaluation No.94-097)

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.

TM S2-94-0S Temporary Modification 05-12-94 (Safety Evaluation No.94-100)

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.

TM Sl-94-33 Temporary Modification 05-13-94 (Safety Evaluation No.94-101)

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.

e e Surry Monthly Operating Report No. 94-05 Page 11 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1994 DCP 90-35 Design Change Package 05-16-94 (Safety Evaluation No.92-200)

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.

WO 00290056 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.

FS 93-05 Updated Final Safety Analysis Report Change 05-25-94 (Safety Evaluation 94-111)

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.

DCP 93-57 Design Change Package 05-27-94 (Safety Evaluation No.93-172)

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.

e e Surry Monthly Operating Report No. 94-05 Page 12 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1994 DCP 93-24 Design Change Package 05-28-94 (Safety Evaluation No.93-171)

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.

e e Surry Monthly Operating Report No. 94-05 Page 13 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1994 O-AP-13.00 Abnormal Procedure 05-02-94 O-FCA-6.01 Fire Contingency Action Procedure (Safety Evaluation No.94-090)

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.

0-FCA-7.02 Fire Contingency Action Procedure 05-02-94 (Safety Evaluation No.94-091)

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.

O-MOP-SW-012 Maintenance Operating Procedures 05-10-94 O-MOP-SW-013 (Safety Evaluation No.94-099)

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.

1-0P-RC-002 Operating Procedures 05-10-94 2-0P-RC-002 (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.

e e Surry Monthly Operating Report No. 94-05 Page 14 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1994 SE 94-103 Safety Evaluation 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.

DR S-94-1075 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.

2-TOP-4039 Temporary Operating Procedures 05-20-94 2-TOP-4040 (Safety Evaluation No.94-107) 2-TOP-4041 2-TOP-4042 2-TOP-4045 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.

e e Surry Monthly Operating Report No. 94-05 Page 15 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1994 O-ECM-1408-01 Electrical Corrective Maintenance Procedure 05-25-94 (Safety Evaluation No.94-112)

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.

1-0P-RT-003 Operating Procedures 05-26-94 2-0P-RT-003 (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.

e e 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 e Surry Monthly Operating Report No. 94-05 Page 17 of 19 CHEMISTRY REPORT Mmmr/YEAR: May, 1994 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Avg.

Gross Radioactivity, µCi/ml 3.14E-1 3.18E-2 2.40E-1 l.90E-1 7.36E-2 l.29E-1 Suspended Solids, ppm <0.1 <0.1 <0.1 <0.1 <0.1 <0.1 Gross Tritium, µCi/ml 2.63E-1 2.22E-1 2.47E-1 6.05E-1 5.70E-1 5.83E-1 r131, µCi/ml 3.96E-4 9.62E-5 2.91E-4 l.28E-4 4.88E-5 7.88E-5 1131;1133 0.08 0.05 0.06 0.11 0.05 0.07 Hydrogen, cc/kg 46.1 34.6 40.3 47.2 35.6 41.6 Lithium, ppm 2.32 2.07 2.21 2.34 2.06 2.21 Boron - 10, ppm" 257.0 209.5 221.2 146.4 135.4 140.5 Oxygen, (DO), ppm <0.005 <0.005 <0.005 <0.005 <0.005 <0.005 Chloride, ppm 0.008 0.003 0.006 0.007 0.003 0.005 pH at 25 degree Celsius 6.74 6.56 6.64 7.01 6.82 6.92

None

Surry Monthly Operating Report No. 94-05 Page 18 of 19 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: May, 1994 New or Number of New or Spent Fuel Date Stored Assemblies Assembly ANSI Initial Spent Fuel Shipment or Received per Number Number Enrichment Shipping.

Number Shipment Cask Activit No Fuel Received or Stored During the Reporting Period.

Surry Monthly Operating Report No. 94-05 Page 19 of ,19 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.

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