ML18153B461

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Monthly Operating Repts for Jan 1994 for Surry Nuclear Power Station.W/940210 Ltr
ML18153B461
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/31/1994
From: Bowling M, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-076, 94-76, NUDOCS 9402180142
Download: ML18153B461 (19)
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Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 10, 1994 U. S. Nuclear Regulatory Commission Serial No.94-076 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 January 1994.

Very truly yours,

~/2~

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 .

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' ft VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 94-01 Approved:

Station Manager Date

e esurry Monthly Operating Report No. 94-01 Page 2 of 18 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. .............................................................................. 1O Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 13 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 15 Chemistry Report ............................................................................................................................. 16 Fuel Handling - Unit No. 1 ................................................................................................................... 17 Fuel Handling - Unit No. 2 ................................................................................................................... 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 18

-Surry Monthly Operating Report No. 94-01 Page 3of 18 OPERATING DATA REPORT Docket No.: 50-280 Date: 02-03-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: ................................................. .. Surry Unit 1
2. Reporting Period: ........................................ .. January, 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 .......................... 744.0 744.0 185064.0
12. Number of Hours Reactor Was Critical .......... 509.2 509.2 124316.4
13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5
14. Hours Generator On-Line ........................... 506.1 506.1 122185.1
15. Unit Reserve Shutdown Hours..................... 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 745423.1 745423.1 283913168.2
17. Gross Electrical Energy Generated (MWH) .... 251015.0 251015.0 92790563.0
18. Net Electrical Energy Generated (MWH) ........ 237463.0 237463.0 88064564.0
19. Unit Service Factor ................................... 68.0% 68.0% 66.0%
20. Unit Availability Factor ............................... 68.0% 68.0% 68.0%
21. Unit Capacity Factor (Using MDC Net) ........... 40.9% 40.9% 61.4%
22. Unit Capacity Factor (Using DER Net) ........... 40.5% 40.5% 60.4%
23. Unit Forced Outage Rate ............................ 0.0% 0.0% 17.4%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling (1 O Year ISi), January 22, 1994, 64 Days

25. If Shut Down at End of Report Period, Estimated Date of Start-up: March 26, 1994
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICAUTY INITIAL ELECTRICITY COMMERCIAL OPERATION

- Surry Monthly Operating Report No. 94-01 Page 4of 18 OPERATING DATA REPORT Docket No.: 50-281 Date: 02-03-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . January, 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 .......................... 744.0 744.0 181944.0
12. Number of Hours Reactor Was Critical .......... 744.0 744.0 120820.3
13. Reactor Reserve Shutdown Hours ............... 0 0 328.1
14. Hours Generator On-Line ........................... 744.0 744.0 118959.6
15. Unit Reserve Shutdown Hours..................... 0 0 0
16. Gross Thermal Energy Generated (MWH) ...... 1806923.8 1806923.8 277482666.2
17. Gross Electrical Energy Generated (MWH) .... 606580.0 606580.0 90552204.0
18. Net Electrical Energy Generated (MWH) ........ 585524.0 585524.0 85917594.0
19. Unit Service Factor ................................... 100.0% 100.0% 65.4%
20. Unit Availability Factor............................... 100.0% 100.0% 65.4%
21. Unit Capacity Factor (Using MDC Net) ........... 100.8% 100.8% 60.6%
22. Unit Capacity Factor (Using DER Net) ........... 99.9% 99.9% 59.9%
23. Unit Forced Outage Rate ............................ 0.0% 0.0% 14.0%
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 ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 94-01 Page 5of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: January, 1994 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02-03-94 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 940122 s 237.9 C NIA AB RCT Refueling Shutdown (1 O Year ISi)

(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 Surry Monthly Operating Report No. 94-01 Page 6of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: January, 1994 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 02-03-94 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 940104 F 0 B NIA NIA IG RIT Turbine runback occurred during the performance of Special Test 2-ST-307, "Nuclear Instrumentation System Noise Measurement and Analysis",

when a control power fuse in the power range nuclear instrumentation drawer failed due to an inadequately grounded oscilloscope.

(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 Surry Monthly Operating Report No. 94-01 Page 7of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02-06-94 Completed by: Pat Kessler Telephone: 365,-2790 MONTH: January, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 494 17 452 2 494 18 447 3 491 19 434 4 491 20 435 5 490 21 420 6 491 22 13 7 485 23 0 8 486 24 0 9 486 25 0 10 480 26 0 11 479 27 0 12 470 28 0 13 464 29 0 14 468 30 0 15 467 31 0 16 459 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. 94-01 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit2 Date: 02-06-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: January, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 790 17 793 2 791 18 792 3 790 19 783 4 665 20 793 5 789 21 792 6 788 22 792 7 789 23 790 8 789 24 792 9 790 25 793 10 791 26 794 11 791 27 795 12 791 28 794 13 791 29 794 14 790 30 793 15 790 31 791 16 792 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. 94-01 Page 9of 18

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: January, 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.

UNIT ONE:

01/01/94 0000 The reporting period began with the Unit operating at 63% power, 516 MWe, in a power coast down.

01/21/94 2217 Started power reduction at 53.5%, 425 MWe, to begin refueling shutdown.

01/22/94 0206 Unit off-line. Reactor remained critical to facilitate main turbine overspeed testing.

01/22/94 0512 Manual reactor trip initiated; began Reactor Coolant system cooldown.

01/31/94 2400 The reporting period ended with the Unit in the refueling shutdown mode.

UNIT Two:

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

01/04/94 1025 Turbine runback occurred during the performance of Special Test 2-ST-307, "Nuclear Instrumentation System Noise Measurement and Analysis", when a control power fuse in the power range nuclear instrumentation drawer failed due to an inadequately grounded oscilloscope.

1032 Turbine runback stopped at 48% power, 390 MWe. Steam dumps open.

1033 Steam transferred from steam dumps to turbine. Started power increase.

1043 Turbine runback occurred from 70% power, 600 MWe, as a result of the previous runback signal not being reset.

1044 Turbine run back stopped at 60% power, 480 MWe.

1810 Started power increase.

2214 Stopped power increase at 100%, 825 MWe.

01/19/94 1005 Started power reduction due to decreasing intake canal inventory (resulting from the formation of ice at the low level intake structure) and main condenser vacuum.

1035 Stopped power reduction at 92%, 690 MWe.

1102 Started power increase.

1134 Stopped power increase at 100%, 825 MWe.

01/31/94 2400 The reporting period ended with the Unit operating at 100% power, 825 MWe.

e Surry Monthly Operating Report No. 94-01 Page 10 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January, 1994 SE 93-235 Safety Evaluation 12-16-93 Safety Evaluation 93-235 was performed to evaluate the interim storage of replacement control rod guide tubes (CRGT) in the Surry Steam Generator Storage Facility until they are installed in Unit 2. The evaluation also included the construction of the two storage containers that will be used.

The evaluation concluded that this activity is acceptable since the storage containers are designed to remain functional during a design basis event and the increase in radiation levels resulting from the contaminated CRGTs will be negligible and within the original design basis. This change will not impact any safety-related components or systems. Therefore, an unreviewed safety question does not exist.

EWR 89-352 Engineering Work Request 01-05-94 Engineering Work Request 89-352 replaced certain Gaseous Wasie (GW) system nonsafety-related piping, components and isolation valves with equivalent safety-related equipment.

The replacement valves and piping were manufactured in accordance with ASME Ill, Code Class 3 standards, which is consistent with the existing design. The modifications improved the reliability of the subject equipment and did not affect the performance of the GW system. Therefore, an unreviewed safety question did not exist.

DCP 89-19 Design Change Package 01-11-94 (Safety Evaluation No.91-005)

Design Change Package 89-19 replaced the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> equalize charging timers in the station battery uninterruptible power supply (UPS) units with equivalent timers that have a 160 hour0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> maximum timing cycle.

This modification eliminated the need for resetting the timers daily and enabled the charging cycle to be uninterrupted. The change did not affect the operation or performance characteristics of the UPS units. Therefore, an unreviewed safety question did not exist.

DCP 93-13 Design Change Package 01-17-94 (Safety Evaluation No.93-160)

Design Change Package 93-160 installed Pyrocrete over the existing Thermo-Lag fire barrier enclosure surrounding Service Water (SW) system lines in Mechanical Equipment Room No. 3. The Thermo-Lag had to be removed prior to the installation of the Pyrocrete in certain locations due to space limitations.

This modification was implemented to ensure the subject lines are protected by a three hour fire-rated barrier. The design or operability of the SW system was not affected. Therefore, an unreviewed safety question did not exist.

e Surry Monthly Operating Report No. 94-01 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January, 1994 FS 91-19 UFSAR Change 01-17-94 (Safety Evaluation 94-005)

Updated Final Safety Analysis Report Change 91-19 revised Section 10.3.5.3,

"[Auxiliary Feedwater System] Performance Analysis", to de let~ references to auxiliary feedwater (AFW) pump flow restrictions that were instituted in response to water hammer concerns.

New steam generators were installed in 1979 and 1980 which incorporated a different feed ring and nozzle design for feedwater flow to the SGs. A loop seal in the feedwater system line was also installed. These modifications effectively eliminated the water hammer concerns. The change to the UFSAR did not affect the operation of the AFW system. Therefore, an unreviewed safety question did not exist.

WO 264317 Work Order 01-17-94 (Safety Evaluation No.94-004)

Work Order 264317 removed Unit 1 breaker 01-EP-BKR-1481-5 from service to perform corrective maintenance. This activity de-energized lncore Neutron Flux Detector Drive 1-IC-DET-1B, Main Steam Non-return Valve 1-MS-MOV-1018, and the bypass transformer for the Technical Support Center (TSC) uninterruptible power supply (UPS).

This activity did not affect the ability of 1-MS-MOV-101 B to perform its design basis accident function (i.e., mechanical closure on reverse flow). 1-IC-DET-18 and the TSC UPS are not considered in the UFSAR accident analyses.

Therefore, an unreviewed safety question did not exist.

SE 94-011 Safety Evaluation 01-21-94 Safety Evaluation 94-011 was performed to evaluate the 1994 Unit 1 refueling outage schedule.

The evaluation concluded that the refueling outage schedule is acceptable based on a review of the planning, procedures, policies, shutdown risk, and monitoring management that are performed for the outage. Therefore, an unreviewed safety question does not exist.

TSR 94-014 Temporary Shielding Request 01-24-94 (Safety Evaluation 94-013)

Temporary Shielding Request 94-013 installed temporary lead shielding on certain Unit 1 reactor coolant loop lines and valves to reduce the radiation dose received by personnel while removing the resistance temperature device by-pass lines and performing other work in the area.

Installation of the shielding while the subject lines remain "operable" was determined to be acceptable through the performance of seismic piping analyses, provided the pressure and temperature do not exceed 385 psi and 400° F. The shielding will not adversely affect the design functions of the affected system and will be removed prior to exceeding the specified operating conditions. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 94-01 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January, 1994 TSR 94-017 Temporary Shielding Request 01-24-94 (Safety Evaluation 94-012)

Temporary Shielding Request 94-017 installed temporary lead shielding on the elbows of three Unit 1 Safety Injection system accumulator discharge lines to reduce the radiation dose received by personnel while working in the area.

Installation of the shielding while the subject lines remain "operable" was determined to be acceptable through the performance of seismic and deadweight piping analyses. The shielding will not adversely affect the design functions of the affected system and will be removed prior to Unit start-up.

Therefore, an unreviewed safety question does not exist.

SE 94-017 Safety Evaluation 01-26-94 Safety Evaluation 94-017 was performed to evaluate the acceptability of using the existing inflatable cavity seal (which had exceeded the nominal service life specified by the manufacturer) during the 1994 Unit 1 refueling outage. This action became necessary when an inspection of the new inflatable cavity seal revealed unacceptable defects in the vulcanized joints.

The evaluation concluded that it is acceptable to use the existing inflatable cavity seal since it was inspected and found to be in good condition and it will be tested to ensure seal integrity prior to flooding the reactor cavity. The inflatable cavity seal is nonsafety-related and is a back-up to the J-seal, which is the primary method for controlling reactor cavity leakage. Therefore, an unreviewed safety question does not exist.

FS 94-03 UFSAR Change 01-28-94 (Safety Evaluation 94-018)

Updated Final Safety Analysis Report Change 94-03 revised Section 2.3.1.2.2, "Hurricane Flooding", to clarify that the Emergency Service Water (ESW)

Pumphouse door seal plates and the exterior louver covers are not required to be completely watertight.

An engineering evaluation determined that the subject flood protection devices are required only to limit the leakage of water into the ESW Pumphouse in order to maintain the ESW pump diesel engines in an operable condition. This change did not involve any physical modifications and did not affect the margin of safety or the Technical Specifications. Therefore, an unreviewed safety question did not exist.

e Surry Monthly Operating Report No. 94-01 Page 13 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January, 1994 1-TMOP-EPH-001 Temporary Maintenance Operating Procedure 01-20-94 (Safety Evaluation No.94-008)

Temporary Maintenance Operating Procedure 1-TMOP-EPH-001, "Unit 1 34.5 KV Bus 6 and RSS Transformer C Outage" was developed to provide instructions for conducting an outage of 34.5 KV Bus No. 6 and Reserve Station Service Transformer (RSST) "C". The bus and RSST outage is required to enable the replacement of the Bus No. 6 disconnect insulators and to implement Design Change Package 93-078, "EP Switchyard Reliability Assessment Modification".

This procedure provides for a controlled reliable electric plant line-up that is allowed by the UFSAR and Technical Specifications. Unit 1 will be at cold shutdown and in a backfeed line-up. Unit 2 will enter the appropriate Technical Specification Limiting Condition for Operation since the primary power supply to Emergency Bus 2J will not be available. The emergency diesel generators will remain operable during this procedure. Therefore, an unreviewed safety question does not exist.

1-FDTP-92-64-3-1 Flnal Design Test Procedure 01-25-94 2-FDTP-92-64-3-1 (Safety Evaluation No.94-016)

Final Design Test Procedures 1/2-FDTP-92-64-3-1, were developed to provide instructions for performing an integrated functional test and verification of operability of the Unit 1 and 2 charging pumps following the completion of Design Change Package 92-64, "Charging Pump Logic Modifications".

The test does not affect the charging system and will be performed while the Unit is at refueling shutdown (when the charging pumps are not required). Therefore, an unreviewed safety question does not exist.

TOP-4031 Temporary Operating Procedure 01-29-94 (Safety Evaluation No. 94-019A)

Temporary Operating Procedure TOP-4031, "Installation and Removal of PDTT to Seal Return Jumpers", was developed to provide instructions for temporarily installing approximately 25 feet of hose from the Unit 1 Primary Drains Transfer Tank to the reactor coolant pump seal return line in order to recover reactor coolant leakage past a loop stop valve.

The jumper hose will be tested prior to use at a pressure that is greater than the system pressure to which it will be exposed. The installation will be monitored periodically to ensure any degradation is promptly identified. The procedure will be performed while the Unit is at cold shutdown and will not impact the operation of the Residual Heat Removal system. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 94-01 Page 14 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January, 1994 1-0PT-EG-001 Operations Periodic Test Procedures 01-31-94 (Safety Evaluation No.94-021)

Operations Periodic Test Procedure 1-0PT-EG-001, "No. 1 Emergency Diesel Generator Monthly Start Exercise Test", was temporarily revised to provide instructions for installing a temporary bypass (or kill) switch to block the start signal to the primary fuel oil transfer pump. This modification was necessary to facilitate testing of the backup fuel oil transfer pump.

The procedure will be performed while Unit 1 is at cold shutdown and Emergency Diesel Generator (EDG) No. 1 is out of service. Post maintenance testing will be performed to ensure the operability of EDG No. 1 prior to returning it to service.

Therefore, an unreviewed safety question does not exist.

- Surry Monthly Operating Report No. 94-01 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRIE NRC APPROVAL MONTH/YEAR: January, 1994 None during this reporting period.

e Surry Monthly Operating Report No. 94-01 Page 16 of 18 CHEMISTRY REPORT MONTH/YEAR: January, 1994 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. AvQ. Max. Min. Avg.

Gross Radioactivity, u.Ci/ml 8.54E-1 1.06E-2 2.82E-1 1.67E-1 3.26E-2 1.18E-1 Susoended Solids, nnm < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Gross Tritium, u.Ci/ml 5.28E-2 5.13E-2 5.19E-2 4.92E-1 4.22E-1 4.53E-1 r131 u.Ci/ml 2.28E-1 1.06E-3 3.15E-2 1.68E-4 2.79E-5 8.97E-5 1131/I133 0.34 0.22 0.28 0.18 0.06 0.09 Hvdroaen cc/ka 38.9 3.4 23.9 44.9 35.4 40.6 Lithium, oom 0.81 0.69 0.75 2.34 2.08 2.21 Boron - 10, oom* 460.8 0.2 146.6 203.6 186.6 194.0 OxyQen, (DO), oom 5.5 <0.005 1.93 < 0.005 <0.005 < 0.005 Chloride, oom < 0.050 <0.001 0.003 < 0.050 0.006 0.010 pH at 25 demee Celsius 9.12 4.40 6.34 6.45 6.22 6.35

None

e Surry Monthly Operating Report No. 94-01 Page 17 of 18 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: January, 1994 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received ~rShiement Number Number Enrichment Cask Activi!l CASTORV/21 500-11-018 01/19194 NIA D40 LMOOCC 3.325 NIA 6A1 LM04UQ 3.393 W14 LM040E 3.203 4A4 LMD4UC 3.393 D35 LMOOBJ 3.325 D36 LM007Y 3.325 D01 LM007M 3.325 D15 LM008C 3.325 D51 LM0079 3.325 W15 LM040G 3.203 1AO LM04TT 2.901 D03 LM008M 3.325 D45 LMOOCB 3.325 D52 LM007H 3.325 D04 LM007C 3.325 D09 LM0088 3.325 W03 LM040S 3.203 D16 LMOOSA 3.325 D18 LM0086 3.325 D21 LM0071 3.325 D26 LM007A 3.325

  • Surry Monthly Operating Report No. 94-01 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: January, 1994 None during this reporting period.
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