ML18153B138

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Oct 1994 for Surry Power Station Units 1 & 2.W/941109 Ltr
ML18153B138
Person / Time
Site: Surry  Dominion icon.png
Issue date: 10/31/1994
From: Bowling M, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-650, NUDOCS 9411150416
Download: ML18153B138 (22)
v • d • e


Text

,' ~

I r

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 9, 1994 U.S. Nuclear Regulatory Commission Serial No.94-650 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555. Docl<et .Nps. 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 October 1994.

Very truly yours, M. L. Bowling, Manager Nuclear Licensing and Programs Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station 9411150416 941031 PDR ADOCK 05000280 R PDR

VIRGINIA ELECTRIC AND POWER COMPANY

~ .

SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 94-10 Approved:

Station Manager

) ' J

  • Surry Monthly Operating Report No. 94-10

', Page 2of 21 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 Av~rage 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 ...................................................................... 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 ................................................................................................... 21

.,/

  • Surry Monthly Operating Report No. 94-10 Page 3 of 21 OPERATING DATA REPORT Docket No.: 50-280 Date: 11-02-94 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . October, 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 ......................... . 745.0 7296.0 191616.0
12. Number of Hours Reactor Was Critical ......... . 745.0 5794.7 129601.9
13. Reactor Reserve Shutdown Hours .............. . 0 0 3774.5
14. Hours Generator On-Line .......................... . 745.0 5757.5 127436.5
15. Unit Reserve Shutdown Hours.................... . 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... . 1792471.6 13419214.7 296586959.8
17. Gross Electrical Energy Generated (MWH) .. .. 597190.0 4453050.0 96992598.0
18. Net Electrical Energy Generated (MWH) ...... .. 575524.0 4283373.0 92110474.0
19. Unit Service Factor ................................. .. 100.0% 78.9% 66.5%
20. Unit Availability Factor .............................. . 100.0% 78.9% 68.5%
21. Unit Capacity Factor (Using MDC Net) .......... . 98.9% 75.2% 62.0%
22. Unit Capacity Factor (Using DER Net) .......... . 98.0% 74.5% 61.0%
23. Unit Forced Outage Rate ........................... . 0.0% 0.5% 16.8%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Maintenance (Steam Generator Chemical Cleaning), December 1, 1994, 23 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

  • ) . ]'
  • .Surry Monthly Operating Report No. 94-10 Page 4of 21 OPERATING DATA REPORT Docket No.: 50-281 Date: 11-02-94 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: ................................................. .. Surry Unit 2
2. Reporting Period: ......................................... . October, 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): .: .. *020
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, HAny (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .......................... 745.0 7296.0 188496.0
12. Number of Hours Reactor Was Critical .......... 745.0 6797.2 126873.5
13. Reactor Reserve Shutdown Hours ............... 0 0 328.1
14. Hours Generator On-Line ........................... 745.0 6787.5 125003.1
15. Unit Reserve Shutdown Hours ..................... 0 0 0
16. Gross Thermal Energy Generated (MWH) ...... 1817197.2 16020726.5 291696468.9
17. Gross Electrical Energy Generated (MWH) .... 604515.0 5305770.0 95251394.0
18. Net Electrical Energy Generated (MWH) ........ 583296.0 5111591.0 90443661.0
19. Unit Service Factor ................................... 100.0% 93.0% 66.3%
20. Unit Availability Factor ............................... 100.0% 93.0% 66.3%
21. Unit Capacity Factor (Using MDC Net) ........... 100.2% 89.7% 61.5%
22. Unit Capacity Factor (Using DER Net) ........... 99.4% 88.9% 60.9%
23. Unit Forced Outage Rate ............................ 0% 0% 13.4%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling (10 Year ISi), February 4, 1995, 55 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

') j

  • .Surry Monthly Operating Report No. 94-10 Page 5of 21 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: October, 1994 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11-03-94 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration * * *of . --LER ... System

  • Component -Calise & Correctiv1fAction 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 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)

J

  • Surry Monthly Operating Report No. 94-10 Page 6of 21 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: October, 1994 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11-03-94 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method

  • Duration * * - *of . . - LER ' .-Syste*m . 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 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)

_)

  • Surry Monthly Operating Report No. 94-10 Page 7of 21 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: October, 1994 o.,. 1, *., .*i Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 781 17 763 2 781 18 762 3 784 19 761 4 785 20 761 5 785 21 760 6 786 22 760 7 787 23 760 8 785 24 760 9 783 25 760 10 784 26 763 11 787 27 763 12 787 28 765 13 786 29 762 14 787 30 793 15 775 31 759 16 766 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.
  • Surry Monthly Operating Report No. 94-10 Page Bot 21 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: October, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 1 768 17 786 2 779 18 787 3 780 19 787 4 766 20 782 5 781 21 785 6 780 22 785 7 762 23 786 8 779 24 785 9 784 25 785 10 785 26 786 11 786 27 787 12 786 28 788 13 785 29 789 14 784 30 822 15 786 31 788 16 786 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.
  • Surry Monthly Operating Report No. 94-10 Page 9 of 21

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: October, 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:

10/01/94 0000 The reporting period began with the unit operating at 100% power, 81 O MWe.

10/15/94 1028 Started power reduction to stabilize Steam Generator "C" level oscillations.

1034 Stopped power reduction at 97.5%, 800 MWe.

10/31/94 2400 The reporting period ended with the unit operating at 97.5% power, 800 MWe, due to Steam Generator "C" level oscillations.

UNIT TWO:

10/01 /94 0000 The reporting period began with the unit operating at 100% power, 805 MWe.

10/04/94 0910 Started power reduction to perform Operations Surveillance Test, 2-0SP-TM-001, "Turbine Inlet Valve Freedom Test."

0945 Stopped power reduction at 94%, 770 MWe.

1133 Started power reduction to continue performance of 2-0SP-TM-001.

1235 Stopped power reduction at 88%, 725 MWe.

1338 Started power increase.

1450 Stopped power increase at 100%, 815 MWe.

10/31/94 2400 The reporting period ended with the unit operating at 100% power, 815 MWe.

..

  • Surry Monthly Operating Report No. 94-10 Page 10 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1994 TM S1-94-35 Temporary Modification 10-03-94 (Safety Evaluation No.94-174)

Temporary Modification S1-94-35 installed electrical jumpers to bypass test switch PB ..,.,-TA on the Unit 1 Reactor Protection System (RPS) Train ."A" circuitry to allow the switch to be replaced without rendering the circuits inoperable.

RPS Train "B" 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.

DCP 88-10 Design Change Package 10-10-94 (Safety Evaluation No.91-085)

Design Change Package 88-10 added additional inputs to the NUREG-0696 multiplexing system and the Emergency Response Facility computer to provide emergency ventilation damper position and semi-vital bus voltage indications of the Technical Support Center and the Local Emergency Operations Facility.

This modification provides a reliable means of monitoring required Regulatory Guide 1.97 variables in the TSC and the LEOF during and following a design basis event. The operation of safety-related equipment or the availability of safety-related power sources is not affected. Therefore, an unreviewed safety question does not exist.

SE 94-021 Safety Evaluation 10-10-94 Safety Evaluation 94-021 was performed to evaluate a vendor nonconformance report regarding a tipover impact limiter for spent fuel storage casks. Specifically, the crush strength was determined to be slightly below the vendor specified limit for two sections of aluminum honeycomb for a CASTOR X/33 cask tipover impact limiter.

The evaluation concluded that the acceleration of a cask tipover event would actually be less using the lower crush strength sections and would thereby decrease the loads and stresses on the cask and fuel basket. Therefore, the tipover impact limiter remains capable of performing its intended function and an unreviewed safety question does not exist.

SE 94-031 Safety Evaluation 10-17-94 Safety Evaluation 94-031 was performed to evaluate a vendor nonconformance report regarding a spent fuel storage cask. Specifically, the magnesium content of the ductile cast iron for the CASTOR X/33 cask No. 001 was determined to be below the vendor specified limits.

The results of metallurgical and mechanical testing indicated that the cask annealing process was correct, that the magnesium difference had no effect on the metallographic formation of ductile cast iron, and that the mechanical properties of the material were not altered. Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report No. 94-10 Page 11 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1994 SE94-181 Safety Evaluation 10-25-94 Safety Evaluation 94-181 was performed to evaluate the temporary installation and operation of a skid mounted wet oxidation system at the Surry Radwaste Facility (SRF).

--- The wet oxidation equipment will be used -to process liquid waste --containing ethylene diamine tetra-acetic (EDTA) acid resulting from the steam generator chemical cleaning process.

The evaluation concluded that the temporary installation and operation of a skid mounted wet oxidation system was acceptable. Adequate spill control measures will be established and the integrity of the SRF systems will be maintained. Therefore, an unreviewed safety question does not exist.

SE 94-183 Safety Evaluation 10-26-94 Safety Evaluation 94-183 was performed to evaluate the operation of the Unit 1 steam generators (SG) with tube support plate broached quatrefoil holes that are partially blocked by sludge deposits. The blockage causes hydrodynamic instability resulting in SG water level oscillations.

The condition exhibited by the Unit 1 SGs was determined to be bounded by the previous evaluations and analyses of a similar condition that was exhibited by the Unit 2 SGs before being chemically cleaned in June, 1994. The evaluation concluded that continued Unit 1 operation is acceptable until the SGs can be chemically cleaned provided that steady state reactor power remains at or above 85%. Therefore, an unreviewed safety question does not exist.

EWR 90-142 Engineering Work Request 10-26-94 (Safety Evaluation No.91-085)

Engineering Work Request 90-142 replaced chilled water pumps 1-VS-P-2A, 1-VS-P-2B, and 1-VS-P-2C since they were approaching the end of their service life. Obtaining replacement parts had also become difficult.

The seismically qualified replacement pumps meet the system design flow requirements and will improve system availability. Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report No. 94-10 Page 12 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1994 TM S2-94-15 Temporary Modification 10-28-94 (Safety Evaluation No.94-185)

Temporary Modification S2-94-15 installed a temporary electrical jumper to bypass Cell 52

. of the Main Station Battery 2A to allow the weak cell to be replaced.

The electrical jumper material and quality were equivalent to the existing battery cables and connections and was capable of carrying the load of the 2A DC bus. An evaluation of the impact of this activity on battery design performance was performed. The evaluation concluded that the battery would remain operable with the electrical jumper installed without any reduction in the Technical Specifications margin of safety. This activity was discussed with and agreed upon by the NRC during a conference call on October 28, 1994. Therefore, an unreviewed safety question did not exist.

  • Surry Monthly Operating Report No. 94-10 Page 13 of 21 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1994 1(2)-MOP-IA-001 Maintenance Operating Procedures 10-11-94 (Safety Evaluation No.94-175)

Maintenance Operating Procedures 1(2)-MOP-IA-001, "Containment Instrument Air Compressors/'.. were revised to provide. instructions .. for lifting electrical leads to the low water level switch when a containment instrument air (IA) compressor is removed from service. By lifting the subject electrical leads, the associated control room annunciator remains functional for the containment IA compressor that remains in service.

The subject electrical leads will be landed before the respective containment IA compressor is returned to service. Implementation of this procedure will not change the normal operating configuration of the Containment IA System. Therefore, an unreviewed safety question does not exist.

1(2)-0P-CH-015 Operating Procedures 10-13-94 (Safety Evaluation No.94-177)

Operating Procedures 1(2)-0P-CH-015, "Installation and Operation of the POTT to CH System Jumper," were developed to provide instructions for the installation of a temporary mechanical jumper to connect the Gaseous Drains (DG) System to the Chemical and Volume Control System (CVCS).

The mechanical jumper will be installed when a unit is shut down in order to conserve primary system inventory and thereby reduce the volume of liquid waste. The jumper and associated connections will be leak tested before being placed in service. Instructions are also provided to prevent inadvertent Reactor Coolant System dilution and to ensure refueling containment integrity is maintained. Therefore, an unreviewed safety question does not exist.

2-TMOP-3029 Temporary Maintenance Operating Procedure 10-13-94 (Safety Evaluation No.94-176)

Temporary Maintenance Operating Procedure 2-TMOP-3029, "Resin Removal of 2-CH-l-1A: Vacuum Method," was developed to provide instructions for cleaning any residual resin or foreign debris from the retention element of the Unit 2 "A" mixed bed demineralizer, 2-CH-l-1A.

The subject procedure will be implemented while the demineralizer is isolated from the in-service letdown train and within the ventilation boundaries of the Auxiliary Building filtered exhaust. Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report No. 94-10 Page 14of 21 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1994 1-TOP-4045 Temporary Operating Procedure 10-17-94 (Safety Evaluation No.94-178)

Temporary Operating Procedure 1-TOP-4045, "Reactor Coolant Pump 1C Number 1 Seal

... Leakoff.Bucket Check,"..was developed to provide instructionsJor..verifying the accuracy of the low range flow instrumentation for Unit 1 reactor coolant pump (RCP) "C" seal leak-off flow.

Implementation of this procedure, which involves the collection and measurement of RCP seal leak-off flow, will not affect the reactor coolant system pressure boundary and will not reduce the margin of safety as described by the Technical Specifications. Therefore, an unreviewed safety question does not exist.

1-TOP-4046 Temporary Operating Procedure 10-19-94 (Safety Evaluation No.94-179)

Temporary Operating Procedure 1-TOP-4046, "Reactor Coolant Pump 1C Number 2 Seal Leakoff Bucket Check," was developed to provide instructions for measuring the amount of water that is bypassing the Unit 1 reactor coolant pump (RCP) "C" No. 1 seal leak-off flow instrumentation.

Implementation of this procedure, which involves the collection and measurement of RCP No. 2 seal leak-off flow, will not affect the reactor coolant system pressure boundary and will not reduce the margin of safety as described by the Technical Specifications.

Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report No. 94-10 Page 15 of 21 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1994 None During the Reporting Period

e

  • Surry Monthly Operating Report No. 94-10 Page 16 of 21 CHEMISTRY REPORT MONTH/YEAR: October, 1994 Unit No. 1 Unit No. 2 Primarv Coolant Analvsis Max. Min. Ava. Max. Min. Ava.

Gross Radioactivitv, uCi/ml 3.23E-1 2.44E-1 2.79E-1 1.93E-1 8.01E-2 1.26E-1 Suspended Solids, ppm .:;;0.1 .s.0.1 .:;;0.1 .:;;0.1 .:;;0.1 .:;;0.1 Gross Tritium, µCi/ml 2.95E-1 2.54E-1 2.77E-1 2.50E-1 2.10E-1 2.35E-1 1131, uCi/ml 4.79E-4 3.43E-4 4.23E-4 1.83E-4 2.02E-4 1.48E-4 113111133 0.08 0.06 0.07 0.10 0.06 0.08 Hvdroaen, cc/kg 35.1 25.5 32.2 43.1 26.1 37.6 Lithium, oom 2.28 2.09 2.17 2.27 1.83 2.07 Boron - 10, oom* 155.2 140.9 148.4 65.3 44.3 53.5 Oxygen, (DO), ppm .s.0.005 .s.0.005 .s.0.005 .s.0.005 .:;;0.005 .:;;0.005 Chloride, oom 0.011 0.002 0.004 0.010 0.001 0.003 pH at 25 degree Celsius 6.92 6.76 6.85 7.41 7.29 7.36 Boron - 1O = Total Boron x 0.196 Comments:

None

  • FUEL HANDLING
  • Surry Monthly Operating Report No. 94-10 Page 17 of 21 UNITS 1 & 2 MONTH/YEAR: October, 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~

Spent Fuel Storage Cask CASTORV/21 500.11-023 10/12/94 21 N21 NOANSI 2.5560 NIA T05 LM02JW 3.1100 T06 LM02JV 3.1100 5R4 LMOC2W 3.6032 N27 NOANSI 2.5560 N28 NOANSI 2.5560 T20 LM02KO 3.1100 T21 LM02JE 3.1100 N29 NOANSI 2.5560 T22 LM02JF 3.1100 N30 NOANSI 2.5560 N22 NOANSI 2.5560 N31 NOANSI 2.5560 N32 NOANSI 2.5560 N23 NOANSI 2.5560 3RO LMOC1V 5.5948 N24 NOANSI 2.5560 T04 LM02JK 3.1100 4R9 LMOC2F 3.5907 N25 NOANSI 2.5560 N26 NOANSI 2.5560

FUEL HANDLING

  • Surry Monthly Operating Report No. 94-10 Page 18 of 21 UNITS 1 & 2 MONTH/YEAR: October, 1994 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity New Fuel Unit2 Batch 15 Receipt 1 10/18/94 8 2X7 LMOZX8 3.8238 9.96Ci 2XO LMOZX1 3.8135 2X2 LMOZX3 3.8145 2X1 LMOZX2 3.8136 2X9 LMOZXA 4.0113 2X8 LMOZX9 3.8147 5XO LMOZXX 4.0231 4X9 LMOZXW 4.0082 Receipt 2 10/20/94 12 5X5 LMOZV2 4.0186 14.73Ci 2X6 LMOZX7 3.8149 1X2 LMOZWT 3.8060 2X5 LMOZX6 3.8257 4X7 LMOZXU 4.0097 OX1 LMOZWG 3.8162 5X3 LMOZVO 4.0026 5X4 LMOZV1 4.0281 1X9 LMOZXO 3.8176 1X4 LMOZWV 3.8153 2X3 LMOZX4 3.8097 1X3 LMOZWU 3.8184

,r, .,.,

  • *Surry Monthly Operating Report No. 94-10 Page 19 of 21 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: October, 1994 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received eer Shiement Number Number Enrichment Cask Activi~

New Fuel Unit2 Batch 15 Receipt 3 10/25/94 12 2X4 LMOZX5 3.8113 14.92Ci Ox9 LMOZWQ 3.8186 4x0 LMOZXM 4.0112 3X9 LMOZXL 4.0118 4X6 LMOZXT 4.0207 4X8 LMOZXV 3.9990 3X2 LMOZXD 4.0108 OX? LMOZWN 3.8095 1X8 LMOZWZ 3.8118 OX5 LMOZWL 3.8132 3X3 LMOZXE 4.0098 5X1 LMOZXY 4.0309 Receipt 4 10/27/94 12 5X6 LM02Y3 4.0252 14.85Ci 3X6 LMOZXH 4.0044 4X4 LMOZXR 4.0079 1X1 LMOZWS 3.8075 OX4 LMOZWK 3.8117 5X2 LMOZXZ 4.0012 1X7 LMOZWV 3.8105 1X5 LMO"ZWW 3.8166 1X6 LMOZWX 3.8024 3XO LMOZXB 4.0068

  • FUEL HANDLING
  • Surry Monthly Operating Report No. 94-10 Page 20 of 21 UNITS 1 & 2 MONTH/YEAR: October, 1994 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received eer Shiement Number Number Enrichment Cask Activi~

New Fuel Unit2 Batch 15 Receipt 4 (Continued) OX2 LMOZWH 3.8136 3X5 LMOZWG 4.0109

e

  • DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED Surry Monthly Operating Report No. 94-10 Page 21 of 21 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: October, 1994 Number Title LERNumber O-EPT-0109 Weekly Emergency Diesel Generator Battery Pilot Cell and Bus S 1-94-010-00 Voltage Checks
Retrieved from "https://kanterella.com/w/index.php?title=ML18153B138&oldid=2402923"