ML18153B138

Monthly Operating Repts for Oct 1994 for Surry Power Station Units 1 & 2

ML18153B138
Person / Time
Site:	Surry
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)

Text

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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 9, 1994 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555.

Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.

NO/RPC:vlh Docl<et.Nps.

License Nos.94-650 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 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 TABLE OF CONTENTS Section Surry Monthly Operating Report No. 94-10 Page 2of 21 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

.,/

OPERATING DATA REPORT Surry Monthly Operating Report No. 94-10 Page 3 of 21 Docket No.:

Date:

Completed By:

50-280 11-02-94 D. Mason Telephone:

(804) 365-2459

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 October, 1994 2441 847.5 788 820 781

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

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............................

745.0 745.0 0

745.0 0

1792471.6 597190.0 575524.0 100.0%

100.0%

98.9%

98.0%

0.0%

YTD 7296.0 5794.7 0

5757.5 0

13419214.7 4453050.0 4283373.0 78.9%

78.9%

75.2%

74.5%

0.5%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Cumulative 191616.0 129601.9 3774.5 127436.5 3736.2 296586959.8 96992598.0 92110474.0 66.5%

68.5%

62.0%

61.0%

16.8%

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 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED

• )

. ]'

.Surry Monthly Operating Report No. 94-10 Page 4of 21 OPERATING DATA REPORT Docket No.:

Date:

Completed By:

50-281 11-02-94 D. Mason Telephone:

(804) 365-2459 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 October, 1994 2441 847.5 788

• 020 781

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, H Any (Net MWe):

1 0. Reasons For Restrictions, If Any:

This Month

11. Hours In Reporting Period..........................

745.0

12. Number of Hours Reactor Was Critical..........

745.0

13. Reactor Reserve Shutdown Hours...............

0

14. Hours Generator On-Line...........................

745.0

15. Unit Reserve Shutdown Hours.....................

0

16. Gross Thermal Energy Generated (MWH)......

1817197.2

17. Gross Electrical Energy Generated (MWH)....

604515.0

18. Net Electrical Energy Generated (MWH)........

583296.0

19. Unit Service Factor...................................

100.0%

20. Unit Availability Factor...............................

100.0%

21. Unit Capacity Factor (Using MDC Net)...........

100.2%

22.

Unit Capacity Factor (Using DER Net)...........

99.4%

23. Unit Forced Outage Rate............................

0%

YTD 7296.0 6797.2 0

6787.5 0

16020726.5 5305770.0 5111591.0 93.0%

93.0%

89.7%

88.9%

0%

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):

Cumulative 188496.0 126873.5 328.1 125003.1 0

291696468.9 95251394.0 90443661.0 66.3%

66.3%

61.5%

60.9%

13.4%

FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION

')

j Date (1)

(1)

Type F:

Forced S: Scheduled (4)

.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 (2)

(3)

(4)

Method (5)

Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11-03-94 Completed by: Craig Olsen Telephone: (804) 365-2155 Duration * *

• of

. --LER... System

• Component -Calise & Correctiv1fAction to Hours Reason Shutting No.

Code Code Prevent Recurrence (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)

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Exhibit 1 - Same Source.

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 (1)

(2)

(3)

(4)

(5)

Method Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11-03-94 Completed by: Craig Olsen Telephone: (804) 365-2155

• Duration * *

-*of

.. - LER '. -Syste*m. Component'. Cause '& Corrective Action to Date Type Hours Reason Shutting No.

Code 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)

(5)

Exhibit 1 - Same Source.

_)

Surry Monthly Operating Report No. 94-10 Page 7of 21 AVERAGE DAILY UNIT POWER LEVEL MONTH:

October, 1994 Average Daily Power Level Day (MWe-Net) 1 781 2

781 3

784 4

785 5

785 6

786 7

787 8

785 9

783 10 784 11 787 12 787 13 786 14 787 15 775 16 766 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11-02-94 Completed by: Pat Kessler Telephone: 365-2790 o.,.

1, *.

,.*i Average Daily Power Level (MWe-Net) 763 762 761 761 760 760 760 760 760 763 763 765 762 793 759 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:

October, 1994 Day 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 INSTRUCTIONS Surry Monthly Operating Report No. 94-10 Page Bot 21 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe-Net)

Day 768 17 779 18 780 19 766 20 781 21 780 22 762 23 779 24 784 25 785 26 786 27 786 28 785 29 784 30 786 31 786 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11-02-94 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level (MWe-Net) 786 787 787 782 785 785 786 785 785 786 787 788 789 822 788 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 10/15/94 10/31/94 UNIT TWO:

10/01 /94 10/04/94 10/31/94 0000 The reporting period began with the unit operating at 100% power, 81 O MWe.

1028 Started power reduction to stabilize Steam Generator "C" level oscillations.

1034 Stopped power reduction at 97.5%, 800 MWe.

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

0000 0910 0945 1133 1235 1338 1450 2400 The reporting period began with the unit operating at 100% power, 805 MWe.

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

Stopped power reduction at 94%, 770 MWe.

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

Stopped power reduction at 88%, 725 MWe.

Started power increase.

Stopped power increase at 100%, 815 MWe.

The reporting period ended with the unit operating at 100% power, 815 MWe.

TM S1-94-35 DCP 88-10 SE 94-021 SE 94-031 Surry Monthly Operating Report No. 94-10 Page 10 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1994 Temporary Modification (Safety Evaluation No.94-174) 10-03-94 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.

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

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.

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.

SE94-181 SE 94-183 EWR 90-142 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1994 Safety Evaluation Surry Monthly Operating Report No. 94-10 Page 11 of 21 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.

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.

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

TM S2-94-15 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October, 1994 Temporary Modification (Safety Evaluation No.94-185)

Surry Monthly Operating Report No. 94-10 Page 12 of 21 10-28-94 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.

1 (2)-MOP-IA-001 1 (2)-0P-CH-015 2-TMOP-3029 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 Maintenance Operating Procedures (Safety Evaluation No.94-175) 10-11-94 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.

Operating Procedures (Safety Evaluation No.94-177) 10-13-94 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.

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

1-TOP-4045 1-TOP-4046 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 Temporary Operating Procedure (Safety Evaluation No.94-178) 10-17-94 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.

Temporary Operating Procedure (Safety Evaluation No.94-179) 10-19-94 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 Primarv Coolant Analvsis Gross Radioactivitv, uCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml 1131, uCi/ml 113111133 Hvdroaen, cc/kg Lithium, oom Boron - 10, oom*

Oxygen, (DO), ppm Chloride, oom pH at 25 degree Celsius Boron - 1 O = Total Boron x 0.196 Comments:

None CHEMISTRY REPORT MONTH/YEAR: October, 1994 Unit No. 1 Max.

Min.

Ava.

3.23E-1 2.44E-1 2.79E-1

.:;;0.1

.s.0.1

.:;;0.1 2.95E-1 2.54E-1 2.77E-1 4.79E-4 3.43E-4 4.23E-4 0.08 0.06 0.07 35.1 25.5 32.2 2.28 2.09 2.17 155.2 140.9 148.4

.s.0.005

.s.0.005

.s.0.005 0.011 0.002 0.004 6.92 6.76 6.85 Surry Monthly Operating Report No. 94-10 Page 16 of 21 Unit No. 2 Max.

Min.

Ava.

1.93E-1 8.01E-2 1.26E-1

.:;;0.1

.:;;0.1

.:;;0.1 2.50E-1 2.10E-1 2.35E-1 1.83E-4 2.02E-4 1.48E-4 0.10 0.06 0.08 43.1 26.1 37.6 2.27 1.83 2.07 65.3 44.3 53.5

.s.0.005

.:;;0.005

.:;;0.005 0.010 0.001 0.003 7.41 7.29 7.36

New or Spent Fuel Shipment Date Stored or Number Received Spent Fuel Storage Cask CASTORV/21 500.11-023 10/12/94 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: October, 1994 Number of Assemblies Assembly ANSI

~rShiement Number Number 21 N21 NOANSI T05 LM02JW T06 LM02JV 5R4 LMOC2W N27 NOANSI N28 NOANSI T20 LM02KO T21 LM02JE N29 NOANSI T22 LM02JF N30 NOANSI N22 NOANSI N31 NOANSI N32 NOANSI N23 NOANSI 3RO LMOC1V N24 NOANSI T04 LM02JK 4R9 LMOC2F N25 NOANSI N26 NOANSI Surry Monthly Operating Report No. 94-10 Page 17 of 21 New or Spent Initial Fuel Shipping Enrichment Cask Activi~

2.5560 NIA 3.1100 3.1100 3.6032 2.5560 2.5560 3.1100 3.1100 2.5560 3.1100 2.5560 2.5560 2.5560 2.5560 2.5560 5.5948 2.5560 3.1100 3.5907 2.5560 2.5560

New or Spent Fuel Shipment Date Stored or Number Received New Fuel Unit2 Batch 15 Receipt 1 10/18/94 Receipt 2 10/20/94 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: October, 1994 Number of Assemblies Assembly ANSI per Shipment Number Number 8

2X7 LMOZX8 2XO LMOZX1 2X2 LMOZX3 2X1 LMOZX2 2X9 LMOZXA 2X8 LMOZX9 5XO LMOZXX 4X9 LMOZXW 12 5X5 LMOZV2 2X6 LMOZX7 1X2 LMOZWT 2X5 LMOZX6 4X7 LMOZXU OX1 LMOZWG 5X3 LMOZVO 5X4 LMOZV1 1X9 LMOZXO 1X4 LMOZWV 2X3 LMOZX4 1X3 LMOZWU Surry Monthly Operating Report Initial Enrichment 3.8238 3.8135 3.8145 3.8136 4.0113 3.8147 4.0231 4.0082 4.0186 3.8149 3.8060 3.8257 4.0097 3.8162 4.0026 4.0281 3.8176 3.8153 3.8097 3.8184 No. 94-10 Page 18 of 21 New or Spent Fuel Shipping Cask Activity 9.96Ci 14.73Ci

,r, New or Spent Fuel Shipment Date Stored or Number Received New Fuel Unit2 Batch 15 Receipt 3 10/25/94 Receipt 4 10/27/94 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: October, 1994 Number of Assemblies Assembly ANSI eer Shiement Number Number 12 2X4 LMOZX5 Ox9 LMOZWQ 4x0 LMOZXM 3X9 LMOZXL 4X6 LMOZXT 4X8 LMOZXV 3X2 LMOZXD OX?

LMOZWN 1X8 LMOZWZ OX5 LMOZWL 3X3 LMOZXE 5X1 LMOZXY 12 5X6 LM02Y3 3X6 LMOZXH 4X4 LMOZXR 1X1 LMOZWS OX4 LMOZWK 5X2 LMOZXZ 1X7 LMOZWV 1X5 LMO"ZWW 1X6 LMOZWX 3XO LMOZXB Surry Monthly Operating Report Initial Enrichment 3.8113 3.8186 4.0112 4.0118 4.0207 3.9990 4.0108 3.8095 3.8118 3.8132 4.0098 4.0309 4.0252 4.0044 4.0079 3.8075 3.8117 4.0012 3.8105 3.8166 3.8024 4.0068 No. 94-10 Page 19 of 21 New or Spent Fuel Shipping Cask Activi~

14.92Ci 14.85Ci

New or Spent Fuel Shipment Date Stored or Number Received New Fuel Unit2 Batch 15 Receipt 4 (Continued)

FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: October, 1994 Number of Assemblies Assembly ANSI eer Shiement Number Number OX2 LMOZWH 3X5 LMOZWG Surry Monthly Operating Report No. 94-10 Page 20 of 21 New or Spent Initial Fuel Shipping Enrichment Cask Activi~

3.8136 4.0109

Number e

Surry Monthly Operating Report No. 94-10 Page 21 of 21 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: October, 1994 Title LERNumber O-EPT-0109 Weekly Emergency Diesel Generator Battery Pilot Cell and Bus Voltage Checks S 1-94-010-00