ML18153A529

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Monthly Operating Repts for Feb 1996 for SPS.W/960313 Ltr
ML18153A529
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/29/1996
From: Bowling M, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-125, NUDOCS 9603210202
Download: ML18153A529 (19)
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Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 13, 1996 U.S. Nuclear Regulatory Commission Serial No.96-125 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 February 1996.

Very truly yours, M. L. Bowling, Manager Nuclear Licensing & Operations Support 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 210030 9603210202 960229 ...

PDR ADOCK 05000280 i R PDR

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 96-02 Approved:

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Station Manager

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Date

.urry Monthly Operating Report No. 96-02 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 ....................................................................................... 1O Facility Changes That Did Not Require NRG Approval ............................................................................... 11 Procedure or Method of Operation Changes That Did Not Require NRG Approval ........................................... 13 Tests and Experiments That Did Not Require NRG 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

~urry Monthly Operating Report No. 96-02 Page 3 of 18 OPERATING DATA REPORT Docket No.: 50-280 Date: 03-04-96 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: ................... : .............................. . Surry Unit 1
2. Reporting Period: ......................................... . February, 1996
3. Licensed Thermal Power (MWt): ...................... . 2546
4. Nameplate Rating (Gross MWe): ...................... . 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 840
7. Maximum Dependable Capacity (Net MWe): ....... . 801
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 ......................... . 696.0 1440.0 203280.0
12. Number of Hours Reactor Was Critical ......... . 696.0 1440.0 138050.7
13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 3774.5
14. Hours Generator On-Line .......................... . 696.0 1440.0 139490.7
15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... . 1760711.8 3654630.0 320052422.8
17. Gross Electrical Energy Generated (MWH) ... . 589705.0 1223910.0 104801093.0
18. Net Electrical Energy Generated (MWH) ....... . 569445.0 1183868.0 99639841.0
19. Unit Service Factor. ................................. . 100.0% 100.0% 68.6%
20. Unit Availability Factor .............................. . 100.0% 100.0% 70.5%
21. Unit Capacity Factor (Using MDC Net) .......... . 102.1% 102.6% 63.1%
22. Unit Capacity Factor (Using DER Net) .......... . 103.8% 104.3% 62.2%
23. Unit Forced Outage Rate ........................... . 0.0% 0.0% 15.7%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
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

tturry Month;y Operating Report No. 96-02 Page4 of 18 OPERATING DATA REPORT Docket No.: 50-281 Date: 03-04-96 Completed By: D. Mason Telephone: (804) 365-2459 1 . Unit Name: .................................................. . Surry Unit 2

2. Reporting Period: ......................................... . February, 1996
3. Licensed Thermal Power (MWt): ...................... . 2546
4. Nameplate Rating (Gross MWe): ...................... . 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 840
7. Maximum Dependable Capacity (Net MWe): ....... . 801
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 YfD Cumulative

11. Hours In Reporting Period ......................... . 696.0 1440.0 200160.0
12. Number of Hours Reactor Was Critical ......... . 609.8 1353.8 136856.7
13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 328.1
14. Hours Generator On-Line .......................... . 603.1 1347.1 134903.2
15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ..... . 1518740.0 3405998.1 315941052.1
17. Gross Electrical Energy Generated (MWH) ... . 506235.0 1135590.0 103291234.0
18. Net Electrical Energy Generated (MWH) ....... . 490746.0 1099453.0 98209868.0
19. Unit Service Factor. ................................. . 86.7% 93.5% 67.4%
20. Unit Availability Factor .............................. . 86.7% 93.5% 67.4%
21. Unit Capacity Factor (Using MDC Net) .......... . 88.0% 95.3% 62.9%
22. Unit Capacity Factor (Using DER Net) .......... . 89.5% 96.9% 62.3%
  • 23. Unit Forced Outage Rate ........................... . 13.3% 6.5% 13.0%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, May 3, 1996, 37 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

tlturry Monthly Operating Report No. 96-02 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February, 1996 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 03-05-96 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 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)

.urry Monthly Operating Report No. 96-02 Page 6 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February, 1996 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 03-05-96 Completed by: Craig Olsen Telephone: {804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action to Date Type Hours Reason Shutting Code Code Prevent Recurrence Down Rx 960223 F 92.9 A 96-001 BP PSP Loss of containment integrity due to leaking Residual Heat Removal system piping. Affected piping was replaced.

(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)

tturry Monthly Operating Report No. 96-02 Page 7 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 03-06-96 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: February, 1996 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe- Net) 1 826 17 825 2 798 18 826 3 783 19 826 4 784 20 826 5 826 21 826 6 827 22 826 7 828 23 809 8 830 24 808 9 827 25 809 10 811 26 802 11 826 27 825 12 825 28 824 13 823 29 824 14 823 15 823 16 809 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.

tlturry Monthly Operating Report No. 96-02 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 03-06-96 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: February, 1996 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe - Net) 819 17 826 2 819 18 826 3 820 19 826 4 822 20 826 5 823 21 825 6 823 22 739 7 823 23 2 8 825 24 0 9 825 25 0 10 825 26 26 11 826 27 739 12 824 28 821 13 825 29 817 14 826 15 825 16 824 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.

tlturry Monthly Operating Report No. 96-02 Page 9 of 18

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: February, 1996 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:

02/01/96 0000 The reporting period began with the unit operating at 100% power, 855 MWe.

02/02/96 1217 Started power reduction to perform Operations Surveillance Procedure 1-0SP-TM-001, Turbine Inlet Valve Freedom Test.

1440 Stopped power reduction at 81 %, 700 MWe.

1715 Started power increase.

1822 Stopped power increase at 100%, 850 MWe.

02/03/96 0604 Started power reduction due to the opening of main steam cross-under safety valve 1-MS-SV-109B.

0645 Stopped power reduction at 91 %, 776 MWe.

1030 Started power increase.

1525 Stopped power increase at 100%, 855 MWe. 1-MS-SV-109B was seated.

1651 Started power reduction due to the opening of 1-MS-SV-109B.

1735 Stopped power reduction at 90%, 775 MWe.

02/04/96 0116 Started power increase. 1-MS-SV-109B was mechanically restrained in the closed position.

0154 Stopped power increase at 94%, 804 MWe.

2103 Started power increase.

2140 Stopped power increase at 100%, 850 MWe.

02/10/96 0836 Started power reduction to perform 1-0SP-TM-001.

1012 Stopped power reduction at 82%, 705 MWe.

1050 Started power increase.

1235 Stopped power increase at 100%, 850 MWe.

02/29/96 2400 The reporting period ended with the unit operating at 100% power, 850 MWe.

~urry Monthly Operating Report No. 96-02 Page 10 of 18

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: February, 1996 UNIT Two:

02/01/96 0000 The reporting period began with the unit operating at 100% power, 845 MWe.

02/22/96 1904 Started power reduction to Hot Shutdown in accordance with Technical Specifications due to a loss of containment integrity resulting from leaking Residual Heat Removal system piping.

02/23/96 0033 Generator off-line.

0047 Reactor manually tripped.

02/26/96 1451 Reactor critical.

2128 Generator on line. Started power increase.

02/27/96 0950 Stopped power increase at 100%, 850 MWe.

02/29/96 2400 The reporting period ended with the unit operating at 100% power, 850 MWe.

~urry Monthly Operating Report No. 96-02 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: February, 1996 TM S1-96-01 Temporary Modifications 2-07-96 TM S1-96-02 (Safety Evaluation No. 96-008A, Revision 1)

Temporary Modifications (TM) S1-96-01 and S1-96-02 mechanically restrained Unit 1 main steam cross-under safety valves 1-MS-SV-1098 and 1-MS-SV-111 B to prevent the valves from inadvertently opening until the proper lift setpoints can be reestablished.

The nonsafety-related cross-under safety valves provide overpressure protection for the moisture separators and cross-under system in the event the reheat and intercept valves close and the main turbine inlet valves fail to close. The evaluation concluded that sufficient relief capacity remains available with the subject valves mechanically bound.

Therefore, an unreviewed safety question does not exist.

DCP 91-012 Design Change Package 2-12-96 (Safety Evaluation No.91-257)

Design Change Package (DCP)91-012 replaced the existing (pitot venturi design) Unit 1 and 2 recirculating spray heat exchanger (RSHX) service water (SW) inlet and outlet flow elements with V-cone design flow elements. The DCP also replaced the RSHX SW radiation monitor pump discharge piping and upgraded the pump suction to a self-priming design.

The new flow elements and piping enhanced the ability to meet the design and qualification requirements of Regulatory Guide 1.97, Type D, Category 2 variables and improved the operator's ability to accurately and reliably monitor the flow of service water to/from the RSHXs in the unlikely event of a design basis accident. The modifications did not alter the performance characteristics of the RSHXs or radiation monitor pumps. Therefore, an unreviewed safety question does not exist.

SE 94-193 Rev. 1 Safety Evaluation 2-12-96 Safety Evaluation 94-193, Revision 1 was performed, in response to Information Notice 91-40, to evaluate the potential for unmonitored, uncontrolled, radioactivity releases to the environment from the component cooling (CC) system in light of the higher activity levels that have been noted during sampling.

The evaluation concluded that a CC system heat exchanger tube leak to the service water system would be required for a release to the discharge canal to occur. In the event of such a leak, minimal circulating water system flow would dilute existing contamination levels to well below the regulatory limits. Periodic sampling is performed to monitor system contamination levels. Therefore, an unreviewed safety question does not exist.

~urry Monthly Operating Report No. 96-02 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: February, 1996 DCP 95-042 Design Change Package 2-13-96 (Safety Evaluation No.95-171)

Design Change Package 95-042 replaced the Unit 1 and 2 steam generator (SG) channel head drain lines (some of which had exhibited leakage) with a pipe nipple and cap.

The subject drain lines provided a means for draining the SG channel head to facilitate maintenance. The subject modifications did not affect Reactor Coolant System operation and improved the reliability of SG channel head isolation. Therefore, an unreviewed safety question does not exist.

DCP 95-028 Design Change

  • Package 2-21-96 (Safety Evaluation No.95-091)

Design Change Package 95-028 implemented an alternate shutdown methodology to enhance control of pressurizer heatup and cooldown rates during plant shutdown and to place the plant in a condition in which hydrogen peroxide can be injected into the Reactor Coolant System (RCS). Hydrogen peroxide reacts with and reduces dissolved hydrogen in the RCS. Hydrogen peroxide also changes the RCS chemistry to an acid oxidizing state to control the dissolution of activated cobalt species.

Implementation of the new shutdown method requires adherence to the following conditions and limitations: 1) At least one reactor coolant pump must be running while filling the pressurizer and collapsing the bubble, 2) The safety injection accumulators must be depressurized and/or .isolated, 3) The pressurizer power operated relief valves must be operable, 4) Reactor Operators tasked with RCS pressure control during this evolution must have received related simulator training, 5) No more than one charging pump can be in operation while the RCS is water solid, 6) Isolation of charging flow to the reactor core is prohibited, 7) Both residual heat removal trains must be filled and vented before making the RCS water solid, and 8) RCS pressure and temperature must be < 365 psig and 350 °F, respectively, while the RCS is solid. These measures will ensure that affected plant equipment is operated within their design temperature and pressure limits and in accordance with the Technical Specifications. Therefore, an unreviewed safety question does not exist.

DR S-96-0379 Deviation Report 2-26-96 (Safety Evaluation No.96-014)

Safety Evaluation 96-014 assessed Deviation Report S-96-0379 concerning the failure of three of the Unit 2 "A" group pressurizer heaters.

Virginia Power's response to NUREG-0737, Item 11.E.3.1 indicated that at least 125 kW of pressurizer heater capacity will be available on each emergency bus. The assessment of this deviating condition concluded that compliance with this commitment continues to be satisfied by the operability of the "E" group heaters ("H" emergency bus) and the remaining 150 kW of "A" group heater capacity ("J" emergency bus). Therefore, an unreviewed safety question does not exist.

tllurry Monthly Operating Report No. 96-02 Page 13 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MoNTHNEAR: February, 1996 O-OP-FC-003 Operating Procedure 2/06/96 1-TOP-4071 Temporary Operating Procedure (Safety Evaluation No.96-008)

Operating Procedure O-OP-FC-003, "Spent Fuel Pit -- Makeup From and Transfer to the Boron Recovery Tanks," and Temporary Operating Procedure 1-TOP-4071, "Removal and Installation of the Swing Check Assembly of 1-BR-506," were developed to provide instructions for the installation and operation of a temporary modification to allow water to be transferred between the spent fuel pit and the boron recovery tanks.

The subject procedures and procedurally controlled temporary modifications will support transfer canal desludging operations. The procedures include administrative controls that limit spent fuel pit temperature and require monitoring of the spent fuel pit level, boron concentration, and contamination levels. The activity will not affect the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

1-0SP-TM-001 Operations Surveillance Procedure 2-08-96 (Safety Evaluation No.96-009)

Operations Surveillance Procedure 1-0SP-TM-001, "Turbine Inlet Valve Freedom Test" was temporarily changed to provide instructions for the implementation of a temporary modification (TM) that allows the solenoid operated valves for the "A" main steam reheat intercept and reheat stop valves to be energized in order to verify the valves are free to cycle.

This testing activity will verify that the "A" turbine inlet valves are free to move to provide assurance that they will close following a turbine trip. The TM affects only test circuitry and does not involve safety-related equipment. Therefore, an unreviewed safety question does not exist.

O-ECM-1412-01 Electrical Corrective Maintenance Procedure 2-15-96 (Safety Evaluation No.96-012)

Electrical Corrective Maintenance Procedure O-ECM-1412-01, "Charging Pump Motor Maintenance," was developed to provide instructions for the installation of a temporary modification to allow the removal of the smoke detector from the ventilation system for each of the Unit 1 and 2 charging pump motors. This temporary modification will permit the removal of ventilation ducting to facilitate the inspection/repair of the charging pump motors.

During the implementation of this procedure, a ceiling mounted smoke detector in the respective charging pump cubicle will remain operable and a temporary ventilation system smoke detector will be installed. In the event the ceiling mounted smoke detector is inoperable, the appropriate Limiting Condition for Operation will be entered and the necessary compensatory measures will be taken to maintain compliance with the Technical Specifications. Therefore, an unreviewed safety question does not exist.

~urry Monthly Operating Report No. 96-02 Page 14 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: February, 1996 2-0SP-TM-001 Operations Surveillance Procedure 2-22-96 (Safety Evaluation No.96-013)

Operations Surveillance Procedures 2-0SP-TM-001, "Turbine Inlet Valve Freedom Test" was temporarily changed to provide instructions for the implementation of a temporary modification (TM) that allows the solenoid operated valves for the main steam reheat intercept and reheat stop valves to be energized in order to verify the valves are free to cycle.

This testing activity will verify that the turbine inlet valves are free to move to provide assurance that they will close following a turbine trip. The TM affects only test circuitry and does not involve safety-related equipment. Therefore, an unreviewed safety question does not exist.

SU-C-DSE-804 Surry Switchyard Procedure 2-29-96 (Safety Evaluation No.96-015)

Surry Switchyard Procedure SU-C-DSE-804, "Surry Switchyard -- Add Oil to RSST 'A' Load Tap Changer (LTC) Tank," was developed to provide instructions for placing the LTC in the manual mode of operation to facilitate the addition of oil to the Reserve Station Service Transformer (RSST) "A" LTC compartment.

This procedure will be implemented during stable unit operations with three operable emergency diesel generators. While the LTC is in the manual mode, a Limiting Condition for Operation will be entered in accordance with Technical Specification 3.16.B.2.

Therefore, an unreviewed safety question does not exist.

-urry Monthly Operating Report No. 96-02 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1996 None During the Reporting Period

-urry Monthly Operating Report No. 96-02 Page 16 of 18 CHEMISTRY REPORT MONTHNEAR: February, 1996 Unit No. 1 Unit No. 2 Primarv Coolant Analysis Max. Min. Avq. Max. Min. Avq.

Gross Radioactivity, µCi/ml 9.86E-1 4.77E-1 7.30E-1 2.02E-1 6.12E-3 1.07E-1 Suspended Solids, ppm :s;o.010 :s;o.010 :s;0.010 0.175 :s;0.010 0.078 Gross Tritium, µCi/ml 6.73E-1 6.06E-1 6.36E-1 3.50E-1 1.23E-1 2.85E-1 11 3 1, µCi/ml 3.27E-2 2.33E-3 8.93E-3 2.02E-4 7.79E-5 1.34E-4 113111133 1.10 0.37 0.65 1.10 0.05 0.07 Hvdrogen, cc/kq 39.4 35.9 37.3 38.3 19.6 33.1 Lithium, oom 2.33 2.05 2.18 2.60 0.24 2.03 Boron - 10, oom* 200.1 186.8 193.9 239.5 82.3 131.5 Oxygen, (DO), ppm :s;0.005 :s;0.005 :s;0.005 :s;0.005 :s;0.005 :s;0.005 Chloride, oom 0.010 0.004 0.006 0.008 0.002 0.004 pH at 25 degree Celsius 6.70 6.58 6.64 7.15 5.68 6.97 Boron - 10 = Total Boron x 0.196 Comments:

None

.. .urry Monthly Operating Report No. 96-02 Page 17 of 18 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: February, 1996 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 No Fuel Received or Stored During the Reporting Period

i

.urry Monthly Operating Report No. 96-02 Page 18 of 18 DESCRIPTION OF PERIODIC TEST{S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: February, 1996 None During the Reporting Period

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