ML18153A687

Monthly Operating Repts for Mar 1996 for Sps,Units 1 & 2. W/960412 Ltr

ML18153A687
Person / Time
Site:	Surry
Issue date:	03/31/1996
From:	Bowling M, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-181, NUDOCS 9604180088
Download: ML18153A687 (21)

Text

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. 'V\ VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 12, 1996 U.S. Nuclear Regulatory Commission Serial No.96-181 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 March 1996.

Very truly yours, J/AI_J~

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

~8~4180088 960331 R ADDCK osooo200 PDR

.. e e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 96-03 Approved:

';\JJ~MStation Manager

-'I-'

Date

.urry Monthly Operating Report No. 96-03 Page 2 of 20 TABLE OF CONTENTS Section Page Operating Data Report - Unit No. 1 ......................................................................................................... 3 Operating Data Report - Unit No. 2 ......................................................................................................... 4 Unit Shutdowns and Power Reductions - Unit No. 1.................................................................................... 5 Unit Shutdowns and Power Reductions - Unit No. 2 .................................................................................... 6 Average Daily Unit Power Level - Unit No. 1 .............................................................................................. 7 Average Daily Unit Power Level - Unit No. 2 .............................................................................................. 8 Summary of Operating Experience - Unit No. 1 ......................................................................................... 9 Summary of Operating Experience - Unit No. 2 ......................................................................................... 9 Facility Changes That Did Not Require NRC Approval ............................................................................... 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 13 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 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 ................................................................................................... 20

.urry Monthly Operating Report No. 96-03 Page 3 of 20 OPERATING DATA REPORT Docket No.: 50-280 Date: 4-01-96 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 1

2. Reporting Period: ......................................... . March, 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 ......................... . 744.0 2184.0 204024.0

12. Number of Hours Reactor Was Critical ......... . 744.0 2184.0 140234.7

13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 3774.5

14. Hours Generator On-Line .......................... . 744.0 2184.0 137931.0

15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 3736.2

16. Gross Thermal Energy Generated (MWH) ..... . 1893857.4 5548487.7 321946280.2

17. Gross Electrical Energy Generated (MWH) ... . 633240.0 1857150.0 105434333.0

18. Net Electrical Energy Generated (MWH) ....... . 613888.0 1797756.0 100253729.0

19. Unit Service Factor .................................. . 100.0% 100.0% 67.6%

20. Unit Availability Factor .............................. . 100.0% 100.0% 69.4%

21. Unit Capacity Factor (Using MDC Net) .......... . 103.0% 102.8% 63.3%

22. Unit Capacity Factor (Using DER Net) .......... . 104.7% 104.5% 62.4%

23. Unit Forced Outage Rate ........................... . 0.0% 0.0% 15.8%

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

-urry Monthly Operating Report No. 96-03 Page 4 of 20 OPERATING DATA REPORT Docket No.: 50-281 Date: 4-01-96 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 2

2. Reporting Period: ........................................ .. March, 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 ........................ .. 744.0 2184.0 200904.0

12. Number of Hours Reactor Was Critical ......... . 744.0 2097.8 137600.7

13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 328.1

14. Hours Generator On-Line .......................... . 744.0 2091.1 135647.2

15. Unit Reserve Shutdown Hours ................... .. 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) ..... . 1852978.8 5258976.9 317794030.9

17. Gross Electrical Energy Generated (MWH) ... . 617675.0 1753265.0 103908909.0

18. Net Electrical Energy Generated (MWH) ....... . 597632.0 1697085.0 98807500.0

19. UnitServiceFactor .................................. . 100.0% 95.7% 67.5%

20. Unit Availability Factor .............................. . 100.0% 95.7% 67.5%

21. Unit Capacity Factor (Using MDC Net) .......... . 100.3% 97.0% 63.0%

22. Unit Capacity Factor (Using DER Net) .......... . 101.9% 98.6% 62.4%

23. Unit Forced Outage Rate ........................... . 0.0% 4.3% 12.9%

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

(

lturry Monthly Operating Report No. 96-03 Page 5 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%}

REPORT MONTH: March, 1996 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 4-04-96 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. 96-03 Page 6 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EOUAL To OR GREATER THAN 20%)

REPORT MONTH: March, 1996 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 4-04-96 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 960313 s N/A B N/A N/A AB p Reactor coolant pump (RCP), 2-RC-P-1A, motor bearing oil leak reduced the margin between the oil collection tank capacity and the total capacity of the RCP motor. Power was reduced to facilitate the installation of temporary piping from the oil collection tank drain to a low dose area outside of the loop room to provide a means for remotely draining the subject tank, if necessary.

(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 (NU REG 0161)

tlurry Monthly Operating Report No. 96-03 Page 7 of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 4-03-96 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: March, 1996 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe-Net) 825 17 825 2 825 18 826 3 825 19 825 4 827 20 825 5 822 21 824 6 821 22 827 7 819 23 826 8 818 24 826 9 821 25 826 10 828 26 826 11 828 27 824 12 829 28 826 13 827 29 823 14 828 30 826 15 827 31 826 16 826 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.

-urry Monthly Operating Report No. 96-03 Page 8 of 20 AVERAGE DAILY UNIT POWER LEVEL

• Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 4-03-96 Completed by: Barry C. Bryant Telephone: {804) 365-2786 MONTH: March, 1996 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe -Net) 1 820 17 823 2 820 18 823 3 820 19 823 4 820 20 824 5 821 21 824 6 821 22 817 7 821 23 826 8 820 24 825 9 821 25 825 10 821 26 825 11 820 27 825 12 817 28 825 13 314 29 824 14 745 30 824 15 823 31 822 16 823 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. 96-03 Page 9 of 20

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: March, 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:

3/01/96 0000 The reporting period began with the unit operating at 100% power, 850 MWe.

3/31/96 2400 The reporting period ended with the unit operating at 100% power, 850 MWe.

UNIT TWO:

3/01/96 0000 The reporting period began with the unit operating at 100% power, 850 MWe.

3/13/96 0258 Started power reduction to facilitate the installation of temporary piping from the reactor coolant pump, 2-RC-P-1 A, oil collection tank drain to a low dose area outside of the loop room to provide a means for remotely draining the subject tank, if necessary.

0605 Stopped power reduction at 30%, 220 MWe.

2315 Started power increase.

3/14/96 0706 Stopped power increase at 96%, 800 MWe, to perform calorimetric calculation.

0854 Started power increase.

0919 Stopped power increase at 100%, 855 MWe.

3/31/96 2400 The reporting period ended with the unit operating at 100% power, 835 MWe.

tlurry Monthly Operating Report No. 96-03 Page 10 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1996 TM S2-96-002 Temporary Modification 3-06-96 (Safety Evaluation No.96-019)

Temporary Modification (TM) S2-96-002 interchanged the electrical leads to the Unit 2 high level intake structure rotating screen motor. This modification reversed the direction of screen rotation in order to facilitate the installation of new drive chains.

The high level intake structure remained fully operable during the subject maintenance activity and the ability of the service water system to perform its design function was not affected. Therefore, an unreviewed safety question does not exist.

DR S-96-0448 Deviation Report 3-11-96 (Safety Evaluation No.96-021, Revision 1)

Safety Evaluation 96-021 assessed Deviation Report S-95-0448 concerning the existence of a motor bearing oil leak on the Unit 2 "A" Reactor Coolant Pump (RCP).

The evaluation concluded that continued RCP operation is acceptable since the estimated leakage amount is small and within the current capacity of the oil collection system tank.

In addition, adequate warning systems and procedures exist to alert operators and address low oil level and high bearing temperature conditions. Therefore, an unreviewed safety question does not exist.

JCO S2-96-001 Justification for Continued Operation 3-11-96 (Safety Evaluation 96-023)

A through wall leak was recently discovered on Unit 2 residual heat removal system pipe 6"-RH-120-152. The cause of the failure was preliminarily identified as intergranular corrosion in combination with a reduction in pipe wall thickness. The leaking section of piping was replaced and ultrasonic testing (UT) was performed on the remainder of the affected Unit 2 piping and the corresponding Unit 1 piping. The UT identified the existence of degradation at other locations on the Unit 2 piping. The Unit 1 piping was acceptable.

Justification For Continued Operation (JCO) 82-96-001 assessed the acceptability of continued Unit 2 operation with the degraded piping. The JCO requires a visual inspection of the affected Unit 2 piping on a monthly basis, until the piping is replaced, to ensure that any additional leakage is identified and that containment integrity is maintained.

An engineering evaluation concluded that the affected piping will maintain its integrity during normal and accident conditions and can be considered fully operable. Therefore, an unreviewed safety question does not exist.

-urry Monthly Operating Report No. 96-03 Page 11 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1996 TM S2-96-003 Temporary Modification 3-12-96 (Safety Evaluation No.96-024)

Temporary Modification (TM) S2-96-003 installed temporary piping from the Unit 2 "A" reactor coolant pump oil collection tank drain to a low dose area outside of the loop room.

The TM was implemented to provide a means for remotely draining the subject tank, if necessary, to accommodate a small motor bearing oil leak that has reduced the margin between the tank capacity and the total capacity of the RCP motor.

The temporary piping is seismically restrained and does not affect the performance of the oil collection system. Any oil drained from the oil collection tank will be removed from the containment. Therefore, an unreviewed safety question does not exist.

DCP 95-037 Design Change Package 3-13-96 (Safety Evaluation No.95-139)

Design Change Package 95-037 installed an electrical jumper to bypass failed Unit 1 consequence limiting safeguards (CLS) relay, 1-CLS-RLY-1 A9, and clear control room annunciator 1-B-4, "CLS Coil Failure."

The subject relay is a spare that currently performs no function. The modification did not affect the CLS or other systems. Therefore, an unreviewed safety question does not exist.

TM S2-96-004 Temporary Modification 3-14-96 (Safety Evaluation No.96-025)

Temporary Modification (TM) S2-96-004 installed an electrical jumper to maintain alarm module circuit continuity during the replacement of the Unit 2 "A" circulating water (CW) pump thrust bearing alarm module.

The module alarm functions do not provide any control or interlock functions for the CW pump motor supply breakers and do not prevent the start or cause the trip of a CW pump.

The TM did not affect the other Unit 2 "A" CW pump motor temperature thermocouples and alarm functions and did not impose any operational limitations on the subject pump.

Double verification of jumper installation/removal and post-maintenance testing was performed. Therefore, an unreviewed safety question does not exist.

FS 96-05 Updated Final Safety Analysis Report Change 3-18-96 (Safety Evaluation No.96-026)

UFSAR Change 96-05 revised Section 14.2.8, "Excessive Load Increase Incident," to reflect the results of a new analysis that was recently performed based on the Unit 1 and Unit 2 uprated core power (2546 MWt) conditions and the new design limits for the moderator temperature and Doppler temperature coefficients.

The new analysis parameters were equivalent to, or conservative with respect to, those allowed by Technical Specifications limits. The analysis parameters are therefore expected to be conservative with respect to actual plant conditions. Thus, continued operation in accordance with the Technical Specifications will not violate the design basis of plant safety systems and equipment. Therefore, an unreviewed safety question does not exist.

-urry Monthly Operating Report No. 96-03 Page 12 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1996 DCP 91-004 Design Change Package 3-27-96 (Safety Evaluation No.91-122)

Design Change Package 91-004 eliminated the dilute ammonia tanks, installed new ammonia injection pumps, and cross-connected the Unit 1 and Unit 2 ammonia injection pump suction and discharge piping to provide greater operational flexibility.

The modifications provided an alternative method of injecting the proper amount of ammonia into the condensate system to control the pH level. The changes did not affect the operation or ability of equipment important to safety to perform its designed safety function. Therefore, an unreviewed safety question does not exist.

DCP 96-009 Design Change Package 3-28-96 (Safety Evaluation No.96-030)

Design Change Package 96-009 replaced emergency service water pump 1-SW-P-1A. To accommodate the installation of the replacement pump, the diesel engine drive shaft coupling and the inlet/outlet piping for the lube oil cooler were modified. In addition, the nonsafety-related electric motor driver, which was used for maintenance purposes, was not compatible with the replacement pump and, therefore, was removed.

The replacement pump is sized to satisfy the flow requirements for the design basis conditions defined in the Updated Final Safety Analysis Report. The modifications were structurally and seismically evaluated and determined to be acceptable. The operability, availability, and performance characteristics of the subject pump were not affected by the changes. Therefore, an unreviewed safety question does not exist.

FS 96-12 Updated Final Safety Analysis Report Change 3-29-96 (Safety Evaluation 96-034)

Updated Final Safety Analysis Report Change 96-12 revised various sections that address fuel handling to accurately reflect current station practices.

The changes did not represent significant deviations from the design basis of the fuel handling system and did not reduce the Technical Specifications margin of safety. The changes also did not affect any of the assumptions made in any fuel handling or other design basis accident analyses. Therefore, an unreviewed safety question does not exist.

~urry Monthly Operating Report No. 96-03 Page 13 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1996 1[2]-0P-Sl-002 Operating Procedures 3-01-96 (Safety Evaluation No.96-018)

Operating Procedures 1[2]-0P-Sl-002, "Safety Injection Accumulators", were revised to provide instructions for administratively controlling safety injection system valves 1[2]-

81-26 while performing the subject procedures.

Appropriate administrative controls are provided in the procedures to ensure that the subject valves are closed within 60 seconds of the initiation of a safety injection. Closure of the valves within this time limit ensures that sufficient refueling water storage tank inventory is maintained for accident mitigation. Therefore, an unreviewed safety question does not exist.

2-0P-Sl-002 Operating Procedure 3-07-96 (Safety Evaluation No.96-020)

Operating Procedure 2-0P-Sl-002, "Safety Injection Accumulators", was revised to provide instructions for installing a temporary mechanical jumper to permit the Unit 2 refueling water storage tank recirculation pumps to be used to fill the Safety Injection (SI)

System accumulators.

The procedure allows the mechanical jumper to be installed while the unit is at cold/refueling shutdown when the SI System is not required. The jumper will be rated for the pressure of the associated piping flow path, inspected for leakage after it is placed in service, and removed before the unit leaves cold shutdown. Therefore, an unreviewed safety question does not exist.

1[2]-0P-Sl-004 Operating Procedures 3-07-96 (Safety Evaluation No. 96-020A)

Operating Procedures 1[2]-0P-Sl-004, "Filling Safety Injection Accumulators Using a Temporary Hydro Pump," were developed to provide instructions for administratively controlling safety injection system valves 1 [2]-Sl-26 while performing the subject procedures. The revision also incorporated instructions for installing temporary modifications to facilitate the use of a temporary hydro pump in the event the normal pump is not operational.

Appropriate administrative controls are provided in the procedures to ensure that the subject valves are closed within 60 seconds of the initiation of a safety injection. Closure of the valves within this time limit ensures that sufficient refueling water storage tank inventory is maintained for accident mitigation. Therefore, an unreviewed safety question does not exist.

-urry Monthly Operating Report No. 96-03 Page 14 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March, 1996 O-ECM-1806-01 Electrical Corrective Maintenance Procedure 3-11-96 (Safety Evaluation No. 96-022}

Electrical Corrective Maintenance Procedure O-ECM-1806-01, "Protective Relay and Associated Control Circuit Replacement," was temporarily changed to provide instructions for placing the recirculation mode transfer (RMT) system switch for train "B" in the refueling position to facilitate the replacement of electrical relay 1-CS-R-100A2.

While switched to the refueling position, RMT system train "B" will not function and the appropriate Technical Specifications Limiting Condition for Operation will be entered. The redundant train "A" will not be affected and will function as designed. Therefore, an unreviewed safety question does not exist.

-urry Monthly Operating Report No. 96-03 Page 15 of 20 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1996 None During the Reporting Period

-urry Monthly Operating Report No. 96-03 Page 16 of 20 CHEMISTRY REPORT MONTHNEAR: March, 1996 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Ava.

Gross Radioactivity, µ,Ci/ml 6.97E-1 4.73E-1 5.87E-1 1.77E-1 4.28E-2 1.18E-1 Suspended Solids, ppm :s;0.01 :s;o.01 :s;0.01 :s;0.01 :s;0.01 :s;0.01 Gross Tritium, µ,Ci/ml 7.49E-1 5.71E-1 6.87E-1 1.47E-1 1.04E-1 1.26E-1 1131, µ,Ci/ml 5.13E-3 1.41E-3 2.75E-3 1.18E-3 2.22E-5 2.07E-4 113111133 0.55 0.21 0.36 0.15 0.05 0.09 Hvdroqen, cc/kg 40.1 36.2 38.3 35.5 23.4 30.9 Lithium, oom 2.34 2.08 2.21 2.34 1.93 2.17 Boron - 10, oom* 188.6 175.4 181.2 100.5 65.1 76.4 Oxygen, (DO}, ppm :s;0.005 :s;0.005 :s;0.005 :s;0.005 :s;0.005 :s;0.005 Chloride, oom 0.006 0.003 0.005 0.005 0.002 0.003 pH at 25 deqree Celsius 6.68 6.38 6.53 7.13 6.91 7.03 Boron - 10 = Total Boron x 0.196 Comments:

None

.J .. 4lurry Monthly Operating Report No. 96-03 Page 17 of 20 FUEL HANDLING UNITS 1 & 2 MoNTHNEAR: March, 1996 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 Activitt New Fuel Unit2 Batch 16 Shipment 1 3/14/96 12 OY9 LM12P6 3.8059 14.84 Ci 3Y2 LM12PV 3.8007 OY1 LM12NY 3.7905 5Y6 LM12QK 4.0258 1Y7 LM12PE 3.7887 5Y8 LM12QM 4.0025 4Y1 LM12Q4 4.0190 6YO LM12QP 4.0054 5Y1 LM12QE 4.0130 5Y5 LM12QJ 4.0024 2Y8 LM12PR 3.7987 3Y3 LM12PW 3.9835 New Fuel Unit2 Batch 16 Shipment 2 3/19/96 12 1Y9 LM12PG 3.8262 14.87 Ci 5Y4 LM12QH 4.0030 5YO LM12QD 4.0111 2Y1 LM12PJ 3.8010 2Y2 LM12PK 3.8136 2Y4 LM12PM 3.8218 2Y6 LM12PP 3.7950 3Y6 LM12PZ 4.0067 4Y2 LM12Q5 4.0156 5Y9 LM12QN 4.0238 4Y9 LM12QC 4.0140 5Y2 LM12QF 4.0007

.' .urry Monthly Operating Report No. 96-03 Page 18 of 20 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: March, 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 New Fuel Unit 2 Batch 16 Shipment 3 3/21/96 12 OY7 LM12P4 3.7804 14.56 Ci OY4 LM12P1 3.7789 2Y7 LM12PQ 3.7946 4Y6 LM12Q9 4.0075 1Y5 LM12PC 3.8005 1Y2 LM12P9 3.7952 1Y3 LM12PA 3.7969 5Y3 LM12QG 4.0019 3YO LM12PT 3.7944 OY6 LM12P3 3.7892 2Y5 LM12PN 3.7942 5Y7 LM12QL 4.0058 New Fuel Unit 2 Batch 16 Shipment4 3/26/96 12 2YO LM12PH 3.7942 14.83 Ci 4Y8 LM12QB 4.0118 1Y4 LM12PB 3.7883 4Y7 LM12QA 4.0025 3Y8 LM12Q1 3.9951 3Y4 LM12PX 3.9836 1Y6 LM12PD 3.7890 1Y8 LM12PF 3.7865 3Y1 LM12PU 3.8140 4Y5 LM12Q8 4.0163 3Y9 LM12Q2 3.9938 4YO LM12Q3 4.0185

.urry Monthly Operating Report

• No. 96-03 Page 19 of 20 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: March, 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 New Fuel Unit2 Batch 16 Shipment 5 3/28/96 12 OY2 LM12NZ 3.8101 14.64 Ci OY3 LM12PO 3.7986 4Y3 LM12Q6 4.0085 OY8 LM12P5 3.7986 3Y5 LM12PY 3.9867 OY5 LM12P2 3.7900 1YO LM12P7 3.7858 1Y1 LM12P8 3.7881 2Y3 LM12PL 3.7933 2Y9 LM12PS 3.8009 3Y7 LM12QO 3.9977 4Y4 LM12Q7 4.0108 New Fuel Return Unit 2 Batch 16 Shipment 1 3/29/96 1 2Y4 LM12PM 3.8218 1.21 Ci

• .urry Monthly Operating Report No. 96-03 Page 20 of 20 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: March, 1996 None During the Reporting Period