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

.. ' ,, . 'V\ e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 12, 1996 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 Docket Nos. License Nos.96-181 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 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~M -'I-' Station Manager Date TABLE OF CONTENTS Section .urry Monthly Operating Report No. 96-03 Page 2 of 20 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 OPERATING DATA REPORT .urry Monthly Operating Report No. 96-03 Page 3 of 20 Docket No.: Date: Completed By: 50-280 4-01-96 D. Mason 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 March, 1996 2546 847.5 788 840 801 Telephone:

(804) 365-2459 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: 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 ........................... . This Month 744.0 744.0 0.0 744.0 0.0 1893857.4 633240.0 613888.0 100.0% 100.0% 103.0% 104.7% 0.0% YTD 2184.0 2184.0 0.0 2184.0 0.0 5548487.7 1857150.0 1797756.0 100.0% 100.0% 102.8% 104.5% 0.0% Cumulative 204024.0 140234.7 3774.5 137931.0 3736.2 321946280.2 105434333.0 100253729.0 67.6% 69.4% 63.3% 62.4% 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):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED OPERATING DATA REPORT -urry Monthly Operating Report No. 96-03 Page 4 of 20 Docket No.: 50-281 4-01-96 D. Mason Date: Completed By: 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 March, 1996 2546 847.5 788 840 801 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: 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. UnitServiceFactor

.................................. . 20. Unit Availability Factor .............................. . 21. Unit Capacity Factor (Using MDC Net) .......... . 22. Unit Capacity Factor (Using DER Net) .......... . 23. Unit Forced Outage Rate ........................... . This Month 744.0 744.0 0.0 744.0 0.0 1852978.8 617675.0 597632.0 100.0% 100.0% 100.3% 101.9% 0.0% YTD 2184.0 2097.8 0.0 2091.1 0.0 5258976.9 1753265.0 1697085.0 95.7% 95.7% 97.0% 98.6% 4.3% Cumulative 200904.0 137600.7 328.1 135647.2 0.0 317794030.9 103908909.0 98807500.0 67.5% 67.5% 63.0% 62.4% 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 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ( ACHIEVED 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 (1) (2) (3) (4) (5) Method Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 4-04-96 Completed by: Craig Olsen Telephone:

(804) 365-2155 Duration of LER System 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.

(1) .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 (2) (3) (4) (5) Method Duration of LER No. System Component Cause & Corrective Action to Date Type Hours Reason Shutting Code Code Prevent Recurrence 960313 s N/A (1) F: Forced S: Scheduled B (2) REASON: Down Rx N/A N/A A -Equipment Failure (Explain)

B Maintenance or Test C Refueling D Regulatory Restriction AB E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NU REG 0161) 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.

(3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)

(5) Exhibit 1 -Same Source.

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.

MONTH: March, 1996 Day 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS -urry Monthly Operating Report No. 96-03 Page 8 of 20 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe-Net) Day 820 17 820 18 820 19 820 20 821 21 821 22 821 23 820 24 821 25 821 26 820 27 817 28 314 29 745 30 823 31 823

• Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 4-03-96 Completed by: Barry C. Bryant Telephone:

{804) 365-2786 Average Daily Power Level (MWe -Net) 823 823 823 824 824 817 826 825 825 825 825 825 824 824 822 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 3/31/96 UNIT TWO: 3/01/96 3/13/96 3/14/96 3/31/96 0000 2400 0000 0258 0605 The reporting period began with the unit operating at 100% power, 850 MWe. The reporting period ended with the unit operating at 100% power, 850 MWe. The reporting period began with the unit operating at 100% power, 850 MWe. 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.

Stopped power reduction at 30%, 220 MWe. 2315 Started power increase.

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

0854 Started power increase.

0919 Stopped power increase at 100%, 855 MWe. 2400 The reporting period ended with the unit operating at 100% power, 835 MWe. --,

TM S2-96-002 DR S-96-0448 JCO S2-96-001 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

March, 1996 Temporary Modification (Safety Evaluation No.96-019) tlurry Monthly Operating Report No. 96-03 Page 10 of 20 3-06-96 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. 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. Justification for Continued Operation (Safety Evaluation 96-023) 3-11-96 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.

TM S2-96-003 DCP 95-037 TM S2-96-004 FS 96-05 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

March, 1996 Temporary Modification (Safety Evaluation No.96-024) -urry Monthly Operating Report No. 96-03 Page 11 of 20 3-12-96 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. Design Change Package (Safety Evaluation No.95-139) 3-13-96 Design Change Package 95-037 installed an electrical jumper to bypass failed Unit 1 consequence limiting safeguards (CLS) relay, 1-CLS-RL Y-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. Temporary Modification (Safety Evaluation No.96-025) 3-14-96 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. Updated Final Safety Analysis Report Change (Safety Evaluation No.96-026) 3-18-96 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.

DCP 91-004 DCP 96-009 FS 96-12 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

March, 1996 Design Change Package (Safety Evaluation No.91-122) -urry Monthly Operating Report No. 96-03 Page 12 of 20 3-27-96 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. Design Change Package (Safety Evaluation No.96-030) 3-28-96 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. Updated Final Safety Analysis Report Change (Safety Evaluation 96-034) 3-29-96 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.

1 [2]-0P-Sl-002 2-0P-Sl-002 1 [2]-0P-Sl-004

~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 Operating Procedures (Safety Evaluation No.96-018) 3-01-96 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. Operating Procedure (Safety Evaluation No.96-020) 3-07-96 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. Operating Procedures (Safety Evaluation No. 96-020A) 3-07-96 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.

O-ECM-1806-01 -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 Electrical Corrective Maintenance Procedure (Safety Evaluation No. 96-022} 3-11-96 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 CHEMISTRY REPORT MONTHNEAR:

March, 1996 Unit No. 1 Primary Coolant Analysis Max. Min. Avg. Gross Radioactivity, µ,Ci/ml 6.97E-1 4.73E-1 5.87E-1 Suspended Solids, ppm :s;0.01 :s;o.01 :s;0.01 Gross Tritium, µ,Ci/ml 7.49E-1 5.71E-1 6.87E-1 1131, µ,Ci/ml 5.13E-3 1.41E-3 2.75E-3 113111133 0.55 0.21 0.36 Hvdroqen, cc/kg 40.1 36.2 38.3 Lithium, oom 2.34 2.08 2.21 Boron -10, oom* 188.6 175.4 181.2 Oxygen, (DO}, ppm :s;0.005 :s;0.005 :s;0.005 Chloride, oom 0.006 0.003 0.005 pH at 25 deqree Celsius 6.68 6.38 6.53 Boron -10 = Total Boron x 0.196 Comments:

None -urry Monthly Operating Report No. 96-03 Page 16 of 20 Unit No. 2 Max. Min. Ava. 1.77E-1 4.28E-2 1.18E-1 :s;0.01 :s;0.01 :s;0.01 1.47E-1 1.04E-1 1.26E-1 1.18E-3 2.22E-5 2.07E-4 0.15 0.05 0.09 35.5 23.4 30.9 2.34 1.93 2.17 100.5 65.1 76.4 :s;0.005 :s;0.005 :s;0.005 0.005 0.002 0.003 7.13 6.91 7.03

. J . . New or Spent Fuel Shipment Number New Fuel Unit2 Batch 16 Shipment 1 New Fuel Unit2 Batch 16 Shipment 2 Date Stored or Received 3/14/96 3/19/96 FUEL HANDLING UNITS 1 & 2 MoNTHNEAR:

March, 1996 Number of Assemblies Assembly ANSI eer Shiement Number Number 12 OY9 LM12P6 3Y2 LM12PV OY1 LM12NY 5Y6 LM12QK 1Y7 LM12PE 5Y8 LM12QM 4Y1 LM12Q4 6YO LM12QP 5Y1 LM12QE 5Y5 LM12QJ 2Y8 LM12PR 3Y3 LM12PW 12 1Y9 LM12PG 5Y4 LM12QH 5YO LM12QD 2Y1 LM12PJ 2Y2 LM12PK 2Y4 LM12PM 2Y6 LM12PP 3Y6 LM12PZ 4Y2 LM12Q5 5Y9 LM12QN 4Y9 LM12QC 5Y2 LM12QF 4lurry Monthly Operating Report No. 96-03 Page 17 of 20 New or Spent Initial Fuel Shipping Enrichment Cask Activitt 3.8059 14.84 Ci 3.8007 3.7905 4.0258 3.7887 4.0025 4.0190 4.0054 4.0130 4.0024 3.7987 3.9835 3.8262 14.87 Ci 4.0030 4.0111 3.8010 3.8136 3.8218 3.7950 4.0067 4.0156 4.0238 4.0140 4.0007

' . New or Spent Fuel Shipment Number New Fuel Unit 2 Batch 16 Shipment 3 New Fuel Unit 2 Batch 16 Shipment4 Date Stored or Received 3/21/96 3/26/96 FUEL HANDLING UNITS 1 & 2 MONTHNEAR:

March, 1996 Number of Assemblies Assembly ANSI per Shipment Number Number 12 OY7 LM12P4 OY4 LM12P1 2Y7 LM12PQ 4Y6 LM12Q9 1Y5 LM12PC 1Y2 LM12P9 1Y3 LM12PA 5Y3 LM12QG 3YO LM12PT OY6 LM12P3 2Y5 LM12PN 5Y7 LM12QL 12 2YO LM12PH 4Y8 LM12QB 1Y4 LM12PB 4Y7 LM12QA 3Y8 LM12Q1 3Y4 LM12PX 1Y6 LM12PD 1Y8 LM12PF 3Y1 LM12PU 4Y5 LM12Q8 3Y9 LM12Q2 4YO LM12Q3 .urry Monthly Operating Report No. 96-03 Page 18 of 20 New or Spent Initial Fuel Shipping Enrichment Cask Activity 3.7804 14.56 Ci 3.7789 3.7946 4.0075 3.8005 3.7952 3.7969 4.0019 3.7944 3.7892 3.7942 4.0058 3.7942 14.83 Ci 4.0118 3.7883 4.0025 3.9951 3.9836 3.7890 3.7865 3.8140 4.0163 3.9938 4.0185

• New or Spent Fuel Shipment Date Stored or Number Received New Fuel Unit2 Batch 16 Shipment 5 3/28/96 New Fuel Return Unit 2 Batch 16 Shipment 1 3/29/96 FUEL HANDLING UNITS 1 & 2 MONTHNEAR:

March, 1996 Number of Assemblies Assembly ANSI per Shipment Number Number 12 OY2 LM12NZ OY3 LM12PO 4Y3 LM12Q6 OY8 LM12P5 3Y5 LM12PY OY5 LM12P2 1YO LM12P7 1Y1 LM12P8 2Y3 LM12PL 2Y9 LM12PS 3Y7 LM12QO 4Y4 LM12Q7 1 2Y4 LM12PM .urry Monthly Operating Report No. 96-03 Page 19 of 20 New or Spent Initial Fuel Shipping Enrichment Cask Activity 3.8101 14.64 Ci 3.7986 4.0085 3.7986 3.9867 3.7900 3.7858 3.7881 3.7933 3.8009 3.9977 4.0108 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