ML18153A703

Monthly Operating Repts for June 1995 for Surry Power Station Units 1 & 2.W/950713 Ltr

ML18153A703
Person / Time
Site:	Surry
Issue date:	06/30/1995
From:	Bryant B, Mason D, Olsen C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9507190316
Download: ML18153A703 (20)

Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 13, 1995 U. S. Nuclear Regulatory Commission Serial No.95-353 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 June 1995.

Very truly yours,

)!lil;J,4 M. L. Bowling, Manager Nuclear Licensing & 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 9507190316 950630 PDR ADDCK 05000280 R PDR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 95-06 Approved:

7 - /0 - 'i!"

Station Manager Date

e Surry Monthly Operating Report No. 95-06 Page 2 of 19 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 N RC Approval. .............................................................................. 1O Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 13 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 14 Chemistry Report ............................................................................................................................. 15 Fuel Handling - Unit No. 1 ................................................................................................................... 16 Fuel Handling - Unit No. 2 ................................................................................................................... 16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 19

-- e Surry Monthly Operating Report No. 95-06 Page 3 of 19 OPERATING DATA REPORT Docket No.: 50-280 Date: 07-05-95 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ......................................... . June, 1995

3. Licensed Thermal Power (MWt): ..................... .. 2441

4. Nameplate Rating (Gross MWe): ..................... .. 847.5

5. Design Electrical Rating (Net MWe): ................ .. 788

6. Maximum Dependable Capacity (Gross MWe): .. .. 820

7. Maximum Dependable Capacity (Net MWe): ....... . 781

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

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

10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .......................... 720.0 4343.0 197423.0

12. Number of Hours Reactor Was Critical .......... 720.0 4163.7 134633.4

13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5

14. Hours Generator On-Line ........................... 720.0 4129.2 132370.2

15. Unit Reserve Shutdown Hours ..................... 0 0 3736.2

16. Gross Thermal Energy Generated (MWH) ...... 1747854.0 9986716.5 308440455.7

17. Gross Electrical Energy Generated (MWH) .... 580410.0 3353980.0 100967813.0

18. Net Electrical Energy Generated (MWH) ........ 557758.0 3232842.0 95941865.0

19. Unit Service Factor ................................... 100.0% 95.1% 67.0%

20. Unit Availability Factor ............................... 100.0% 95.1% 68.9%

21. Unit Capacity Factor (Using MDC Net) ........... 99.2% 95.3% 62.6%

22. Unit Capacity Factor (Using DER Net) ........... 98.3% 94.5% 61.7%

23. Unit Forced Outage Rate ............................ 0.0% 4.9% 16.4%

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

Refueling, September 7, 1995, 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

-urry Monthly Operating Report No. 95-06 Page 4 of 19 OPERATING DATA REPORT Docket No.: 50-281 Date: 07-05-95 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ......................................... . June, 1995

3. Licensed Thermal Power (MWt): ...................... . 2441

4. Nameplate Rating (Gross MWe): ...................... . 847.5

5. Design Electrical Rating (Net MWe): ................. . 788

6. Maximum Dependable Capacity (Gross MWe): .. .. 820

7. Maximum Dependable Capacity (Net MWe): ....... . 781

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

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

10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .......................... 720.0 4343.0 194303.0

12. Number of Hours Reactor Was Critical .......... 665.4 3098.6 131436.1

13. Reactor Reserve Shutdown Hours ............... 0 0 328.1

14. Hours Generator On-Line ........................... 659.9 3028.7 129495.8

15. Unit Reserve Shutdown Hours ..................... 0 0 0

16. Gross Thermal Energy Generated (MWH) ...... 1596999.9 7159394.4 302427858. 7

17. Gross Electrical Energy Generated (MWH) .... 526630.0 2383865.0 98826159.0

18. Net Electrical Energy Generated (MWH) ........ 506995.0 2297384.0 93890420.0

19. Unit Service Factor ................................... 91.7% 69.7% 66.6%

20. Unit Availability Factor ............................... 91.7% 69.7% 66.6%

21. Unit Capacity Factor (Using MDC Net) ........... 90.2% 67.7% 62.0%

22. Unit Capacity Factor (Using DER Net) ........... 89.4% 67.1% 61.3%

23. Unit Forced Outage Rate ............................ 8.3% 6.4% 13.2%

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

e Surry Monthly Operating Report No. 95-06 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION

{EQUAL TO OR GREATER THAN 20%)

REPORT MONTH: June, 1995 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 07-05-95 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 950612 N/A N/A B N/A N/A SG RV Reduced power to facilitate replacement of condensate system relief valve, 1-CN-RV-113B.

(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)

e Surry Monthly Operating Report No. 95-06 Page 6 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: June, 1995 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 07-05-95 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) ~ ~ ~ (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 950614 F 60.1 A 3 2 EL PMG Automatic reactor trip due to 006-00 main transformer generator differential lockout.

(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. 95-06 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 07-06-95 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: June, 1995 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 786 17 782 2 786 18 780 3 785 19 780 4 784 20 778 5 785 21 776 6 787 22 779 7 786 23 778 8 784 24 776 9 783 25 773 10 783 26 771 11 782 27 771 12 747 28 775 13 736 29 768 14 776 30 741 15 763

• 16 762 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.

e e Surry Monthly Operating Report No. 95-06 Page 8 of 19 AVERAGE DAILY UNIT POW.ER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 07-06-95 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: June, 1995 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 774 17 521 2 759 18 778 3 778 19 778 4 776 20 778 5 776 21 776 6 777 22 778 7 775 23 777 8 773 24 774 9 772 25 777 10 771 26 773 11 761 27 776 12 776 28 777 13 780 29 777 14 462 30 775 15 0 16 0 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. 95-06 Page 9 of 19

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: June, 1995 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:

06/01/95 0000 The reporting period began with the unit operating at 100% power, 825 MWe.

06/12/95 1830 Started power reduction to facilitate replacement of Condensate system relief valve 1-CN-RV-113B.

2004 Stopped power reduction at 78%, 630 MWe.

06/13/95 0520 Started power increase.

0745 Stopped power increase at 100%, 820 MWe.

06/30/95 2400 The reporting period ended with the unit operating at 100% power, 820 MWe.

UNIT Two:

06/01/95 0000 The reporting period began with the unit operating at 100% power, 810 MWe.

06/14/95 1415 Automatic reactor trip due to main transformer generator differential lockout.

06/16/95 2050 Reactor critical.

06/17/95 0224 Generator on line. Started power increase.

0322 Stopped power increase at 26%, 180 MWe to perform main transformer testing.

0530 Started power increase.

1510 Stopped power increase at 100%, 820 MWe 06/30/95 2400 The reporting period ended with the unit operating at 100% power, 820 MWe.

e Surry Monthly Operating Report No. 95-06 Page 10 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: June, 1995 FS 94-37 Updated Final Safety Analysis Report Change 6-01-95 (Safety Evaluation No.95-061)

UFSAR Change 94-37 revised Section 9.10, "Fire Protection," to indicate that other materials, as well as foam, are used to seal penetrations to achieve a three hour fire rating.

The subject change was administrative in nature and did not involve physical changes to the plant. Therefore, an unreviewed safety question does not exist.

DCP 87-009-2 Design Change Package 6-07-95 (Safety Evaluation No.91-037)

Design Change Package (DCP) 87-009-2 installed recirculation test piping, valves, and instrumentation to permit periodic full flow testing of the Unit 2 Auxiliary Feedwater (AFW) system pumps. The modification also allows (with operator action) AFW flow back to the emergency condensate storage tank when steam generator flow requirements decrease to less than the minimum recommended continuous flow for the AFW pumps.

This modification does not affect the normal operation of the AFW pumps or the capability of the AFW system to perform its safety functions. The recirculation piping will normally be isolated from the AFW system by administratively controlled valves. Therefore, an unreviewed safety question does not exist.

DCP 87-023-2 Design Change Package 6-07-95 Design Change Package (DCP) 87-023-2 replaced the Unit 2 Recirculating Spray Heat Exchangers (RSHX), the outside RSHX discharge piping, and service water inlet piping elbows.

The new heat exchangers and the originals are of like design with the same duty and pressure drop characteristics. The material composition of the new heat exchangers and associated piping is superior to that of the originals. The performance characteristics of the Recirculating Spray system was not altered by this DCP. Therefore, an unreviewed safety question does not exist.

DCP 87-021-3 Design Change Package 6-08-95 Design Change Package (DCP) 87-021-3 replaced the Unit 1 and Unit 2 Bearing Cooling Heat Exchangers with larger capacity heat exchangers to increase the heat transfer rate.

The new heat exchangers are similar to the design of the originals and meet the original temperature and pressure specifications. The function of the nonsafety-related Bearing Cooling system was not altered by this DCP. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 95-06 Page 11 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: June, 1995 SE 95-064 Safety Evaluation 6-16-95 Safety Evaluation 95-064 assessed the performance of Preventive Electrical Maintenance Procedure EMP-P-RT-209, "Protective Relay In Service Reading Procedure," to obtaining in-service readings from the Unit 2 main transformer differential relays, phase A, B, and C during power ascension following a unit start-up in June 1995.

The evaluation concluded that this activity was acceptable. The protective functions of the subject relays were disabled as the in-service readings were taken on each (one at a time) and back-up relaying was maintained to provide fault protection. The activity did not affect the Electrical Distribution system or reduce the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

DCP 87-008-1 Design Change Package 6-20-95 (Safety Evaluation No.90-191)

Design Change Package (DCP) 87-008-1 installed recirculation test piping, valves, and instrumentation to permit periodic full flow testing of the Unit 1 Auxiliary Feedwater (AFW) system pumps. The modification also allows (with operator action) AFW flow back to the emergency condensate storage tank when steam generator flow requirements decrease to less than the minimum recommended continuous flow for the AFW pumps.

This modification does not affect the normal operation of the AFW pumps or the capability of the AFW system to perform its safety functions. The recirculation piping will normally be isolated from the AFW system by administratively controlled valves. Therefore, an unreviewed safety question does not exist.

DCP 87-028-1 Design Change Package 6-20-95 (Safety Evaluation No.90-205)

Design Change Package (DCP) 87-028-1 replaced the Unit 1 Component Cooling Heat Exchangers 1-CC-E-1 A and 1-CC-E-1 B.

The new heat exchangers and the originals are of like design with the same duty and pressure drop characteristics. The material composition of the new heat exchangers is superior to that of the originals. The performance characteristics of the Component Cooling system were not altered by this DCP. Therefore, an unreviewed safety question does not exist.

-urry Monthly Operating Report No. 95-06 Page 12 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1995 TM S1-95-06 Temporary Modification 6-27-95 (Safety Evaluation No.95-066)

Temporary Modification (TM) S1-95-06 installed a mechanical jumper to temporarily route the discharge of Fish Spray system pumps to a strainer inlet to facilitate the replacement of FS system piping.

An operational check was performed to ensure the mechanical jumper could adequately support the operation of the nonsafety-related FS system. The TM did not affect safety-related systems or components Therefore, an unreviewed safety question does not exist.

FS 95-24 Updated Final Safety Analysis Report Change 6-30-95 (Safety Evaluation No.95-073)

UFSAR Change 95-24 revised the Safety Analysis Limit (SAL) for the minimum Chemical Addition Tank inventory from 4200 gallons to 3800 gallons to be consistent with Engineering Standard STD-GN-0030.

The SAL: change affected accident analysis assumptions and did not involve any physical changes to the plant. An engineering evaluation of the subject change concluded that affected accident analyses remain acceptable with no reduction in the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 95-06 Page 13 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: June, 1995 1[2]-ES-3.2 Emergency Operating Procedures 6-01-95 1[2]-E-3 (Safety Evaluation No.95-060) 1[2]-ECA-3.1 1[2]-ECA-3.2 Emergency Procedures 1[2]-ES-3.2, "Post-SGTR Cooldown Using Slowdown," 1[2]-E-3, 1[2]-ECA-3.3 "Steam Generator Tube Rupture," 1[2]-ECA-3.1, "SGTR with Loss of Reactor Coolant -

Subcooled Recovery," 1[2]-ECA-3.2, "SGTR with Loss of Reactor Coolant - Saturated Recovery," and 1 [2]-ECA-3.3, "SGTR Without Pressurizer Pressure Control," were revised to provide operational guidance for minimizing contamination of secondary systems in the event of a steam generator tube rupture (SGTR) and to provide a method to blow down a steam generator following such an event.

These changes, which were made in response to SOER 93-1, improve the recovery capability following a SGTR event. The changes did not affect the accident analyses or reduce the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

O-TOP-4060 Temporary Operating Procedure 6-01-95 ROP-1.57 Radwaste Operating Procedures ROP-1.58 (Safety Evaluation No.95-059)

Temporary Operating Procedure O-TOP-4060, "Chemical Waste Transfer from the Storage Area to the Radwaste Facility," was developed and Radwaste Operating Procedures ROP-1.57, "Installing Temporary Hose for Transferring S/G Cleaning Liquids to the SRF," and ROP-1.58, "Removing Temporary Hose Used to Transfer S/G Cleaning Liquids to the SRF," were revised to provide instructions for the installation and operation of a temporary piping and hose system to transfer liquid waste from temporary storage tanks at the Radiological Controlled Area yard to the Surry Radwaste Facility Liquid Waste system.

The liquid waste was generated during the 1994 Unit 1 Steam Generator Chemical Cleaning outage.

A spill control plan and procedures, in conjunction with dikes and berms to contain non-isolable leaks from the temporary storage tanks and piping, are in place to ensure compliance with effluent Technical Specifications. Therefore, an unreviewed safety question does not exist.

FS 95-23 Updated Final Safety Analysis Report Change 6-29-95 1[2]-DRP-003 Design Reference Procedures 1[2]-PT-36 Operations Periodic Tests OC-3[4] Operations Checklists (Safety Evaluation No.95-070)

UFSAR Section 6.2.3.11.1, "Low-Head Safety Injection Pumps [NPSH Requirements],"

Design Reference Procedures 1[2]-DRP-003, "Curve Book," Operations Periodic Test 1[2]-PT-36, "Instrument Surveillance," and Operations Checklists OC-3[4], "Containment Envelope Limits Check," were revised to reflect a change in the Refueling Water Storage Tank temperature lower limit from 40 °F to 33 °F.

An engineering analysis of the subject change concluded that the minimum containment design pressure will not be exceeded with the appropriate adjustment in the containment air partial pressure. Therefore, an unreviewed safety question does not exist.

-urry Monthly Operating Report No. 95-06 Page 14 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1995 None During the Reporting Period

e Surry Monthly Operating Report No. 95-06 Page 15 of 19 CHEMISTRY REPORT MONTH/YEAR: June, 1995 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Avg.

Gross Radioactivity, 11Ci/ml 3.54E-1 2.37E-1 2.91E-1 2.18E-1 3.59E-3 1.52E-1 Suspended Solids, ppm 50.01 50.01 50.01 50.01 50.01 50.01 Gross Tritium, µCi/ml 1.29E-1 1.07E-1 1.16E-1 3.32E-1 2.19E-1 2.85E-1 1131, µCi/ml 7.1 OE-4 4.34E-4 6.12E-4 1.82E-4 2.43E-5 1.07E-4 113111133 0.08 0.06 0.07 0.09 0.06 0.07 Hydrogen, cc/kg 43.8 34.0 38.9 45.8 30.5 37.7 Lithium, ppm 1.71 1.16 1.47 2.33 2.08 2.21 Boron - 10, ppm* 37.8 19.6 29.4 286 187 214 Oxygen, (DO), ppm 50.005 50.005 50.005 50.005 50.005 50.005 Chloride, ppm 0.004 50.001 0.001 0.006 0.002 0.004 pH at 25 degree Celsius 7.56 7.32 7.43 6.74 6.37 6.63 Boron - 1O = Total Boron x 0.196 Comments:

None

eSurry Monthly Operating Report No. 95-06 Page 16 of 19 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: June, 1995 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 Activitl'.

New Fuel Unit 1 Batch 16 Shipment 1 6/27/95 8 40A LM11J2 4.0079 10.14 Ci 43A LM11J5 4.0034 41A LM11J3 4.0159 46A LM11J8 4.0115 54A LM11JG 4.0022 50A LM11JC 4.0119 45A LM11J7 4.0009 49A LM11JB 4.0058 6/29/95 12 63A LM11JR 4.0110 14.94 Ci 56A LM11JJ 4.0043 53A LM11JF 3.9960 60A LM11JN 4.0048 03A LM11GZ 3.8039 02A LM11GY 3.8051 39A LM11J1 4.0118 09A LM11H5 3.8052 47A LM11J9 4.0109 57A LM11JK 3.9961 58A LM11JL 4.0067 55A LM11JH 4.0024

.. eSurry Monthly Operating Report No. 95-06

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... ' Page 17 of 19 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: June, 1995 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 Activitl Spent Fuel Cask CASTOR V/21 500.11-020 6/16/95 21 2A5 LM04TF 3.393 N/A OA1 LM04UT 2.901 OA5 LM04TL 2.901 1A9 LM04TJ 2.901 1P5 LM05XC 3.607 2P3 LM05X7 3.607 3P6 LM05XV 3.607 3P7 LM05XR 3.607 3P8 LM05XT 3.607 4P1 LM09PC 3.607 4P9 LM05YU 3.607 2A8 LM04U3 3.393 5P1 LM05YF 3.607 5P9 LM05Y7 3.607 2A9 LM04UW 3.393 3A5 LM04V1 3.393 3A8 LM04UB 3.393 OP6 LM05Y4 3.607 OP? LM05JX 3.607 OP9 LM05XD 3.607 1PO LM05X8 3.607

• eSurry Monthly Operating Report No. 95-06

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FUEL HANDLING Page 18 of 19 UNITS 1 & 2

• MONTHNEAR: June, 1995 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 Activitz'.

Spent Fuel Cask CASTOR V/21 500.11-024 6/28/95 21 G09 LM01QC 2.111 N/A J37 LM035G 2.902 J38 LM035S 2.902 J39 LM035Q 2.902 S24 LMOOVE 2.606 825 LMOOVQ 2.606 J45 LM035H 2.902 5A7 LM04UM 3.393 826 LMOOVD 2.606 6A3 LM04UZ 3.393 S27 LMOOVF 2.606 S11 LMOOTV 2.606 S31 LMOOVP 2.606 C36 NOANSI 3.117 817 LMOOV7 2.606 J05 LM034F 2.902 818 LMOOV9 2.606 J19 LM035A 2.902 J33 LM035F 2.902 821 LMOOVB 2.606 823 LMOOU8 2.606

.~

eSurry Monthly Operating Report No. 95-06 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: June, 1995 Number Title LER Number O-EPT-0102-01 Monthly Station Battery Cell Voltage Check 50-280/

95-004-00