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 C, 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 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.95-353 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 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 TABLE OF CONTENTS Section e Surry Monthly Operating Report No. 95-06 Page 2 of 19 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.

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

1 O 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.: Date: Completed By: 50-280 07-05-95 D. Mason Telephone:

(804) 365-2459 1 . Unit Name: .................................................. . 2. Reporting Period: ......................................... . 3. Licensed Thermal Power (MWt): .....................

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

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

.. 6. Maximum Dependable Capacity (Gross MWe): .. .. 7. Maximum Dependable Capacity (Net MWe): ....... . Surry Unit 1 June, 1995 2441 847.5 788 820 781 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: 9. Power Level To Which Restricted, If Any (Net MWe): 10. Reasons For Restrictions, If Any: This Month 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 OPERATING DATA REPORT -urry Monthly Operating Report No. 95-06 Page 4 of 19 Docket No.: Date: Completed By: 50-281 07-05-95 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 2 June, 1995 2441 847.5 788 820 781 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: 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):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED 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 (1) (2) (3) (4) (5) Method Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 07-05-95 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 950612 N/A 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 SG 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) RV Reduced power to facilitate replacement of condensate system relief valve, 1-CN-RV-113B. (3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)

(5) Exhibit 1 -Same Source.

(1) 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 Method (5) Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 07-05-95 Completed by: Craig Olsen Telephone:

(804) 365-2155 Duration of LER System Component Cause & Corrective Action to Date Type Hours 950614 F 60.1 (1) F: Forced S: Scheduled Reason Shutting No. Code Down Rx A 3 2-95-EL 006-00 (2) REASON: A -Equipment Failure (Explain)

B Maintenance or Test C Refueling D Regulatory Restriction Code Prevent Recurrence PMG Automatic reactor trip due to main transformer generator differential lockout. (3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)

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 (NUREG 0161) (5) Exhibit 1 -Same Source.

MONTH: June, 1995 Day 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS -urry Monthly Operating Report No. 95-06 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe-Net) Day 786 17 786 18 785 19 784 20 785 21 787 22 786 23 784 24 783 25 783 26 782 27 747 28 736 29 776 30 763

• 762 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 07-06-95 Completed by: Barry C. Bryant Telephone:

(804) 365-2786 Average Daily Power Level (MWe-Net) 782 780 780 778 776 779 778 776 773 771 771 775 768 741 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: June, 1995 Day 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS e e Surry Monthly Operating Report No. 95-06 Page 8 of 19 AVERAGE DAILY UNIT POW.ER LEVEL Average Daily Power Level (MWe -Net) Day 774 17 759 18 778 19 776 20 776 21 777 22 775 23 773 24 772 25 771 26 761 27 776 28 780 29 462 30 0 0 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 07-06-95 Completed by: Barry C. Bryant Telephone:

(804) 365-2786 Average Daily Power Level (MWe -Net) 521 778 778 778 776 778 777 774 777 773 776 777 777 775 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 06/12/95 06/13/95 06/30/95 UNIT Two: 06/01/95 06/14/95 06/16/95 06/17/95 06/30/95 0000 1830 The reporting period began with the unit operating at 100% power, 825 MWe. Started power reduction to facilitate replacement of Condensate system relief valve RV-113B. 2004 Stopped power reduction at 78%, 630 MWe. 0520 Started power increase.

0745 Stopped power increase at 100%, 820 MWe. 2400 The reporting period ended with the unit operating at 100% power, 820 MWe. 0000 The reporting period began with the unit operating at 100% power, 810 MWe. 1415 Automatic reactor trip due to main transformer generator differential lockout. 2050 Reactor critical.

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

FS 94-37 DCP 87-009-2 DCP 87-023-2 DCP 87-021-3 e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

June, 1995 Updated Final Safety Analysis Report Change (Safety Evaluation No.95-061) Surry Monthly Operating Report No. 95-06 Page 10 of 19 6-01-95 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. Design Change Package (Safety Evaluation No.91-037) 6-07-95 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. 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. 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.

SE 95-064 DCP 87-008-1 DCP 87-028-1 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

June, 1995 Safety Evaluation e Surry Monthly Operating Report No. 95-06 Page 11 of 19 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. Design Change Package (Safety Evaluation No.90-191) 6-20-95 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. Design Change Package (Safety Evaluation No.90-205) 6-20-95 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.

TM S1-95-06 FS 95-24 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

June, 1995 Temporary Modification (Safety Evaluation No.95-066) -urry Monthly Operating Report No. 95-06 Page 12 of 19 6-27-95 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 related systems or components Therefore, an unreviewed safety question does not exist. Updated Final Safety Analysis Report Change (Safety Evaluation No.95-073) 6-30-95 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.

1 [2]-ES-3.2 1 [2]-E-3 1 [2]-ECA-3.1 1 [2]-ECA-3.2 1 [2]-ECA-3.3 O-TOP-4060 ROP-1.57 ROP-1.58 FS 95-23 1 [2]-DRP-003 1 [2]-PT-36 OC-3[4] 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 Emergency Operating Procedures (Safety Evaluation No.95-060) 6-01-95 Emergency Procedures 1 [2]-ES-3.2, "Post-SGTR Cooldown Using Slowdown," 1 [2]-E-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. Temporary Operating Procedure Radwaste Operating Procedures (Safety Evaluation No.95-059) 6-01-95 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 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. Updated Final Safety Analysis Report Change Design Reference Procedures Operations Periodic Tests Operations Checklists (Safety Evaluation No.95-070) 6-29-95 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 CHEMISTRY REPORT MONTH/YEAR:

June, 1995 Unit No. 1 Primary Coolant Analysis Max. Min. Avg. Gross Radioactivity, 11Ci/ml 3.54E-1 2.37E-1 2.91E-1 Suspended Solids, ppm 50.01 50.01 50.01 Gross Tritium, µCi/ml 1.29E-1 1.07E-1 1.16E-1 1131, µCi/ml 7.1 OE-4 4.34E-4 6.12E-4 113111133 0.08 0.06 0.07 Hydrogen, cc/kg 43.8 34.0 38.9 Lithium, ppm 1.71 1.16 1.47 Boron -10, ppm* 37.8 19.6 29.4 Oxygen, (DO), ppm 50.005 50.005 50.005 Chloride, ppm 0.004 50.001 0.001 pH at 25 degree Celsius 7.56 7.32 7.43 Boron -1 O = Total Boron x 0.196 Comments:

None e Surry Monthly Operating Report No. 95-06 Page 15 of 19 Unit No. 2 Max. Min. Avg. 2.18E-1 3.59E-3 1.52E-1 50.01 50.01 50.01 3.32E-1 2.19E-1 2.85E-1 1.82E-4 2.43E-5 1.07E-4 0.09 0.06 0.07 45.8 30.5 37.7 2.33 2.08 2.21 286 187 214 50.005 50.005 50.005 0.006 0.002 0.004 6.74 6.37 6.63 New or Spent Fuel Shipment Date Stored or Number Received New Fuel Unit 1 Batch 16 Shipment 1 6/27/95 6/29/95 FUEL HANDLING UNITS 1 & 2 MONTHNEAR:

June, 1995 Number of Assemblies Assembly ANSI eer Shiement Number Number 8 40A LM11J2 43A LM11J5 41A LM11J3 46A LM11J8 54A LM11JG 50A LM11JC 45A LM11J7 49A LM11JB 12 63A LM11JR 56A LM11JJ 53A LM11JF 60A LM11JN 03A LM11GZ 02A LM11GY 39A LM11J1 09A LM11H5 47A LM11J9 57A LM11JK 58A LM11JL 55A LM11JH e Surry Monthly Operating Report No. 95-06 Page 16 of 19 New or Spent Initial Fuel Shipping Enrichment Cask Activitl'.

4.0079 10.14 Ci 4.0034 4.0159 4.0115 4.0022 4.0119 4.0009 4.0058 4.0110 14.94 Ci 4.0043 3.9960 4.0048 3.8039 3.8051 4.0118 3.8052 4.0109 3.9961 4.0067 4.0024

.. ... -' New or Spent Fuel Shipment Date Stored or Number Received Spent Fuel Cask CASTOR V/21 500.11-020 6/16/95 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR:

June, 1995 Number of Assemblies Assembly ANSI eer Shiement Number Number 21 2A5 LM04TF OA1 LM04UT OA5 LM04TL 1A9 LM04TJ 1P5 LM05XC 2P3 LM05X7 3P6 LM05XV 3P7 LM05XR 3P8 LM05XT 4P1 LM09PC 4P9 LM05YU 2A8 LM04U3 5P1 LM05YF 5P9 LM05Y7 2A9 LM04UW 3A5 LM04V1 3A8 LM04UB OP6 LM05Y4 OP? LM05JX OP9 LM05XD 1PO LM05X8 e Surry Monthly Operating Report No. 95-06 Page 17 of 19 New or Spent Initial Fuel Shipping Enrichment Cask Activitl 3.393 N/A 2.901 2.901 2.901 3.607 3.607 3.607 3.607 3.607 3.607 3.607 3.393 3.607 3.607 3.393 3.393 3.393 3.607 3.607 3.607 3.607

.. ' '

• New or Spent Fuel Shipment Date Stored or Number Received Spent Fuel Cask CASTOR V/21 500.11-024 6/28/95 FUEL HANDLING UNITS 1 & 2

• MONTHNEAR:

June, 1995 Number of Assemblies Assembly ANSI eer Shiement Number Number 21 G09 LM01QC J37 LM035G J38 LM035S J39 LM035Q S24 LMOOVE 825 LMOOVQ J45 LM035H 5A7 LM04UM 826 LMOOVD 6A3 LM04UZ S27 LMOOVF S11 LMOOTV S31 LMOOVP C36 NOANSI 817 LMOOV7 J05 LM034F 818 LMOOV9 J19 LM035A J33 LM035F 821 LMOOVB 823 LMOOU8 e Surry Monthly Operating Report No. 95-06 Page 18 of 19 New or Spent Initial Fuel Shipping Enrichment Cask Activitz'.

2.111 N/A 2.902 2.902 2.902 2.606 2.606 2.902 3.393 2.606 3.393 2.606 2.606 2.606 3.117 2.606 2.902 2.606 2.902 2.902 2.606 2.606

. Number e Surry 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 Title LER Number O-EPT-0102-01 Monthly Station Battery Cell Voltage Check 50-280/ 95-004-00