ML18153A424

Monthly Operating Repts for June 1997 for SPS

ML18153A424
Person / Time
Site:	Surry
Issue date:	06/30/1997
From:	Mason D, Sarver S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
97-412, NUDOCS 9707220145
Download: ML18153A424 (19)

Text

~,

(--~-

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 11, 1997 United States 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.97-412 NUMAE/JDK RO Docket Nos.

50-280 50-281 License Nos. DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry P9wer Station Units 1 and 2 for the month of June 1997.

If you have any questions or require additional information, please contact us.

S. P. Sarver, Acting Manager Nuclear Licensing and Operations Support Enclosure Commitments made by this letter:

1. None.

cc:

U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. H. A. Musser NRC Senior Resident Inspector Surry Power Station

-9707220145 970630~

\\

PDR ADOCK 05000280 111111111111111111/IIII 11111111111111111

• Iii ___ Iii _ 4 o

1 3

• I

'R PDR

~...

-urry Monthly Operating Report No. 97-06 Page 1 of 18 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERA TING REPORT REPORT No. 97 -06 Approved:

~.-.

TABLE OF CONTENTS Section

~urry Monthly Operating Report No. 97-06 Page 2 of 18 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 NRG Approval............................................................................................ 10 Procedure or Method of Operation Changes That Did Not Require NRG Approval................................................. 14 Tests and Experiments That Did Not Require N RC Approval.................................................................................. 15 Chemistry Report..................................................................................................................................................... 16 Fuel Handling - Unit No. 1........................................................................................................................................ 17 Fuel Handling - Unit No. 2........................................................................................................................................ 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications....................................................................................................................... 18

1.

2.

3.

4.

5.

6.

7.

OPERATING DATA REPORT Unit Name:............................................................

Reporting Period:..................................................

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

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

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

Maximum Dependable Capacity (Gross MWe):...

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

Surry Unit 1 June, 1997 2546 847.5 788 840 801

'9.urry Monthly Operating Report No. 97-06 Page 3 of 18 Docket No.:

Date:

Completed By:

Telephone:

50-280 07/02/97 D. K. Mason (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

11. Hours In Reporting Period.................................

720.0 4343.0

12. Number of Hours Reactor Was Critical..........

720.0 2774.1

13. Reactor Reserve Shutdown Hours..................

0.0 0.0

14. Hours Generator On-Line..................................

720.0 2651.5

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

0.0 0.0

16. Gross Thermal Energy Generated (MWH).....

1832447.9 6398780.1

17. Gross Electrical Energy Generated (MWH)....

608934.0 2129255.0

18. Net Electrical Energy Generated......................

588104.0 2054184.0

19. Unit Service Factor..............................................

100.0%

61.1%

20. Unit Availability Factor.........................................

100.0%

61.1%

21. Unit Capacity Factor (Using MDC Net)............

102.0%

59.0%

22. Unit Capacity Factor (Using DER Net)............

103.7%

60.0%

23. Unit Forced Outage Rate...................................

0.0%

9.7%

24.

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

25.

If Shut Down at End of Report Period, Estimated Date of Start-up:

26.

Unit In Test Status (Prior to Commercial Operation):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST Cumulative 214967.0 149608.8 3774.5 147182.5 3736.2 345034223.9 113102073.0 107647933.0 68.5%

70.2%

64.4%

63.5%

15.1%

ACHIEVED

1.

2.

3.

4.

5.

6.

7.

OPERATING DATA REPORT Unit Name:............................................................

Reporting Period:..................................................

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

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

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

Maximum Dependable Capacity (Gross MWe):...

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

Surry Unit 2 June, 1997 2546 847.5 788 840 801 itlurry Monthly Operating Report No. 97-06 Page 4 of 18 Docket No.:

Date:

Completed By:

Telephone:

50-281 07/02/97 D. K. Mason (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 YrD

11. Hours In Reporting Period.................................

720.0 4343.0

12. Number of Hours Reactor Was Critical..........

720.0 4279.0

13. Reactor Reserve Shutdown Hours..................

0.0 0.0

14. Hours Generator On-Line..................................

720.0 4272.1

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

0.0 0.0

16. Gross Thermal Energy Generated (MWH).....

1830126.0 10803413.6

17. Gross Electrical Energy Generated (MWH)....

603655.0 3611620.0

18. Net Electrical Energy Generated......................

582722.0 3493118.0

19. Unit Service Factor..............................................

100.0%

98.4%

20. Unit Availability Factor.........................................

100.0%

98.4%

21. Unit Capacity Factor (Using MDC Net)............

101.0%

100.4%

22. Unit Capacity Factor (Using DER Net)............

102.7%

102.1%

23. Unit Forced Outage Rate...................................

0.0%

1.6%

24.

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

Refueling, October 4, 1997, 30 Days

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 Cumulative 211847.0 147354.6 328.1 145369.9 0.0 342277670.4 112062419.0 106684997.0 68.6%

68.6%

64.4%

63.9%

12.2%

ACHIEVED

(1)

Date Type (1)

F:

Forced S:

Scheduled (4)

UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: June, 1997 Surry Monthly Operating Report No. 97-06 Page 5 of 18 Docket No.:

50-280 Unit Name:

Surry Unit 1 Date:

07-03-97 Completed by:

M. J. Fanguy Telephone:

(804) 365-2155 (2)

(3)

Method of Shutting Down Rx (4)

(5)

Duration Hours Reason LER No.

System Code Component Code Cause & Corrective Action to Prevent Recurrence None During the Reporting Period (2)

REASON:

A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

(3)

METHOD:

1 -

Manual 2 -

Manual Scram 3 -

Automatic Scram 4 -

Other (Explain)

(5)

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

Exhibit 1 - Same Source

(1)

Date Type 6/5/97 s

(1)

F:

Forced S:

Scheduled (4)

(2)

UNIT SHUTDOWN AND POWER REDUCTION

{EQUAL To OR GREATER THAN 20%)

REPORT MONTH: June, 1997

-urry Monthly Operating Report No. 97-06 Page 6 of 18 Docket No.:

50-281 Unit Name:

Surry Unit 2 Date:

07-03-97 Completed by:

M. J. Fanguy Telephone:

(804) 365-2155 (3)

(4)

(5)

Method Duration of LER No.

System Component Cause & Corrective Action Hours NA Reason B

(2)

REASON:

Shutting Down Rx NA NA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Code TA E

Operator Training & Licensing Examination F

Administrative G

Ope*rational Error (Explain)

Code to Prevent Recurrence V

Reduce power for 2-0SP-TM-001.

(3)

METHOD:

1 -

Manual 2 -

Manual Scram 3 -

Automatic Scram 4 -

Other (Explain)

(5)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Exhibit 1 - Same Source

MONTH:

June, 1997 Day 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 INSTRUCTIONS

-urry Monthly Operating Report No. 97-06 Page 7 of 18 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)

Day 819 17 800 18 820 19 816 20 812 21 822 22 823 23 822 24 819 25 821 26 821 27 822 28 821 29 821 30 820 820 Docket No.: 50-280 Unit Name:

Surry Unit 1 Date: 07-07-97 Completed by:

J. D. Kilmer Telephone: (804) 365-2792 Average Daily Power Level (MWe - Net) 821 818 817 815 816 814 814 814 814 812 813 813 812 812 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, 1997 Day 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 INSTRUCTIONS Surry Monthly Operating Report No. 97-06 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)

Day 816 17 819 18 818 19 821 20 795 21 823 22 823 23 822 24 820 25 817 26 816 27 817 28 816 29 816 30 816 815 Docket No.: 50-281 Unit Name:

Surry Unit 2 Date: 07-07-97 Completed by: John D. Kilmer Telephone: (804) 365-2792 Average Daily Power Level (MWe - Net) 813 808 807 803 801 800 799 802 800 793 793 797 797 796 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.

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: June, 1997

-urry Monthly Operating Report No. 97-06 Page 9 of 18 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:

06/01/97 06/02/97 06/30/97 UNITTWO 06/01/97 06/05/97 06/30/97 0000 1515 Unit 1 begins month at 100% / 850 MWe.

Start power decrease in accordance with 1-0P-TM-005 "Unit Ramping Operations" from 100% / 825 MWe to allow 'B' waterbox cleaning.

1601 Stop power decrease at 96% / 810 MWe.

2005 Start power increase slowly increasing power to 100%

2202 Stop power increase at 100% / 850 MWe.

2400 0000 0611 Unit 1 finishes the month at 100% / 845 MWe.

Unit 2 begins the month at 100% / 850 MWe.

Start power decrease from 100% / 850 MWe in preparation for Turbine Inlet Valve Freedom Test in accordance with 2-0SP-TM-001.

1030 Stop power decrease at 72%/ 620 MWe.

1043 Start power increase after completion of Turbine Inlet Valve Freedom Test.

1247 2400 Stop power increase at 100% / 855 MWe.

Unit 2 finishes the month at 100% / 830 MWe.

TM S1-97-009 TM S2-97-011 SE 97-0021

--urry Monthly Operating Report No. 97-06 Page 10 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: June, 1997 Temporary Modification (Safety Evaluation No.97-078) 6-5-97 This Temporary Modification (TM) installs new Relief Valves (RVs) in the Condensate Polishing System to prevent 98% sulfuric acid from discharging onto the acid skid which is both a personnel and an equipment concern. The discharge piping will be routed to a floor drain system using stainless steel flex hosing since parts for the existing discharge piping are currently unavailable. The discharge piping of the currently installed RVs will be blanked off.

The Condensate Polishing System is non-safety related system. During the acid injection phase of the resin, if the RVs lift the acid will be directed to a Unit 1 waste neutralization sump. The pH of the sump will change and an annunciator will alarm in the condensate polisher control room. Actions identified in the Annunciator Response Procedure would be performed. Therefore, an unreviewed safety question does not exist.

Temporary Modification (Safety Evaluation No.97-077) 6-5-97 This Temporary Modification (TM) involves the removal of two jumpers that provide a ground in the non-protection portion of the First Stage Protection Channels (1-MS-PT-446/447). Troubleshooting has determined that a ground exists in or downstream of the channel selector switch.

If more than one ground exists in a current loop, it will not indicate properly. This TM will lift the installed jumpers on each loop (446 and 447) to allow the ground in the selector switch to serve as the loop ground.

Should failure of the activity occur, operation of the plant would be bounded by current accident analyses. Specifically, UFSAR Chapter 14 describes the plant response for a complete loss of external electrical load coincident with failure of the steam dump valves to open. Therefore, an unreviewed safety question does not exist.

Safety Evaluation 6-5-97 Safety Evaluation 97-0021 was performed to evaluate a vendor nonconformance report regarding a spent fuel storage cask. Specifically, one of the corner basket rails in TN-32 Cask No. 3 was determined to be below the vendor specified limits for wall thickness of 0.6 inches. The actual wall thickness was 0.597 inches.

The undersized condition of the corner basket rail does not affect the function of the rail, which is to provide lateral support for the fuel basket in the event of a tip-over accident.

The area of maximum stress is in a different location of the rail and the calculated stress in the below minimum thickness area is not impacted and remains less than allowable.

The cask will perform as designed. Therefore, an unreviewed safety question does not exist.

I **

TM 82-97-004 TM 81-97-009 SE 97-079 Surry Monthly Operating Report No. 97-06 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: June, 1997 Temporary Modification (Safety Evaluation No. 97-078A) 6-7-97 This Temporary Modification (TM) installs a jumper which prevents the opening of 02-CP-MOV-200 (Condensate Polisher Bypass) during the replacement of pressure switch 2-CP-PS-217.

While the jumper is installed, the condensate polisher can not be automatically bypassed in the event of a loss of turbine load. Automatic bypass of the condensate polisher will be manually controlled. Annunciator Response Procedure 2CP-D2. directs manual operation of 2-CP-MOV-200 if the system differential pressure continues to increase.

Should failure of the activity occur, operation of the plant would be bounded by current accident analyses. Thus, this activity is acceptable and an unreviewed safety question does not exist.

Temporary Modification 6-12-97 (Safety Evaluation No.97-078 Rev. 1)

This Temporary Modification (TM) installs new Relief Valves (RVs) in the Condensate

• Polishing System to prevent 98% sulfuric acid from discharging onto the acid skid which is both a personnel and an equipment concern. The discharge piping will be routed to a floor drain system or routed to 1-CP-TK-14 using stainless steel flex hosing since parts for the existing discharge piping are currently unavailable. The discharge piping of the currently installed RVs will be blanked off.

The Condensate Polishing System is non-safety related system. During the acid injection phase of the resin, if the RVs lift the acid will be directed to a Unit 1 waste neutralization sump. The pH of the sump will change and an annunciator will alarm in the condensate polisher control room. Actions identified in the Annunciator Response Procedure would be performed. Therefore, an unreviewed safety question does not exist.

Safety Evaluation 6-16-97 This Safety Evaluation assesses a Circulating Water Pump being out of service for greater than 30 days.

Circulating Water Pumps provide water required to condense turbine exhaust steam and supply water to the Service Water System.

This condition meets the requirements of Technical Specifications and adequate intake level is maintained by the remaining operable Circulating Water Pumps. Therefore, an unreviewed safety question does not exist.

FS96-042 SE 97-0031 TM S1-97-012

--urry Monthly Operating Report No. 97-06 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1997 Updated Final Safety Analysis Report Change (Safety Evaluation 97-082) 6-19-97 Updated Final Safety Analysis Report Change FS 96-42 corrects a documentation error in Section 9.10.2.2.9.4.c and Table 17.2.0 of the Topical Report. The Surry Training Center records vault is no longer used to store quality assurance records and therefore is no longer required to comply with Regulatory Guide 1.88 or ANSI N45.2.9-197 4.

This revision incorporates changes to the UFSAR including the Topical Report to reflect the current records storage facilities at Surry.

These changes do not reduce commitments in the QA Topical Report.

There is no significant change in the consequences of a fire since records will continue to be stored in accordance with the requirements of ANSI Standard N45.2.9, Chapter 3 of NFPA 232, and Reg. Guide 1.88.

Therefore, an unreviewed safety question does not exist.

Safety Evaluation 6-19-97 Transnuclear TN-32 Cask Topical Safety Analysis Report (TSAR) is being revised to clarify Section 3.1.1 concerning ASME Code section reference for nondestructive weld examination. Section 3.1.1 states that "Other structural and structural attachment welds are examined by the liquid penetrant or the magnetic particle method in accordance with Section Ill, Subsection NF, Paragraph NF-5350."

Paragraph NF-5350 provides acceptance standards for magnetic particle inspection.

Paragraph NF-5040 provides acceptance standards for liquid penetrant inspection.

This revision is an editorial change only to correct the omission of a reference to ASME Section Ill, Subsection NF, Paragraph NF-5340.

Therefore, an unreviewed safety question does not exist.

Temporary Modification (Safety Evaluation No.97-080) 6-19-97 The differential expansion alarm (J-D-5) for Turbine Rotor in the Control Room has been intermittently actuating. There are no indications that the alarm is valid. This change installs a temporary recorder on the outputs from the differential expansion pickup transducers at the Turbine Supervisory Panel to investigate the source of the spurious alarms.

The equipment involved is non-safety related and has no interface with any control or protection circuits. Therefore, an unreviewed safety question does not exist.

4lurry Monthly Operating Report No. 97-06 Page 13 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1997 JCO 82-97-001, Rev. 2 Justification For Continued Operation (Safety Evaluation No.97-002 Rev. 2) 6-27-97 TM S2-97-05 This revision to the Justification for Continued Operation (JCO) discusses the Unit 2 letdown weld leak which developed on June 24, 1997 and was located on the downstream weld of the 'C' letdown HGV. The letdown line was removed from service; the weld flaw was excavated and repaired. Visual exams were performed on the other letdown lines with no indications of flaws existing. During the review of the failure, it was identified that the valve weights previously used in the analyses were incorrect and non-conservative. The seismic pipe stress analysis and representative vibration analysis was performed with the revised valve weights. As documented by Engineering Transmittal, the piping stress was within code allowables, with a valve support exceeding allowables.

Modifications have been made to the valve support to satisfy ASME Ill Appendix F criteria to allow continued operation until the next refueling outage in accordance with NRG Generic Letter 91-18.

This degraded and non-conforming condition has been reviewed and analyzed.

The previous letdown operational restrictions and support modifications made provide reasonable assurance that the letdown piping system and supports meet the structural integrity requirements outlined in Generic Letter 91-18 Section 6.13.

Therefore, an unreviewed safety question does not exist.

Temporary Modification (Safety Evaluation No.97-083) 6-29-97 The annunciator for Charging Pump to Regen HX Hi-Lo Flow (2D-E-5) is alarming frequently as a result of reduced charging flow conditions because of actions to operate with only one letdown orifice in service.

The charging flow setpoint is being reduced by the Temporary Modification but the high flow alarm capabilities will be maintained at the normal setpoint.

Additionally, the annunciator for Regen HX Ltdn Line Hi Temp (2D-F-3) will provide an alternate indication for low charging flow. This condition does not affect accidents previously evaluated and does not create the potential for an accident not previously identified. Therefore, an unreviewed safety question does not exist.

Plastocor 3.1 Surry Monthly Operating Report No. 97-06 Page 14 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: June, 1997 Vendor Procedure (Safety Evaluation 97-076) 6-2-97 Vendor Procedure Plastocor 3.1, "Procedure for the Installation of the Plastocor Epoxy Cladding System for Tubesheets with Down Tube Coating Using P-400U/P-2000U" provides instructions for coating the MER 5 chillers. This is done to protect the chiller condenser tubes from flow induced corrosion during normal operation and will be applied to the two spare chiller condensers located in the warehouse.

Application of Plastocor will increase the reliability and service life of the MER 5 chillers. It will not adversely affect the ability of the chillers to perform their design function. Return to service of the coated MER 5 chiller will include the performance of O-MPM-0210-01 for evaluating chiller performance. Therefore, an unreviewed safety question does not exist.

. 4llturry Monthly Operating Report No. 97-06 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1997 None During the Reporting Period

CHEMISTRY REPORT MONTHNEAR: June, 1997 Unit No. 1 Primary Coolant Analysis Max.

Min.

Avg.

Gross Radioactivity, µCi/ml 3.07E-1 1.61E-1 2.36E-1 Suspended Solids, ppm s0.01 so.01 so.01 Gross Tritium, µCi/ml 4.40E-1 2.42E-1 3.44E-1 1131, µCi/ml 2.46E-4 1.38E-4 2.16E-4 113111133 0.09 0.06 0.07 Hvdroqen, cc/kQ 32.6 27.0 29.2 Lithium, ppm 2.45 2.17

• 2.32 Boron - 1 O, ppm*

258.1 249.5 254.1 Oxygen, (DO), ppm s0.005 s0.005 s0.005 Chloride, ppm 0.006 0.002 0.004 pH at 25 degree Celsius 6.15 5.84 6.00 Boron - 10 = Total Boron x 0.196 Comments:

None tllturry Monthly Operating Report No. 97-06 Page 16 of 18 Unit No. 2 Max.

Min.

Avq.

2.73E-1 1.59E-1 2.00E-1 s0.01 so.01 so.01 4.47E-1 3.19E-1 4.11 E-1 2.22E-4 3.82E-5 8.08E-5 0.11 0.05 0.08 31.6 17.2 25.3 2.32 1.56 2.14 113.3 86.8 103.3 s0.005 s0.005 s0.005 0.005 so.001 0.003 6.78 6.59 6.68

New Fuel Shipment or Cask No.

FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: June, 1997 Number of Date Stored or Assemblies Received per Shipment Assembly Number ANSI Number tlurry Monthly Operating Report No. 97-06 Page 17 of 18 Initial Enrichment New or Spent Fuel Shipping Cask Activity No Fuel Received or Stored During the Reporting Period

lturry Monthly Operating Report No. 97-06 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR:JUNE, 1997 None During the Reporting Period