ML18153A416

Monthly Operating Repts for May 1997 for Surry Power Station Units 1 & 2

ML18153A416
Person / Time
Site:	Surry
Issue date:	05/31/1997
From:	Fanguy M, Kilmer J, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18153A415	List: ML18153A414 ML18153A416 ML18153A417
References
NUDOCS 9706180282
Download: ML18153A416 (18)

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<tllurry Monthly Operating Report No. 97-05 Page 1 of 18 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION 9706180282 970612 PDR ADOCK 05000280 R

PDR MONTHL V OPERATING REPORT REPORT No. 97-05 Approved:

TABLE OF CONTENTS Section Surry Monthly Operating Report No. 97-05 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....................................................................................................... 10 Facility Changes That Did Not Require NRC Approval............................................................................................ 11 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....................................................................................................................... 18

Surry Monthly Operating Report

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 May, 1997 2546 847.5 788 840 801 Docket No.:

Date:

Completed By:

Telephone:

50-280 06/02/97 No. 97-05 Page 3 of 18 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.................................

744.0 3623.0

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

734.0 2054.1

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

0.0 0.0

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

653.2 1931.5

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

0.0 0.0

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

1375878.6 4566332.2

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

455066.0 1520321.0

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

436890.0 1466080.0

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

87.8%

53.3%

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

87.8%

53.3%

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

73.3%

50.5%

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

74.5%

51.4%

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

0.0%

12.9%

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 214247.0 148888.8 3774.5 146462.5 3736.2 343201776.0 112493139.0 107059829.0 68.4%

70.1%

64.3%

63.4%

15.2%

ACHIEVED

~I Surry Monthly Operating Report

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 May, 1997 2546 847.5 788 840 801 Docket No.:

Date:

Completed By:

Telephone:

50-281 06/02/97 No. 97-05 Page 4 of 18 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.................................

744.0 3623.0

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

744.0 3559.0

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

0.0 0.0

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

744.0 3552.1

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

0.0 0.0

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

1890741.1 8973287.6

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

631260.0 3007965.0

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

609928.0 2910396.0

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

100.0%

98.0%

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

100.0%

98.0%

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

102.3%

100.3%

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

104.0%

101.9%

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

0.0%

2.0%

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 211127.0 146634.6 328.1 144649.9 0.0 340447544.4 111458764.0 106102275.0 68.5%

68.5%

64.3%

63.8%

12.2%

ACHIEVED

. ~.

(1)

Date Type 5/1/97 s

5/4/97 s

5/12/97 s

(1)

F:

Forced S:

Scheduled (4)

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

REPORT MONTH: May, 1997 Surry Monthly Operating Report No. 97-05 Page 5 of 18 Docket No.:

50-280 Unit Name:

Surry Unit 1 Date:

06-04-97 Completed by:

M. J. Fanguy Telephone:

(804) 365-2155 (2)

(3)

(4)

(5)

Method Duration of

-LER No.

System Component Cause & Corrective Action Hours 35.3 26.6 28.9 Reason C

B B

(2)

REASON:

Shutting Down Rx NA NA NA NA NA NA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Code NA TA TA E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

Code to Prevent Recurrence NA Refueling Outage TRB Ramp unit off-line to perform a turbine balance shot from 28% / 170 MWe.

TRB Ramp unit off-line to perform a turbine balance shot from 58% / 490 MWe.

(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

Surry Monthly Operating Report No. 97-05 Page 6 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: May, 1997 (1)

(2)

(3)

(4)

Method Docket No.:

50-281 Unit Name:

Surry Unit 2 Date:

06-04-97 Completed by:

M. J. Fanguy Telephone:

(804) 365-2155 (5)

Duration of LER No.

System Component Cause & Corrective Action Date Type Hours Reason Shutting Code (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 {LEA) File (NUREG 0161)

Code to Prevent Recurrence (3)

METHOD:

1 -

Manual 2 -

Manual Scram 3 -

Automatic Scram 4 -

Other (Explain)

(5)

Exhibit 1 - Same Source

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Surry Monthly Operating Report No. 97-05 Page 7 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name:

Surry Unit 1 Date: 06-03-97 Completed by:

J. D. Kilmer Telephone: (804) 365-2792 MONTH:

May, 1997 Average Daily Power Level Average Daily Power Level Day (MWe - Net)

Day (MWe - Net) 0 17 824 2

74 18 823 3

175 19 822 4

6 20 821 5

202 21 820 6

401 22 820 7

409 23 820 8

500 24 819 9

490 25 818 10 477 26 819 11 462 27 819 12 67 28 820 13 192 29 808 14 749 30 821 15 813 31 819 16 819 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:

May, 1997 Day 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 INSTRUCTIONS Surry Monthly Operating Report No. 97-05 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)

Day 817 17 819 18 810 19 818 20 825 21 825 22 824 23 822 24 822 25 821 26 823 27 829 28 823 29 823 30 823 31 823 Docket No.:

50-281 Unit Name:

Surry Unit 2 Date:

06-03-97 Completed by:

John D. Kilmer Telephone:

(804) 365-2792 Average Daily Power Level (MWe - Net) 821 823 823 823 822 823 823 815 774 822 822 823 823 817 815 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.

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SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: May, 1997 Surry Monthly Operating Report No. 97-05 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:

05/01/97 05/02/97 05/03/97 05/04/97 05/05/97 05/08/97 05/12/97 05/13/97 05/14/97 05/16/97 05/31/97 0000 Unit 1 starts month at Hot Shutdown after refueling outage.

0958 Reactor critical.

0005 Unit is stable at 2% power.

1120 Unit is on-line.

1210 Steam dumps closed, unit is stable at 30% power.

2133 0338 Stop power increase at 33% / 235 MWe.

Commence power decrease to take unit off-line for turbine balance shot from 28% I 170 MWe.

0455 Unit is off-line with reactor critical.

0120 Unit is at 2%.

0729 Unit is on-line.

1510 Flux map performed at 50% power.

0851 Flux map performed at 70% power.

1648 Stop power increase at 72% / 600 MWe.

1648 Commence power decrease to reduce turbine vibrations.

1737 Start varying power level to investigate turbine vibrations.

0235 Commence power decrease to perform a turbine balance shot.

0640 Unit is off-line.

1137 1820 1057 1143 2400 Unit is on-line.

Stop power increase at 98.25 / 845 MWe by management until power indication is adjusted.

Commence power increase to 100% from 98.5% I 840 MWe.

Unit is stable at 100% / 855 MWe.

Unit 1 finishes the month at 100% 850 MWe.

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SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: May, 1997

• Surry Monthly Operating Report No. 97-05 Page 10 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.

UNITTWO 05/01/97 05/24/97 05/25/97 05/31/97 0000 2139 Unit 2 starts the month at 100% / 855 MWe.

Initiate power decrease to 90% to attempt the seating of leaking valve 2-ES-SV-201 B.

2215 Stopped power decrease at 90% / 785 MWe, relief valve seated.

0627 Start power increase.

1232 Unit is at 100% / 835 MWe.

1903 Commence power decrease to 95% to prepare for replacement of 2-ES-SV-201 B.

1923 Stop power decrease at 95% / 785 MWe.

2258 2347 2400 Commence power increase to 100%.

Stop power increase at 100% / 850 MWe.

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

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SE 97-0011 FS97-022 TM S1-97-008 TM-S 1-97-10 Surry Monthly Operating Report No. 97-05 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May,.1997 Safety Evaluation 5-8-97 The exterior coating system on the MC-10 cask at the Surry ISFSI does not match the coating system described in the MC-10 Topical Safety Analysis Report (TSAR).

The MC-10 TSAR was reviewed to determine if the exterior coating had any impact on cask design or licensing analysis.

The only potential impact identified was that the analysis of cask temperature used surface emissivity as a design input. The emissivity used for the MC-10 thermal analysis is for epoxy enamel paint. The Keeler & Long topcoat used on the MC-10 cask at the Surry ISFSI is an epoxy enamel. Therefore the emissivity used in the MC-10 thermal analysis is correct for the cask in service and an unreviewed safety question does not exist.

Updated Final Safety Analysis Report Change (Safety Evaluation 97-071) 5-12-97 Updated Final Safety Analysis Report Change FS 97-22 revised Section 9.12.5.4, "Reassembly Sequence," to match the actual sequence performed by plant operations for the reassembly sequence of the Reactor Vessel following refueling.

The change to the fuel handling practices, as described in the UFSAR, are only in the order in which the activities are performed. These changes reflect current fuel handling practices which have been SNSOC approved and have been proven to be safe and successful. Therefore, an unreviewed safety question does not exist.

Temporary Modification (Safety Evaluation No.97-072) 5-13-97 This Temporary Modification (TM) installs a jumper in the turbine turning gear motor start circuitry. This will allow the operation of the turbine turning gear with bearing lift pressure less than 850 psig.

The installation of the jumper is on non-safety related equipment designed for the protection of the turbine. Sufficient oil pressure was available to prevent damage to the turbine bearings. Installation of this jumper can not feed into safety related circuits or control circuits which would affect safety related equipment. The turbine is off-line during this installation and the unit is below the P-7 permissive, therefore failure of this jumper would not cause a reactor trip by turbine trip. Therefore, an unreviewed safety question does not exist.

Temporary Modification (Safety Evaluation 97-074) 5-28-97

• The purpose of this Temporary Modification (TM) is to troubleshoot the Unit 1 Containment Sump level loop by installing a recorder to monitor the Sump level. The Containment Sump level loop is not safety related. The installation of the monitor will not affect indication in the Main Control Room nor will it affect the start circuitry of the Containment Sump Pumps. A failure of the TM may cause an inadvertent start or stop of the Containment Sump Pumps; however, such a failure will not affect equipment assumed to be available in any of the accidents analyzed in Chapter 14 of the UFSAR.

Therefore, an unreviewed safety question does not exist.

DCP 95-035 DCP 97-006 Surry Monthly Operating Report No. 97-05 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: May, 1997 Design Change Package (Safety Evaluation 95-184) 5-28-97 Design Change Package (DCP)95-035, "Waste Gas Decay Tank Oxygen Analyzer Modification," replaces the sample pumps and reroutes the sample return tubing in order to make the sampling system more reliable.

The modification performed by this DCP will not change the function of the Waste Gas Decay Tank Oxygen Sampling System. This change reduces required maintenance on the system. The existing analysis of the Waste Gas Decay Tank rupture bounds any releases of radioactive gases due to this change.

Therefore, an unreviewed safety question does not exist.

Design Change Package (Safety Evaluation 97-061) 5-28-97 Design Change Package (DCP)97-006, "Waste Gas Decay Tank Oxygen Analyzer Enhancement," reconfigures the Waste Gas System to allow the use of one oxygen analyzer and to select the Waste Gas Decay Tank (WGDT) to be monitored with a valve arrangement that allows either the 'A' or 'B' tank to be monitored by either analyzer.

Additionally, this DCP replaces the WGDT oxygen analyzer chart recorder located in the Control Room.

This modification does not change the function of the WGDT Oxygen Sampling System.

The existing analysis of the waste decay tank rupture bounds any releases of radioactive gases due to this change. The modification is to the Sampling System, not any major component of the Gaseous Waste System. The change will not increase the amount of pressure of the gases contained in the WGDT. Therefore, an unreviewed safety question does not exist.

J.,.>

. ~ *.

1-0SP-EG-001 1-MOP-EG-001 O-TMOP-Rl-3035 1-IPT-CC-RC-F-435 Rev5 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1997 Operations Surveillance Procedure Maintenance Operating Procedure (Safety Evaluation 97-068)

Surry Monthly Operating Report No. 97-05 Page 13 of 18 5-2-97 Maintenance Operating Procedure 1-MOP-EG-001, "Number 1 Emergency Diesel Generator Systems Removal From Service" was revised to allow the option for the Alarm System Circuit Breaker and the DC Control Circuit Breaker to remain energized. Using this option allows the testing of the alarm circuits for the Number 1 Emergency Diesel Generator (EOG) using the new Operations Surveillance Procedure 1-0SP-EG-001, "Number 1 Emergency Diesel Generator Local Alarm Panel Functional Test."

The starting systems for the Number 1 EOG will be removed from service preventing an Auto Start and applicable Technical Specification 3.16 action statements will be entered.

The Number 1 EOG will have a procedurally controlled jumper installed to simulate alarms.

The Main Control Room Annunciator System will receive alarm signals generated during the performance of this test. These alarms are normal inputs to this system and will not create an operational or safety concern. Therefore, an unreviewed safety question does not exist.

Temporary Maintenance Operating Procedure (Safety Evaluation 97-069) 5-8-97 Temporary Maintenance Operating Procedure O-TMOP-Rl-3035, "Removal and Return to Service of the WD and Boron Recovery Annunciator Panels," has been developed to provide operational guidance on compensatory measures that must be invoked while these annunciators are out of service for required maintenance.

Required equipment is declared inoperable and appropriate compensatory measures as required by TS or VPAP-2802 are implemented. UFSAR Chapter 14 accidents analyses were reviewed and no credit is taken for the affected annunciators to mitigate the consequences of any analyzed accident. Additionally, increased monitoring assures that the equipment will continue to operate satisfactorily.

Therefore, an unreviewed safety question does not exist.

Instrument Periodic Test Procedure (Safety Evaluation 97-070) 5-8-97 Instrument Periodic Test Procedure 1-IPT-CC-RC-F-435, "Reactor Coolant Flow Loop F 435 Channel Calibration," was revised as a One Time Only PAR.

Channel 2 was inoperable and placed in trip. The One Time Only PAR performed steps which allowed the channel to be bypassed. Technical Specification (TS) 3.7 allows an inoperable RCS flow channel to be bypassed for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing. Placing Channel 2 in bypass allows the surveillance testing for channels 1 and 3 of the Unit 1 'C' Loop RCS flow channels to be completed in accordance with the requirements of Technical Specification 4.1.

TS compliance is maintained during this evolution.

No other RCS flow channels are affected. The other two channels provide the trip function should it be required. Therefore, an unreviewed safety question does not exist.

2-0P-RC-001 O-OP-VS-15 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: May, 1997 Operating Procedure (Safety Evaluation 97-073)

Surry Monthly Operating Report No. 97-05 Page 14 of 18 5-22-97 Operating Procedure 2-0P-RC-001, "Starting and Running Any Reactor Coolant Pump,"

was revised to install the RCP speed sensing circuit supervisory relay paddle plugs prior to an RCP start and remove the paddle plugs following the start for a continuous RCP run.

Additionally, the Pro-Star Motor Protection System start block LEDs will be verified as cleared prior to disconnecting the supervisory relay paddle plugs. This change will prevent a spurious RCP trip during a Station Service to Reserve Station Service power supply auto transfer during a Unit trip.

The RCP speed sensing circuit does not provide a safety related function. It merely defeats the RCP starting overcurrent trip during the start-up of the pump.

Once the RCP has started and is operating at its normal speed and current, the circuit will be defeated. All other protection functions for the RCP that are required during normal pump operation will not be defeated. Therefore, an unreviewed safety question does not exist.

Operating Procedure (Safety Evaluation 97-075) 5-31-97 Operating Procedure O-OP-VS-15, "Normal Switchgear Room Ventilation Systems," was revised to procedurally control the use of spot coolers as a Temporary Modification (TM).

Spot coolers are used in the Unit 1 and 2 Rod Control Power Cabinets if the cabinets normal ventilation fails.

The spot coolers are used to ensure the maximum sustained temperature inside the Rod Control Power Cabinets does not exceed 77 °F.

The installation of the TM does not affect the function or operation of the Rod Control Power Cabinets, does not affect safety related equipment or power supplies and does not affect any Technical Specification basis or condition of operation.

Therefore, an unreviewed safety question does not exist.

Surry Monthly Operating Report TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1997 None During the Reporting Period No. 97-05 Page 15 of 18

• '/.

Primary Coolant Analvsis Gross Radioactivity, µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml 1131, µCi/ml 113111133 Hvdroaen, cc/ka Lithium, oom Boron - 10, oom*

Oxygen, (DO), ppm Chloride, oom pH at 25 dearee Celsius Boron - 1 O = Total Boron x 0.196 Comments:

None Max.

3.51 E-1 0.025 1.81E-1 CHEMISTRY REPORT MoNTHNEAR: May, 1997 Unit No. 1 Min.

Avg.

1.21 E-3 2.07E-1 0.025 0.025 5.93E-2 8.96E-2 3.88E-4 8.74E-6 1.45E-4 0.09 0.05 0.07 39.5 29.7 31.9 3.64 2.23 2.81 380.6 258.5 312.1

o;0.005

'>0.005

'>0.005 0.007 0.004 0.005 6.14 5.58 5.88 Surry Monthly Operating Report Unit No. 2 Max.

Min.

2.60E-1 1.59E-1 4.42E-1 3.78E-1 6.48E-5 2.65E-5 0.10 0.04 32.3 26.9 2.33 2.07 132.5 114.1

'>0.005

'>0.005 0.004 0.003 6.76 6.27 No. 97-05 Page 16 of 18 Ava.

2.02E-1 4.19E-1 4.98E-5 0.07 30.0 2.19 123.0

'>0.005 0.003 6.53

l New Fuel Shipment or Cask No.

FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: May, 1997 Number of Date Stored or Assemblies Received per Shipment Assembly Number ANSI Number Surry Monthly Operating Report Initial Enrichment No. 97-05 Page 17 of 18 New or Spent Fuel Shipping Cask Activity No Fuel Received or Stored During the Reporting Period

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Surry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE Nor COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: MAY, 1997 None During the Reporting Period No. 97-05 Page 18 of 18