ML18153A416

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Monthly Operating Repts for May 1997 for Surry Power Station Units 1 & 2
ML18153A416
Person / Time
Site: Surry  Dominion icon.png
Issue date: 05/31/1997
From: Fanguy M, Kilmer J, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
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ML18153A415 List:
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 MONTHLV OPERATING REPORT REPORT No. 97-05 Approved:

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9706180282 970612 I PDR ADOCK 05000280 I R PDR

  • TABLE OF CONTENTS
  • Surry Monthly Operating Report No. 97-05 Page 2 of 18 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 ....................................................................................................... 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
  • OPERATING DATA REPORT
  • Surry Monthly Operating Report No. 97-05 Page 3 of 18 Docket No.: 50-280 Date: 06/02/97 Completed By: D. K. Mason Telephone: (804) 365-2459
1. Unit Name: ........................................................... . Surry Unit 1
2. Reporting Period: ................................................. . May, 1997
3. Licensed Thermal Power (MWt): ......................... . 2546
4. Nameplate Rating (Gross MWe): ......................... . 847.5
5. Design Electrical Rating (Net MWe): ................... . 788
6. Maximum Dependable Capacity (Gross MWe): .. . 840
7. Maximum Dependable Capacity (Net MWe): ...... . 801
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe): - - - - - - - - - - - - - - - - - - -
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period ................................. 744.0 3623.0 214247.0
12. Number of Hours Reactor Was Critical. ......... 734.0 2054.1 148888.8
13. Reactor Reserve Shutdown Hours .................. 0.0 0.0 3774.5
14. Hours Generator On-Line .................................. 653.2 1931.5 146462.5
15. Unit Reserve Shutdown Hours ......................... 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... 1375878.6 4566332.2 343201776.0
17. Gross Electrical Energy Generated (MWH) .... 455066.0 1520321.0 112493139.0
18. Net Electrical Energy Generated ...................... 436890.0 1466080.0 107059829.0
19. Unit Service Factor.............................................. 87.8% 53.3% 68.4%
20. Unit Availability Factor......................................... 87.8% 53.3% 70.1%
21. Unit Capacity Factor (Using MDC Net) ............ 73.3% 50.5% 64.3%
22. Unit Capacity Factor (Using DER Net) ............ 74.5% 51.4% 63.4%
23. Unit Forced Outage Rate ................................... 0.0% 12.9% 15.2%
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

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  • OPERATING DATA REPORT
  • Surry Monthly Operating Report No. 97-05 Page 4 of 18 Docket No.: 50-281 Date: 06/02/97 Completed By: D. K. Mason Telephone: (804) 365-2459
1. Unit Name: ............................................................ Surry Unit 2
2. Reporting Period: ................................................. . May, 1997
3. Licensed Thermal Power (MWt): ......................... . 2546
4. Nameplate Rating (Gross MWe): ......................... . 847.5
5. Design Electrical Rating (Net MWe): ................... . 788
6. Maximum Dependable Capacity (Gross MWe): .. . 840
7. Maximum Dependable Capacity (Net MWe): ...... . 801
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period ................................. 744.0 3623.0 211127.0
12. Number of Hours Reactor Was Critical. ......... 744.0 3559.0 146634.6
13. Reactor Reserve Shutdown Hours .................. 0.0 0.0 328.1
14. Hours Generator On-Line .................................. 744.0 3552.1 144649.9
15. Unit Reserve Shutdown Hours ......................... 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ..... 1890741.1 8973287.6 340447544.4
17. Gross Electrical Energy Generated (MWH) .... 631260.0 3007965.0 111458764.0
18. Net Electrical Energy Generated ...................... 609928.0 2910396.0 106102275.0
19. Unit Service Factor.............................................. 100.0% 98.0% 68.5%
20. Unit Availability Factor......................................... 100.0% 98.0% 68.5%
21. Unit Capacity Factor (Using MDC Net) ............ 102.3% 100.3% 64.3%
22. Unit Capacity Factor (Using DER Net) ............ 104.0% 101.9% 63.8%
23. Unit Forced Outage Rate ................................... 0.0% 2.0% 12.2%
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):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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  • UNIT SHUTDOWN AND POWER REDUCTION
  • Surry Monthly Operating Report No. 97-05 Page 5 of 18 (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: May, 1997 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 06-04-97 Completed by: M. J. Fanguy Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of -LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to Prevent Recurrence Down Rx 5/1/97 s 35.3 C NA NA NA NA Refueling Outage 5/4/97 s 26.6 B NA NA TA TRB Ramp unit off-line to perform a turbine balance shot from 28% / 170 MWe.

5/12/97 s 28.9 B NA NA TA TRB Ramp unit off-line to perform a turbine balance shot from 58% / 490 MWe.

(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)

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

REPORT MONTH: May, 1997 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 06-04-97 Completed by: M. J. Fanguy Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to Prevent Recurrence Down Rx None During the Reporting Period (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 {LEA) File (NUREG 0161)

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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.

  • AVERAGE DAILY UNIT POWER LEVEL
  • Surry Monthly Operating Report No. 97-05 Page 8 of 18 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 06-03-97 Completed by: John D. Kilmer Telephone: (804) 365-2792 MONTH: May, 1997 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 817 17 821 2 819 18 823 3 810 19 823 4 818 20 823 5 825 21 822 6 825 22 823 7 824 23 823 8 822 24 815 9 822 25 774 10 821 26 822 11 823 27 822 12 829 28 823 13 823 29 823 14 823 30 817 15 823 31 815 16 823 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.

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  • Surry Monthly Operating Report No. 97-05 Page 9 of 18

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: May, 1997 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 0000 Unit 1 starts month at Hot Shutdown after refueling outage.

0958 Reactor critical.

05/02/97 0005 Unit is stable at 2% power.

1120 Unit is on-line.

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

05/03/97 2133 Stop power increase at 33% / 235 MWe.

05/04/97 0338 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.

05/05/97 0120 Unit is at 2%.

0729 Unit is on-line.

1510 Flux map performed at 50% power.

05/08/97 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.

05/12/97 0235 Commence power decrease to perform a turbine balance shot.

0640 Unit is off-line.

05/13/97 1137 Unit is on-line.

05/14/97 1820 Stop power increase at 98.25 / 845 MWe by management until power indication is adjusted.

05/16/97 1057 Commence power increase to 100% from 98.5% I 840 MWe.

1143 Unit is stable at 100% / 855 MWe.

05/31/97 2400 Unit 1 finishes the month at 100% 850 MWe.

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SUMMARY

OF OPERATING EXPERIENCE

  • Surry Monthly Operating Report No. 97-05 Page 10 of 18 MONTH/YEAR: May, 1997 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 0000 Unit 2 starts the month at 100% / 855 MWe.

05/24/97 2139 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.

05/25/97 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 Commence power increase to 100%.

2347 Stop power increase at 100% / 850 MWe.

05/31/97 2400 Unit 2 finishes the month at 100% / 850 MWe.

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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

  • Surry Monthly Operating Report No. 97-05 Page 11 of 18 MONTH/YEAR: May, .1997 SE 97-0011 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.

FS97-022 Updated Final Safety Analysis Report Change 5-12-97 (Safety Evaluation 97-071)

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.

TM S1-97-008 Temporary Modification 5-13-97 (Safety Evaluation No.97-072)

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.

TM-S 1-97-10 Temporary Modification 5-28-97 (Safety Evaluation 97-074)

  • 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.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

  • Surry Monthly Operating Report No. 97-05 Page 12 of 18 MONTHNEAR: May, 1997 DCP 95-035 Design Change Package 5-28-97 (Safety Evaluation 95-184)

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.

DCP 97-006 Design Change Package 5-28-97 (Safety Evaluation 97-061)

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.,.>*.

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  • PROCEDURE OR METHOD OF OPERATION CHANGES
  • Surry Monthly Operating Report No. 97-05 Page 13 of 18 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1997 1-0SP-EG-001 Operations Surveillance Procedure 5-2-97 1-MOP-EG-001 Maintenance Operating Procedure (Safety Evaluation 97-068)

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.

O-TMOP-Rl-3035 Temporary Maintenance Operating Procedure 5-8-97 (Safety Evaluation 97-069)

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.

1-IPT-CC-RC-F-435 Instrument Periodic Test Procedure 5-8-97 Rev5 (Safety Evaluation 97-070)

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.

  • PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL
  • Surry Monthly Operating Report No. 97-05 Page 14 of 18 MONTHNEAR: May, 1997 2-0P-RC-001 Operating Procedure 5-22-97 (Safety Evaluation 97-073)

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.

O-OP-VS-15 Operating Procedure 5-31-97 (Safety Evaluation 97-075)

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 No. 97-05 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: May, 1997 None During the Reporting Period
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  • Surry Monthly Operating Report No. 97-05 Page 16 of 18 CHEMISTRY REPORT MoNTHNEAR: May, 1997 Unit No. 1 Unit No. 2 Primary Coolant Analvsis Max. Min. Avg. Max. Min. Ava.

Gross Radioactivity, µCi/ml 3.51 E-1 1.21 E-3 2.07E-1 2.60E-1 1.59E-1 2.02E-1 Suspended Solids, ppm 0.025 0.025 0.025 - - -

Gross Tritium, µCi/ml 1.81E-1 5.93E-2 8.96E-2 4.42E-1 3.78E-1 4.19E-1 1131, µCi/ml 3.88E-4 8.74E-6 1.45E-4 6.48E-5 2.65E-5 4.98E-5 113111133 0.09 0.05 0.07 0.10 0.04 0.07 Hvdroaen, cc/ka 39.5 29.7 31.9 32.3 26.9 30.0 Lithium, oom 3.64 2.23 2.81 2.33 2.07 2.19 Boron - 10, oom* 380.6 258.5 312.1 132.5 114.1 123.0 Oxygen, (DO), ppm :o;0.005  :'>0.005  :'>0.005 :'>0.005  :'>0.005  :'>0.005 Chloride, oom 0.007 0.004 0.005 0.004 0.003 0.003 pH at 25 dearee Celsius 6.14 5.58 5.88 6.76 6.27 6.53 Boron - 1O = Total Boron x 0.196 Comments:

None

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

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  • Surry Monthly Operating Report No. 97-05 Page 18 of 18 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
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