ML18153A741

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Monthly Operating Rept for July 1995 for Surry Power Station.W/950815 Ltr
ML18153A741
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/31/1995
From: Kansler M, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-409, NUDOCS 9508230137
Download: ML18153A741 (21)
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.' . e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 15, 1995 United States Nuclear Regulatory Commission Serial No.95-409 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHL V OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of July 1995.

Very yo;~,/ J truly

/Jll/?/4~

M;Jl. ~ansler Vice p/esident - Nuclear Services 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 9508230137 950731 PDR ADOCK 05000280 R PDR

. '. e e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 95-07 Approved:

Station Manager

i',*

e Surry Monthly Operating Report No. 95-07 Page 2of 20 TABLE OF CONTENTS Section Page

  • operating Data Report - Unit No. 1 .........................................................................................................3 Operating Data Report - Unit No. 2 ......................................................................*....................**............ 4 Unit Shutdowns* and Power Reductions - Unit No. 1.................................................................................... 5 Unit Shutdowns and Power Reductions - Unit No. 2 .................................................................................... 6 Average Daily Unit Power Level - Unit No. 1.......... :................................................................................... 7 Average Daily Unit Power Level - Unit No. 2 .............................................................. ,............................... 8 Summary of Operating Experience - Unit No. 1 ......................................................................................... 9 Summary of Operating Experience - Unit No. 2 ............. : ........................................................................... 9 Facility Changes That Did Not Require NRC Approval. .............................................................................. 1o Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 14 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 Lirriits Specified in Technical Specifications ................................................................................................... 20

e Surry Monthly Operating Report No. 95-07 Page 3of 20 OPERATING DATA REPORT Docket No.: 50-280 Date: 08-01-95 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . July, 1995
3. Licensed Thermal Power (MWt): ...................... . 2441
4. Nameplate Rating (Gross MWe): ..................... .. 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 820
7. Maximum Dependable Capacity (Net MWe): ...... .. 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):

1O. Reasons For Restrictions, If Any:

This Month YID Cumulative

11. Hours In Reporting Period ......................... . 744.0 5087.0 198167.0
12. Number of Hours Reactor Was Critical ........ .. 744.0 4907.7 135377.4
13. Reactor Reserve Shutdown Hours .............. . 0 0 3774.5
14. Hours Generator On-Line .......................... . 744.0 4873.2 133114.2

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

16. Gross Thermal Energy Generated (MWH) .... .. 1814287.8 11801004.3 310254743.5
17. Gross Electrical Energy Generated (MWH) ... . 592985.0 3946965.0 101560798.0
18. Net Electrical Energy Generated (MWH) ...... .. 569999.0 3802841.0 96511864.0
19. Unit Service Factor ................................. .. 100.0% 95.8% 67.2%
20. Unit Availability Factor.............................. . 100.0% 95.8% 69.1%
21. Unit Capacity Factor (Using MDC Net).......... . 98.1% 95.7% 62.8%
22. Unit Capacity Factor (Using DER Net) .......... . 97.2% 94.9% 61.8%
23. Unit Forced Outage Rate ........................... . 0.0% 4.2% 16.3%
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

      • .*4 e Surry Monthly Operating Report No. 95-07 Page 4of 20 OPERATING DATA REPORT Docket No.: 50-281 Date: 08-01-95 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: ....................*....*......................... Surry Unit 2
2. Reporting Period: ...*...................................... July, 1995
3. Licensed Thermal Power (MWt): **..................... 2441
4. Nameplate Rating (Gross MWe):...................... . 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 820
7. Maximum Dependable Capacity (Net MWe): ....... . 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period ......................... . 744.0 5087.0 195047.0
12. Number of Hours Reactor Was Critical ......... . 744.0 3842.6 132180.1
13. Reactor Reserve Shutdown Hours .............. . 0 0 328.1
14. Hours Generator On-Line ..*........................ 744.0 3772.7 130239.8
15. Unit Reserve Shutdown Hours .................... . 0 0 0
16. Gross Thermal Energy Generated (MWH) ..... . 1815635.3 8975029.7 304243494.0
17. Gross Electrical Energy Generated (MWH) ... . 595545.0 2979410.0 99421704.0
18. Net Electrical Energy Generated (MWH) ....... . 574410.0 2871794.0 94464830.0
19. Unit Service Factor .................................. . 100.0% 74.2% 66.8%
20. Unit Availability Factor.............................. . 100.0% 74.2% 66.8%
21. Unit Capacity Factor (Using MDC Net).......... . 98.9% 72.3% 62.1%
22. Unit Capacity Factor (Using DER Net) .......... . 98.0% 71.6% 61.5%
23. Unit Forced Outage Rate ........................... . 0.0% 5.2% 13.1%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25. If Shut Down at End of Report Period, Estimated Date of Start-up:
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 95-07 Page 5 of 20 UNIT SHUTDOWN AND POWER REDUCTION

{EQUAL To OR GREATER THAN 20%)

REPORT MONTH: July, 1995 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-03-95 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx None During the Reporting Period (1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual 8 - Maintenance or Test 2 - Manual Scram.

C*- Refueling 3 - Automatic Scram.

D - Regulatory Restriction 4 - Other (Explain)

E - Operator Training & Licensing Examination F - Administrative G - Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

e Surry Monthly Operating Report No. 95-07 Page 6 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EaUAL To OR GREATER THAN 20%)

REPORT MONTH: July, 1995 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-03-95 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 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 (LER) File (NUREG 0161)

\.

e Surry Monthly Operating Report No. 95-07 Page ?of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-01-95 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: July, 1995 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 778 17 764 2 779 18 762 3 780 19 762 4 779 20 762 5 778 21 762 6 775 22 763 7 776 23 760 8 755 24 757 9 777 25 755 10 772 26 755 11 772 27 756 12 773 28 757 13 772 29 758 14 770 30 755 15 768 31 752 16 765 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.

esurry Monthly Operating Report No. 95-07 Page Bot 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-01-95 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: July, 1995 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 1 777 17 772 2 780 18 772 3 780 19 771 4 780 20 768 5 778 21 769 6 778 22 770 7 776 23 768 8 777 24 765 9 777 25 763 10 778 26 764 11 777 27 763 12 778 28 764 13 778 29 766 14 777 30 765 15 771 31 761 16 773 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.

'\ .. ,,*.

  • .Surry Monthly Operating Report No. 95-07 Page 9of 20

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: July, 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:

07/01/95 0000 The reporting period began with the unit operating at 100% power, 820 MWe.

07/31/95. 2400 The reporting period ended with the unit operating at 100% power, 790 MWe.

UNIT TWO:

07/01/95 0000 The reporting period began with the unit operating at 100% power, 820 MWe.

07/31/95 2400 The reporting period ended with the unit operating at 100% power, 795 MWe.

e Surry Monthly Operating Report No. 95-07 Page 10 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1995 DC-87-034-3 Design Change Package 7-05-95 Design Change Package 87-034-3 replaced existing safety-related service water piping and valves due to biological fouling, sedimentation entrainment, and erosion.

The replacement components have superior pressure, temperature, and corrosion resistant properties and do not impact the function or operation of the Service Water System. Therefore, an unreviewed safety question does not exist.

DR S-95-1244 Deviation Reports 7-06-95 DR S-95-1268 (Safety Evaluation No.95-074)

Safety Evaluation 95-074 assessed Deviation Reports S-95-1244 and S-95-1268 concerning the loss of capability to obtain a sample from the Unit 1 pressurizer relief tank vapor space due to an inoperable sampling line.

The evaluation concluded that this condition is acceptable since there are alternate means of sampling the Reactor Coolant System (RCS). Compliance with Technical Specification sampling surveillance requirements continues to be maintained using routine samples obtained from the RCS Letdown Subsystem. Therefore, an unreviewed safety question does not exist.

SE 95-075 Safety Evaluation 07-06-95 Safety Evaluation 95-075 assessed the impact of an inoperable meteorological monitoring recorder for "Wind Speed Lower" in the main control room.

The evaluation concluded that this condition is acceptable since an alternate means of monitoring "Wind Speed Lower" is available in the main control room. Furthermore, the ability to obtain wind speed values is not impacted by this recorder being inoperable.

Therefore, an unreviewed safety question does not exist.

SE 95-080 Safety Evaluation 7-12-95 Safety Evaluation 95-080 assessed the impact of temporarily removing fuses for the A, B, and C Steam Generator Level Protection Channel Ill signal comparators. Removal of the fuses prevents spurious control room alarms during the performance of channel calibration and functional testing.

Only one protection channel at a time is removed from service for testing as allowed by Technical Specifications. Thus 2 of 3 steam generator level protection channels remain operable to initiate the design protective action, if required. In addition, adequate procedural guidance is provided to assure the restoration of the initial conditions, including requirements for independent verification and appropriate notifications.

Therefore, an unreviewed safety question does not exist.

'"*" e Surry Monthly Operating Report No. 95-07 Page 11 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1995 DC-91-031-3 Design Change Package 7-13-95 Design Change Package 91-031-3 installed flow limiting spray shields on the expansion joints downstream of the motor-operated isolation valves that supply service water to the bearing and component cooling heat exchangers. Closure plates were also installed around the 96 inch expansion joint shields located at the condenser outlets.

These modifications were implemented in order to protect the Emergency Switchgear Room (ESGR) and the Turbine Building valve pits from potential flooding as a result of a Service Water system pipe rupture. Installation of these modifications satisfies an Individual Plant Evaluation flooding concern, which is not a station design basis event.

Therefore, an unreviewed safety question does not exist.

DC-92-069-3 Design Change Package 7-14-95 (Safety Evaluation No.94-031)

Design Change Package 92-069-3 replaced the solenoid-operated valves (SOV) which vent the actuator dome of the main feedwater regulating valves (MFRV) upon a closure signal.

The replacement SOVs have a larger orifice which vents the actuator dome more quickly, allowing the MFRVs to close faster. The instrument air supply header tubing lines were also enlarged to ensure an adequate supply of air is available to the MFRVs. These modifications improved the control and closure response time of the MFRVs which will help mitigate an excessive cooldown of the Reactor Coolant system upon a MFRV isolation signal. Therefore, an unreviewed safety question does not exist.

AC S2-95-0718 Administrative Control TM S2-95-10 Temporary Modification 7-18-95 (Safety Evaluation No.95-082)

Temporary Modification (TM) S2-95-10 installed an electrical jumper to prevent the Component Cooling (CC) excess letdown control valve 2-CC-HCV-208 from closing during the replacement of a field bus module.

Administrative control of the CC thermal barrier discharge trip valves was established since the removal of the field bus module defeated the high flow trip function of these valves. The trip valves were controlled by a licensed operator who was capable of closing the applicable thermal barrier trip valve if a high flow condition was noted across either loop. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 95-07 Page 12 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1995 DR S-95-1391 Deviation Report 7-20-95 (Safety Evaluation No.95-083)

Safety Evaluation 95-083 assessed Deviation Report S-95-1391 concerning the loss of capability to obtain a sample from the Unit 2 pressurizer vapor space due to an inoperable sampling line.

The evaluation concluded that this condition is acceptable since there are alternate means of sampling the Reactor Coolant System (RCS). Compliance with Technical Specification sampling surveillance requirements continues to be maintained using routine samples obtained from the RCS Letdown Subsystem. Therefore, an unreviewed safety question does not exist.

FS 95-14 Updated Final Safety Analysis Report Change 7-20-95 (Safety Evaluation No. 95-084A)

UFSAR Change 95-14 revised Section 6.2.4.1.4, "[Safety Injection System] Normal Operation [Tests and Inspections)," to correctly reflect the operational status of the low head safety injection and outside recirculation spray pumps' suction lines between the containment sump and the valve pit.

This change was administrative in nature and had no material impact on plant equipment, operation, inspection, or testing. Therefore, an unreviewed safety question does not exist.

SE 95-085 Safety Evaluation 07-22-95 Safety Evaluation 95-085 assessed the removal of Unit 1 Annunciator Panels "A" through "E" from service to allow troubleshooting and repair of the system.

The instrument channels associated with the affected annunciators remained operable.

Alternate indications were used and increased monitoring was performed. The work activities involved the nonsafety-related annunciator logic panel and did not affect any protection circuit. Therefore, an unreviewed safety question does not exist.

TM S1-95-09 Temporary Modification 7-25-94 (Safety Evaluation No.95-084)

Temporary Modification (TM) S1-95-09 defeated the speed adjustment circuit of Hydro Test Pump 1-SI-P-2 until replacement parts can be procured. The pump was set at a fixed speed that is capable of supporting accumulator operations.

The TM did not negatively impact the performance of the hydro test pump or the Safety Injection system. No fission product barriers or safety-related systems were affected.

Therefore, an unreviewed safety question does not exist.

e I ***

Surry Monthly Operating Report No. 95-07 Page 13 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: July, 1995 TM S1-95-08 Temporary Modifications 7-28-95 TM S1-95-10 (Safety Evaluation No.95-078)

Temporary Modifications (TM) S1-95-08 and S1-95-10 blocked the low flow trip signal to the 1A 1 and 1A2 Feedwater Pump motors during the repair of valve 1-FW-129.

The TMs did not affect any other feedwater pump manual or automatic control functions.

No Consequence Limiting Safeguards, Reactor Protection, or Engineered Safeguards Features circuits were affected. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 95-07 Page 14of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1995 Operational Quallty Assurance Program Topical Report 7-11-95 (Safety Evaluation No.95-079)

The Operational Quality Assurance Program Topical Report was revised to reflect Technical Specification Amendment 197 regarding the review of safety evaluations by the Management Safety Review Committee and the review of procedure changes and revisions by the Station Nuclear Safety and Operating Committee.

The changes are administrative or editorial in nature. They have no material impact on plant equipment, operation, inspection, or testing and do not affect the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL No. 95-07 Page 15 of 20 MONTH/VEAR: July, 1995 None During the Reporting Period
  • e Surry Monthly Operating Report No. 95-07 Page 16of 20 CHEMISTRY REPORT MONTH/YEAR: July, 1995 Unit No. 1 Unit No. 2 Primary Coolant Analvsis Max. Min. Ava. Max. Min. Avg.

Gross Radioactivitv, uCi/ml 4;39E-1 2.28E-1 3.20E-1 2.04E-1 1.11E-1 1.71 E-1 Suspended Solids, ppm .s.0.01 .s,0.01 .s,0.01 .s,0.01 .s,0.01 .s.0.01 Gross Tritium, uCi/ml 9.48E-2 5.73E-2 7.16E-2 4.63E-1 3.51 E-1 4.03E-1 1131, uCi/ml 7.59E-4 5.67E-4 6.57E-4 1.54E-4 8.30E-5 1.17E-4 113111133 0.08 0.06 0.07 0.10 0.05 0.08 Hydrogen, cc/kg 48.0 33.0 40.7 47.9 35.4 41.9 Lithium, oom 1.27 0.80 1.00 2.33 2.08 2.21 Boron - 10, oom* 19.8 1.6 10.4 187.6 176.0 184.6 Oxygen, (DO), ppm ,::.0.005 .::;0.005 .::;0.005 ,::.0.005 <0.005 <0.005 Chloride, ppm _s0.050 ,::.0.001 0.004 _s0.050 0.002 0.007 oH at 25 deoree Celsius 8.59 7.45 7.84 6.81 6.62 6.73

None

  • FUEL HANDLING UNITS 1 & 2 e Surry Monthly Operating Report No. 95-07 Page 17of 20 MONTH/YEAR: July, 1995 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received eer Shiement Number Number Enrichment Cask Activi!X New Fuel Unit 1 Batch 16 Shipment 3 7/11/95 12 10A LM11H6 3.8012 14.6 Ci 01A LM11GX 3.8106 23A LM11HK 3.8068 14A LM11HA 3.8024 12A LM11H8 3.8015 13A LM11H9 3.8013 07A LM11H3 3.8038 61A LM11JP 3.9998 04A LM11HO 3.7996 18A LM11HE 3.8094 62A LM11JQ 4.0053 64A LM11JS 4.0040 Unit 1 Batch 16 Shipment 4 7/13/95 12 19A LM11HF 3.8151 14.75 22A LM11HJ 3.8066 48A LM11JA 4.0060 52A LM11JE 4.0081 16A LM11HC 3.8079 26A LM11HN 3.8071 44A LM11J6 4.0105 42A LM11J4 4.0109 21A LM11HH 3.8066

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  • FUEL HANDLING UNITS 1 & 2 e Surry Monthly Operating Report No. 95-07 Page 18of 20 MONTH/YEAR: July, 1995 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received eer Shiement Number Number Enrichment Cask Activit:t Unit 1 Batch 16 Shipment 4 (Continued) 11A LM11H7 3.8019 17A LM11HD 3.8108 20A LM11HG 3.8024 Unit 1 Batch 16 Shipment 5 7/18/95 12 59A LM11JM 4.0017 14.58 05A LM11H1 3.8035 15A LM11HB 3.8095 33A LM11HV 3.8058 32A LM11HU 3.8036 28A LM11HQ 3.8072 29A LM11HR 3.8064 25A LM11HM 3.8077 30A LM11HS 3.8002 31A LM11HT 3.8103 37A LM11HZ 4.0026 06A LM11H2 3.8046 Unit 1 Batch 16 Shipment 6 7/20/95 8 35A LM11HX 3.8119 9.75 27A LM11HP 3.8045 24A LM11HL 3.8062 08A LM11H4 3.6014 38A LM11JO 4.0062 51A LM11JD 4.0090

e Surry Monthly Operating Report No. 95-07 Page 19 of 20 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: July, 1995 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity Unit 1 Batch 16 Shipment 6 (Continued) 34A LM11HW 3.8019 36A LM11HY 3.8102

e e Surry Monthly Operating Report No. 95-07 Page 20 of 20 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: July, 1995 None During the Reporting Period

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