ML18153A741

Monthly Operating Rept for July 1995 for Surry Power Station

ML18153A741
Person / Time
Site:	Surry
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)

Text

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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 15, 1995 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 MONTHL V OPERATING REPORT Serial No.95-409 NO/RPC:vlh Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of July 1995.

Very truly yo;~,/ J

/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',*

TABLE OF CONTENTS Section e Surry Monthly Operating Report No. 95-07 Page 2of 20 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............................................................................... 1 o 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.:

Date:

Completed By:

50-280 08-01-95 D. Mason Telephone:

(804) 365-2459 1. Unit Name:...................................................

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

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

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

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

6. Maximum Dependable Capacity (Gross MWe):....

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

Surry Unit 1 July, 1995 2441 847.5 788 820 781

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe):

1 O. Reasons For Restrictions, If Any:

This Month

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

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

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

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

.15.

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

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

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

18. Net Electrical Energy Generated (MWH)........

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

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

21.

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

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

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

744.0 744.0 0

744.0 0

1814287.8 592985.0 569999.0 100.0%

100.0%

98.1%

97.2%

0.0%

YID 5087.0 4907.7 0

4873.2 0

11801004.3 3946965.0 3802841.0 95.8%

95.8%

95.7%

94.9%

4.2%

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):

Cumulative 198167.0 135377.4 3774.5 133114.2 3736.2 310254743.5 101560798.0 96511864.0 67.2%

69.1%

62.8%

61.8%

16.3%

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

• • • .*4 OPERATING DATA REPORT e

Surry Monthly Operating Report No. 95-07 Page 4of 20 Docket No.:

Date:

Completed By:

50-281 08-01-95 D. Mason

1. Unit Name:....................*....*.........................

2. Reporting Period:...*......................................

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

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

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

6. Maximum Dependable Capacity (Gross MWe):....

7.

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

Surry Unit 2 July, 1995 2441 847.5 788 820 781 Telephone:

(804) 365-2459

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe):

1 0. Reasons For Restrictions, If Any:

This Month

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

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

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

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

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

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

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

18. Net Electrical Energy Generated (MWH)........

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

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

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

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

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

744.0 744.0 0

744.0 0

1815635.3 595545.0 574410.0 100.0%

100.0%

98.9%

98.0%

0.0%

YTD 5087.0 3842.6 0

3772.7 0

8975029.7 2979410.0 2871794.0 74.2%

74.2%

72.3%

71.6%

5.2%

Cumulative 195047.0 132180.1 328.1 130239.8 0

304243494.0 99421704.0 94464830.0 66.8%

66.8%

62.1%

61.5%

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):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED

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 (1)

(2)

(3)

(4)

(5)

Method Docket No.:

50-280 Unit Name: Surry Unit 1 Date: 08-03-95 Completed by: Craig Olsen Telephone:

(804) 365-2155 Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No.

Code Code Prevent Recurrence (1)

F:

Forced S: Scheduled (4)

(2)

REASON:

Down Rx None During the Reporting Period A -

Equipment Failure (Explain) 8 -

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 (LER) File (NUREG 0161)

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

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

REPORT MONTH: July, 1995 (2)

(3)

(5)

Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-03-95 Completed by: Craig Olsen Telephone:

(804) 365-2155 Duration Method of Reason Shutting Down Rx LER No.

(4)

System Code Component Cause & Corrective Action to Date Type Hours Code Prevent Recurrence (1)

F:

Forced S: Scheduled (4)

(2)

REASON:

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 (LER) File (NUREG 0161)

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

\\.

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.

MONTH:

July, 1995 Day 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 INSTRUCTIONS esurry Monthly Operating Report No. 95-07 Page Bot 20 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe-Net)

Day 777 17 780 18 780 19 780 20 778 21 778 22 776 23 777 24 777 25 778 26 777 27 778 28 778 29 777 30 771 31 773 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-01-95 Completed by: Barry C. Bryant Telephone: (804) 365-2786 Average Daily Power Level (MWe-Net) 772 772 771 768 769 770 768 765 763 764 763 764 766 765 761 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. 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 07/31/95.

UNIT TWO:

07/01/95 07/31/95 0000 The reporting period began with the unit operating at 100% power, 820 MWe.

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

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

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

DC-87-034-3 DR S-95-1244 DR S-95-1268 SE 95-075 SE 95-080 e Surry Monthly Operating Report No. 95-07 Page 10 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1995 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.

Deviation Reports 7-06-95 (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.

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.

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.

DC-91-031-3 DC-92-069-3 AC S2-95-0718 TM S2-95-10 e

Surry Monthly Operating Report No. 95-07 Page 11 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1995 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.

Design Change Package (Safety Evaluation No.94-031) 7-14-95 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.

Administrative Control Temporary Modification (Safety Evaluation No.95-082) 7-18-95 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.

DR S-95-1391 FS 95-14 SE 95-085 TM S1-95-09 e Surry Monthly Operating Report No. 95-07 Page 12 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1995 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.

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

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.

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

! I TM S1-95-08 TM S1-95-10 e Surry Monthly Operating Report No. 95-07 Page 13 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: July, 1995 Temporary Modifications (Safety Evaluation No.95-078) 7-28-95 Temporary Modifications (TM) S1-95-08 and S1-95-10 blocked the low flow trip signal to the 1 A 1 and 1 A2 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 (Safety Evaluation No.95-079) 7-11-95 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 No. 95-07 Page 15 of 20 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: July, 1995 None During the Reporting Period

Primary Coolant Analvsis Gross Radioactivitv, uCi/ml Suspended Solids, ppm Gross Tritium, uCi/ml 1131, uCi/ml 113111133 Hydrogen, cc/kg Lithium, oom Boron - 10, oom*

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

None CHEMISTRY REPORT MONTH/YEAR: July, 1995 Unit No. 1 Max.

Min.

Ava.

4;39E-1 2.28E-1 3.20E-1

.s.0.01

.s,0.01

.s,0.01 9.48E-2 5.73E-2 7.16E-2 7.59E-4 5.67E-4 6.57E-4 0.08 0.06 0.07 48.0 33.0 40.7 1.27 0.80 1.00 19.8 1.6 10.4

,::.0.005

.::;0.005

.::;0.005

_s0.050

,::.0.001 0.004 8.59 7.45 7.84 e Surry Monthly Operating Report No. 95-07 Page 16of 20 Unit No. 2 Max.

Min.

Avg.

2.04E-1 1.11E-1 1.71 E-1

.s,0.01

.s,0.01

.s.0.01 4.63E-1 3.51 E-1 4.03E-1 1.54E-4 8.30E-5 1.17E-4 0.10 0.05 0.08 47.9 35.4 41.9 2.33 2.08 2.21 187.6 176.0 184.6

,::.0.005

<0.005

<0.005

_s0.050 0.002 0.007 6.81 6.62 6.73

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

v New or Spent Fuel Shipment Number Unit 1 Batch 16 Shipment 4 (Continued)

Unit 1 Batch 16 Shipment 5 Unit 1 Batch 16 Shipment 6 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: July, 1995 Number of Date Stored or Assemblies Assembly ANSI Received eer Shiement Number Number 11A LM11H7 17A LM11HD 20A LM11HG 7/18/95 12 59A LM11JM 05A LM11H1 15A LM11HB 33A LM11HV 32A LM11HU 28A LM11HQ 29A LM11HR 25A LM11HM 30A LM11HS 31A LM11HT 37A LM11HZ 06A LM11H2 7/20/95 8

35A LM11HX 27A LM11HP 24A LM11HL 08A LM11H4 38A LM11JO 51A LM11JD e Surry Monthly Operating Report No. 95-07 Page 18of 20 New or Spent Initial Fuel Shipping Enrichment Cask Activit:t 3.8019 3.8108 3.8024 4.0017 14.58 3.8035 3.8095 3.8058 3.8036 3.8072 3.8064 3.8077 3.8002 3.8103 4.0026 3.8046 3.8119 9.75 3.8045 3.8062 3.6014 4.0062 4.0090

New or Spent Fuel Shipment Date Stored or Number Received Unit 1 Batch 16 Shipment 6 (Continued)

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