ML18153A295

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Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr
ML18153A295
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/31/1998
From: Marshall G, Mason D, Steinert J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
98-192, NUDOCS 9804170215
Download: ML18153A295 (18)
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Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April .8,1998 United States Nuclear Regulatory Commission Serial No.98-192 Attention: Document Control Desk SPS Lie/JCS RO 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 MONTHLY OPERATING REPORT The Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of March 1998, is provided in the attachment.

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

Very truly yours,

~~cc_

D. A. Christian, Site Vice President Attachment Commitments made by this letter: None cc: U.S. Nuclear Regulatory Commission I

Region II Atlanta Federal Center 61 Forsyth Street, S. W.

d._,

Suite 23T85 /*l'/7,'~. *l Atlanta, Georgia 30303 ~~ i;--*@"

Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station 9804170215 980331 PDR ADOCK 05000280 R PDR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 98-03 Approved:

Site Vice President Date I_

  • TABLE OF CONTENTS

-Surry Monthly Operating Report No. 98-03 Page 2 of 17 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 Nos. 1 and 2 ............................................................................................. 9 Facility Changes That Did Not Require NRG Approval ............................................................................................ 10 Procedure or Method of Operation Changes That Did Not Require NRG Approval ................................................. 13 Tests and Experiments That Did Not Require NRG Approval .................................................................................. 15 Chemistry Report ..................................................................................................................................................... 16 Fuel Handling - Unit Nos. 1 and 2 ............................................................................................................................ 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ....................................................................................................................... 18

-Surry Monthly Operating Report No. 98-03 Page 3 of 17 OPERATING DATA REPORT Docket No.: 50-280 Date: 04/02/98 Completed By: D. K. Mason Telephone: (757) 365-2459

1. Unit Name: ........................................................... . Surry Unit 1
2. Reporting Period: ................................................. . March, 1998
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 Year-To-Date Cumulative

11. Hours in Reporting Period 744.0 2160.0 221544.0
12. Hours Reactor Was Critical 493.9 1859.3 155885.1
13. Reactor Reserve Shutdown Hours 0.0 0.0 3774.5
14. Hours Generator On-Line 481.2 1839.5 153439.0
15. Unit Reserve Shutdown Hours 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) 1206302.9 4654401.7 360899417. 3
17. Gross Electrical Energy Generated (MWH) 403900.0 1559994.0 118375748.0
18. Net Electrical Energy Generated (MWH) 390464.0 1508543.0 112742764.0
19. Unit Service Factor 64.7% 85.2% 69.3%
20. Unit Availability Factor 64.7% 85.2% 70.9%
21. Unit Capacity Factor (Using MDC Net) 65.5% 87.2% 65.4%
22. Unit Capacity Factor (Using DER Net) 66.6% 88.6% 64.6%
23. Unit Forced Outage Rate 0.0% 3.0% 14.6%
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

- OPERATING DATA REPORT

-Surry Monthly Operating Report No. 98-03 Page 4 of 17 Docket No.: 50-281 Date: 04/02/98 Completed By: D. K. Mason Telephone: (757) 365-2459

1. Unit Name: ........................................................... . Surry Unit 2
2. Reporting Period: ................................................. . March, 1998
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:
11. Hours in Reporting Period 744.0 2160.0 218425.0
12. Hours Reactor Was Critical 744.0 2160.0 153310.3
13. Reactor Reserve Shutdown Hours 0.0 0.0 328.1
14. Hours Generator On-Line 744.0 2160.0 151293.5
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1891107.7 5495754.9 357029322.2
17. Gross Electrical Energy Generated (MWH) 633365.0 1842315.0 116967923.0
18. Net Electrical Energy Generated (MWH) 612967.0 1783495.0 111426646.0
19. Unit Service Factor 100.0% 100.0% 69.3%
20. Unit Availability Factor 100.0% 100.0% 69.3%
21. Unit Capacity Factor (Using MDC Net) 102.9% 103.1% 65.2%
22. Unit Capacity Factor (Using DER Net) 104.6% 104.8% 64.7%
23. Unit Forced Outage Rate 0.0% 0.0% 11.8%
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. 98-03 Page 5 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: March, 1998 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04/03/98 Completed by: G. N. Marshall Telephone: (757) 365-2465 (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 03/08/98 F 16h14m A N/A NONE LE FAN Broken iso-phase fan belt replaced 03/20/98 s 10d22h B 1 NONE N/A N/A Scheduled Preventive Maintenance Outage (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)

.urry Monthly Operating Report No. 98-03 Page 6 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL TO OR GREATER THAN 20%)

REPORT MONTH: March, 1998 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04/03/98 Completed by: G. N. Marshall Telephone: (757) 365-2465 (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 03/14/98 F 11 B N/A NONE SB V Freedom Valve Test (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)

eurry Monthly Operating Report No. 98-03 Page 7 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04/03/98 Completed by: J. C. Steinert Telephone: (757) 365-2834 MONTH: March, 1998 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 830 17 829 2 828 18 826 3 827 19 825 4 824 20 701 5 823 21 0 6 823 22 0 7 826 23 0 8 676 24 0 9 824 25 0 10 826 26 0 11 826 27 0 12 826 28 0 13 826 29 0 14 828 30 0 15 828 31 17 16 829 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.

.urry Monthly Operating Report No. 98-03 Page 8 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04/03/98 Completed by: John C. Steinert Telephone: (757) 365-2837 MONTH: March, 1998 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 828 17 829 2 829 18 828 3 826 19 825 4 825 20 825 5 824 21 817 6 826 22 821 7 826 23 822 8 825 24 828 9 824 25 825 10 825 26 827 11 826 27 822 12 826 28 821 13 827 29 822 14 791 30 822 15 829 31 821 16 828 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.

.urry Monthly Operating Report No. 98-03 Page 9 of 17

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: March, 1998 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:

03/01/98 0000 Unit 1 operating at 100%, 855 MWe.

03/08/98 0941 Commenced ramp down to self-cooling rating of iso-phase bus.

03/08/98 1246 Stopped ramp at 65%, 540 MWe.

03/08/98 2136 Commenced ramp up at 64%, 540 MWe.

03/09/98 0155 Unit 1 operating at 100%, 855 MWe.

03/20/98 1717 Commenced unit shutdown from 100%, 855 MWe.

03/20/98 2254 Unit off line. Reactor power 4%.

03/21/98 0259 Tripped main turbine.

03/21/98 0307 Manually tripped reactor.

03/31/98 1314 Reactor Critical 03/31/98 2141 Unit on line, commence ramp up.

03/31/98 2400 Unit 1 operating at 50% , 414 MWe.

UNIT Two:

03/01/98 0000 Unit 2 operating at 100%, 855 MWe.

03/14/98 0630 Commenced Ramp Down for Unit Freedom Valve Test 03/14/98 1216 Stopped ramp at 74%, 650 MWe 03/14/98 1313 Commenced ramp up 03/24/98 1530 Unit operating at 100%, 855 MWe 03/31/98 2400 Unit 2 operating at 100%, 855 MWe.

9surry Monthly Operating Report No. 98-03 Page 10 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1998 JCO SC-97-006 Justification for Continued Operation 03/26/98 (SE 97-0152 Rev. 1)

The purpose of this revision to the JCO is modify the method of monitoring eighteen containment Radiant Thermal Detectors (RTDs). The RTD high alarm limits will be set 15 degrees above the existing containment temperature. The revision provides the formal tracking mechanism and on shift training of Operations personnel to provide the necessary instructions for operator response to alarms received on the P-250 printer through operations procedures. The RTDs will be monitored and a weekly review of RTD temperatures will be performed in accordance with a periodic test for any temperature shifts. A design change will be completed for each unit during the next refueling outage to correct the radiant energy shield deficiency.

SE 98-0027 Safety Evaluation 03/05/98 The Safety Evaluation was performed because two heat trace circuits on Unit 1 had been inoperable for greater that thirty days due to a low wattage output ratio. One heat trace circuit is on the boron injection flow path and one is in the charging discharge flow path.

The heat trace circuits are designed to prevent solidification of boric acid in the associated piping and components by maintaining boric acid solution temperature at greater than technical specification limits. There are redundant heat trace circuits for the affected piping and they are verified operable daily by operator logs and a Main Control Room annunciator alarms whenever the temperature of the heat trace circuits are within the same temperature band as required by the logs.

FS 98-04 UFSAR Change Request 03/12/98 (Safety Evaluation No. 98-0029)

UFSAR Change Request FS 98-04 documents Quality Assurance (QA) Program organizational responsibilities for the Independent Spent Fuel Storage Installation (ISFSI) in Chapter 17. The changes to the UFSAR are administrative in nature and do not reduce the effectiveness of the QA Program or reduce commitments in the program.

FS97-044 UFSAR Change Request 03/12/98 (Safety Evaluation No. 98-0030)

UFSAR Change Request FS97-004 documents an alternative to ANSI/ANS 3.1 (Draft 12/79) by stating that the requalification training requirements for Shift Supervisor, Senior Reactor Operator, Reactor Operator, and Shift Technical Advisor, are located in Technical Specifications (TS). This change was made to ensure consistency between the Quality Assurance Topical Report and TS in stating that the above referenced requalification program is in accordance with 10CFR55.59(c).

FS 98-05 UFSAR Change Request 03/12/98 (Safety Evaluation No. 98-0031)

UFSAR Change Request FS 98-05 documents the elimination of the position of Supervisor Administrative Services from the QA Topical Report and administrative procedures. This change is administrative in nature and re-assignes the responsibilities of the eliminated position to other positions within the organization. This change does not reduce the commitments in the QA Program.

9surry Monthly Operating Report No. 98-03 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1998 FS 98-08 UFSAR Change Request 03/19/98 (Safety Evaluation No. 98-0033)

UFSAR Change Request 98-08 incorporates a sensitivity evaluation to Section 6.3 to account for the impact of flow through vents and drains in the Recirculation Spray (RS)

Subsystem. The evaluation of this change confirms the ability of the RS subsystems to meet the containment analysis acceptance criteria considering the flow diverted from the spray headers by the vents and drains while crediting expected RS subsystem flow. The safety evaluation assessed the effect of this change upon the existing accident analysis and accounts for the diverted flow impact until the flow through the vents and drains is reduced and Outside Recirculation Spray minimum flow is restored to the value explicitly used in the core uprate analysis.

TM S1-98-06 Temporary Modification 03/23/98 (Safety Evaluation No. 98-0034)

This Temporary Modification installs a jumper across the switch in the "C" service water line of the ultrasonic level sensors for the High Level screens. The purpose of the TM is to allow the alarm circuit to function for the remaining three lines thus allowing the Main Control Room to monitor the High Level screens with the "C" line out of service without having the indicator light locked in.

SE 98-0037 Safety Evaluation 03/24/98 Safety Evaluation 98-0037 was performed because one heat trace circuit on Unit 2 had been inoperable for greater that thirty days due to a low wattage output ratio. The heat trace circuit is on the boron injection flow path. The heat trace circuit is designed to prevent solidification of boric acid in the associated piping and components by maintaining boric acid solution temperature at greater than technical specification limits. There is a redundant heat trace circuit for the affected piping and it is verified operable daily by operator logs. A Main Control Room annunciator alarms whenever the temperature of the heat trace circuits are not within the temperature band required by technical specification.

SE 98-0038 Safety Evaluation 03/24/98 Safety Evaluation 98-0038 documents how the fire barriers separating the Unit 1and Unit 2 Normal Switchgear Rooms (NSGRs) from their respective Mechanical Equipment Rooms (MERs) are adequate as they exist with ventilation dusts between the two areas not completely sealed. The evaluation will also be added to Chapter 1O of the Appendix R Report. The evaluation was performed in accordance with Generic Letter 86-10, Interpretation #4, allowing engineering evaluations of fire area boundaries. The NSGRs both contain smoke detectors for early warning of fires the annunciate in the Main Control Room and each area is equipped with a total flooding CO 2 system. The MERs are large open areas with a limited amount of combustibles. If a fire were to occur in the MERs, it would not be expected to impinge on the ventilation duct penetrations due to the limited amount of combustibles in the room, the lack of combustibles in the pipe chase, and the open room design would dissipate the heat quickly.

9surry Monthly Operating Report No. 98-03 Page 12 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March, 1998 TM S1-98-07 Temporary Modification 03/26/98 (SE 98-0040)

TM S1-98-07 installed a seal weld plug in a leaking reactor coolant pump Resistance Temperature Detector (RTD) thermowell found during a scheduled maintenance outage.

The RTD was removed and the seal weld plug installed and will remain in place until a future refueling outage when it will be replaced with a wet RTD insert. Normal operating procedures were revised to provide guidance on available indications for pump bearing seal water temperature. The failure of the plug and weld are no different than those postulated for the failure of the thermowell and the potential bearing degradation as a result of a loss of seal cooling water flow. The condition is bounded by previous UFSAR analysis.

e Surry Monthly Operating Report No. 98-03 Page 13 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1998 1/2-LPT-FP-017 & 018 Loss Prevention Periodic Test Procedures 03/03/98 O-LPT-FP-010 & 022 (Safety Evaluation No. 98-0026)

O-LPT-FP-026 & 027 Loss Prevention Periodic Test Procedures 1/2-LPT-FP-017 & 018 "Emergency Switchgear Room Halon System," O-LPT-FP-101 & 022 "Fuel Oil Pump House High Pressure CO 2 System," and O-LPT-FP-026 & 027 "Emergency Service Water Diesel Fuel Oil Tank Room High Pressure CO 2 Sysyem," were permanently changed by adding a Temporary Modification to facilitate testing. The procedures will allow the lifting of the solenoid operating valves (SOV) from each pilot valve on the Halon gas* and CO 2 gas cylinders during testing thus preventing the trip of the systems and the release of suppression gas into the affected area.

O-LSP-FP-010 & 011 Loss Prevention Surveillance Procedures 03/24/98 O-LSP-FP-029 & 030 (Safety Evaluation No. 98-0036)

O-LSP-FP-033 & 034 O-LSP-FP-035 & 036 O-LSP-FP-038 & 039 O-LSP-FP-042 PT-24.35 Loss Prevention Surveillance Procedures O-LSP-FP-010 & 011 "Administrative Building High Pressure CO 2 System," O-LSP-FP-029 & 030 "Training Center Computer Room Halon System," and O-LSP-FP-033 & 034 "Training Center Simulator Halon System," O-LSP-FP-035 & 036 "Security Halon System," O-LSP-FP-038 & 039 "LEOF Halon System," O-LSP-FP-042 "TSC Vent Filters High Pressure CO 2 System," and O-PT-24.35 "TSC Vent Filter Test,"

were permanently changed by adding a Temporary Modification to facilitate testing. The procedures will allow the lifting of the solenoid operating valves (SOV) from each pilot valve on the Halon gas and CO 2 gas cylinders during testing thus preventing the inadvertent trip of the systems and the release of suppression gas into the affected area.

GOP-1.1 General Operating Procedure 03/27/98 (Safety Evaluation 98-0041)

General Operating Procedure 1-GOP-1.1 "Unit Startup, RCS Heat-up From Ambient to 190° F," was revised to procedurally control a temporary modification to allow the installation and removal of a Passive Autocatalytic Recombiner (PAR) in Unit 1 containment. The PAR will be used and the current method of "feed and bleed" using the containment vacuum pumps will remain available for the control of the hydrogen concentration in containment.

1-TMOP-RH-3047 Temporary Maintenance Operating Procedure (Safety Evaluation 98-0042)

Temporary Maintenance Operating Procedure 1-TMOP-RH-3047 "Draining and Flushing the RHR System," was developed to procedurally control the temporary installation of a hose between the containment Nitrogen Header and the Residual Heat Removal System (RHR).

The nitrogen gas will be used to assist in draining the RHR system while precluding the introduction of oxygen in the RHR and Reactor Coolant Systems (RCS). The RHR system will be isolated from the RCS and declared inoperable for the evolution and pressure will be controlled at less than 100 psig.

tlurry Monthly Operating Report No. 98-03 Page 14 of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1998 None During the Reporting Period

e 9urry Monthly Operating Report No. 98-03 Page 15 of 17 CHEMISTRY REPORT MONTH/YEAR: March, 1998 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Avg.

Gross Radioactivity, µCi/ml 5.20E-1 1.90E-2 2.44E-1 2.17E-1 1.12E-1 1.66E-1 Suspended Solids, ppm 0.500 ~0.010 0.17 ~0.010 ~0.001 ~0.001 Gross Tritium, µCi/ml 3.79E-1 3.43E-1 3.60E-1 8.65E-1 8.21 E-1 8.48E-1 1131, µCi/ml 2.01 E-1 6.95E-4 1.55E-2 5.39E-5 2.59E-5 4.27E-5 113111133 0.23 0.11 0.15 0.10 0.05 0.08 Hydrogen, cc/kg 33.0 0.8 12.1 40.2 31.6 35.1 Lithium, ppm 2.42 1.31 2.06 2.34 2.06 2.21 Boron - 10, ppm* 324.2 108.4 228.8 214.4 200.7 208.4 Oxygen, (DO), ppm 0.200 ~0.005 0.012 ~0.005 ~0.005 ~0.005 Chloride, ppm ~0.050 0.002 0.007 0.005 0.005 0.005 pH at 25 degree Celsius 6.99 6.08 6.59 6.68 6.48 6.56 Boron - 10 = Total Boron x 0.196 Comments:

None

9urry Monthly Operating Report No. 98-03 Page 16 of 17 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: March, 1998 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 None During the Reporting Period

. . r r y Monthly Operating Report No. 98-03 Page 17 of 17 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: March, 1998 None During the Reporting Period

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