ML18152B572

Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr

ML18152B572
Person / Time
Site:	Surry
Issue date:	11/30/1998
From:	Ashley J, Pincus J, Stief R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
98-724, NUDOCS 9812210231
Download: ML18152B572 (19)

Text

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e e VIRGINIA ELECTRIC Al'ID POWER COMPANY RICHMOND, VIRGINIA 23261 December 14, 1998 United States Nuclear Regulatory Commission Serial No. 98~724 Attention: Document Control Desk SPS Lic/JSA 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 November 1998 is provided in the attachment.

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

Very truly yours, E. S. Grecheck, Site Vice President Surry Power Station Attachment Commitments made by this letter: None cc: U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, S. W.

Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Stationi , *. ~ P

( 9812210231 981130 ii '

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 98-11 Approved: ~~ Q - (;:2 ,,Hq,g

..'.-evicePresident Date

e Surry Monthly Operating Report No. 98-11 Page 2 of 18 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 Nos. 1 and 2 ............................................................................................. 9 Facility Changes That Did Not Require NRG Approval ............................................................................................ 11 Procedure or Method of Operation Changes That Did Not Require NRG Approval. ................................................ 14 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

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Surry Monthly Operating Report No. 98-11 Page 3 of 18 OPERATING DATA REPORT Docket No.: 50-280 Date: 12/03/98 Completed By: R. Stief Telephone: (757) 365-2486

1. Unit Name: ........................................................... Surry Unit 1

2. Reporting Period: ................................................ . November 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 720.0 8016.0 227400.0

12. Hours Reactor Was Critical 232.1 6546.7 160573.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 3774.5

14. Hours Generator On-Line 146.1 6427.0 158027.4

15. Unit Reserve Shutdown Hours 0.0 0.0 3736.2

16. Gross Thermal Energy Generated (MWH) 245387.7 16059355.7 372304371 .3

17. Gross Electrical Energy Generated (MWH) 75706.0 5324391.0 122140145.0

18. Net Electrical Energy Generated (MWH) 71919.0 5143534.0 116377755.0

19. Unit Service Factor 20.2% 80.1% 69.4%

20. Unit Availability Factor 20.2% 80.1% 71.1%

21. Unit Capacity Factor (Using MDC Net) 12.5% 80.1% 65.7%

22. Unit Capacity Factor (Using DER Net) 12.7% 81.4% 64.9%

23. Unit Forced Outage Rate 37.8% 7.6% 14.5%

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 e Surry Monthly Operating Report No. 98-11 Page 4 of 18 OPERATING DATA REPORT Docket No.: 50-281 Date: 12/03/98 Completed By: R. Stief Telephone: (757) 365-2486

1. Unit Name: ........................................................... Surry Unit 2

2. Reporting Period: ................................................ . November 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 720.0 8016.0 224281.0

12. Hours Reactor Was Critical 720.0 8016.0 159166.3

13. Reactor Reserve Shutdown Hours 0.0 *o.o 328.1

14. Hours Generator On-Line 720.0 8016.0 157149.5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1832936.7 20370118.5 371903685.8

17. Gross Electrical Energy Generated (MWH) 614975.0 6787245.0 121912853.0

18. Net Electrical Energy Generated (MWH) 595661.0 6564925.0 116208076.0

19. Unit Service Factor 100.0% 100.0% 70.1%

20. Unit Availability Factor 100.0% 100.0% 70.1%

21. Unit Capacity Factor (Using MDC Net) 103.3% 102.2% 66.2%

22. Unit Capacity Factor (Using DER Net) 105.0% 103.9% 65.8%

23. Unit Forced Outage Rate 0.0% 0.0% 11.4%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, April 19, 1999, 35 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

e Surry Monthly Operating Report No. 98-11 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: November 1998 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12/01/98 Completed by: J. R. Pincus Telephone: (757) 365-2863 (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 11/01/98 s 485H02M C 1 N/A N/A N/A Refueling Outage 11/22/98 F 62H25M A 3 S1-98-013-00 SB SG "B" Steam Generator High Level 11/26/98 F 26H27M A 2 S1-98-014-00 SJ FCV Flow Control Valve Failed Closed (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)

• e Surry Monthly Operating Report No. 98-11 Page6of18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: November 1998 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12/01 /98 Completed by: J. R. Pincus Telephone: (757) 365-2863 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 (NU REG 0161)

I

______J

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Surry Monthly Operating Report No. 98-11 Page 7 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12/03/98 Completed by: J. S. Ashley Telephone: (757) 365-2161 MONTH: November 1998 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (Mwe - Net) 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 132 6 0 22 30 7 0 23 0 8 0 24 32 9 0 25 322 10 0 26 487 11 0 27 0 12 0 28 431 13 0 29 754 14 0 30 806 15 0 16 0 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. 98-11 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12/03/98 Completed by: J. S. Ashley Telephone: (757) 365-2161 MONTH: November 1998 Average Daily Power Level Average Daily Power Level Day (Mwe - Net) Day (Mwe - Net) 829 17 824 2 829 18 824 3 830 19 825 4 831 20 825 5 830 21 826 6 832 22 825 7 832 23 824 8 832 24 824 9 828 25 826 10 828 26 827 11 829 27 824 12 828 28 826 13 828 29 826 14 827 30 827 15 828 16 827 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.

• e Surry Monthly Operating Report No. 98-11 Page 9 of 18

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: November 1998 The following chronological sequence by unit is a summary of operating experiences for this month that required load reductions or resulted in significant non-load related incidents.

UNIT ONE:

11/01/98 0000 Unit starts the month at 0% IO MWe due to Refueling Outage.

11/19/98 0354 Commenced reactor start-up.

11/19/98 0527 Reactor critical.

11/21/98 0502 Unit on-line, commenced ramp up.

11/21/98 0550 Stopped ramp, unit at 29% / 210 MWe.

11/22/98 0031 Clear for power increase > 30%.

11/22/98 0430 Reactor tripped.

11/23/98 1218 Commenced reactor start-up.

11/23/98 1346 Reactor critical.

11/24/98 1855 Unit on-line, commenced ramp up.

11/24/98 1945 Stopped ramp, unit at 30% / 217 MWe.

11/25/98 0305 Recommended ramp up, unit at 29% / 199 MWe.

11/25/98 0505 Stopped ramp, unit at 35% / 253 MWe.

11/25/98 0610 Recommenced ramp, unit at 35% / 253 MWe.

11/25/98 1445 Stopped ramp, unit at 54% I 415 MWe.

11/25/98 1820 Recommenced ramp, unit at 54% I 415 MWe.

11/26/98 0200 Stopped ramp, unit at 70% / 560 MWe.

11/26/98 1511 Recommenced ramp, unit at 68% / 571 MWe.

11/26/98 2108 Reactor tripped.

11/27/98 1439 Reactor critical.

11/27/98 2335 Unit on-line, commenced ramp up.

11/28/98 0017 Stopped ramp, unit at 30% / 210 MWe.

11/28/98 0027 Recommenced ramp, unit at 30% / 210 MWe.

11/28/98 0740 Stopped ramp, unit at 49.75% / 400 MWe.

11/28/98 0758 Unit at 50%, ramping up at 3% per hour.

11/28/98 2325 Stopped ramp, unit at 80% / 700 MWe.

11/29/98 0051 Recommenced ramp, unit at 80% / 700 MWe.

11/29/98 0411 Stopped ramp, unit at 90% / 770 MWe.

11/29/98 0659 Recommenced ramp, unit at 90% / 770 MWe.

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Surry Monthly Operating Report No. 98-11 Page 10 of 18

SUMMARY

OF OPERATING EXPERIENCE (CONTINUED)

MONTHNEAR: November 1998 UNIT ONE (CONTINUED}:

11/29/98 0824 Stopped ramp, unit at 94.5% / 810 MWe.

11/29/98 1255 Recommenced ramp, unit at 94.5% / 810 MWe.

11/29/98 1505 Stopped ramp, unit at 96% I 820 MWe.

11/29/98 1720 Commenced ramp down, unit at 96% I 820 MWe.

11/29/98 1940 Stopped ramp, unit at 90.2% / 785 MWe.

11/29/98 1945 Commenced ramp up, unit at 90.2% / 785 MWe.

11/29/98 2305 Stopped ramp, unit at 98.5% / 835 MWe.

11/30/98 2400 Unit finishes the month at 98.5% / 837 MWe.

UNIT TWO:

11/01/98 0000 Unit starts the month at 100% / 855 MWe.

11/30/98 2400 Unit finishes the month at 100% / 855 MWe.

• e Surry Monthly Operating Report No. 98-11 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November 1998 DCP 94-071 Design Change Package 11/03/98 (Safety Evaluation 94-051)

Design Change Package 94-071, "Condensate Polishing Setpoint Changes for Resin Regeneration/Surry/1 &2", added additional cation resin to the polishers for longer run time.

DCP 97-059 Design Change Package 11/11/98 (Safety Evaluation 98-051 Rev. 1)

Design Change Package 97-059, "CS CAT Supply Valves Replacement 01-CS-MOV-102A/B", eliminates the leakage of the Chemical Addition Tank (CAT) contents past the CAT isolation valves into the Containment Spray piping by replacing the valves with new ones.

DCP 98-007 Design Change Package 11/03/98 (Safety Evaluation 98-058, Rev. 1)

Design Change Package 98-007, "Containment Radiant Energy Shields", installs Marinite board and stainless steel in containment that either replaces or sheaths existing Thermo-Lag material to perform as radiant energy shields. The installation of the Marinite board and stainless steel will provide a noncombustible radiant energy shield in accordance with NRG requirements.

SE 98-076, Rev. 1 Safety Evaluation 11/14/98 JCO 97-006 set Compensatory Actions to provide additional monitoring of containment temperatures for indication of a possible fire due to a regulatory compliance issue regarding Thermo-lag radiant energy shields inside Unit 1 and 2 containments. Revision 1 of Safety Evaluation 98-076 addresses Revision 2 of JCO 97-006 which: (1) updates the status of the JCO in accordance with administrative procedures; (2) evaluates the discontinuance of the Unit 1 Compensatory Actions following implementation of Unit 1, DCP 98-007, which resolved the Thermo-lag regulatory compliance issue inside Unit 1 containment; and (3) evaluates continuance of the Unit 2 Compensatory Actions.

SE 98-103, Rev. 1 Safety Evaluation 11/05/98 A safety evaluation has been performed to determine whether an unreviewed safety question will result from the refueling and operation of Surry Unit 1 Cycle 16. Revision 1 of Safety Evaluation 98-103 accommodates the reevaluation performed for introducing an additional reconstituted assembly in the core - the present core loading already contains a reconstituted assembly at the core's center. Fuel inspection at the end of Cycle 15 identified a leaker among the once burned assemblies intended for re-use in Cycle 16. The failed assembly was reconstituted by replacing the failed fuel rod with a stainless steel filler rod.

The reevaluation shows the effect of this reconstitution is negligible.

Surry Monthly Operating Report No. 98-11 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: November 1998 TM S 1-98-020 Temporary Modifications 11/03/98 TM S1-98-021 (Safety Evaluation 98-114)

Temporary Modifications S 1-98-020 and S 1-98-021 were used to remove the containment sump pump discharge containment isolation trip valve actuators, one at a time, for maintenance and install electrical jumpers to allow operation of the containment sump pumps with the trip valve actuator removed.

DCP 98-069 Design Change Package 11/03/98 (Safety Evaluation 98-115)

Design Change Package 98-069, "Control Rod Drive Mechanism (CROM) Housing Leak Repair/Surry/Unit 1", describes the repairing of two reactor vessel head nozzle canopy seal weld leaks using Canopy Seal Clamp Assemblies (CSCA). CSCA is a permanent non-welded mechanical method of leak repair developed by ABB Combustion Engineering and has been fully tested at operating temperature, pressure and seismic conditions for nuclear power plant use.

TM S1-98-022 Temporary Modification 11/06/98 (Safety Evaluation 98-116)

The Primary Drain Transfer Tank (PDTI) Pressure Control Valve, 1-DG-PCV-100, has been noted to be difficult to open once closed due to plant conditions. Temporary Modification S1-98-022 was used to fail 1-DG-PCV-100 in the open position during Cold Shutdown or Refueling Shutdown in order to provide a flow path for Reactor Cooling System (RCS) loop drains to the PDTI. The TM was removed before unit start-up.

DCP 98-044 Design Change Package 11/13/98 (Safety Evaluation 98-118)

Design Change Package 98-044, Turbine Driven Auxiliary Feedwater Pump (TDAFWP)

Steam Supply Circuit Upgrade", modifies the TDAFWP circuit logic such that, when the pump is started by an automatic signal and the initiating signal is cleared, steam flow to the TDAFWP can only be stopped after the circuit is manually reset.

TM S1-98-023 Temporary Modification 11/17/98 (Safety Evaluation 98-121)

Temporary Modification S1-98-023 will be used during plant shutdown to bypass the bearing lift oil pressure anti-start interlock in the Main Turbine Turning Gear motor circuitry to allow periodic rotation of the turbine rotor using the turning gear.

TM S2-98-007 Temporary Modification 11/20/98 (Safety Evaluation 98-123)

Temporary Modification 82-98-007 is to disable a leaking thermal relief valve (RV) and install another RV at the vent valve on the discharge side of the Unit 2 Feedwater Heater.

ASME Code section VIII allows this change until the next available outage in which the defective RV shall be replaced.

e Surry Monthly Operating Report No. 98-11 Page 13 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November 1998 SE 98-124 Safety Evaluation 11/23/98 Safety Evaluation 98-124 evaluates the reduction in Containment wall thickness from that specified in UFSAR Section 15 while work is in process to remove and repair spalled/loose concrete from the Unit 2 Containment exterior wall.

TM S 1-98-024 Temporary Modifications 11/27/98 TM S 1-98-025 (Safety Evaluation 98-125)

Temporary Modifications S1-98-024 and S1-98-025 were used to bypass the bearing lift oil pressure anti-start interlock in the Main Turbine Turning Gear motor circuitry to allow periodic rotation of the turbine rotor using the turning gear.

e Surry Monthly Operating Report No. 98-11 Page 14 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: November 1998 1/2-0PT-FW-008 Operations Periodic Test Procedures 11/03/98 1/2-AP-21.01 Abnormal Procedures (Safety Evaluation 96-074, Rev. 1)

UFSAR Chapter 10.3.5, Condensate and Feedwater System specifies that the Auxiliary Feedwater (AFW) motor operated throttle valves are in full open position during normal operations. Operations Periodic Test Procedures 1/2-0PT-FW-008, "AFW Check Valve Test", were evaluated for unit operation with all six MOV's closed during the testing of AFW cross-connect capability to the other unit which was in cold shutdown or refueling mode.

Abnormal Procedures 1/2-AP-21.01 were evaluated for check valve back leakage concerns.

O-ECM-0103-02 Electrical Corrective Maintenance Procedure 11/10/98 (Safety Evaluation 98-117)

Electrical Corrective Maintenance Procedure, O-ECM-0103-02, "Station Battery UPS System Maintenance", was revised to connect a dummy load to the UPS for troubleshooting, periodic maintenance and testing. This is allowed during plant shutdown conditions or by entering the appropriate limiting condition for operation (LCO) time limit.

1-0P-RC-001 A Operations Procedure 11/14/98 (Safety Evaluation 98-119)

Loop "A" drain valve 1-RC-HCV-1557A is leaking by at a rate of 1.6 gpm to the Primary Drain Transfer Tank (POTT) which is not acceptable for long term unit operation. Operations Procedure 1-0P-RC-001A, "Reactor Coolant System Valve Alignment", was changed to continue Unit 1 operation with Loop 'A' drain valve manually isolated.

O-ECM-1401-02 Electrical Corrective Maintenance Procedure 11/19/98 (Safety Evaluation 98-122)

Electrical Corrective Maintenance Procedure, O-ECM-1401-02, "Emergency Operation of Charging Pump Component Cooling Water Motors", installs the TM to allow Operations to operate the Charging Pump CC Pumps by energizing the Motor Control Center breaker.

This provides additional detail for post Appendix R fire scenarios.

lturry Monthly Operating Report No. 98-11 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November 1998 None during the Reporting Period

e --urry Monthly Operating Report No. 98-11 Page 16 of 18 CHEMISTRY REPORT MONTHNEAR: November 1998 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. AvQ. Max. Min. AvQ.

Gross Radioactivity, µCi/ml 3.13E-1 7.73E-4 3.32E-2 1.82E-1 9.21 E-2 1.37E-1 Suspended Solids, ppm 0.250 s 0.010 0.064 - - -

Gross Tritium, µCi/ml 4.04E-2 3.07E-2 3.35E-2 5.41E-1 4.57E-1 5.05E-1 1131, µCi/ml 8.21 E-3 2.68E-5 4.79E-4 1.37E-4 3.27E-5 7.45E-5 113111133 - - - 0.09 0.03 0.05 HydroQen, cc/kQ 33.1 23.7 28.9 40.3 38.3 39.1 Lithium, ppm 3.59 s 0.10 2.77 2.25 1.96 2.12 Boron - 10, oom* 485.9 269.5 392.4 77.6 58.6 67.8 Oxygen, (DO), ppm 9.0 so.005 3.57 so.005 so.005 so.005 Chloride, ppm 0.038 s 0.001 0.008 0.004 s 0.001 0.002 pH @ 25 demee Celsius 6.30 4.35 4.98 7.27 6.59 6.96

• Boron - 10 = Total Boron x 0.196 Comments:

None

'turry Monthly Operating Report No. 98-11 Page 17 of 18 FUEL HANDLING UNITS 1&2 MONTH/YEAR: November 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

• - Surry Monthly Operating

. Report No. 98-11 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: November 1998 None during the Reporting Period