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 S, PINCUS J R, 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

.. ( e e VIRGINIA ELECTRIC Al'ID POWER COMPANY RICHMOND, VIRGINIA 23261 December 14, 1998 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 MONTHLY OPERATING REPORT Serial No. SPS Lic/JSA Docket Nos. License Nos. 98~724 RO 50-280 50-281 DPR-32 DPR-37 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 ' PDR ADOCK 05000280 r(-R

• PDR \~

.. ' ' VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 98-11 Approved: Q -(;:2 ,,Hq,g .. '.-evicePresident Date e TABLE OF CONTENTS Section Surry Monthly Operating Report No. 98-11 Page 2 of 18 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

1. 2. 3. 4. 5. 6. 7. OPERATING DATA REPORT e . Surry Monthly Operating Report Docket No.: Date: No. 98-11 Page 3 of 18 Completed By: 50-280 12/03/98 R. Stief Unit Name: .......................................................... . Reporting Period: ................................................ . Licensed Thermal Power (MWt): ......................... . Nameplate Rating (Gross MWe): ........................ . Design Electrical Rating (Net MWe): ................... . Maximum Dependable Capacity (Gross MWe): .. . Maximum Dependable Capacity (Net MWe): ...... . Surry Unit 1 November 1998 2546 847.5 788 840 801 Telephone:

(757) 365-2486 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 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED

1. 2. 3. 4. 5. 6. 7. e OPERATING DATA REPORT e Surry Monthly Operating Report No. 98-11 Page 4 of 18 Docket No.: Date: Completed By: 50-281 12/03/98 R. Stief Unit Name: .......................................................... . Reporting Period: ................................................ . Licensed Thermal Power (MWt): ......................... . Nameplate Rating (Gross MWe): ........................ . Design Electrical Rating (Net MWe): ................... . Maximum Dependable Capacity (Gross MWe): .. . Maximum Dependable Capacity (Net MWe): ...... . Surry Unit 2 November 1998 2546 847.5 788 840 801 Telephone:

(757) 365-2486 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

11. Hours in Reporting Period 720.0 8016.0 12. Hours Reactor Was Critical 720.0 8016.0 13. Reactor Reserve Shutdown Hours 0.0 *o.o 14. Hours Generator On-Line 720.0 8016.0 15. Unit Reserve Shutdown Hours 0.0 0.0 16. Gross Thermal Energy Generated (MWH) 1832936.7 20370118.5

17. Gross Electrical Energy Generated (MWH) 614975.0 6787245.0

18. Net Electrical Energy Generated (MWH) 595661.0 6564925.0

19. Unit Service Factor 100.0% 100.0% 20. Unit Availability Factor 100.0% 100.0% 21. Unit Capacity Factor (Using MDC Net) 103.3% 102.2% 22. Unit Capacity Factor (Using DER Net) 105.0% 103.9% 23. Unit Forced Outage Rate 0.0% 0.0% 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 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED Cumulative 224281.0 159166.3 328.1 157149.5 0.0 371903685.8 121912853.0 116208076.0 70.1% 70.1% 66.2% 65.8% 11.4%

e Surry Monthly Operating Report No. 98-11 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) (1) Date Type 11/01/98 s 11/22/98 F 11/26/98 F (1) F: Forced S: Scheduled (4) REPORT MONTH: November 1998 (2) Duration Hours Reason 485H02M C 62H25M A 26H27M A (2) REASON: (3) Method of LER No. Shutting Down Rx 1 N/A 3 S1-98-013-00 2 S1-98-014-00 A -Equipment Failure (Explain)

B Maintenance or Test C Refueling D Regulatory Restriction (4) System Code N/A SB SJ 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 (NU REG 0161) Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12/01/98 Completed by: J. R. Pincus Telephone:

(757) 365-2863 (5) Component Code N/A SG FCV (3) METHOD: 1 -Manual Cause & Corrective Action to Prevent Recurrence Refueling Outage "B" Steam Generator High Level Flow Control Valve Failed Closed 2 -Manual Scram 3 -Automatic Scram 4 -Other (Explain)

(5) Exhibit 1 -Same Source

• e Surry Monthly Operating Report No. 98-11 Page6of18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) (1) F: Forced S: Scheduled (4) REPORT MONTH: November 1998 None during the Reporting Period (2) REASON: 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 (NU REG 0161) Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12/01 /98 Completed by: J. R. Pincus Telephone:

(757) 365-2863 (3) METHOD: 1 -Manual 2 -Manual Scram 3 -Automatic Scram 4 -Other (Explain)

(5) Exhibit 1 -Same Source I ______J MONTH: November 1998 Day 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS

• AVERAGE DAILY UNIT POWER LEVEL e . Surry Monthly Operating Report Docket No.: 50-280 No. 98-11 Page 7 of 18 Unit Name: Surry Unit 1 Date: 12/03/98 Completed by: J. S. Ashley Telephone:

(757) 365-2161 Average Daily Power Level Average Daily Power Level (MWe -Net) Day (Mwe -Net) 0 17 0 0 18 0 0 19 0 0 20 0 0 21 132 0 22 30 0 23 0 0 24 32 0 25 322 0 26 487 0 27 0 0 28 431 0 29 754 0 30 806 0 0 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: November 1998 Day 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS

• Surry Monthly Operating Report No. 98-11 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (Mwe -Net) 829 829 830 831 830 832 832 832 828 828 829 828 828 827 828 827 Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12/03/98 Completed by: J. S. Ashley Telephone:

(757) 365-2161 Average Daily Power Level (Mwe -Net) 824 824 825 825 826 825 824 824 826 827 824 826 826 827 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.

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR:

November 1998 e Surry Monthly Operating Report No. 98-11 Page 9 of 18 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.

UNIT ONE (CONTINUED}:

11/29/98 11/29/98 11/29/98 11/29/98 11/29/98 11/29/98 11/29/98 11/30/98 UNIT TWO: 11/01/98 11/30/98 0824 1255 1505 1720 1940 1945 2305 2400 0000 2400

• e . Surry Monthly Operating Report

SUMMARY

OF OPERATING EXPERIENCE (CONTINUED)

MONTHNEAR:

November 1998 Stopped ramp, unit at 94.5% / 810 MWe. Recommenced ramp, unit at 94.5% / 810 MWe. Stopped ramp, unit at 96% I 820 MWe. Commenced ramp down, unit at 96% I 820 MWe. Stopped ramp, unit at 90.2% / 785 MWe. Commenced ramp up, unit at 90.2% / 785 MWe. Stopped ramp, unit at 98.5% / 835 MWe. Unit finishes the month at 98.5% / 837 MWe. Unit starts the month at 100% / 855 MWe. Unit finishes the month at 100% / 855 MWe. No. 98-11 Page 10 of 18 DCP 94-071 DCP 97-059 DCP 98-007 SE 98-076, Rev. 1 SE 98-103, Rev. 1

• e Surry Monthly Operating Report No. 98-11 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

November 1998 Design Change Package (Safety Evaluation 94-051) 11/03/98 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. Design Change Package (Safety Evaluation 98-051 Rev. 1) 11/11/98 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. 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 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.

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. 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.

TM S 1-98-020 TM S1-98-021 DCP 98-069 TM S1-98-022 DCP 98-044 TM S1-98-023 TM S2-98-007

--Surry Monthly Operating Report FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR:

November 1998 Temporary Modifications (Safety Evaluation 98-114) No. 98-11 Page 12 of 18 11/03/98 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. Design Change Package (Safety Evaluation 98-115) 11/03/98 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. Temporary Modification (Safety Evaluation 98-116) 11/06/98 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.

Design Change Package (Safety Evaluation 98-118) 11/13/98 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. Temporary Modification (Safety Evaluation 98-121) 11/17/98 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. Temporary Modification (Safety Evaluation 98-123) 11/20/98 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.

SE 98-124 TM S 1-98-024 TM S 1-98-025 e Surry Monthly Operating Report No. 98-11 Page 13 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

November 1998 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. Temporary Modifications (Safety Evaluation 98-125) 11/27/98 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.

1/2-0PT-FW-008 1/2-AP-21.01 O-ECM-0103-02 1-0P-RC-001 A O-ECM-1401-02 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 Operations Periodic Test Procedures Abnormal Procedures (Safety Evaluation 96-074, Rev. 1) 11/03/98 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.

Electrical Corrective Maintenance Procedure (Safety Evaluation 98-117) 11/10/98 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. Operations Procedure (Safety Evaluation 98-119) 11/14/98 Loop "A" drain valve 1-RC-HCV-1557 A 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.

Electrical Corrective Maintenance Procedure (Safety Evaluation 98-122) 11/19/98 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 CHEMISTRY REPORT MONTHNEAR:

November 1998 Unit No. 1 Primary Coolant Analysis Max. Min. AvQ. Gross Radioactivity, µCi/ml 3.13E-1 7.73E-4 3.32E-2 Suspended Solids, ppm 0.250 s 0.010 0.064 Gross Tritium, µCi/ml 4.04E-2 3.07E-2 3.35E-2 1131, µCi/ml 8.21 E-3 2.68E-5 4.79E-4 113111133

---HydroQen, cc/kQ 33.1 23.7 28.9 Lithium, ppm 3.59 s 0.10 2.77 Boron -10, oom* 485.9 269.5 392.4 Oxygen, (DO), ppm 9.0 so.005 3.57 Chloride, ppm 0.038 s 0.001 0.008 pH @ 25 demee Celsius 6.30 4.35 4.98

• Boron -10 = Total Boron x 0.196 Comments:

None --urry Monthly Operating Report No. 98-11 Page 16 of 18 Unit No. 2 Max. Min. AvQ. 1.82E-1 9.21 E-2 1.37E-1 ---5.41E-1 4.57E-1 5.05E-1 1.37E-4 3.27E-5 7.45E-5 0.09 0.03 0.05 40.3 38.3 39.1 2.25 1.96 2.12 77.6 58.6 67.8 so.005 so.005 so.005 0.004 s 0.001 0.002 7.27 6.59 6.96 New Fuel Shipment or Cask No. FUEL HANDLING UNITS 1 & 2 MONTH/YEAR:

November 1998 Number of Date Stored or Assemblies Received per Shipment Assembly Number ANSI Number None during the Reporting Period 'turry Monthly Operating Report No. 98-11 Page 17 of 18 Initial Enrichment New or Spent Fuel Shipping Cask Activity

,. .* * -. 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