ML18153D177

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Monthly Operating Repts for Oct 1992 for Surry Power Station Units 1 & 2.W/921112 Ltr
ML18153D177
Person / Time
Site: Surry  Dominion icon.png
Issue date: 10/31/1992
From: Bowling M, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-725, NUDOCS 9211240035
Download: ML18153D177 (19)
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Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 12, 1992 U. S. Nuclear Regulatory Commission Serial No.92-725 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHL V OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of October 1992.

Very truly yours,

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M. L. Bowling, Manager Nuclear Licensing & Programs 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

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 92-10 Approved:

esurry Monthly Operating Report No. 92-10 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 No. 1 ......................................................................................... 9 Summary of Operating Experience - Unit No. 2 ......................................................................................... 9 Facility Changes That Did Not Require NRC Approval. .............................................................................. 10 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 Limits Specified in Technical Specifications ................................................................................................... 18

esurry Monthly Operating Report No. 92-10 Page 3 of 18 OPERATING DATA REPORT Docket No.: 50-280 Date: 11-06-92 Completed By: D. Mason Telephone: (804) 365-2459

1. Unn Name: .................................................. . Surry Unit 1
2. Reporting Period: .....*.................................... . October 1992
3. Licensed Thermal Power (MWt): ...................... . 2441
4. Nameplate Rating (Gross MWe): ...................... . 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacny (Gross MWe): .. .. 820
7. Maximum Dependable Capacity (Net MWe): ....... . 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .......................... 745.0 7320.0 174096.0
12. Number of Hours Reactor Was Critical .......... 745.0 5676.8 113911.0
13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 3774.5
14. Hours Generator On-Line ........................... 745.0 5571.2 111811.4
15. Unit Reserve Shutdown Hours ..................... 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 1804235.9 12940460.9 260057137.6
17. Gross Electrical Energy Generated (MWH) .... 606695.0 4300680.0 84815868.0
18. Net Electrical Energy Generated (MWH) ........ 576898.0 4079989.0 80454055.0
19. Unit Service Factor ................................... 100.0% 76.1% 64.2%
20. Unit Availability Factor ............................... 100.0% 76.1% 66.4%
21. Unit Capacity Factor (Using MDC Net) ........... 99.1% 71.4% 59.6%
22. Unit Capacity Factor (Using DER Net) ........... 98.3% 70.7% 58.6%
23. Unit Forced Outage Rate .............. :............. 0.0% 4.0% 18.6%
24. Shutdowns Schedule 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

9surry Monthly Operating Report No. 92-10 Page 4 of 18 OPERATING DATA REPORT Docket No.: 50-281 Date: 11-06-92 Completed By: D. Mason Telephone: (804) 365-2459

1. Un~ Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . October 1992
3. Licensed Thermal Power (MWt): ...................... . 2441
4. Nameplate Rating (Gross MWe): ...................... . 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 820
7. Maximum Dependable Capacity (Net MWe): ....... . 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .......................... 745.0 7320.0 170976.0
12. Number of Hours Reactor Was Critical .......... 745.0 7014.8 112222.9
13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 328.1
14. Hours Generator On-Line ........................... 745.0 7006.1 110467.0
15. Unit Reserve Shutdown Hours ..................... 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ...... 1816084.5 16889605.7 257768287.8
17. Gross Electrical Energy Generated (MWH) .... 602915.0 5574110.0 84007959.0
18. Net Electrical Energy Generated (MWH) ........ 573123.0 5296726.0 79660664.0
19. Unit Service Factor .................... , .............. 100.0% 95.7% 64.6%
20. Unit Availability Factor ............................... 100.0% 95.7% 64.6%
21. Unit Capacity Factor (Using MDC Net) ........... 98.5% 92.6% 59.8%
22. Unit Capacity Factor (Using DER Net) ........... 97.6% 91.8% 59.1%
23. Unit Forced Outage Rate ............................ 0.0% 0.0% 14.5%
24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, March 6, 1993 -- 74 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

esurry Monthly Operating Report No. 92-10 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: October 1992 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11-06-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 921031 F 0 A 4 NIA EL FAN Reduced Unit power to 62% due to the loss of the isolated phase bus duct fans.

(1) (2) (3)

F: Forced REASON: METHOD:

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

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

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

(4) (5)

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

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

e Surry Monthly Operating Report No. 92-10 Page 6 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: October 1992 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11-06-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 921028 s 0 B 4 NIA TA V Reduced Unit power to 80% to perform turbine valve freedom 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)

-Surry Monthly Operating Report No. 92-10 Page 7 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 11-06-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: October 1992 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 778 17 780 2 779 18 782 3 774 19 782 4 779 20 782 5 780 21 782 6 781 22 781 7 781 23 781 8 779 24 781 9 779 25 774 10 779 26 782 11 779 27 782 12 780 28 780 13 780 29 780 14 779 30 781 15 779 31 606 16 780 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. 92-10 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 11-06-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: October 1992 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe - Net) 767 17 770 2 767 18 769 3 760 19 771 4 766 20 773 5 771 21 772 6 773 22 772 7 771 23 773 8 771 24 772 9 771 25 768 10 771 26 773 11 770 27 772 12 771 28 741 13 771 29 773 14 770 30 772 15 769 31 773 16 769 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. 92-10 Page 9of 18

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: October 1992 Listed below in 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 10-01-92 0000 This reporting period began with the Unit operating at 100% power, 815 MWe.

10-31-92 0138 Started ramp down due to a loss of both Isolated Phase Bus Duct Cooling Fans; 100%

power, 815 MWe 0354 Stopped ramp; 62% power, 490 MWe.

1601 Started ramp up after fan motors were replaced; 63.5% power, 510 MWe.

1820 Stopped ramp; 100% power, 820 MWe.

2400 This reporting period ended with the Unit operating at 100% power, 81 O MWe.

UNIT TWO 10-01-92 0000 This reporting period began with the Unit operating at 100% power, 815 MWe.

10-28-92 0905 Started ramp down to perform OSP-TM-001, Turbine Valve Freedom Test; 100% power, 815 MWe.

1319 Stopped ramp; 80% power, 670 MWe.

1332 Started ramp up after completion of test; 80% power, 670 MWe.

1833 Stopped ramp; 100% power, 820 MWe.

10-31-92 2400 This reporting period ended with the Unit operating at 100% power, 810 MWe.

-Surry Monthly Operating Report No. 92-10 Page 10 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: October 1992 SE 92-202 Safety Evaluation 10-01-92 This Safety Evaluation was performed to evaluate the operation of the general fuel building ventilation system with supply fan 1-VS-F-39 and exhaust fan 1-VS-F-?A running and supply fan 1-VS-F-6 and exhaust fan 1-VS-F-7B out of service.

The evaluation of this operational configuration concluded that the exhaust capacity remains in excess of the supply capacity, thus maintaining inward leakage, as designed. In addition, the fuel building ventilation supply and exhaust fans are nonsafety-related and do not help to mitigate the consequences of an accident described in the UFSAR. Therefore, an unreviewed safety question is not created.

SE 92-203 Safety Evaluation 10-01-92 This Safety Evaluation was performed to evaluate the operation of the auxiliary building ventilation system with exhaust fan 1-VS-F-8B running and fan 1-VS-F-59 exhausting through the Category II filter train (in lieu of exhaust fan 1-VS-F-SA which is out of service).

The evaluation of this operational configuration concluded that it is permitted by the UFSAR and that the air flow requirements are being maintained.

Therefore, an unreviewed safety question is not created.

FS 92-12 UFSAR Change 10-01-92 (Safety Evaluation 92-204)

The Updated Final Safety Analysis Report (UFSAR) Section 9.12, "Fuel Handling System" was revised to correct typographical errors and to reflect the current fuel handling system and refueling methods.

The change is administrative in nature and provides clarification only. No procedures or plant equipment are affected and no physical modifications are involved. Therefore, an unreviewed safety question is not created.

-Surry Monthly Operating Report No. 92-10 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October 1992

[continued]

FS 92-32 UFSAR Change 10-01-92 (Safety Evaluation 92-205)

The Updated Final Safety Analysis Report (UFSAR) Sections 14B.5.1.6.3, "Basis for the Inspection Program" and 14B.5.1.6.4, "Fracture Mechanics" were revised to include alternate materials for the potential replacement of feedwater and main steam piping.

The new materials have been tested, analyzed, and determined to have adequate toughness relative to the existing materials. They also exhibit a greater resistance to erosion/corrosion. The new materials may be used as a replacement material (through the erosion/corrosion control program) and would reduce the possibility of piping failures due to erosion/corrosion.

Therefore, an unreviewed safety question is not created.

FS 92-35 UFSAR Change 10-01-92 (Safety Evaluation 92-206)

The Updated Final Safety Analysis Report (UFSAR) Sections 12.2.2.3.1.5, "Check Operator" and 12.2.2.3.1.6, "Shift Manning" were revised to delete references to the discontinued Check Operator program.

The change is administrative in nature. No plant equipment is affected and no physical modifications are involved. Therefore, an unreviewed safety question is not created.

FS 90-53 UFSAR Change 1 0-06-92 (Safety Evaluation 92-212)

The Updated Final Safety Analysis Report (UFSAR) Section 14.2.13, "Likelihood of Turbine-Generator Unit Overspeed" was revised to clarify the basis for stating that the probability of a turbine missile entering the spent fuel pool is essentially zero.

The change is administrative in nature and provides clarification only. No procedures or plant equipment are affected and no physical modifications are involved. Therefore, an unreviewed safety question is not created.

-Surry Monthly Operating Report No. 92-10 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October 1992

[continued]

FS 92-44 UFSAR Change 1 0-08-92 (Safety Evaluation 92-213)

The Updated Final Safety Analysis Report (UFSAR) Section 10.3.9, "Bearing Cooling Water System" was revised to reflect the current operating practice of manually (as opposed to automatically) controlling the bearing cooling temperature control valves for the hydrogen gas coolers and the main turbine lube oil cooler.

This change in operation does not adversely impact the reliability of the turbine auxiliary coolers and does not require constant operator attention since the cooler parameters do not change rapidly. The bearing cooling system is not used to mitigate any accidents described in UFSAR. Therefore, an unreviewed safety question is not created.

TM S1-92-36 Temporary Modification 1 0-08-92 (Safety Evaluation No.92-215)

This Temporary Modification (TM) installed a spoolpiece in place of the Unit 1 hotwell high volume make-up valve, 1-CN-LCV-1028. The valve was leaking and had to be removed to facilitate its repair.

The subject valve is normally shut during power operation, therefore the temporary spoolpiece was manually isolated while installed. Additional hotwell make-up was available (with operator action) by opening the isolation valve.

This TM did not adversely affect nuclear safety since the nonsafety-related hotwell high volume make-up is not needed to mitigate the consequences of an accident. Therefore, an unreviewed safety question was not created.

TM S2-92-24 Temporary Modification 10-12-92 (Safety Evaluation No.92-216)

This Temporary Modification (TM) installed an individual rod position indication (IRPI) rod bottom bistable module with a soldered jumper which defeats the IRPI dropped control rod turbine runback and rod stop for control rod L-11. This modification will prevent a spurious turbine runback while troubleshooting drift problems associated with the Unit 2 control rod L-11 IRPI circuitry.

Other IRPI turbine runback and rod stop circuits, as well as nuclear instrument, over-pressure delta temperature and over-temperature delta temperature turbine runback and rod stop circuitry remained operable while this modification was installed. Therefore, an unreviewed safety question was not created.

esurry Monthly Operating Report No. 92-10 Page 13 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: October 1992

[continued]

TM S1-92-37 Temporary Modifications 10-13-92 TM S2-92-25 (Safety Evaluation No.92-217)

These Temporary Modifications (TM) added two temporary quick disconnects to the containment instrument air system to facilitate testing the air quality.

The quantity of air required for this testing is small and well within the capacity of the containment instrument air compressor. In the event of a transient, the control room will notify an operator (stationed at the test point) to close an isolation valve, terminating air flow to the test devices. Therefore, an unreviewed safety question is not created.

DR S-92-1722 Deviation Report 1 0-26-92 (Safety Evaluation No.92-223)

This Safety Evaluation was performed to evaluate Deviation Report S0 92-1722 concerning operation with the fire pump suction cross-tie valve, 1-FP-19, locked open.

The evaluation concluded, based on a review of the NRC's Fire Protection Safety Evaluation Report, that the subject valve is intended to be locked open.

Therefore, an unreviewed safety question does not exist.

TM S2-92-26 Temporary Modification 1 0-29-92 (Safety Evaluation No.92-224)

This Temporary Modification (TM) lifted an electrical lead for the turbine stop valve number 3 input to the turbine trip inputs to the reactor protection circuitry in order to simulate the valve being in a closed position. This action was initiated when it was discovered during the performance of a surveillance that the subject valve does not indicate when it is fully closed.

This TM conservatively changed the 4-out-of-4 stop valves closed turbine trip signal to the reactor trip logic to 3-out-of-3 and did not affect the ability to generate a valid reactor trip signal from a turbine trip. Therefore, an unreviewed safety question was not created.

e Surry Monthly Operating Report No. 92-10 Page 14of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: October 1992 1-0P-RX-004 Operating Procedures 1 0-02-92 2-0P-RX-004 Design Reference Procedures 1-DRP-003 (Safety Evaluation No.92-209) 2-DRP-003 Operating Procedures 1/2-0P-RX-004, "Estimated Critical Conditions" and Design Reference Procedures 1/2-DRP-003, "Curve Book" were revised to provide additional operator curves for estimated critical conditions (ECC) and to widen the administrative band for achieving criticality.

These changes will improve ECC predictions and the widened band will provide flexibility in performing normal startups while remaining narrow enough to detect anomalies. Procedural guidance is also provided in the event of a missed ECC. Therefore, an unreviewed safety question is not created.

2-NPT-RX-002 Engineering Periodic Test Procedure 1 0-26-92 (Safety Evaluation No. 92-222A)

Engineering Periodic Test Procedure 2-NPT-RX-002, "Reactor Core Flux Maps" was revised to provide instructions for installing an electrical jumper around the withdrawn limit switch on the Unit 2 "8" incore detector. This jumper will allow use of the "B" detector 10 path transfer device along with the "A" detector 5 path transfer device and drive motor to perform Technical Specification required full core flux maps. The "8" detector 5 path transfer switch will also be disabled to prevent damaging the detector cable when the detector is inserted into its storage location. This option is being made available due to periodic thermal trips of the "B" incore detector drive motor.

This change will prevent unnecessary containment entries (to reset the drive motor) and unnecessary radiation hazards. Furthermore, operation of the incore detection system will not be adversely affected and the integrity of the reactor coolant system boundary at the seal table will not be compromised.

Therefore, an unreviewed safety question is not created.

-Surry Monthly Operating Report No. 92-10 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: October 1992 None during this reporting period.

4tsurry Monthly Operating Report No. 92-10 Page 16 of 18 CHEMISTRY REPORT MONTH/YEAR: October 1992 Unit No. 1 Unit No. 2 Primarv Coolant Analysis Max. Min. Avg. Max. Min. Avg.

Gross Radioact., u.Ci/ml 3.95E-1 2.60E-1 3.21 E-1 2.35E-1 1.52E-1 1.91E-1 Suspended Solids, oom < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Gross Tritium, µCi/ml 3.58E-1 3.26E-1 3.46E-1 3.39E-1 3.13E-1 3.31E-1 1131, µCi/ml 8.58E-4 4.35E-4 6.45E-4 5.26E-4 2.17E-4 3.76E-4 1131/1133 0.14 0.07 0.10 0.16 0.06 0.10 Hydrogen, cc/kQ 35.6 27.0 31.4 38.5 26.3 30.7 Lithium, oom 2.31 2.07 2.19 2.29 2.00 2.23 Boron - 10, oom* 200.7 186.4 192.0 77.4 59.0 68.6 OxyQen, (00), oom < 0.005 < 0.005 < 0.005 < 0.005 < 0.005 < 0.005 Chloride, oom < 0.050 0.003 0.008 < 0.050 < 0.001 0.003 pH at 25 demee Celsius 6.71 6.50 6.62 7.32 7.09 7.20 Boron - 10 = Total Boron x 0.196 Comments:

None.

-Surry Monthly Operating Report No. 92-10 Page 17of 18 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: October 1992 New or Spent Number for New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity CA V/21-016 10-14-92 NIA S32 LMOOVN 2.61 NIA S29 LMOOVH 2.61 S15 LMOOUZ 2.61 S01 LMOOTK 2.61 P13 NOANSI 3.11 H22 LM0105 2.62 H20 LM01R3 2.62 H19 LM01R4 2.62 G16 LM01QL 2.11 3A9 LM04V3 3.39 5A1 LM04V4 3.39 2A6 LM04TD 3.39 5A3 LM04U7 3.39 5A4 LM04UD 3.39 4A9 LM04U8 3.39 6AO LM04lW 3.39 2A1 LM04TZ 3.39 3A7 LM04UK 3.39 6A4 LM04VO 3.39 2A2 LM04TK 3.39 4A1 LM04UH 3.39

  • ..l .... ...

esurry Monthly Operating Report No. 92-10 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: October 1992 None During This Reporting Period.

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