ML18153C187

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Monthly Operating Repts for Mar 1990 for Surry Power Station Units 1 & 2
ML18153C187
Person / Time
Site: Surry  
Issue date: 03/31/1990
From: Stewart W, Warren L
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-205, NUDOCS 9004200556
Download: ML18153C187 (22)
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 16, 1990 U. S. 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.

NO/RPC:vlh Docket Nos.

License Nos.90-205 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of March 1990.

W. L. Ste rt Senior Vice President - Nuclear Enclosure cc:

U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station

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e POW 34-04 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT I 90-03 APPROVED:

Station Manager

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SECTION e

TABLE OF CONTENTS Operating Data Report - Unit No. 1 Operating Data Report - Unit No. 2 Unit Shutdowns and Power Reductions - Unit No. 1 Unit Shutdowns and Power Reductions - Unit No. 2 Average Daily Unit Power Level

- Unit No. 1 Average Daily Unit Power Level

- Unit No. 2 Summary of Operating Experience - Unit No. 1 Summary of Operating Experience - Unit No. 2 Facility Changes That Did Not Require NRC Approval Procedure or Method of Operation Changes that Did Not Require NRC Approval Tests and Experiments That Did Not Require NRC Approval Chemistry Report Fuel Handling - Unit No. 1 Fuel Handling - Unit No. 2 Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications PAGE 1

2 3

4 5

6 7

8 9

13 14 15 16 18 19

OPERATING DATA REPORT DOCKET NO.:

50-280 DATE: _0"""'4,......,/=05=-;=9-=-o -----

COMPLETED BY:

L.A. Warren TELEPHONE: ----r;(8=0-=-4).-::3=5=-7_-=3""""18=-4,....--x3=5=5~

OPERATING STATUS NOTES

1. Unit Name:

Surry Unit 1

2. Reporting Period: MAR 01-31, 1990
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. Reason For Restrictions, If Any:

THIS MONTH YTD CUMULATIVE

11. Hours In Reporting Period 744.0 2160.0 151416.0
12. Number of Hours Reactor Was Critical 744.0 2160.0 94910.8
13. Reactor Reserve Shutdown Hours 0

0 3774.5

14. Hours Generator On-Line 744.0 2160.0 92983.2
15. Unit Reserve Shutdown Hours 0

0 3736.2

16. Gross Thermal Energy Generated (MWH) 1774040.5 5201973.5 216318776. 5
17. Gross Electrical Energy Generated (MWH) 600880.0 1763235.0 70308638.0
18. Net Electrical Energy Generated (MWH) 571260. 0 1679204.0 66690134.0
19. Unit Service Factor 100%

100%

61.4%

20. Unit Availability Factor 100%

100%

63.9%

21. Unit Capacity Factor (Using MDC Net) 98.3%

99.5%

56.9%

22. Unit Capacity Factor (Using DER Net) 97.4%

98.7%

55.9%

23. Unit Forced Outage Rate 0

0 21.2%

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 Startup:_---=--=r,"'=""'"==---
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1

e OPERATING DATA REPORT DOCKET NO.:

50-281 DATE:

04/05/90 COMPLETED BY:.....,L,-."""=A-.......;W...,....a-r-re_n ___ _

TELEPHONE:

(804)357-3184 x355 OPERATING STATUS NOTES

1. Unit Name:

Surry Unit 2

2. Reporting Period: MAR 01-31, 1990
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. Reason For Restrictions, If Any: -------------------

THIS MONTH YTD CUMULATIVE

11. Hours In Reporting Period 744.0 2160.0 148296.0
12. Number of Hours Reactor Was Critical 744.0 2160.0 93358.6
13. Reactor Reserve Shutdown Hours 0

0 328.1

14. Hours Generator On-Line 744.0 2160.0 91808.9
15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1812120.1 5124459.1 214734793.9
17. Gross Electrical Energy Generated (MWH) 609865.0 1726670.0 69807269.0
18. Net Electrical Energy Generated (MWH) 580218. 0 1643536.0 66184495.0
19. Unit Service Factor 100%

100%

61.9%

20. Unit Availability Factor 100%

100%

61.9%

21. Unit Capacity Factor (Using MDC Net) 99.9%

97.4%

57.3%

22. Unit Capacity Factor (Using DER Net) 99%

96.6 56.6

23. Unit Forced Outage Rate 0

0 15.4

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 Startup:.---:-.,,..,..,..,e-=-:-==--
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 2

NO.

DATE (1)

F:

Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTION (Equal To or Greater Than 20%)

REPORT MONTH:

MARCH 1990 METHOD OF LICENSEE DOCKET NO.:

50-280 UNIT NAME:

Surry Unit 1 DATE:

04/05/90 COMPLETED BY:

L.A. Warren TELEPHONE:

804-357-3184 x355 DURATION SHUTTING EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENT TYPE(l)

(HOURS)

REASON(2) DO~ REACTOR(3) REPORT#

CODE(4)

CODE(5)

NONE DURING THIS REPORTING PERIOD (2)

REASON:

A - Equipment Failure (Explain)

B ~ Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)

H - Other (Explain)

(3)

METHOD:

1 - Manual 2 - Manual Scram.

3 - Automatic Scram.

4 - Other (Explain) 3 (4)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)

File (NUREG 0161)

(5)

Exhibit 1 - Same Source

NO.

DATE DOCKET NO.:

50-281

.<(

UNIT NAME: -s=-u-r-ry__,.,U,_n 1-=-* t----=-2--

UNIT SHUTDOWN AND POWER REDUCTION (Equal To or Greater Than 20%)

DATE:

04/05/90 COMPLETED BY: --l-*...:,,.A-*....;..W-ar_r_e_n __ _

REPORT MONTH:

MARCH 1990 METHOD OF LICENSEE DURATION SHUTTING EVENT SYSTEM COMPONENT TYPE(!)

(HOURS)

REASON(2) DONN REACTOR(3) REPORT#

CODE(4)

CODE(5)

TELEPHONE:

804-357-3184 x355 CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENT 03/15/90 S 0.0 B

4 N/A TA V

Scheduled power reduction in order to perfonn 2-PT-29.1, which is the monthly exercise of the governor, stop, intercept, and reheat valves on the main turbine.

(1)

F:

Forced S: Scheduled (2)

REASON:

A - Equipment Failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training & license Examination F - Administrative G - Operational Error (Explain)

H - Other (Explain)

(3)

METHOD:

1 - Manual 2 - Manual Scram.

3 - Automatic Scram.

4 - Other (Explain)

.4 (4)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)

File (NUREG 0161)

(5)

-Exhibit 1 - Same Source

e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:

50-280 UNIT NAME:

Surry Unit 1 DATE:

04/05/90 COMPLETED BY:

L.A. Warren TELEPHONE:(804)357-3184 x355 MONTH:

MARCH 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 789 17 788 2

790 18 788 3

791 19 787 4

790 20 789 5

790 21 790 6

791 22 790 7

790 23 728 8

772 24 661 9

792 25 664 10 792 26 652 11 792 27 663 12 791 28 709 13 791 29 787 14 790 30 787 15 789 31 791 16 789 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.

5

e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:

50-281 UNIT NAME:

Surry Unit 2 DATE:

04/05/90 COMPLETED BY:

L.A. Warren TELEPHONE:(804)357-3184 x355 MONTH:

MARCH 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 784 17 780 2

783 18 781 3

783 19 781 4

783 20 779 5

782 21 781 6

782 22 781 7

783 23 776 8

781 24 780 9

781 25 780 10 781 26 781 11 782 27 780 12 781 28 782 13 781 29 781 14 782 30 783 15 737 31 782 16 781 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.

6

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR:

MARCH 1990 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 03/01/90 03/08/90 03/23/90 03/24/90 03/28/90 03/31/90 0000 0932 This reporting period started with the unit operating at 100%

power, 825 MW.

Started ramp down to perform 1-PT-29.1; 100% power, 830 MW.

1032 Stopped ramp; 85% power, 705 MW.

1341 Started ramp up after 1-PT-29.1 completion; 85%

power, 705 MW.

1455 Stopped ramp; 100% power, 830 MW.

1239 Placed 1-SD-P-lB in service, received a low level in l-SD-TK-1, and stopped 1-SD-P-lB.

While throttling 1-SD-P-lA manual discharge valve to conserve inventory in l-SD-TK-1, 1-SD-P-lA tripped on low level.

Started unit power reduction; 100% power, 830 MW.

1256 Unit stabilized at 91.5% power, 710 MW.

1628 Started ramp down to fully close 1-CP-AOV-122; 91.5% power, 710 MW.

1647 Stopped ramp; 87% power, 675 MW.

0356 Started ramp down to remove 18 1 train of 2nd, 3rd, and 4th point feedwater heaters in order to repair discharge pipe on l-SD-P-2B; 86% power, 710 MW.

0418 Stopped ramp; 81.5% power, 680 MW.

1350 Started ramp up after feedwater heaters returned to service; 82.5% power, 680 MW 1540 Stopped ramp; 100% power, 820 MW.

2400 This reporting period ended with the unit operating at 100%

power, 830 MW.

7

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR:

MARCH 1990 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 TWO 03/01/90 03/15/90 03/31/90 0000 1004 This reporting period started with the unit operating at 100%

power, 825 MW.

Started ramp down to perform 2-PT-29.1; 100% power, 820 MW.

1225 Stopped ramp; 75% power, 630 MW.

1538 Started ramp up after completion of 2-PT-29.1; 75% power, 630 MW.

1735 Stopped ramp; 100% power, 820 MW.

2400 This reporting period ended with the unit operating at 100%

power, 820 MW.

8

e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

MARCH 1990 2-EWR-89-711 ENGINEERING WORK REQUEST (Safety Evaluation #N89-0026) 01/09/90 EWR-87-115 This engineering work request (EWR) documents the removal of pressurizer safety valve loop seal drain line valves to alleviate seal and packing leakage.

The EWR includes removal of the pressurizer safety valve loop seal drain line valves and the common header isolation valve and associated piping and includes subsequently capping the remaining pipe stub ends.

The Unit 2 pressurizer safety valves have experienced leakage problems due to loss of the loop seal liquid level.

The loop seal contains a drain line with a valve that is subject to seat and packing leakage over an extended period of time and is considered a contributor to the loss of loop seal.

Removal of the drain valves will mitigate this condition.

Implementing this modification will enhance the integrity of the reactor coolant system pressure boundary by removing sources of potential small break loss of coolant accident.

This safety analysis review concludes that an unreviewed safety question does not exists, and that the consequences of failure are bounded by the accident analysis presented in chapter 14.5 of the UFSAR.

ENGINEERING WORK REQUEST UNIT 1 & 2 03/01/90 This Engineering Work Request was written to document the installation of bellows seals in certain ventilation system (VS) fans.

The permanent installation of a bellows seal on the drive shaft of the fan does not involve an unreviewed safety question. Since the seal modification helps ensure that in-leakage is in accordance with the requirements of the Technical Specifications and does not inhibit the safe operation of the fans, the probability and consequences of the accidents previously evaluated in the safety analysis report are not increased nor are any different malfunctions or accidents created.

The margin of safety as defined in the basis of the Technical Specifications is not reduced since the function or operation of the fans is not adversely affected. This modification has no detrimental effect on station operation or the operation of any safety related equipment.

The bellows seals installed by this EWR can be replaced if damaged and failure of the seals would not inhibit operation of the fans.

9

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

MARCH 1990 SCAFFOLD REQUEST UNIT 1 03/01/90 (Safety Evaluation #90-0071)

This request is for the erection of temporary scaffold to support the investigation and repair of an oil leak for exhaust damper actuator 01-VSP-MOD-1008 in the auxiliary building EL. 45 1 10 11 per w.o. #3800092596.

This temporary scaffold is required for safe working.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 2 (Safety Evaluation #90-0072) 03/01/90 This request is for the erection of temporary scaffold to repair overhead lighting in the Unit 2 emergency diesel generator room per W.O. #090282.

This temporary scaffold is required for safe working.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 1 03/01/90 (Safety Evaluation #90-0073)

This request is for the erection of temporary scaffold to support the brake maintenance on hoist for crane 1-FH-BRDG-13 located in fuel building at EL. 45 1 10 11 The work is to be performed per W.O.

  1. 092509.

This temporary scaffold is required for safe working.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

10

(

e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

MARCH 1990 SCAFFOLD REQUEST UNIT 1 03/01/90 (Safety Evaluation #90-0074)

This request is for the erection of scaffold located over 1-SW-MOV-103A/B to work (component/subject) pull cable in trays over valves.

The installation of this temporary scaffolding was reviewed for affect on accident analyses and equipment operability/function.

Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

Sl-TM-90-07 TEMPORARY MODIFICATION UNIT 1 03/13/90 (Safety Evaluation #90-0075)

This temporary modification allows Unit 1 power operation while replacing the PRB-XB relay.

This modification is required to return the 'B' train reactor trip circuitry to design condition.

The

'B' reactor trip bypass breaker will be closed as allowed by Technical Specifications in order to preclude possible reactor trip.

Since this method of operation has been evaluated by the Safety Analysis Report, an unreviewed safety question does not exist.

SCAFFOLD REQUEST UNIT 1 03/19/90 (Safety Evaluation #90-0077)

This request is for the erection of temporary scaffold to reconnect a detached pipe hanger in the Unit 1 auxiliary building per per W.O. #090269.

This temporary scaffold is required for safe working.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

S2-TM-90-03 TEMPORARY MODIFICATION (Safety Evaluation #90-0078) 03/20/90 This temporary modification allows Unit 2 power operation while replacing the IRB-XA relay.

This modification will return the "A" train reactor trip circuitry low power operation (permissive P-10) to design condition.

The full power reactor trip circuitry should not be affected by these jumpers.

The "A" reactor trip bypass breaker will be closed during the testing as allowed by the safety analysis report.

Therefore, an unreviewed safety question does not exist.

11

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

MARCH 1990 S2-TM-90-04 TEMPORARY MODIFICATION (Safety Evaluation #90-0084) 03/21/90 This temporary modification allows Unit 2 power operation while replacing IRB-XB relay.

This modification will return the 1 8 1 train reactor trip circuitry low power operation (permissive P-10) to design condition.

The full power operation reactor trip circuitry will not be affected by these jumpers.

The 1 8 1 reactor trip bypass breaker will be closed during the testing as allowed by the UFSAR.

Therefore, an unreviewed safety question does not exist.

12

e e

PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

MARCH 1990 NONE DURING THIS REPORTING PERIOD 13

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  • l TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

MARCH 1990 NONE DURING THIS REPORTING PERIOD 14

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PRIMARY COOLANT ANALYSIS Gross Radioact., µCi/ml Suspended Solids, ppm Gross Tritium, ~Ci/ml Iodine-131, µCi/ml Iodine-131/Iodine-133 Hydrogen, cc/kg Lithium, ppm Boron - 10, ppm*

Oxygen, (DO), ppm Chloride, ppm pH@ 25 degree Celsius

  • Boron - 10 = Total REMARKS:

e VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT MONTH/YEAR:

MAR 1990 UNIT NO. 1 MAX.

MIN.

AVG.

8.72E-1 5.85E-1 7.21E-1 0.0 0.0 0.0 2.34E-1 2.03E-1 2.14E-1 5.58E-3 3.31E-3 4.37E-3 0.19 0.09 0.13 40.2 25.4 30.7 2.34 2.01 2.18 69 54 63 0.005 0.005 0.005 0.008 0.004 0.006 7.15 7.02 7.09 Boron x 0.196 15 UNIT NO. 2 MAX.

MIN.

AVG.

2.36E-1 1.43E-1 1.86E-1 0.0 0.0 0.0 4.15E-1 4.22E-1 4.33E-1 7.09E-4 3.37E-4 4.60E-4 0.18 0.06 0.10 34.8 25.1 31.2 2.33 2.13 2.24 158 143 151 0.005 0.005 0.005 0.009 0.006 0.008 6.68 6.53 6.60

~--

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UNIT 1

NEW OR SPENT FUEL SHIPMENT#

1 2

3 DATE SHIPPED OR RECEIVED 03/13/90 03/15/90 03/20/90 e

FUEL HANDLING NUMBER OF ASSEMBLIES ASSEMBLY ANSI PER SHIPMENT NUMBER NUMBER 4

12 12 NEW SHIPMENTS RECEIVED 5Hl OH4 4H9 2H3 4H8 1H2 OH8 OH6 1H9 1H3 5HO 5H2 1H7 4H4 lHl 1H8 OH9 OH2 OH3 1H4 4HO OHl 3H9 4H6 4H5 1H6 OH7 3H7 16 LMORPB LMORMY LMORP9 LMORNH LMORP8 LMORN6 LMORN2 LMORNO LMORND LMORN7 LMORPA LMORPC LMORNB LMORP4 LMORN5 LMORNC LMORN3 LMORMW LMORMX LMORN8 LMORPO LMORMV LMORNZ LMORP6 LMORP5 LMORNA LMORNl LMORNX e

INITIAL ENRICHMENT 4.0%

3.8%

4.0%

3.8%

4.0%

3.8%

3.8%

3.8%

3.8%

3.8%

4.0%

4.0%

3.8%

4.0%

3.8%

3.8%

3.8%

3.8%

3.8%

3.8%

4.0%

3.8%

4.0%

4.0%

4.0%

3.8%

3.8%

4.0%

DATE:

MARCH 1989 NEW OR SPENT FUEL SHIPPING CASK ACTIVITY LEVEL N/A N/A N/A

~------ -- -

. \\

I-UNIT 1

NEW OR SPENT FUEL SHIPMENT II 4

5 DATE SHIPPED OR RECEIVED 03/27/90 03/29/90 e

FUEL HANDLING NUMBER OF ASSEMBLIES ASSEMBLY ANSI PER SHIPMENT NUMBER

~UMBER NEW SHIPMENTS RECEIVED 12 3H6 LMORNW OH5 LMORMZ 3HO LMORNQ 2H8 LMORNN 3H3 LMORNT 3H2 LMORNS 4H7 LMORP7 4H2 LMORP2 2H6 LMORNL 1H5 LMORN9 2H5 LMORNK 2HO LMORNE 12 3H4 LMORNU 3H5 LMORNV 3Hl LMORNR 2H7 LMORNM 2H4 LMORNJ 4H3 LMORP3 2H9 LMORNP IHO LMORN4 3H8 LMORNY 4Hl LMORPl 2Hl LMORNF 2H2 LMORNG 17 INITIAL ENRICHMENT 4.0%

3.8%

4.0%

4.0%

4.0%

4.0%

4.0%

4.0%

4.0%

3.8%

4.0%

3.8%

4.0%

4.0%

4.0%

4.0%

3.8%

4.0%

4.0%

3.8%

4.0%

4.0%

3.8%

3.8%

DATE:

MARCH 1989 NEW OR SPENT FUEL SHIPPING CASK ACTIVITY LEVEL N/A N/A

[========--=---~-

UNIT 2

NEW OR SPENT FUEL SHIPMENT#

DATE SHIPPED OR RECEIVED FUEL HANDLING NUMBER OF ASSEMBLIES ASSEMBLY ANSI PER SHIPMENT NUMBER NUMBER e

INITIAL ENRICHMENT NONE DURING THIS REPORTING PERIOD 18 DATE:

MARCH 1989 NEW OR SPENT FUEL SHIPPING CASK ACTIVITY LEVEL

DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: ~~MA_R_C_H_1_9_90~~

NONE DURING THIS REPORTING PERIOD 19

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