ML18153C599

Monthly Operating Repts for Mar 1991 for Surry Power Station Units 1 & 2

ML18153C599
Person / Time
Site:	Surry
Issue date:	03/31/1991
From:	Negron M, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-206, NUDOCS 9104180292
Download: ML18153C599 (21)

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VrROINIA ELECTRIC AND PowER COMPANY RICHMOND, VIRGiNIA 23261 April 15, 1991 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.91-206 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 1991.

Very truly yours, 0)~

W. L. Stewart 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

-.,.-,9--:* 910331

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9i041B~t~t o~600280 F'DR Ai.J -._. **

F'DR R

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 91-03 Approved:

'p~u~

Station Manager

'f - ~- 1 I Date

1-~

TABLE OF CONTENTS Section aurry Monthly Operating Report No. 91-03 Page 2 of 20 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........................................... 15 Tests and Experiments That Did Not Require NRC Approval...................................................................... 16 Chemistry Report............................................................................................................................. 17 Fuel Handling - Unit No. 1................................................................................................................... 18 Fuel Handling - Unit No. 2................................................................................................................... 18 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications................................................................................................... 20

e

'lurry Monthly Operating Report No. 91-03 Page 3 of 20 OPERATING DATA REPORT

1. Un~ Name:...................................................

2. Reporting Period:..........................................

3. Licensed Thermal Power (MWt):.......................

4. Nameplate Rating (Gross MWe):.......................

5.

Design Electrical Rating (Net MWe):..................

6. Maximum Dependable Capacity (Gross MWe):....

7. Maximum Dependable Capacity (Net MWe):........

Surry Unit 1 March 1991 2441 847.5 788 820 781 Docket No.:

Date:

Completed By:

Telephone:

50-280 04-03-91 M.A. Negron 804-365-2795

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):

1 O. Reasons For Restrictions, If Any:

This Month

11. Hours In Reporting....................................

12. Number of Hours Reactor Was Critical..........

13. Reactor Reserve Shutdown Hours...............

14. Hours Generator On-Line...........................

15. Unit Reserve Shutdown Hours.....................

16. Gross Thermal Energy Generated (MWH)......

17. Gross Electrical Energy Generated (MWH)....

18. Net Electrical Energy Generated (MWH)........

19. Unit Service Factor...................................

20. Unit Availability Factor...............................

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

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

23. Unit Forced Outage Rate............................

744.0 744.0 0.0 744.0 0.0 1791731.0 604070.0 573968.0 100.0%

100.0%

98.8%

97.9%

0.0%

YID 2160.0 2160.0 0.0 2160.0 0.0 5232540.0 1769450.0 1685391.0 100.0%

100.0%

99.9%

99.0%

0.0%

Cumulative 160176.0 101634.2 3774.5 99640.2 3736.2 231452450.3 75346273.0 71468520.0 62.2%

64.5%

57.6%

56.6%

20.3%

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):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED

I~

41tsurry Monthly Operating Report No. 91-03 Page 4 of 20 OPERATING DATA REPORT 1. Unit Name:...................................................

2.

Reporting Period:..........................................

3. Licensed Thermal Power (MWt):.......................

4. Nameplate Rating (Gross MWe):.......................

5. Design Electrical Rating (Net MWe):..................

6.

Maximum Dependable Capacity (Gross MWe):....

7. Maximum Dependable Capacity (Net MWe):........

Surry Unit 2 March 1991 2441 847.5 788 820 781 Docket No.:

Date:

Completed By:

Telephone:

50-281 04-03-91 M.A. Negron 804-365-2795

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....................................

12. Number of Hours Reactor Was Critical..........

13. Reactor Reserve Shutdown Hours................

14. Hours Generator On-Line...........................

15. Unit Reserve Shutdown Hours.....................

16. Gross Thermal Energy Generated (MWH)......

17. Gross Electrical Energy Generated (MWH)....

18. Net Electrical Energy Generated (MWH)........

19. Unit Service Factor...................................

20. Unit Availability Factor...............................

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

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

23. Unit Forced Outage Rate............................

This Month 744.0 720.0 0.0 698.8 0.0 1387703.0 467470.0 442007.0 93.9%

93.9%

76.1%

75.4%

0.0%

YID 2160.0 2136.0 0.0 2114.8 0.0 4493943.2 1510315.0 1432860.0 97.9%

97.9%

84.9%

84.2%

0.0%

Cumulative 157056.0 101308.3 328.1 99685.4 0.0 232629411.5 75740429.0 71811585.0 63.5%

63.5%

58.7%

58.0%

15.0%

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

Refueling 30 67 days

25. If Shut Down at End of Report Period Estimated Date of Start-up:

26. Unit In Test Status (Prior to Commercial Operation):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST 06-05-91 ACHIEVED

(1)

Date Type 03-07-91 s

(1)

F:

Forced S: Scheduled e

-urry Monthly Operating Report No. 91-03 Page 5 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: March 1991 (2)

(3)

(4)

Method (5)

Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-03-91 Completed by: M. A. Negron Telephone: 804-365-2795 Duration of LER System Component Cause & Corrective Action to Hours 0

Reason B

(2)

REASON:

Shutting No.

Down Rx 4

N/A A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Code Code TA V

E Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

Prevent Recurrence Ramped unit to 70% power to perform 1-PT-29.1 (Turbine Valve Freedom Test).

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

(4)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Exhibit 1 - Same Source.

eurry Monthly Operating Report No. 91-03 Page 6 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: March 1991 (1)

(2)

(3)

(4)

(5)

Method Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-03-91 Completed by: M. A. Negron Telephone: 804-365-2795 Duration of LER System Component Cause & Corrective Action to Date Type Hours 03-30-91 s

45.2 (1)

F:

Forced S: Scheduled (4)

Reason C

(2)

REASON:

Shutting No.

Down Rx 1

NIA A -

Equipment Failure (Explain)

B -

Maintenance or Test C -

Refueling D -

Regulatory Restriction Code Code NIA NIA 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 (NUREG 0161)

Prevent Recurrence Shut Unit down in accordance with applicable operating procedures for a scheduled refueling outage. Duration expected to be 67 days.

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

Month:

March 1991 Day 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 INSTRUCTIONS e

-urry Monthly Operating Report No. 91-03 Page 7of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-03-91 Completed by: M.A. Negron Telephone: 804-365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 782 17 783 784 18 720 785 19 679 785 20 681 786 21 725 786 22 779 720 23 784 788 24 785 790 25 784 790 26 777 788 27 783 785 28 783 783 29 783 783 30 786 783 31 785 783 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:

March 1991 Day 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 INSTRUCTIONS aurry Monthly Operating Report No. 91-03 Page 8 of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-03-91 Completed by: M.A. Negron Telephone: 804-365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net)

Day (MWe-Net) 700 17 629 700 18 623 698 19 617 691 20 610 686 21 605 679 22 600 673 23 593 670 24 588 666 25 580 662 26 575 657 27 569 653 28 564 645 29 550 643 30 19 639 31 0.0 634 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. 91-03 Page 9of 20

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: March 1991 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 03-01-91 03-07-91 03-18-91 03-21-91 03-31-91 UNIT TWO 03-01-91 03-03-91 03-29-91 03-30-91 03-31-91 0000 0958 This reporting period started with the Unit operating at 100% power and 825 MWe.

Started ramp down to perform 1-PT-29.1; 100% power, 825 MWe.

1146 Stopped ramp; 70% power, 608 MWe.

1812 Started ramp up after completion of 1-PT-29.1; 70% power, 608 MWe.

2100 Stopped ramp; 100% power, 825 MWe.

0846 Started ramp down to remove the first point feedwater heaters from service in order to repair a steam leak; 100% power, 825 MWe.

0921 Stopped ramp; 90% power, 720 MWe.

1355 Started ramp up after return to service of the first point feedwater heaters; 89% power, 740MWe.

1504 Stopped ramp; 100% power, 820 MWe.

2400 0000 0717 2200 0249 0344 2400 This report period ended with the Unit operating at 100% power and 825 MWe.

This report period started with the Unit operating at 90% power and 740 MWe.

Commence end of cycle unit coastdown.

Started unit shutdown for the refueling outage; 73% power, 595 MWe.

Unit offline.

Reactor manually tripped.

This report period ended with the Unit at Cold Shutdown and preparing for Refueling Shutdown.

&urry Monthly Operating Report No. 91-03 Page 10of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL EWR 89-703 AC S2-91-0304 TSR 91-013 MONTH/YEAR: March 1991 Engineering Work Request (Safety Evaluation No.90-002) 03-13-91 This Engineering Work Request replaces the existing Fischer Porter transmitter, 1-CC-PT-100, with an equivalent Rosemount model.

Replacement of the Fischer Porter Transmitter is necessary because replacement parts are no longer easily obtained. The transmitter is not safety related and performs no safe shutdown function. The replacement transmitter is seismically qualified, meets nuclear and other design requirements and does not perform a safety related function.

Therefore, an unreviewed safety question is not created.

Administrative Control (Safety Evaluation No.91-041) 03-05-91 Upon its removal, Administrative Control will be established over the "A" Recirculation Spray (RS)/Service Water (SW) Valve Pit missile shield to allow an inspection of the valve pit sump level probe.

This inspection is being performed as part of an investigation as to the cause of the valve pit Hi Level alarm actuation. The missile shield is a passive component required to protect RS/SW piping during adverse weather conditions. Only blank flanged RS/SW piping exists in the "A" valve pit and personnel and equipment will be available to replace the shield if adverse weather conditions approach the plant. Therefore, an unreviewed safety question is not created.

Temporary Shielding Request (Safety Evaluation No.91-044) 03-05-91 This Temporary Shielding Request installs lead shielding around lines (4"-CH-112-152, 6"-CH-18-152, 8"-CH-17-152) in the unit one "A" and "B" charging pump cubicles.

The temporary shielding will lower area radiation levels and reduce the dose received by personnel while painting the charging pumps cubicles. The subject lines will remain operable while the shielding is installed and Engineering calculations have determined that additional seismic loading is acceptable.

Therefore, an unreviewed safety question is not created.

&urry Monthly Operating Report No. 91-03 Page 11 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL JCO 91-3-001 TM S1-91-006 AC S1 0314 MONTH/YEAR: March 1991

[continued]

Justification for Continued Operation (Safety Evaluation No.91-048) 03-07-91 This Justification for Continued Operation opens power supply breakers and de-energizes, in the open position, Containment Spray (CS) pump suction valves from the Chemical Addition Tank, 1-CS-MOV-103A, B, C, D and 2-CS-MOV-203A, B, C, D.

This change will ensure these valves remain open following initiation of a Hi Hi Consequence-Limiting Safeguard (CLS) and do not unnecessarily close due to the erroneous indication of low pressure on the discharge of the CS pumps. In addition, the function of these valves on a low pressure CS pump condition will be eliminated since it is no longer required. Maintaining the valves open during a

. Hi Hi CLS and low pressure condition on the CS pump will have no impact on CS system functions and will prevent spurious closures. Therefore, an unreviewed safety question is not created.

Temporary Modification (Safety Evaluation No.91-049) 03-08-91 This Temporary Modification (TM) bypasses the relays in the remote start circuitry of the ESW pumps to provide direct operator control of starter engagement.

This TM will improve start reliability by bypassing the crank-rest circuitry installed for remote start purposes and will be effective until a permanent change is implemented. Since the diesels are now local-only start, the remote start circuitry is no longer required and can be bypassed. The design basis function of the ESW pumps is not affected and the probability of start failure is reduced since the operators directly control starter engagement. Therefore, an unreviewed safety question is not created.

Administrative Control (Safety Evaluation No.91-055) 03-14-91 Administrative Control (AC) has been established to permit the installation of a jacking device in the Unit 1 "C" feedwater regulation valve to permit l&C technicians to troubleshoot flow fluctuations.

This AC locates an operator at the valve to manually remove the jacking device and isolate feedwater if directed by the control room to ensure the intended safety function is maintained. Therefore, an unreviewed safety question is not created.

&urry Monthly Operating Report No. 91-03 Page 12 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL AC S1-91-0314A CAL SM-787 TSR 91-023 MONTH/VEAR: March 1991

[continued]

Administrative Control (Safety Evaluation No.91-057) 03-15-91 Administrative Control (AC) has been established to permit manual starting of the Independent Spent Fuel Storage Installation (ISFSI) diesel during a loss of normal electrical power.

The ISFSI diesel supplies power to ISFSI pressure and temperature monitoring instrumentation during a loss of normal power. This AC is necessary due to a faulty start coil on the fuel oil solenoid. When a replacement solenoid becomes available it will be installed and the AC will be terminated. A temporary loss of ISFSI monitoring, until a manual start can be initiated, would not increase the probability or consequence of a cask failure. Therefore, an unreviewed safety question is not created.

Calculation 03-22-91 (Safety Evaluation No. 91 ~062A)

Calculation SM-787 examines the pressure response with time of both the Main Steam System and the Reactor Coolant System under a Loss of Electrical Load, assuming that one of the 15 main steam safety valves fails to open.

The excess capacity of the Main Steam Safety Valves at 110% system design

-pressure (1210 psia), compared to the required capacity at the peak Main Steam System pressure (1179 psia), is greater than the capacity of any one valve. Since additional safety valves are available to provide relief capability prior to reaching the maximum analyzed pressure, the Main Steam System will be able to perform its design function with one valve inoperable on each of the three steam lines. Therefore, an unreviewed safety question does not exist.

Temporary Shielding Request (Safety Evaluation No.91-066) 03-26-91 This Temporary Shielding Request installs lead shielding around lines, 2"-RL-103-152, 2"-DA-134-152, and valve 2-RL-12 in the Unit 2 Containment basement.

The temporary shielding will lower area radiation levels and reduce the dose received for personnel while work in this area is performed. The reactor cavity drain lines will remain operable while the shielding is installed and Engineering calculations have determined that additional seismic loading is acceptable. Therefore, an unreviewed safety question is not created.

9surry Monthly Operating Report No. 91-03 Page 13 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL AC S1 0321 AC S1-91-0320 AC S1-91-0320A MONTH/VEAR: March 1991

[continued]

Administrative Control (Safety Evaluation No.91-070) 03-28-91 Administrative Control (AC) will be established over outside instrument air supply isolation valves, 2-IA-446 and 2-IA-447, to Unit 1 Containment from Unit 2 instrument air to ensure containment integrity can be maintained with the valves open.

Personnel will be continuously stationed in the vicinity of the valves and will close them upon notification from the Control Room. This AC will ensure the ability to maintain containment partial pressure within the limits established by Technical Specifications. Therefore, an unreviewed safety question is not created.

Administrative Control (Safety Evaluation No.91-071) 03-28-91 Administrative Control will be established upon the removal of the flood dike at the Emergency Switchgear Room (ESGR) door.

The dike will be temporarily removed to facilitate moving heavy equipment into and out of the ESGR. A flood watch will be posted at the door to reinstall the dike, and a roving flood watch will be in the Turbine building while the dike is removed. The removal of the dike will not affect safety related equipment and the administrative controls provide adequate compensatory actions to combat potential flooding. Therefore, an unreviewed safety question is not created.

Administrative Control (Safety Evaluation No.91-072) 03-28-91 Administrative Control will be established upon the removal of the flood dike at the entrance to Mechanical Equipment Room (MER) 3.

The dike will be temporarily removed to facilitate moving heavy equipment into or out of MER 3. A flood watch will be posted at the door to reinstall the dike, and another flood watch will be posted in the MER while the dike is removed.

The removal of the dike will not affect safety related equipment and the administrative controls provide adequate compensatory actions to combat potential flooding. Therefore an unreviewed safety question is not created.

TSR 91-028 TSR 91-038 TSR 91-039 e

esurry Monthly Operating Report FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL No. 91-03 Page 14of 20 MONTH/VEAR: March 1991

[continued]

Temporary Shielding Request (Safety Evaluation No.91-074) 03-28-91 These Temporary Shielding Requests install lead shielding on the "A", "B", and "C" Loop Resistance Temperature Detector (RTD) Manifold Lines in the Reactor Coolant Pump cubicles.

This temporary shielding will lower area radiation levels and reduce the dose received for personnel while work is being performed. The RTD lines will be inoperable while lead shielding is installed and the unit will be in cold shutdown.

A deadweight analysis has been performed for the additional loading on the RTD manifolds and found to be acceptable. There is a small possibility of the lines rupturing in a seismic event, however, this break is enveloped by the LOCA accidents previously evaluated. Therefore, an unreviewed safety question is not created.

2-0PT-22-001 2-0PT-22-002

.urry Monthly Operating Report No. 91-03 Page 15of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1991 Periodic Test Procedure (Safety Evaluation No.91-064) 3-21-91 A new periodic test, 2-0PT-22-001, was developed to comply with the Technical Specifications refueling test requirements for Engineered Safety Feature (ESF) actuation with delayed undervoltage on the "2H" emergency bus.

The unit will be at cold shutdown conditions when ESF functions are not required. Two cooling loops, consisting of the Residual Heat Removal pump not being tested and a Reactor Coolant Pump loop, will be available to provide core decay heat removal. No permanent changes to systems are required. Electrical jumpers and lifted leads required for the testing will be controlled with Temporary Modifications (TM) requiring double verification for installation and removal. Therefore, an unreviewed safety question does not exist.

Periodic Test Procedure (Safety Evaluation No.91-063) 3-25-91 A new periodic test, 2-0PT-22-002, was developed to comply with the Technical Specifications refueling test requirements for Engineered Safety Feature (ESF) actuation with delayed undervoltage on the "2J" emergency bus.

The unit will be at cold shutdown conditions when ESF functions are not required. Two cooling loops, consisting of the Residual Heat Removal pump not being tested and a Reactor Coolant Pump loop, will be available to provide core decay heat removal. No permanent changes to systems are required. Electrical jumpers and lifted leads required for the testing will be controlled with Temporary Modifications (TM) requiring double verification for installation and removal. Therefore, an unreviewed safety question does not exist.

-Surry Monthly Operating Report No. 91-03 Page 16 of 20 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March 1991 None During This Reporting Period.

e Primary Coolant Analysis Gross Radioact., µCi/ml Suspended Solids, oom Gross Tritium, µCi/ml 1131, µCi/ml 1131/I133 HydroQen, cc/kQ Lithium, oom Boron - 10, oom*

OxyQen, (DO), ppm Chloride, oom pH at 25 dearee Celsius Boron - 1 O = Total Boron x 0.196 Comments:

CHEMISTRY REPORT MONTH/YEAR: March 1991 Unit No. 1 Max.

Min.

AvQ.

7.15E-1 3.42E-1 5.06E-1 0.0 0.0 0.0 3.84E-1

3. 71 E-1 3.79E-1 3.37E-3 1.41 E-3 1.87E-3 0.17 0.07 0.10 48.5 32.4 37.7 2.44 2.05 2.18 157.2 141.9 149.5

<0.005

<0.005

<0.005 0.007

,;0.001 0.003 6.67 6.52 6.60 Unit 1 - Lithium out-of-specification high for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> on 3/22/91.

-urry Monthly Operating Report No. 91-03 Page 17of 20 Unit No. 2 Max.

Min.

Ava.

2.59E-1 9.85E-3 1.26E-1 0.0 0.0 0.0 1.67E-1 1.21 E-1 1.43E-1 9.31 E-4 3.37E-4 5.52E-4 0.15 0.06 0.10 39.7 3.5 26.8 0.96 0.28 0.73 321 0.20 39.8 1.0

<0.005 0.067 0.007

,;0.001 0.002 9.29 5.36 7.95

&urry Monthly Operating Report No. 91-03 Page 18of 20 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: March 1991 Units One and Two Number for Nominal New or Spent Assemblies Assembly ANSI Initial Fuel Shipping Cask Stored per Shipment Number Number Enrichment Cask Activity NAC-128.1 03-26-91 NIA A01 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A02 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A03 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A06 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A07 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A10 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A11 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A15 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A16 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A18 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A23 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A27 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A28 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A30 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A31 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A34 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A36 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A37 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A39 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A41 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A42 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A43 NIA 1.87 NIA

[continued]

FUEL HANDLING MONTH/YEAR: March 1991 Units One and Two Number for Assemblies Assembly ANSI Cask Stored per Shipment Number Number NAC-128.1 03-26-91 NIA A44 NIA NAC-128.1 03-26-91 NIA A45 NIA NAC-128.1 03-26-91 NIA A47 NIA NAC-128.1 03-26-91 NIA A48 NIA NAC-128.1 03-26-91 NIA A51 NIA NAC-128.1 03-26-91 NIA A53 NIA

-urry Monthly Operating Report No. 91-03 Page 19 of 20 Nominal New or Spent Initial Fuel Shipping Enrichment Cask Activity 1.87 NIA 1.87 NIA 1.87 NIA 1.87 NIA 1.87 NIA 1.87 NIA

.urry Monthly Operating Report No. 91-03 Page 20 of 20 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS Number PT-53.3 2-PT-18.61 MONTH/VEAR: March 1991 High Energy Line Inspection Pressurizer Block Valve Stroke Test LERNo S1-91-001-00 S2-91-001-00