ML18153C599

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Monthly Operating Repts for Mar 1991 for Surry Power Station Units 1 & 2.W/910415 Ltr
ML18153C599
Person / Time
Site: Surry  Dominion icon.png
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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e e VrROINIA ELECTRIC AND PowER COMPANY RICHMOND, VIRGiNIA 23261 April 15, 1991 U. S. Nuclear Regulatory Commission Serial No.91-206 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 MONTHLY OPERATING REPORT 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 \

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 - ~-

Date 1I

aurry Monthly Operating Report No. 91-03 Page 2 of 20 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 ........................................... 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 Docket No.: 50-280 Date: 04-03-91 Completed By: M.A. Negron Telephone: 804-365-2795

1. Un~ Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . March 1991
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):

1 O. Reasons For Restrictions, If Any:

This Month YID Cumulative

11. Hours In Reporting ................................... . 744.0 2160.0 160176.0
12. Number of Hours Reactor Was Critical ........ .. 744.0 2160.0 101634.2
13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 3774.5
14. Hours Generator On-Line .......................... . 744.0 2160.0 99640.2
15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... . 1791731.0 5232540.0 231452450.3
17. Gross Electrical Energy Generated (MWH) ... . 604070.0 1769450.0 75346273.0
18. Net Electrical Energy Generated (MWH) ....... . 573968.0 1685391.0 71468520.0
19. Unit Service Factor .................................. . 100.0% 100.0% 62.2%
20. Unit Availability Factor............................. .. 100.0% 100.0% 64.5%
21. Unit Capacity Factor (Using MDC Net) ......... .. 98.8% 99.9% 57.6%
22. Unit Capacity Factor (Using DER Net) ......... .. 97.9% 99.0% 56.6%
23. Unit Forced Outage Rate ........................... . 0.0% 0.0% 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):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

41tsurry Monthly Operating Report No. 91-03 Page 4 of 20 OPERATING DATA REPORT Docket No.: 50-281 Date: 04-03-91 Completed By: M.A. Negron Telephone: 804-365-2795

1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . March 1991
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 YID Cumulative

11. Hours In Reporting ................................... . 744.0 2160.0 157056.0
12. Number of Hours Reactor Was Critical. ........ . 720.0 2136.0 101308.3
13. Reactor Reserve Shutdown Hours ............... . 0.0 0.0 328.1
14. Hours Generator On-Line .......................... . 698.8 2114.8 99685.4
15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ..... . 1387703.0 4493943.2 232629411.5
17. Gross Electrical Energy Generated (MWH) ... . 467470.0 1510315.0 75740429.0
18. Net Electrical Energy Generated (MWH) ....... . 442007.0 1432860.0 71811585.0
19. Unit Service Factor .................................. . 93.9% 97.9% 63.5%
20. Unit Availability Factor .............................. . 93.9% 97.9% 63.5%
21. Unit Capacity Factor (Using MDC Net) .......... . 76.1% 84.9% 58.7%
22. Unit Capacity Factor (Using DER Net) .......... . 75.4% 84.2% 58.0%
23. Unit Forced Outage Rate ........................... . 0.0% 0.0% 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: 06-05-91
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION I~

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 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-03-91 Completed by: M. A. Negron Telephone: 804-365-2795 (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 03-07-91 s 0 B 4 N/A TA V Ramped unit to 70% power to perform 1-PT-29.1 (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)

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 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-03-91 Completed by: M. A. Negron Telephone: 804-365-2795 (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 03-30-91 s 45.2 C 1 NIA NIA NIA Shut Unit down in accordance with applicable operating procedures for a scheduled refueling outage. Duration expected to be 67 days.

(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 -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 Month: March 1991 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 782 17 783 2 784 18 720 3 785 19 679 4 785 20 681 5 786 21 725 6 786 22 779 7 720 23 784 8 788 24 785 9 790 25 784 10 790 26 777 11 788 27 783 12 785 28 783 13 783 29 783 14 783 30 786 15 783 31 785 16 783 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.

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 Month: March 1991 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 1 700 17 629 2 700 18 623 3 698 19 617 4 691 20 610 5 686 21 605 6 679 22 600 7 673 23 593 8 670 24 588 9 666 25 580 10 662 26 575 11 657 27 569 12 653 28 564 13 645 29 550 14 643 30 19 15 639 31 0.0 16 634 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.

&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 0000 This reporting period started with the Unit operating at 100% power and 825 MWe.

03-07-91 0958 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.

03-18-91 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.

03-21-91 1355 Started ramp up after return to service of the first point feedwater heaters; 89% power, 740MWe.

1504 Stopped ramp; 100% power, 820 MWe.

03-31-91 2400 This report period ended with the Unit operating at 100% power and 825 MWe.

UNIT TWO 03-01-91 0000 This report period started with the Unit operating at 90% power and 740 MWe.

03-03-91 0717 Commence end of cycle unit coastdown.

03-29-91 2200 Started unit shutdown for the refueling outage; 73% power, 595 MWe.

03-30-91 0249 Unit offline.

0344 Reactor manually tripped.

03-31-91 2400 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 MONTH/YEAR: March 1991 EWR 89-703 Engineering Work Request 03-13-91 (Safety Evaluation No.90-002)

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.

AC S2-91-0304 Administrative Control 03-05-91 (Safety Evaluation No.91-041)

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.

TSR 91-013 Temporary Shielding Request 03-05-91 (Safety Evaluation No.91-044)

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 MONTH/YEAR: March 1991

[continued]

JCO 91-3-001 Justification for Continued Operation 03-07-91 (Safety Evaluation No.91-048)

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.

TM S1-91-006 Temporary Modification 03-08-91 (Safety Evaluation No.91-049)

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.

AC S1 0314 Administrative Control 03-14-91 (Safety Evaluation No.91-055)

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 MONTH/VEAR: March 1991

[continued]

AC S1-91-0314A Administrative Control 03-15-91 (Safety Evaluation No.91-057)

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.

CAL SM-787 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.

TSR 91-023 Temporary Shielding Request 03-26-91 (Safety Evaluation No.91-066)

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 MONTH/VEAR: March 1991

[continued]

AC S1 0321 Administrative Control 03-28-91 (Safety Evaluation No.91-070)

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.

AC S1-91-0320 Administrative Control 03-28-91 (Safety Evaluation No.91-071)

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.

AC S1-91-0320A Administrative Control 03-28-91 (Safety Evaluation No.91-072)

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.

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

[continued]

TSR 91-028 Temporary Shielding Request 03-28-91 TSR 91-038 (Safety Evaluation No.91-074)

TSR 91-039 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.

.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 2-0PT-22-001 Periodic Test Procedure 3-21-91 (Safety Evaluation No.91-064)

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.

2-0PT-22-002 Periodic Test Procedure 3-25-91 (Safety Evaluation No.91-063)

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 -urry Monthly Operating Report No. 91-03 Page 17of 20 CHEMISTRY REPORT MONTH/YEAR: March 1991 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. AvQ. Max. Min. Ava.

Gross Radioact., µCi/ml 7.15E-1 3.42E-1 5.06E-1 2.59E-1 9.85E-3 1.26E-1 Suspended Solids, oom 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, µCi/ml 3.84E-1 3. 71 E-1 3.79E-1 1.67E-1 1.21 E-1 1.43E-1 1131, µCi/ml 3.37E-3 1.41 E-3 1.87E-3 9.31 E-4 3.37E-4 5.52E-4 1131/I133 0.17 0.07 0.10 0.15 0.06 0.10 HydroQen, cc/kQ 48.5 32.4 37.7 39.7 3.5 26.8 Lithium, oom 2.44 2.05 2.18 0.96 0.28 0.73 Boron - 10, oom* 157.2 141.9 149.5 321 0.20 39.8 OxyQen, (DO), ppm <0.005 <0.005 <0.005 1.0 <0.005 0.067 Chloride, oom 0.007  :,;0.001 0.003 0.007  :,;0.001 0.002 pH at 25 dearee Celsius 6.67 6.52 6.60 9.29 5.36 7.95 Boron - 1O = Total Boron x 0.196 Comments:

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 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]

-urry Monthly Operating Report No. 91-03 Page 19 of 20 FUEL HANDLING 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 A44 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A45 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A47 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A48 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A51 NIA 1.87 NIA NAC-128.1 03-26-91 NIA A53 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 MONTH/VEAR: March 1991 Number LERNo PT-53.3 High Energy Line Inspection S1-91-001-00 2-PT-18.61 Pressurizer Block Valve Stroke Test S2-91-001-00

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