ML18153C842

Monthly Operating Repts for Nov 1991 for Surry Power Station Units 1 & 2.W/911213 Ltr

ML18153C842
Person / Time
Site:	Surry
Issue date:	11/30/1991
From:	Negron M, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-730, NUDOCS 9112180168
Download: ML18153C842 (20)

Text

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 13, 1991 U. S. Nuclear Regulatory Commission Serial No.91-730 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 November 1991.

Very truly yours, dL~

W. r'... 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. M. W. Branch NRC Senior Resident Inspector Surry Power Station

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 91-11 Approved:

• - TABLE OF CONTENTS e Surry Monthly Operating Report No.91-11 Page 2 of 19 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 NRG Approval ............................................................................... 1O Procedure or Method of Operation Changes That Did Not Require NRG Approval ........................................... 15 Tests and Experiments That Did Not Require NRG 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 ................................................................................................... 19

• - OPERATING DATA REPORT e Surry Monthly Operating Report No.91-11 Page 3 of 19 Docket No.: 50-280 Date: 12-05-91 Completed By: M.A. Negron Telephone: 804-365-2795

1. Unit Name: .................................................. . Surry Unit 1

2. Reporting Period: ......................................... . November 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 YTD Cumulative

11. Hours In Reporting Period .......................... 720.0 8016.0 166032.0

12. Number of Hours Reactor Was Critical .......... 720.0 8016.0 107490.2

13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 3774.5

14. Hours Generator On-Line ........................... 720.0 8016.0 105496.2

15. Unit Reserve Shutdown Hours ..................... 0.0 0.0 3736.2

16. Gross Thermal Energy Generated (MWH) ...... 1756404.0 19084705.4 245304615.7

17. Gross Electrical Energy Generated (MWH) .... 589260.0 6328030.0 79904853.0

18. Net Electrical Energy Generated (MWH) ........ 561041.0 6010282.0 75793411.0

19. Unit Service Factor ................................... 100.0% 100.0% 63.5%

20. Unit Availability Factor ............................... 100.0% 100.0% 65.8%

21. Unit Capacity Factor (Using MDC Net) ........... 99.8% 96.0% 58.9%

22. Unit Capacity Factor {Using DER Net) ........... 98.9% 95.2% 57.9%

23. Unit Forced Outage Rate ............................ 0.0% 0.0% 19.4%

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

Refueling, February 15, 1991, 64 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

• - OPERATING DATA REPORT e Surry Monthly Operating Report No. 91-11 Page 4of 19 Docket No.: 50-281 Date: 12-05-91 Completed By: M.A. Negron Telephone: 804-365-2795

1. Unit Name: .................................................. . Surry Unit 2

2. Reporting Period: ......................................... . November 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 YTD Cumulative

11. Hours In Reporting Period ......................... . 720.0 8016.0 162912.0

12. Number of Hours Reactor Was Critical ......... . 720.0 5461.5 104633.8

13. Reactor Reserve ~hutdown Hours .............. . 0.0 0.0 328.1

14. Hours Generator On-Line .......................... . 720.0 5337.2 102907.8

15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) ..... . 1679485.9 11418653.3 239554121.6

17. Gross Electrical Energy Generated (MWH) ... . 557720.0 3761100.0 77991214.0

18. Net Electrical Energy Generated (MWH) ....... . 530616.0 3563984.0 73942709.0

19. Unit Service Factor .................................. . 100.0% 66.6% 63.2%

20. Unit Availability Factor .............................. . 100.0% 66.6% 63.2%

21. Unit Capacity Factor (Using MDC Net) .......... . 94.4% 56.9% 58.2%

22. Unit Capacity Factor (Using DER Net) .......... . 93.5% 56.4% 57.6%

23. Unit Forced Outage Rate ........................... . 0.0% 16.0% 15.3%

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

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

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

• -UNIT SHUTDOWN AND POWER REDUCTION e Surry Monthly Operating Report No.91-11 Page 5 of 19

{EQUAL To OR GREATER THAN 20%)

REPORT MONTH: November 1991 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12-05-91 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 None during this reporting period.

(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)

UNIT SHUTDOWN AND POWER REDUCTION e Surry Monthly Operating Report No.91-11 Page 6 of 19 (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: November 1991 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12-05-91 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 11-01-91 F 0 F 4 NIA KD Cond Ramped unit from 47% to 29%

when a chemistry action level was entered due to condenser tube leaks.

(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)

• - AVERAGE DAILY UNIT POWER LEVEL e Surry Monthly Operating Report No. 91-11 Page 7 of 19 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12-05-91 Completed by: M.A. Negron Telephone: 804-365-2795 Month: November 1991 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 777.9 17 783.0 2 772.8 18 783.5 3 779.5 19 782.5 4 776.0 20 779.6 5 779.7 21 778.9 6 782.5 22 778.3 7 781.5 23 779.3 8 779.1 24 776.0 9 781.5 25 771.5 10 783.3 26 773.1 11 783.8 27 771.8 12 784.6 28 773.2 13 783.7 29 774.8 14 784.0 30 778.5 15 782.7 31 16 780.3 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.

• - AVERAGE DAILY UNIT POWER LEVEL e Surry Monthly Operating Report No.91-11 Page 8 of 19 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12-05-91 Completed by: M.A. Negron Telephone: 804-365-2795 Month: November 1991 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe-Net) 1 299.3 17 779.9 2 346.3 18 767.8 3 591.4 19 768.3 4 730.7 20 781.6 5 770.0 21 780.9 6 775.2 22 775.2 7 765.2 23 765.2 8 749.5 24 776.5 9 778.8 25 777.5 10 780.9 26 774.3 11 783.2 27 774.6 12 782.5 28 774.5 13 782.6 29 769.5 14 781.5 30 761.8 15 782.0 31 16 782.3 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.

SUMMARY

OF OPERATING EXPERIENCE

• Surry Monthly Operating Report No. 91-11 Page 9 of 19 MONTH/YEAR: November 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 11-01-91 0000 This report period started with the Unit operating at 100% power, 815 MWe.

11-30-91 2400 This report period ended with the Unit operating at 100% power, 830 MWe.

UNIT TWO 11-01-91 0000 This report period started with the Unit operating at 56% power, 430 MWe due to secondary chemistry concerns.

0800 Started ramp down to maintain condenser vacuum while repairing tube leaks in waterboxes; 56% power, 420 MWe.

0823 Stopped ramp at 47% power, 330 MWe.

1408 Started ramp down due to entry into secondary chemistry action level resulting from condenser tube leaks; 47% power, 370 MWe.

1501 Stopped ramp at 29% power, 240 MWe.

11-02-91 0457 Started raising unit power; 29% power, 240 MWe.

11-03-91 2101 Stopped power increase at 98% power, 770 MWe.

11-05-91 0409 Raised Unit power to 100% power, 820 MWe.

11-30-91 2400 This report period ended with the Unit operating at 100% power, 795 MWe with "C" waterbox out of service to repair traveling fish screen (1-CW-S-8C).

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL e Surry Monthly Operating Report No. 91-11 Page 10 of 19 MONTH/YEAR: November 1991 TM S2-91-46 Temporary Modification 11-03-91 (Safety Evaluation No.91-237)

- This Temporary Modification (TM) lifted an electrical lead to remove the undervoltage lockout for the Unit 2 Charging Pump "A" to prevent the potential loss of high head safety injection (assuming the active failure to be the "B" charging pump powered from the emergency bus "J" or emergency diesel generator number 3) in the event of a simultaneous design basis accident and emergency bus "H" undervoltage condition.

Each unit has three charging pumps with two required to be operable. One pump is normally operating and the other pump is in standby designed to start automatically upon receipt of an engineered safeguards feature (ESF) signal.

One of the three pumps can be supplied from either emergency electrical bus

("H" or "J" bus). The charging pump electrical supply breakers are equipped with interlock logic to ensure that only one charging pump can be supplied from an emergency bus at any given time. One such interlock for the "A" pump can stop the pump or prevent the pump from auto-starting in one operational configuration. This TM ensures that Unit 2 Charging Pump "A" will continue to operate or automatically start following receipt of an ESF signal coincident with a loss of offsite power. This TM does not affect Emergency Diesel Generator loading and assures the proper equipment response during accident conditions.

Therefore, an unreviewed safety question is not created._

DCP 90-031-2 Design Change Package 11-05-91 This Design Change Package (DCP) relocated Unit 2 Appendix "R" emergency lighting fixtures 2-FP-ELT-20 and 2-FP-ELT-21 to facilitate maintenance of the lights and to improve the illumination characteristics.

This modification did not affect other equipment or systems, nor did it affect Appendix "R" compliance. Therefore, an unreviewed safety question is not created.

TM S1-91-25 Temporary Modification 1,1 91 (Safety Evaluation No. 91 -240)

This Temporary Modification (TM) provides an alternate water supply (Fish Screens system) to the Vacuum Priming (VP) system seal recirculation subsystem until the normal well water supply pump is returned to service.

This TM will enable the nonsafety-related VP system to operate normally with the alternate water supply. Therefore, an unreviewed safety question is not created.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL e Surry Monthly Operating Report No. 91-11 Page 11 of 19 MONTH/YEAR: November 1991

[continued]

EWR 89-313 Engineering Work Request 11-08-91 This Engineering Work Request (EWR) replaced an existing analog ventilation vent radiation monitor ratemeter with a digital ratemeter.

A backup channel was in service during the installation and testing of the new equipment. Prior to being placed in service, the new equipment was fully tested and operators were instructed on its use. Therefore, an unreviewed safety question is not created.

TM S2-91-47 Temporary Modification 11-10-91 (Safety Evaluation No.91-241)

This Temporary Modification (TM) lifted an electrical lead to remove the undervoltage lockout for the Unit 2 Charging Pump "A" to prevent the potential loss of high head safety injection (assuming the active failure to be the "B" charging pump powered from the emergency bus "J" or emergency diesel generator number 3) in the event of a simultaneous design basis accident and emergency bus "H" undervoltage condition.

Each unit has three charging pumps with two required to be operable. One pump is normally operating and the other pump is in standby designed to start automatically upon receipt of an engineered safeguards feat"ure (ESF) signal.

One of the three pumps can be supplied from either emergency electrical bus

("H" or "J" bus). The charging pump electrical supply breakers are equipped with interlock logic to ensure that only one charging pump can be supplied from an emergency bus at any given time. One such interlock for the "A" pump can stop the pump or prevent the pump from auto-starting in one operational configuration. This TM ensures that Unit 2 Charging Pump "A" will continue to operate or automatically start following receipt of an ESF signal coincident with a loss of offsite power. This TM does not affect Emergency Diesel Generator loading and assures the proper equipment response during accident conditions.

Therefore, an unreviewed safety question is not created.

TM S2-91-48 Temporary Modification 11-10-91 (Safety Evaluation No.91-242)

This Temporary Modification (TM) removed the Unit 2 Vacuum Priming (VP) system vent valve, 2-VP-31, and installed a blank flange and temporary one inch valve to permit piping repairs to be completed while allowing the VP system and the "2D" condenser waterbox to remain in service.

This TM only affects the nonsafety-related VP system and does not pose* an internal flooding concern, since the modification is located above the intake canal level. Therefore, an unreviewed safety question is not created.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL e Surry Monthly Operating Report No.91-11 Page 12 of 19 MONTH/YEAR: November 1991

[continued]

TM S1-91-26 Temporary Modification 11-17-91 (Safety Evaluation No.91-245)

This Temporary Modification (TM) connected a test resistor and flow recorder to'the control room ventilation panel 1/E converter to enable an evaluation of the Unit 1 vent stack flow indicator, 1-VS-Fl-116.

This TM was installed on a nonsafety-related portion of the system and does not affect system operability, except for the short period during which electrical leads were landed. Technical Specifications requirements, including the establishment of a preplanned alternate method of monitoring, are being adhered to while the TM is in place. Therefore, an unreviewed safety question is not created.

TM S2-91-49 Temporary Modification 11-17-91 2-TOP-3068 Temporary Operating Procedure (Safety Evaluation No.91-246)

This Temporary Modification (TM) removed the Unit 2 containment sump trip valve 2-DA-TV-200A for overhaul and installed a blank flange on the downstream side piping and a flanged hose connection with a jumper hose to the Gaseous Drains (DG) system on the upstream side. ,

Installation of this TM and its operation in accordance with Temporary Operating Procedure, 2-TOP-3068, allow the Unit 2 containment sump to be pumped down while maintaining containment integrity for both normal and

.emergency conditions. Therefore, an unreviewed safety question is not created.

DCP 90-034-2 Design Change Package 11-19-91 (Safety Evaluation No.91-422)

This Design Change Package (DCP) replaced Unit 2 feedwater flow elements 2-FW-FE-2476, 2-FW-FE-2486 and 2-FW-FE-2496 and adjoining piping with new flow elements and piping constructed of erosion/corrosion resistant materials.

The new piping and flow elements were hydrostatically tested following installation and the feedwater flow instrument loops were recalibrated. This modification was essentially a one-for-one replacement of an enhanced design and did not affect the operation or ability of the equipment to perform its intended function. Therefore, an unreviewed safety question is not created.

e e Surry Monthly Operating Report No.91-11 Page 13 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: November 1991

[continued]

DCP 91-031-3 Design Change Package 11-20-91 This Design Change Package (DCP) installed flow limiting spray shields over the Service Water system expansion joints in the supply piping for the Bearing and Component Cooling heat exchangers.

The flow limiting spray shields are passive devices that do not alter the expansion joints or impact their function or operation. Therefore, an unreviewed safety question is not created.

AC S1-91-1122 Administrative Control 11-22-91 (Safety Evaluation No.91-248)

Administrative Control of the Unit 2 Emergency Switchgear room (ESGR)/Turbine Building door was established during testing of ESGR drain backflow preventers. The controls included a person stationed at the door to the ESGR from the Turbine building. The person's duties were to immediately isolate and disconnect temporary testing hoses routed through the door and close the door in the event of a main control room (MCR) air bottle bank discharge. The person also performed the required fire watch responsibilities while the door was open.

The controls for the subject door ensured the capability of the MCR/ESGR pressure envelope to achieve the proper positive pressure for minimizing the potential for exposure of MCR personnel to radioactivity releases in the event of design basis accidents. Therefore, an unreviewed safety question is not created.

TM S1-91-27 Temporary Modification 11-26-91 (Safety Evaluation No.91-249)

This Temporary Modification (TM) installed electrical jumpers to permit the replacement of Unit 1 Reactor Protection System (RPS) "B" train test switch, LC-496-TB.

This TM only affected RPS train "B" and enabled the protective functions of the "C" steam generator Hi-level signal to be maintained. RPS trains "A" and "B" were able to perform their intended safety function. Therefore, an unreviewed safety question did not exist.

e Surry Monthly Operating Report No.91-11 Page 14 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November 1991

[continued]

TM S1-91-28 Temporary Modification 11-27-91 (Safety Evaluation No.91-252)

This Temporary Modification (TM) lifted an electrical lead to remove the undervoltage lockout for the Unit 1 Charging Pump "A" to prevent the potential loss of high head safety injection (assuming the active failure to be the "B" charging pump powered from the emergency bus "J" or emergency diesel generator number 3) in the event of a simultaneous design basis accident and emergency bus "H" undervoltage condition.

Each unit has three charging pumps with two required to be operable. One pump is normally operating and the other pump is in standby designed to start automatically upon receipt of an engineered safeguards feature (ESF) signal.

One of the three pumps can be supplied from either emergency electrical bus

("H" or "J" bus). The charging pump electrical supply breakers are equipped with interlock logic to ensure that only one charging pump can be supplied from an emergency bus at any given time. One such interlock for the "A" pump can stop the pump or prevent the pump from auto-starting in one operational configuration. This TM ensures that Unit 1 Charging Pump "A" will continue to operate or automatically start following receipt of an ESF signal coincident with a loss of offsite power. This TM does not affect Emergency Diesel Generator loading and assures the proper equipment response during accident conditions.

Therefore, an unreviewed safety question is not created.

JCO C-91-006 Justification tor Continued Operation 11-29-91 (Safety Evaluation No.91-253)

This Justification for Continued Operation (JCO) assessed the degraded condition of the Unit 1 and 2 condenser outlet waterbox expansion joints, 1-CW-REJ-1018 and 2-CW-REJ-2018, with respect to the continued operation of Units 1 and 2 until the subject expansion joints can be replaced.

The assessment concluded that the degraded condition of the expansion joints does not increase the consequences of failure beyond those previously analyzed in the Safety Analysis Report or the Individual Plant Evaluation (IPE) Analysis.

Therefore, an unreviewed safety question does not exist.

PROCEDURES OR METHOD OF OPERATION CHANGES e Surry Monthly Operating Report -

No.91-11 Page 15 of 19 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November 1991 None during this reporting period.

• - e TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL Surry Monthly Operating Report No.91-11 Page 16 of 19 MONTH/VEAR: November 1991 None during this reporting period.

-- CHEMISTRY REPORT e Surry Monthly Operating Report No. 91-11 Page 17 of 19 MONTH/YEAR: November 1991 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Ave~. Max. Min. Avg.

Gross Radioact., µCi/ml 8.56E-1 5.31 E-1 6.20E-1 3.00E-1 1.20E-2 1.89E-1 Suspended Solids, oom 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, uCi/ml 2.49E-1 2.09E-1 2.31 E-1 3.80E-1 1.89E-1 2.93E-1 1131, uCi/ml 3.86E-3 1.80E-3 2.45E-3 1.79E-3 1.66E-4 3.27E-4 113111133 0.15 0.08 0.11 0.12 0.07 0.09 Hydrogen, cc/kg 45.2 27.1 36.4 45.8 30.1 35.4 Lithium, oom 1.84 1.39 1.64 2.63 2.06 2.23 Boron - 1o, oom* 42.5 27.4 35.1 301.6 228.7 239.0 OxyQen, (DO), oom <0.005 <0.005 <0.005 <0.005 <0.005 <0.005 Chloride, oom 0.003 <0.001 0.002 0.006 0.003 0.004 pH at 25 degree Celsius 7.44 7.26 7.36 6.60 6.28 6.39 Boron - 10 = Total Boron x 0.196 Comments: None

,~

• - FUEL HANDLING e Surry Monthly Operating Report No. 91-11 Page 18 of 19 UNITS 1 & 2 MONTH/YEAR: November 1991 Units One and Two New or Spent Newer Number for Fuel Shipping Spent Fuel Assemblies Assembly ANSI Initial Cask Activity Shiement No. Date Stored eer Shiement Number Number Enrichment Level LMO NIA 11-13-91 NIA E01 07X 2.61 NIA LMO NIA 11-13-91 NIA H02 10W 2.62 NIA LMO NIA 11-13-91 NIA H03 10T 2.62 NIA LMO NIA 11-13-91 NIA H04 104 2.62 NIA LMO NIA 11-13-91 NIA H05 10S 2.62 NIA LMO NIA 11-13-91 NIA H06 1oz 2.62 NIA LMO NIA 11-13-91 NIA H07 10Y 2.62 NIA LMO NIA 11-13-91 NIA H09 10G 2.62 NIA LMO NIA 11-13-91 NIA H10 10P 2.62 NIA LMO NIA 11-13-91 NIA H11 10P 2.62 NIA LMO NIA 11-13-91 NIA H12 106 2.62 NIA LMO NIA 11-13-91 NIA E03 07Z 2.61 NIA LMO NIA 11-13-91 NIA H13 10J 2.62 NIA LMO NIA 11-13-91 NIA H14 1R6 2.62 NIA LMO NIA 11-13-91 NIA H15 1R2 2.62 NIA LMO NIA 11-13-91 NIA H16 1RO 2.62 NIA LMO NIA 11-13-91 NIA H18 1R1 2.62 NIA LMO NIA 11-13-91 NIA E04 OBN 2.61 NIA LMO NIA 11-13-91 NIA E05 07S 2.61 NIA LMO NIA 11-13-91 NIA E06 085 2.61 NIA LMO NIA 11-13-91 NIA E07 07V 2.61 NIA LMO NIA 11-13-91 NIA E11 070 2.61 NIA LMO NIA 11-13-91 NIA E12 072 2.61 NIA LMO NIA 11-13-91 NIA H01 10v 2.62 NIA

-e e Surry Monthly Operating Report No.91-11 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/VEAR: November 1991 None During This Reporting Period.