ML18153A386

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Monthly Operating Repts for Nov 1997 for Surry Power Station,Units 1 & 2.W/971211 Ltr
ML18153A386
Person / Time
Site: Surry  Dominion icon.png
Issue date: 11/30/1997
From: Fanguy M, Kilmer J, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
97-727, NUDOCS 9712180330
Download: ML18153A386 (19)
v • d • e


Text

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e e VIRGINIA ELECTRIC A~D POWER COMPANY

.... RICHMOND, VIRGINIA 23261 December 11,1997 United States Nuclear Regulatory Commission Serial No.97-727 Attention: Document Control Desk SPS Lic/JDK RO 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 MONTHLV OPERATING REPORT The Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of November 1997 is provided in the attachment.

If you have any questions or require additional information, please contact us.

Very truly yours, b...w~

D. A. Christian, Station Manager Surry Power Station Attachment Commitments made by this letter: None cc: U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, S. W.

Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station 1

j - - - - 9712180330 971130 ~_:, ' ) J --1 ,*1,_111111111111111 11111 11111B111111B11111.n:

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' m y Monthly Operating Report No. 97-11 Page 1 of 18 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 97-11 Approved:

Station Manager

e Surry Monthly Operating Report No. 97-11 Page 2 of 18 TABLE OF CONTENTS Section Page Operating Data Report - Unit No. 1 ..................................................................................................................... 3 Operating Data Report - Unit No. 2 ..................................................................................................................... 4 Unit Shutdowns and Power Reductions - Unit No. 1 ............................................................................................ 5 Unit Shutdowns and Power Reductions - Unit No. 2 ............................................................................................ 6 Average Daily Unit Power Level - Unit No. 1........................................................................................................ 7 Average Daily Unit Power Level - Unit No. 2 ........................................................................................................ 8 Summary of Operating Experience - Unit Nos. 1 and 2 ........................................................................................ 9 Facility Changes That Did Not Require NRC Approval ....................................................................................... 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval ............................................. 14 Tests and Experiments That Did Not Require NRC Approval ............................................................................. 15 Chemistry Report .............................. ,............................................................................................................... 16 Fuel Handling - Unit Nos. 1 and 2 ...................................................................................................................... 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................................. 18

e Surry Monthly Operating Report No. 97-11 Page 3 of 18 OPERATING DATA REPORT Docket No.: 50-280 Date: 11/1/97 Completed By: D. K. Mason Telephone: (757) 365-2459

1. Unit Name: ........................................................ . Surry Unit 1
2. Reporting Period: ............................................... . November, 1997
3. Licensed Thermal Power (MWt): ........................ . 2546
4. Nameplate Rating (Gross MWe): ....................... . 847.5
5. Design Electrical Rating (Net MWe): ................. .. 788
6. Maximum Dependable Capacity (Gross MWe): .. . 840
7. Maximum Dependable Capacity (Net MWe): ...... . 801
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 Year-To-Date Cumulative

11. Hours in Reporting Period 720.0 8016.0 218640.0
12. Hours Reactor Was Critical 720.0 6447.1 153281.8
13. Reactor Reserve Shutdown Hours 0.0 0.0 3774.5
14. Hours Generator On-Line 720.0 6324.5 150855.5
15. Unit Reserve Shutdown Hours 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) 1828842.7 15715408.9 354350852. 7
17. Gross Electrical Energy Generated (MWH) 610826.0 5208489.0 116181307.0
18. Net Electrical Energy Generated (MWH) 590437.0 5026275.0 110620024. 0
19. Unit Service Factor 100.0% 78.9% 69.0%
20. Unit Availability Factor 100.0% 78.9% 70.7%
21. Unit Capacity Factor (Using MDC Net) 102.4% 78.3% 65.0%
22. Unit Capacity Factor (Using DER Net) 104.1% 79.6% 64.2o/~
23. Unit Forced Outage Rate 0.0% 4.3% 14.8%
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

e e Surry Monthly Operating Report No. 97-11 Page 4of 18 OPERATING DATA REPORT Docket No.: 50-281 Date: 11/01/97 Completed By: D. K. Mason Telephone: (757) 365-2459

1. Unit Name: ........................................................ . Surry Unit 2
2. Reporting Period: ............................................... . November, 1997
3. Licensed Thermal Power (MWt): ........................ . 2546
4. Nameplate Rating (Gross MWe): ....................... . 847.5
5. Design Electrical Rating (Net MWe): .................. . 788
6. Maximum Dependable Capacity (Gross MWe): .. . 840
7. Maximum Dependable Capacity (Net MWe): ...... . 801
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.

12.

Hours in Reporting Period Hours Reactor Was Critical This Month 720.0 720.0 Year-To-Date 8016.0 7363.9 Cumulative 215520.0 150439.5

~

13. Reactor Reserve Shutdown Hours 0.0 0.0 328.1
14. Hours Generator On-Line 720.0 7329.8 148427.6
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1745130.4 18374734.3 349848991 .1
17. Gross Electrical Energy Generated (MWH) 585680.0 6110449.0 114561248.0
18. Net Electrical Energy Generated (MWH) 566236.0 5905174.0 109097053. 0
19. Unit Seniice Factor 100.0% 91.4% 68.9%
20. Unit Availability Factor 100.0% 91.4% 68.9%
21. Unit Capacity Factor (Using MDC Net) 98.2% 92.0% 64.8%
22. Unit Capacity Factor (Using DER Net) 99.8% 93.5% 64.2%
23. Unit Forced Outage Rate 0.0% 1.0% 12.0%
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

e e Surry Monthly Operating Report No. 97-11 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: NOVEMBER, 1997 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12-01-97 Completed by: M. J. Fanguy Telephone: (757) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to Prevent Recurrence Down Rx 11/14/97 s NA B NA NA TA V Power reduction for Turbine Valve Freedom Testing (1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram C Refueling 3 - Automatic Scram D Regulatory Restriction 4 - other (Explain)

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

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source for Licensee Event Report (LER) File (NUREG 0161)

e Surry Monthly Operating Report No. 97-11 Page 6 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: NOVEMBER, 1997 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12-01-97 Completed by: M. J. Fanguy Telephone: (757) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to Prevent Recurrence Down Rx None During the 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 (NU REG 0161)

e e Surry Monthly Operating Report No. 97-11 Page 7 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12-01-97 Completed by: J. D. Kilmer Telephone: (757) 365-2792 MONTH: NOVEMBER, 1997 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 819 17 823 2 819 18 825 3 819 19 824 4 819 20 823 5 819 21 824 6 820 22 824 7 821 23 826 8 822 24 830 9 822 25 825 10 818 26 825 11 821 27 825 12 802 28 825 13 811 29 825 14 772 30 825 15 824 16 824 INSTRUCTIONS On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.

e e Surry Monthly Operating Report No. 97-11 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12-01-97 Completed by: John D. Kilmer Telephone: (757) 365-2792 MONTH: NOVEMBER, 1997 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 183 17 827 2 424 18 826 3 671 19 826 4 791 20 827 5 823 21 827 6 822 22 827 7 826

  • 23 827 8 827 24 827 9 828 25 831 10 828 26 832.

11 830 27 832 12 831 28 831 13 827 29 831 14 827 30 832 15 828 16 827 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.

. r r y Monthly Operating Report No. 97-11 Page 9 of 18

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: NOVEMBER, 1997 The following 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:

11/01/97 0000 Unit 1 starts the month at 100% / 847 MWe.

11/14/97 0530 Start power decrease to perform 1-0SP-TM-001, "Turbine Inlet Valve Freedom Test".

1143 Stop power decrease at 73% for Intercept and Reheat Stop valve testing.

1405 Start power increase after completion of Turbine Inlet Valve Freedom Test.

1906 Stop power increase at 100% / 855 MWe.

11/30/97 2400 Unit 1 finishes the month at 100% / 855 MWe.

UNrrTwo:

11/01/97 0000 Unit 2 starts the month at 29.5% / 210 MWe holding for chemistry and flux map results.

11/02/97 0045 Chemistry hold cleared, start power increase.

1050 Stop power increase at 56% / 480 MWe to raise hi flux trip setpoint to 100% and rod stop setpoint to 96%.

1223 Start power increase.

1755 Stop power increase at 70% / 600 MWe for flux map.

11/03/97 0409 Start power increase.

11/04/97 0731 Stop power increase at 95% / 825 MWe.

11/04/97 1650 Start power increase based on ET 97-0367, Alternate Rx Power Indications.

1758 Stop power increase at 98% / 850 MWe for alternate power verification.

2055 Start power increase to 99% by Feed flow CALCALC.

2115 Stop power increase at 99% I 855 MWe.

11/06/97 1810 Swap to Steam flow CALCALC andstart power increase to 100%.

1840 Unit is at 100% / 855 MWe.

11/30/97 2400 Unit 2 finishes the month at 100% / 855 MWe.

e Surry Monthly Operating Report No. 97-11 Page 10 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: NOVEMBER, 1997 DCP 96-034 Design Change Package 10-18-97 (Safety Evaluation 96-127)

Design Change Package (DCP)96-034, installs equalization lines for 1-SI-MOV-1890 A/8 and 2-SI-MOV-2890 A/8 to prevent pressure locking of these valves. This modification was installed to meet the commitment specified in our response to GL 95-07. The valves will operate as originally designed. The addition of the pressure equalization line will provide the means to passively bleed off any fluid and pressure in the Motor Operated Valves (MOVs) bonnet cavity area between the discs. This ensures that those areas will not become a pressurized volume preventing the MOVs from opening. This task was completed during the October Unit 2 Refueling Outage.

For the previously analyzed accident (LOCA) there is no increase in the probability or consequences of this accident, nor does it create the possibility for an accident of another type. For this modification, a failure of the equalization line would result in a small break LOCA and is not deemed a creditable accident. The modification is consistent with the design requirements, has been seismically analyzed and has no adverse effect on componenUsystem performance. Therefore, an unreviewed safety question does not exist.

DCP 94-047 Design Change Package 10-20-97 (Safety Evaluation 96-029)

Design Change Package (DCP)94-047, replaces the existing Steam Generator Slowdown (SGBD) coolers and adds an independent divert line to direct the coolers' condensate return flow to the main condenser. The existing coolers shell side design rating is inadequate to support current system operating condition. Additionally, the copper tubes are a contributing factor to the units copper carry over to the steam generators. This task was completed during the October Unit 2 Refueling Outage.

The systems affected by this design change are non-safety related. The design change does not affect the performance characteristics of any safety related system or component. Therefore, an unreviewed safety question does not exist.

DCP 96-020 Design Change Package 10-23-97 (Safety Evaluation 96-076 Rev 2)

Design Change Package 96-020, "Inadequate Core Cooling Monitor Firmware Modifications," revises the configuration data to allow the Inadequate Core Cooling Monitor (ICCM) to operate with two or more operable thermocouples in a quadrant in order to maintain a good quality average. The modification replaces two system electronic EPROMs and CPUs with a new CPU containing revised firmware for each train.

This modification was needed since a failure of a thermocouple in some quadrants of the core would result in a ICCM failure and entry into a seven day Limiting Condition of Operation to Hot Shutdown. This task was completed during the October Unit 2 Refueling Outage.

This change will not affect the measurements, calculations, or setpoints for the ICCM.

The Safety Analysis Report and Technical Specifications only require two operable thermocouples per quadrant per train. Since the Technical Specification requirements and design criteria continue to be satisfied, the margin of safety is not reduced.

Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 97-11 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: NOVEMBER, 1997 DCP 94-030 Design Change Package 10-24-97 (Safety Evaluation 95-055)

Design Change Package (DCP)94-030, changes Instrument scaling and protection system setpoints because the rated thermal power of the reactor will be increased from 2441 MWt to 2546 MWt. Operating with higher reactor thermal output impacts both primary and secondary system parameters. The impact of these uprated parameters has been evaluated in the Core Uprating Licensing Report. With minor modifications, the plant is capable of supporting operation at uprated conditions. The last action required for Core Uprate was the respanning of steam flow and feed flow transmitters which could only be accomplished during a refueling outage. This task was completed during the October Unit 2 Refueling Outage.

During the implementation of the revised setpoints/scaling plant parameters will be conservative with respect to these functions. Following Uprating, certain systems or components will operate at different points within their design ranges. The protection functions and process controls will reflect the Uprated conditions. However, the system and component evaluations have shown that all design requirements are met. Therefore, an unreviewed safety question does not exist.

DCP 95-039 Design Change Package 10-27-97 (Safety Evaluation 96-116)

Design Change Package (DCP)95-039, improves the performance and reliability of the Turbine Driven Auxiliary Feedwater Pumps by removing the steam admission bypass valve, replacing the slip linkage of the Terry Turbine governor with a solid linkage and installs a new 3.5 inch thick spacer between the Woodward governor housing and governor servo. This task was completed during the October Unit 2 Refueling Outage.

The modifications performed by this DCP do not change or reduce the margin of safety of any section of the Technical Specification, does not create the possibility of an accident of a different type, or increase the probability of any applicable accident. Implementation of the DCP occurs with the respective Unit at Cold Shutdown. Therefore, an unreviewed safety question does not exist.

DCP 97-052 Design Change Package 10-27-97 (Safety Evaluation 97-145)

Design Change Package (DCP)97-052, repairs a leak of a reactor vessel head nozzle canopy seal weld using a Canopy Seal Clamp Assembly (CSCA). This task was completed during the October Unit 2 Refueling Outage.

The CSCA is supplied as a pressure retaining device and does not serve as a structural member. CSCAs are considered a permanent fix and are qualified as a ASME Code Section II I and XI replacement item. It is constructed of materials meeting ASME Sections II and Ill. The CSCA is designed as a Class I component for service involving 2500 psia and 650 °F. The CSCA will not affect RCS integrity. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 97-11 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: NOVEMBER, 1997 DCP 94-038 Design Change Package 11-24-97 (Safety Evaluation 94-122)

Design Change Package (DCP)94-038, installs mechanical jumpers to establish a flow path between fuel oil pump 1-EE-P-1E and the EOG No. 2 fuel oil tank 2-EE-TK-3 due to a leak in the existing piping. This task was completed during the October Unit 2 Refueling Outage.

The mechanical jumpers are the same size and class of material as the existing piping and were seismically installed. The change did not impact the design flow requirements of the system and did not alter the operation or function of the emergency diesel generators. Therefore, an unreviewed safety question does not exist.

TM S2-97-014 Temporary Modification 11-25-97 (Safety Evaluation No.97-152)

This Temporary Modification (TM) was performed to replace the damaged Unit 2 Instrument Air Flow Element 02-IA-FE-200 with a temporary spool piece pending receipt of back ordered repair parts.

The spool piece will be fabricated of materials conforming to the same piping class as the Containment Instrument Air System. The pressure ratings will be unchanged. The replacement spool piece is a pressure boundary of equal or superior quality to the Instrument Air Flow Element. Therefore, an unreviewed safety question does not exist.

DCP 95-032 Design Change Package 11-26-97 (Safety Evaluation 95-146)

Design Change Package (DCP)95-032, reworks the tubing after the removal of the unused functional on-line test circuitry for series "A" and "B" Solenoid Operated Valves (SOVs) and the partial closure test circuitry for the Main Steam Trip Valve. The wiring associated with the trip SOVs "A" and "B" for containment isolation and steam line break isolation is not being modified. This task was completed during the October Unit 2 Refueling Outage.

Leaks from tubing or an error in tubing rework would prevent the unit from leaving Cold Shutdown conditions or would close the MSTV while on line. The latter would initiate a reactor trip of Safety Injection which is within the boundaries of the safety analysis.

Therefore, an unreviewed safety question does not exist.

TM S2-97-015 Temporary Modification 11-26-97 (Safety Evaluation No.97-153)

This Temporary Modification (TM) allows the replacement of test switch PC-484-TA in the Unit 2 train "A" of the Safety Injection (SI) system. All work performed will be in the train "A" portion of the SI system only. Train "B" will remain unaffected and will function as designed at all times. With the jumpers installed, train "A" of the SI system will operate as designed.

The test switch replacement is a like-for-like replacement with no change to the design of the system or any station isolation. During the time of switch replacement both trains of SI will function as designed. Therefore, an unreviewed safety question does not exist.

e -Surry Monthly Operating Report No. 97-11 Page 13 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: NOVEMBER, 1997 TM S-97-019 Temporary Modification 11-26-97 (Safety Evaluation No.95-084 Rev 2)

Temporary Modification (TM) S-97-019 defeats the speed adjustment circuit of Hydro Test Pump 1-SI-P-2. The pump is set at a fixed speed that is capable of supporting accumulator operations.

The TM did not negatively impact the performance of the hydro test pump or the Safety Injection system. No fission product barriers or safety-related systems were affected.

Therefore, an unreviewed safety question does not exist.

e .

Surry Monthly Operating Report No. 97-11 Page 14 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID Nor REQUIRE NRC APPROVAL MONTHNEAR: NOVEMBER, 1997 HP-3010.031 Health Physics Procedure 11-13-97 (Safety Evaluation No.92-150)

Health Physics Procedure HP-3010.031, "Radioactive Gaseous Waste Sampling Analysis",

was revised to provide compensatory actions to sample the containment atmosphere on a four hour frequency. This is required when the skids associated with monitors 1-RM-RMS-159/160 and 2-RM-RMS-259/260 are removed from service for maintenance because the vacuum pump on the skid which moves air through the monitors will not be available. A particulate and iodine grab sample of containment atmosphere will be obtained using a portable air sampler using the existing sample valves on the monitor skid.

The Radiation Monitoring System is not a safety related system. Grab sample data does not affect the other in-service components or piping components associated with the skid.

Having sample data every four hours meets UFSAR requirements. Additionally, other indicators, i.e., containment sump level and RCS makeup flow, are available for the operator to determine leakage rate. Therefore, an unreviewed safety question does not exist.

O-ECM-2202-01 Electrical Corrective Maintenance Procedure 11-20-97 (Safety Evaluation No.97-151)

Electrical Corrective Maintenance Procedure O-ECM-2202-01, "RSST B LTC Controller Testing With Transformer In Service", was revised to procedurally control a Temporary Modification to isolate the Automatic Load Tap Changer (ALTC). This will allow the 'B' Reserve Service Station Transformer (RSST) to continue to power Emergency Bus 2H while the ALTC is removed from service for calibration.

The RSST ALTC will be defeated. Manual operation of the LTC circuits will be utilized to maintain voltage within acceptable limits. All indications of Emergency, Station Service, and Transfer Bus Voltages remain available during this activity. These procedurally controlled temporary modifications are installed and removed with the LTC circuits in manual. No other control or monitoring equipment is affected by this activity. Control Room alarm functions remain in service and unaffected. Therefore, an unreviewed safety question does not exist.

tlurry Monthly Operating Report No. 97-11 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: NOVEMBER, 1997 2-ST-308, "Controlling Procedure for Implementation of Core Uprate for Surry Power Station Unit 2," was completed on October 30, 1998. The last action required for Core Uprate was the respanning of steam flow and feed flow transmitters which could only be accomplished during a refueling outage. This task was completed during the October Unit 2 Refueling Outage. Special Test 308 was completed and closed.

e tlurry Monthly Operating Report No. 97-11 Page 16 of 18 CHEMISTRY REPORT MONTHNEAR: NOVEMBER, 1997 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avg. Max. Min. Avg.

Gross Radioactivity, µCi/ml 4.76E-1 2.81 E-1 3.69E-1 2.69E-1 1.38E-1 1.98E-1 Suspended Solids, ppm - - - - - -

Gross Tritium, µCi/ml 6.53E-1 5.68E-1 6.15E-1 2.36E-1 3.36E-2 1.25E-1 1131, µCi/ml 1.58E-2 8.95E-4 5.42E-3 1.29E-4 1.72E-5 6.82E-5 113111133 1.99 0.15 0.77 0.10 0.04 0.08 Hydrogen, cc/kg 31.9 29.6 30.5 35.4 24.0 31.8 Lithium, com 2.33 2.06 2.18 3.12 2.13 2.38 Boron - 10, rmm* 192.5 177.0 185.0 335.4 245.8 258.0 Oxygen, (DO}, ppm  :<,;0.005  :<,;0.005  :<,;0.005 :<,;0.005  :<,;0.005  :<,;0.005 Chloride, com 0.004 0.003 0.003 0.003 0.002 0.003 pH at 25 degree Celsius 6.67 6.56 6.62 6.50 6.27 6.36

None

Surry Monthly Operating Report No.97-11 Page 17 of 18 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: NOVEMBER, 1997 New Fuel Number of New or Spent Shipment or Date Stored Assemblies Assembly ANSI Initial Fuel Shipping Cask No. or Received per Shipment Number Number Enrichment Cask Activity None During the Reporting Period

e e Surry Monthly Operating Report No. 97-11 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: NOVEMBER, 1997 Number Title LER Number O-OPT-FP-009 Diesel Driven Fire Protection Water Pump 1-FP-P-2 50-280/

97-010-00

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