ML18153B256

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Monthly Operating Repts for Feb 1995 for Surry Power Station Units 1 & 2.W/950310 Ltr
ML18153B256
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/28/1995
From: Kansler M, Mason D, Olsen C
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-131, NUDOCS 9503200276
Download: ML18153B256 (20)
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 10, 1995 U. S. Nuclear Regulatory Commission Serial No.95-131 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 February 1995.

Very truly yours, 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 9503200276 950228 PDR ADOCK 05000280 R PDR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 95-02 Approved:

Station Manager

  • ' u r r y Monthly Operating Report No. 95-02 Page 2 of 19 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 ........................................... 14 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 ................................................................................................... 19
  • ' u r r y Monthly Operating Report No. 95-02 Page 3 of 19 OPERATING DATA REPORT Docket No.: 50-280 Date: 03-05-95 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . February, 1995
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 ......................... . 672.0 1416.0 194496.0
12. Number of Hours Reactor Was Critical ......... . 672.0 1271.9 131741.6
13. Reactor Reserve Shutdown Hours .............. . 0 0 3774.5
14. Hours Generator On-Line .......................... . 672.0 1243.1 129484.1
15. Unit Reserve Shutdown Hours .................... . 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... . 1615922.4 3000965.3 301454704.5
17. Gross Electrical Energy Generated (MWH) ... . 544955.0 1012140.0 98625973.0
18. Net Electrical Energy Generated (MWH) ....... . 527354.0 978265.0 93687288.0
19. Unit Service Factor .................................. . 100.0% 87.8% 66.6%
20. Unit Availability Factor .............................. . 100.0% 87.8% 68.5%
21. Unit Capacity Factor (Using MDC Net) .......... . 100.5% 88.5% 62.1%
22. Unit Capacity Factor (Using DER Net) .......... . 99.6% 87.7% 61.1%
23. Unit Forced Outage Rate ........................... . 0.0% 12.2% 16.7%
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

  • ' u r r y Monthly Operating Report No. 95-02 Page 4of 19 OPERATING DATA REPORT Docket No.: 50-281 Date: 03-05-95 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . February, 1995
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, HAny (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period .......................... 672.0 1416.0 191376.0
12. Number of Hours Reactor Was Critical .......... 51.1 795.1 129132.6
13. Reactor Reserve Shutdown Hours ............... 0 0 328.1
14. Hours Generator On-Line ........................... 50.1 794.1 127261.2
15. Unit Reserve Shutdown Hours..................... 0 0 0
16. Gross Thermal Energy Generated (MWH) ...... 98304.0 1812706.1 297081170.4
17. Gross Electrical Energy Generated (MWH) .... 32600.0 606585.0 97048879.0
18. Net Electrical Energy Generated (MWH) ........ 31230.0 584057.0 92177093.0
19. Unit Service Factor ................................... 7.5% 56.1% 66.5%
20. Unit Availability Factor............................... 7.5% 56.1% 66.5%
21. Unit Capacity Factor (Using MDC Net) ........... 6.0% 52.8% 61.8%
22. Unit Capacity Factor (Using DER Net) ........... 5.9% 52.3% 61.1%
23. Unit Forced Outage Rate ............................ 0% 0% 13.2%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling (1 O Year ISi), February 3, 1995, 49 Days

25. If Shut Down at End of Report Period, Estimated Date of Start-up: March 24, 1995
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

- * 'urry Month~ Operating Report No. 95-02 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February, 1995 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 03-05-95 Completed by: Craig Olsen Telephone: (804) 365-2155 (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 950210 s NIA 8 NIA NIA SJ SEAL Degraded outboard seal on Main Feedwater Pump 1-FW-P-18. Seal was replaced.

(1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual 8 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)

  • ' u r r y Monthly Operating Report No. 95-02 Page 6of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: February, 1995 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 03-05-95 Completed by: Craig Olsen Telephone: (804) 365-2155 (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 950203 s 621.9 C 2 NIA AB RCT Refueling Shutdown (1 O Year ISi)

(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)

  • ' u r r y Monthly Operating Report No. 95-02 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 03-04-95 Completed by: Pat Kessler Telephone: 365-2790 MONTH: February, 1995 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 1 790 17 799 2 795 18 799 3 789 19 800 4 792 20 801 5 797 21 799 6 801 22 798 7 801 23 797 8 801 24 789 9 799 25 797 10 777 26 798 11 479 27 796 12 796 28 796 13 798 14 797 15 797 16 794 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.
  • Surry Monthly Operating Report No. 95-02 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 03-04-95 Completed by: Pat Kessler Telephone: 365-2790 MONTH: February, 1995 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 655 17 0 2 635 18 0 3 12 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 14 0 15 0 16 0 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.

-

  • Surry Monthly Operating RepM No. 95-02 Page 9 of 19

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: February, 1995 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:

02/01/95 0000 The reporting period began with the unit operating at 100% power, 825 MWe.

02/10/95 2104 Started power reduction to replace main feedwater pump, 1-FW-P-1 B, outboard seal.

2333 Stopped power reduction at 59%, 470 MWe.

2350 1-FW-P-1 B removed from service.

02/11/95 1957 1-FW-P-1 B returned to service following outboard seal replacement.

2115 Started power increase.

02/12/95 0310 Stopped power increase at 100%.

02/28/95 2400 The reporting period ended with the unit operating at 100% power, 825 MWe.

UN!JTWO:

02/01/95 0000 The reporting period began with the unit operating at 85% power, 703 MWe in a power coastdown.

02/02/95 2104 Began power reduction from 83%, 790 MWe, to prepare for start of refueling outage.

02/03/95 0207 Generator off-line.

0308 Reactor manually tripped.

02/28/95 2400 The reporting period ended with the unit at refueling shutdown.

e

  • Surry Monthly Operating Report No. 95-02 Page 10 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1995 TM S1-95-02 Temporary Modification 2-02-95 (Safety Evaluation No.95-018)

Temporary Modification (TM) S1-95-02 installed a mechanical jumper to temporarily route the discharge of the Unit 1 recirculation spray heat exchanger (RSHX) radiation monitor pumps 1-SW-P-58 and 1-SW-P-5C to a spare penetration on the Unit 2 SW piping to facilitate the application of coating on recirculation spray heat exchanger service water discharge piping.

The mechanical jumper was pressure rated to safely convey the discharge of the subject pumps and was functionally tested after installation. The RSHX service water radiation monitoring system was maintained in an operable condition while the TM was in place and was tested following the removal of the jumper. Therefore, an unreviewed safety question did not exist.

SE 95-020 Safety Evaluation 2-07-95 Safety Evaluation 95-020 assessed the handling of a new spent fuel cask design (TN-32) within the station.

The evaluation concluded that the handling of the TN-32 cask will be performed in a manner similar to previously used cask designs and use the same cask handling equipment. The cask drop analyses performed for the spent fuel pool remains bounding for the use of the TN-32 cask. Therefore, an unreviewed safety question does not exist.

TM S1-95-03 Temporary Modification 2-09-95 (Safety Evaluation No.95-021 A)

Temporary Modification (TM) S1-95-03 manually opened damper 1-VS-MOD-1008 to align the Unit 1 safeguards areas to the Auxiliary Ventilation System filtered exhaust. This configuration protects the system from a loss of power or instrument air event and ensures the exhaust from the Unit 1 safeguards area is filtered during a Unit 1 safety injection (SI).

The TM will be in place only while Unit 2 is shutdown with no fuel handling being performed.

The TM assures the mitigation of a Unit 1 SI and does not affect the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report No. 95-02 Page 11 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1995 DCP 93-14-3 Design Change Package 2-17-95 (Safety Evaluation No.93-179)

Design Change Package 93-14 modified the Unit 1- arid :2. power* range nuclear instrumentation loops to compensate for the loss of detector current resulting from the use of flux suppression inserts, low leakage core configurations, the potential for operating with an inoperable control rod, and to improve the detector current indication.

The subject instrumentation loops were tested and calibrated following the modifications to ensure the detector current to reactor power relationships and margins of safety were maintained consistent with the original design. Therefore, an unreviewed safety question does not exist.

SE 95-023 Safety Evaluation 2-20-95 Safety Evaluation 95-023 assessed the continued operation of Unit 1 with a malfunction in the turbine control system that causes the output of the load reference controller to be approximately 10% higher than the value set by the operator.

To compensate for the subject malfunction, the governor valve limiter was set to physically limit the valve to a position corresponding to actual turbine power and the applicable shutdown procedure was revised to require the turbine to be tripped before opening the generator output breakers. The evaluation concluded that the operation of the turbine with these compensatory actions is bounded by the current accident analysis.

Therefore, an unreviewed safety question does not exist.

DCP 93-88-3 Design Change Package 2-21-95 (Safety Evaluation No.94-157)

Design Change Package 93-88-3 installed test jacks in the electrical cabinet doors for Unit 1 and 2 safety injection master relays SIA-A[B] to reduce the potential for inadvertent relay actuation caused by human error during the performance of periodic testing.

The modifications were implemented when the units were at cold shutdown and did not alter the existing logic circuitry. Therefore, an unreviewed safety question did not exist.

  • Surry Monthly Operating Report No. 95-02 Page 12 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1995 SE 95-026 Safety Evaluation 02-23-95 Safety Evaluation 95-026 was performed to evaluate the Unit 2 Cycle 13 reload core, including the implementation of additional debris resistance features and realigned mixing vane mid-grids to reduce the potential for assembly vibration.

Parameters affected by the reload were calculated and compared to the existing safety analysis assumptions. These parameters were shown to be either 1) explicitly bounded, or 2) accommodated by existing safety analysis margins and/or conservatism. Operation of the reload core in accordance with the Technical Specifications will not violate the design basis of plant safety equipment.. Thus, the probabilities and consequences of analyzed accidents and equipment malfunctions are not changed by the reload.

Therefore, an unreviewed safety question does not exist.

TMS2-95-02 Temporary Modification 2-24-95 (Safety Evaluation No.95-027)

Temporary Modification (TM) S2-95-02 temporarily reconfigured electrical leads, due to an inoperable alarm module, to provide valid alarms from the Unit 2 "B" circulating water (CW) pump thrust bearing, lower guide bearing, and stator RTD at the GETAC panel. The TM also provided local indication of upper guide bearing temperature following pump start.

The alarm module functions do not provide control or interlock functions for the CW pump motor supply breakers and does not prevent starting the pumps. The TM did not affect electrical protection circuits or controls. Accident analyses are not affected since the CW pumps are not required to mitigate accident conditions. Therefore, an unreviewed safety question did not exist.

DCP 90-18 Design Change Package 2-27-95 (Safety Evaluation No.91-110)

Design Change Package 90-18 replaced four degraded moisture separator drain pipes on each of the Unit 1 and 2 steam generators to eliminate the potential of the pipes from becoming loose parts. The four inch diameter drain pipes were located circumferentially about the central drain on the mid-deck plate of the moisture separator.

The modifications did not affect the operation or functional ability of equipment important to safety and did not alter the bases of the Technical Specifications. Therefore, an unreviewed safety question does not exist.

  • FACILITY CHANGES THAT DID NOT
  • Surry Monthly Operating Report No. 95-02 Page 13 of 19 REQUIRE NRC APPROVAL MONTH/YEAR: February, 1995 DCP 92-37-3 Design Change Package 2-27-95 (Safety Evaluation No.92-077)
    • Design Change Package *92-37-3 changed the *Classification of diesel generator temperature switches, 1[2]-DG-TS-107[207], from "Safety-Related" (SR) to "Nonsafety-Related" (NSR). .

The subject components do not perform a nuclear safety function and do not penetrate a safety pressure boundary. This change did not result in a physical change and did not affect the design and operational requirements of the equipment. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES.

  • Surry Monthly Operating Report No. 95-02 Page 14 of 19 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1995 O-MOP-SW-014 Maintenance Operating Procedure 2-02-95 (Safety Evaluation No.95-019)

Maintenance Operating Procedure O-MOP-SW-014, "Removal from Service and Return to Service of Service Water Supply Strainer 1-VS-S-1A," was _developed to provide instructions for bypassing rotating strainer 1-VS-S-1A through duplex strainer 1-SW-S-10 to facilitate the performance of maintenance on 1-VS-S-1 A and the associated piping.

The procedure requires certain administrative controls to be established during the performance of the subject maintenance to ensure compliance with Appendix R fire protection requirements and to ensure the service water flow paths to the charging pump service water and control room chiller systems remain operable. Therefore, an unreviewed safety question does not exist.

2-0PT-Sl-006 Operations Periodic Test Procedure 2-07-95 (Safety Evaluation No.95-021)

Operations Periodic Test Procedure, 2-0PT-Sl-006, "SI Accumulator Discharge Check Valves Full Open Test" was temporarily changed to provide instructions for throttling the Unit 2 charging pump "C" discharge motor operated valve during the performance of the subject test to facilitate accurate full range flow testing of the pump. The change also provides directions for the implementation of associated temporary system modifications (e.g., removal of seal-in contacts, installation of suction and discharge gauges, and installation of a flow transmitter).

Unit 2 will be at cold shutdown during the performance of this test. The installation and removal of the temporary modifications will be independently verified and will not affect the operation of the system. Therefore, an unreviewed safety question does not exist.

1[2]-E-0 Emergency Procedure 2-14-95 O-AP-22.0 Abnormal Procedures O-AP-5.20 Annunciator Response Procedures O-RM-D5 (Safety Evaluation No. 95-023A)

O-RM-B4 O-RM-85 Emergency Procedure 1[2]-E-0, "Reactor Trip or Safety Injection," Abnormal Procedure O-RM-C5 O-AP-22.0, "Fuel Handling Abnormal Conditions," Abnormal Procedure O-AP-5.20, "Radiation Monitor System Ventilation Vent High Alarm," and Annunciator Response Procedures O-RM-D5, "Control Room Hi," O-RM-84, "New Fuel Storage - Hi," O-RM-85, "Fuel Pit Bridge - Hi," and O-RM-C5, "Control Room Alert," were revised to require supply fan 1-VS-AC-4 to be manually tripped whenever control room isolation is required. These procedural changes were made to limit the potential leakage of unfiltered air past the control room isolation dampers in the event of an accident.

The safety analysis determined that the consequences of the limited leakage are within the bounds of existing analyses for control room dose consequences. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES

  • Surry Monthly Operating Report No. 95-02 Page 15 of 19 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1995 2-TMOP-EPH-002 Temporary Maintenance Operating Procedure 2-17-95 (Safety Evaluation No.95-025)

Temporary Maintenance Operating Procedure 2-TMOP-EPH-002, "Unit 2 34.5 KV Bus 5, ASST A and B, and Transfer Bus E. Outage" was developed to provide instructions for conducting an outage of 34.5 KV Bus No. 5, Reserve Station Service Transformers (ASST) "A" and "8", and Transfer Bus "E". The bus and RSST outage is required to enable the replacement of the Bus No. 5 disconnect insulators and to allow testing and inspection-of certain Bus No. 5 components.

This procedure provides for a controlled reliable electrical system line-up that is allowed by the UFSAR and Technical Specifications. Unit 2 will be defueled and in a backfeed line-up. Unit 2 will enter the appropriate Technical Specification limiting condition for backfeed operation since the primary power supply to Emergency Bus 2H will not be available. The emergency diesel generators will remain operable during this procedure. Therefore, an unreviewed safety question does not exist.

1[2]-0P-CS-003 Operating Procedures 2-22-95 2-0P-CS-005 (Safety Evaluation No.95-010, Revision 1)

Operating Procedures 1[2]-0P-CS-003, "Refueling Water Storage Tank Temperature Control," and 2-0P-CS-005, "Purifying Unit 2 RWST," were revised to provide instructions for administratively controlling Condensate System valves 1[2]-CS-27 when performing the subject procedure Appropriate administrative controls are provided in the procedure to ensure that the subject valves are closed within 90 seconds of the initiation of a safety injection. Closure of the valves within this time limit ensures that sufficient Refueling Water Storage Tank (RWST) inventory is maintained for accident mitigation. Therefore, an unreviewed safety question does not exist.

1[2]-0PT-Sl-018 Operations Periodic Test Procedures 2-28-95 (Safety Evaluation No.95-028)

Operations Periodic Test Procedures 1[2]-0PT-Sl-018, "RMT Functional Test" were developed to provide instructions for the temporary installation of electrical jumpers to facilitate the performance of the test.

The safety injection system and the recirculation mode transfer (RMT) function are not required to be operable while the electrical jumpers are in place. Double verification of jumper installation/removal will be performed. Therefore, an unreviewed safety question does not exist.

  • Surry Monthly Operating Report TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL No. 95-02 Page 16 of 19 MONTH/YEAR: February, 1995 None During the Reporting Period
  • Surry Monthly Operating Report No. 95-02 P!lge 17 of 19 CHEMISTRY REPORT MONTH/YEAR: February, 1995 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Ava.
  • Max. Min. Ava.

Gross Radioactivity, J.J.Ci/ml 3.18E-1 2.18E-1 2.63E-1 1.76E-1 5.92E-4 3.01 E-2 Suspended Solids, ppm .s.0.1 .s.0.1 .s.0.1 0.150 .s.0.01 0.055 Gross Tritium, uCi/ml 1.74E-1 1.37E-1 1.56E-1 - - -

1131, J.J.Ci/ml 7.11E-4 3.15E-4 5.10E-4 7.84E-5 3.91 E-5 5.84E-5 113111133 0.09 0.06 0.07 0.07 0.07 0.07 Hydrogen, cc/kg 40.3 32.6 37.3 45.3 1.0 9.8 Lithium, oom 2.28 2.05 2.15 0.80 0.27 0.52.

Boron - 1O, oom* 118.0 91.7 101.1 189.3 0.2 83.5 Oxygen, (DO), ppm s_0.005 <0.005 s.0.005 7.0 s.0.005 2.02 Chloride, ppm 0.004 0.002 0.003 0.016 s.0.001 0.007 oH at 25 degree Celsius 7.14 6.75 7.05 9.28 4.65 5.28

None

  • FUEL HANDLING
  • Surry Monthly Operating Report No. 95-02 Page 18 of 19 UNITS 1 & 2 MONTH/YEAR: February, 1995 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity No Fuel Received or Stored During the Reporting Period

Surry Monthly Operating Report No. 95-02 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS*

MONTH/YEAR: February, 1995 Number Title LER Number O-EPT-0904-04 Six Month Smoke Detector Test (Pyrotronics) S 1-95-002-00

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