ML18153A793

Monthly Operating Repts for Mar 1995 for Surry Power Station Units 1 & 2.W/950412 Ltr

ML18153A793
Person / Time
Site:	Surry
Issue date:	03/31/1995
From:	Bowling M, Mason D, Olsen C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-187, NUDOCS 9504180343
Download: ML18153A793 (20)

Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 12, 1995 U.S. Nuclear Regulatory Commission Serial No.95-187 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 1995.

Very truly yours, M. L. Bowling, Manager Nuclear Licensing & Programs Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRG Senior Resident Inspector Surry Power Station

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 95-03 Approved:

Station Manager

e Surry Monthly Operating Report No. 95-03 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 ........................................... 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 ................................................................................................... 19

• Surry Monthly Operating Report

. No. 95-03 Page 3 of 19 OPERATING DATA REPORT Docket No.: 50-280 Date: 04-03-95 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ......................................... . March, 1995

3. Licens~d 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 .......................... 744.0 2160.0 195240.0

12. Number of Hours Reactor Was Critical .......... 744.0 2015.9 132485.6

13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5

14. Hours Generator On-Line ........................ : .. 744.0 1987.1 130228.1

15. Unit Reserve .Shutdown Hours ..................... 0 0 3736.2

16. Gross Thermal Energy Generated (MWH) ...... 1813409.1 4814374.4 303268113.6

17. Gross Electrical Energy Generated (MWH) .... 610405.0 1622545.0 99236378.0

18. Net Electrical Energy Generated (MWH) ........ 588599.0 1566864.0 94275887.0

19. Unit Service Factor ................................... 100.0% 92.0% 66.7%

20. Unit Availability Factor ............................... 100.0% 92.0% 68.6%

21. Unit Capacity Factor (Using MDC Net) ........... 101.3% 92.9% 62.2%

22. Unit Capacity Factor (Using DER Net) ........... 100.4% 92.1% 61.3%

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

• 0.0% 8.0% 16.6%

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

Refueling, August 31, 1995, 38 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

• e Surry Monthly Operating Report No. 95-03 Page 4 of 19 OPERATING DATA REPORT Docket No.: 50-281 .

Date: 04-03-95 Completed By: D. Mason Telephone: (804) 365-2459

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

2. Reporting Period: ......................................... . March, 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 .......................... 744.0 2160.0 192120.0

12. Number of Hours Reactor Was Critical .......... 289.2 1084.3 129421.8

13. Reactor Reserve Shutdown Hours ............... 0 0 328.1

14. Hours Generator On-Line ........................... 258.2 1052.3 127519.4

15. Unit Reserve Shutdown Hours ..................... 0 0 0

16. Gross Thermal Energy Generated (MWH) ...... 551216.7 2363922.8 297632387 .1

17. Gross Electrical Energy Generated (MWH) .... 184825.0 791410.0 97233704.0

18. Net Electrical Energy Generated (MWH) ........ 177626.0 761683.0 92354719.0

19. Unit Service Factor ................................... 34.7% 48.7% 66.4%

20. Unit Availability Factor ............................... 34.7% 48.7% 66.4%

21. Unit Capacity Factor (Using MDC Net) ........... 30.6% 45.2% 61.7%

22. Unit Capacity Factor (Using DER Net) ........... 30.3% 44.8% 61.0%

23. Unit Forced Outage Rate ............................ 0% 0% 13.2%

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 Surry Monthly Operating Report No. 95-03 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION

{EQUAL To OR GREATER THAN 20%)

REPORT MONTH: March, 1995 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-03-95 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 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 (NUREG 0161)

• e Surry Monthly Operating Report No. 95-03 Page 6 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: March, 1995 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-04-95 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 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 (NUREG 0161)

e Surry Monthly Operating Report No. 95-03 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 04-06-95 Completed by: John Kilmer Telephone: 365-2792 MONTH: March, 1995 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 797 17 789 2 796 18 791 3 797 19 791 4 796 20 790 5 797 21 741 6 797 22 792 7 796 23 794 8 795 24 793 9 794 25 793 10 794 26 793 11 793 27 793 12 789 28 792 13 790 29 793 14 789 30

• 794 15 791 31 791 16 787 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 Surry Monthly Operating Report No. 95-03 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 04-06-95 Completed by: John Kilmer Telephone: 365-2792 MONTH: March, 1995 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe- Net) 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 152 6 0 22 363 7 0 23 664 8 0 24 762 9 0 25 786 10 0 26 773 11 0 27 771 12 0 28 771 13 0 29 777 14 0 30 790 15 0 31 790 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.

e Surry Monthly Operating Report No. 95-03 Page 9 of 19

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: March, 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:

03/01/95 0000 The reporting period began with the unit operating at 100% power, 825 MWe.

03/21/95 0510 Started power reduction to maintain condenser vacuum while cleaning waterboxes.

0620 Stopped power reduction at 92%, 739 MWe.

1824 Started power increase.

1905 Stopped power increase at 100%.

03/31/95 2400 The reporting period ended with the unit operating at 100% power, 825 MWe.

UNIT TWO:

03/01/95 0000 The reporting period began with the unit at refueling shutdown.

03/19/95 2249 Reactor critical.

03/21/95 0548 Generator on line. Started power increase.

0641 Stopped power increase at 30%, 230 MWe 03/22/95 0355 Started power increase.

03/23/95 0122 Stopped power increase at 69%, 590 MWe.

0613 Started power increase.

1543 Stopped power increase at 96%, 792 MWe.

03/29/95 1752 Started power increase.

1826 Stopped power increase at 100%.

03/31/95 2400 The reporting period ended with the unit operating at 100% power, 825 MWe.

e Surry Monthly Operating Report No. 95-03 Page 10 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1995 DCP 94-021 Design Change Package 3-02-95 (Safety Evaluation No.94-114)

Design Change Package 94-021 de-terminated the unused average temperature -input signal to the Rod insertion Limit modules. The signal is not used in the development of the Rod Insertion Limits. Disconnecting the unused wiring will not affect the average temperature input signal to the Rod Control, Pressurizer Level, Steam Dump or Feedwater Isolation systems. The change will eliminate electrical cross-talk that causes a spurious annunciation following an operational switching evolution. Since the input is unused and no safety related functions are affected, an unreviewed safety question does not exist.

DCP 93-075-3 Design Change Package 3-02-95 (Safety Evaluation No.93-228)

Design Change Package 93-075 replaced the Steam Generator (SG) Channel Head Drain Lines utilizing butt welded joints. The previous joints were socket welded. The use of butt welded joints eliminates the corrosive environment in the joints of the drain lines. The replacements were performed at cold shutdown conditions and the SG was drained. The modification improves the reliability of the drain line welded joints and therefore does not represent and unreviewed safety question.

DCP 92-68-3 Design Change Package 3-03-95 (Safety Evaluation No.93-190)

Design Change Package 92-068 installed a bypass line with a flow restricting orifice around certain main steam check valves in steam supply piping to the steam driven auxiliary feedwater (AFW) pump turbine for Unit 1 and Unit 2. The change is designed to eliminate damage induced by low flow conditions which cause chattering of the check valves resulting in damage to the valves. The design will allow a limited bypass flow around the check valve to prevent the chattering. The bypass lines do not affect the ability of the AFW pump to perform their safety function. The reliability of the check valves will be improved. The lines are fabricated in accordance with the appropriate codes and standards. Therefore the design change does not represent an unreviewed safety question.

DCP 94-056 Design Change Package 3-06-95 (Safety Evaluation No.93-182)

Design Change Package 94-056 connected the compensating lead to one of the two normal leads for Unit 2 Reactor Coolant System (RCS) "C" hot leg wide range temperature indication spare element, 2-RC-TE-2433-2. This configuration allows the compensating lead to be used in lieu of a failed normal lead, enabling 2-RC-TE-2433-2 to be returned to service.

The associated transmitter was adjusted, based on previous measurements, to offset the change in lead resistance and ensure the accuracy of the subject temperature indicator.

This modification did not affect other RCS temperature indication. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 95-03 Page 11 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March, 1995 TM 82-95-03 Temporary Modification 3-07-95 (Safety Evaluation No.95-031)

Temporary Modification (TM) 82-95-03 removed inside trip valve 2-DA-TV-200A"for maintenance, installed a spool piece to maintain an operable flowpath from the Unit 2 containment sump pumps 2-DA-P-4A/B, and maintained an operable flowpath for the containment sump sample pump. Installation of electrical jumpers allowed 2-DA-P-4A/B to operate with the limit switches for 2-DA-TV-200A removed.

This activity will not affect the operability of the containment sump pumps, nor the operability of the containment sump sample pump. Leakage into the containment due to spool piece failure could be isolated by the pump discharge valves and the outside trip valve 2-DA-TV-2008. Containment integrity is not required by Technical Specification (TS) 3.8 when the Unit is at COLD SHUTDOWN. If refueling integrity is required in accordance with TS 3.10, 2-DA-TV-2008 can be maintained operable or closed. This TM is required to be removed prior to exceeding 200°F. Since the system will be returned to its design condition following repairs and prior to operation, an unreviewed safety question does not exist.

TM 82-95-04 Temporary Modification 3-07-95 (Safety Evaluation No.95-032)

Temporary Modification (TM) 82-95-04 will remove the Unit 2 "B" Circulating Water (CW) pump upper guide bearing alarm module which is inoperable and must be removed from the alarm circuit to be repaired. In order to maintain the remainder of the alarm module circuits operable while the module is being removed, a jumper will be installed between thermocouples TC-CW-201 C and TC-CW-200C. When the module is removed, the 200C and 201 C leads will be shorted together to restore and maintain circuit continuity.

The module alarm functions do not provide any control or interlock functions for the CW pump motor supply breakers and will not prevent the start or cause the trip of a CW pump.

Since the components affected by this activity perform no protective or mitigating functions and are not part of the safety-related Emergency Service Water pump controls, an unreviewed safety question is not created.

e Surry Monthly Operating Report No. 95-03 Page 12 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1995 TM S2-95-06 Temporary Modification 3-08-95 (Safety Evaluation No.95-033)

Temporary Modification (TM) S2-95-06 will remove the Unit 2 "A" Circulating Water (CW) pump upper guide bearing alarm module which is inoperable and must be removed from the alarm circuit to be repaired. In order to maintain the remainder of the alarm module circuits operable while the module is being removed, a jumper will be installed between thermocouples TC-CW-201 A and TC-CW-200B. When the module is removed, the 200B and 201 A leads will be shorted together to restore and maintain circuit continuity.

The module alarm functions do not provide any control or interlock functions for the CW pump motor supply breakers and will not prevent the start or cause the trip of a CW pump.

Since the components affected by this activity perform no protective or mitigating functions and are not part of the safety-related Emergency Service Water pump controls, an unreviewed safety question is not created.

TM S2-95-05 Temporary Modification 3-09-95 (Safety Evaluation No.95-034)

Temporary Modification (TM) S2-95-05 will replace relay 2-RP-RL Y-TTXA. Three jumpers are required to perform this task. Two of the jumpers will provide closed contacts to the steam dump and turbine trip circuits during the relay replacement in order to maintain the relay's output signal. The third jumper is used to keep the train "A" reactor protection circuit intact during the relay replacement.

This task will be performed on train "A" only while train "B" will remain unaffected during relay replacement. The module alarm functions do not provide any control or interlock functions for the CW pump motor supply breakers and will not prevent the start or cause the trip of a CW pump. Since Unit 2 will be at COLD SHUTDOWN with the reactor trip breakers open while the work is performed, an unreviewed safety question is not created.

TM S2-95-07 Temporary Modification 3-09-95 (Safety Evaluation No.95-035)

Temporary Modification (TM) S2-95-07 will install electrical jumpers to allow manual operation of the containment sump pumps 2-DA-P-4A/B. Also this activity will defeat the low level cutoff for 2-DA-P-4A/B and local sump level observation will be required during the pumping evolution.

Operability of the sump pumps is not affected by this maintenance activity since manual operation is an original design feature. Sump pump and level indications will be restored prior to exceeding 200°F. Since the system will be returned to its design condition following repairs and prior to operation, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 95-03 Page 13 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1995 DCP 94-009 Design Change Package 3-10-95 (Safety Evaluation No.94-128)

Design Change Package 94-009 changes the thermal overloads for a number-of safety related motor operated valves (MOVs) to a different size and setting to assure operation of the MOV under conditions in accordance with the requirefl1ents of Generic Letter (GL) 89-10. The change implements industry standards to assure that the thermal overloads are set to assure that the MOV motor will not experience failure as a result of operation during accident conditions. The change will improve the reliability of the MOV by improving the ability for the MOV to be operated additional times. This change does not affect the ability of the valve to perform its safety function or reduce the margin of safety.

Therefore, an unreviewed safety question is not created.

DCP 91-06-2 Design Change Package 3-12-95 (Safety Evaluation No.92-190)

Design Change Package 91-06-2 removed the Unit 2 resistance temperature device (RTD) bypass piping system and replaced it with thermowell mounted RTDs directly in the RCS hot and cold leg pipes.

The modification did not degrade the performance or increase the challenges to equipment assumed to function during an accident condition. Therefore, an unreviewed safety question did not exist.

SES95-037 Safety Evaluation 3-17-95 Safety Evaluation S95s037 assessed the acceptability of "as-left" leakage testing results for valves in piping from the refueling water storage tank (RWST) and the high head safety injection pump suction prior to commencing startup following Unit 2 refueling. The leak rate results were found to be unacceptably high by current 1ST test criteria in 2-0PT 012. This condition provides a leak path back to the RWST during Post-LOCA conditions when the Safety Injection System is operating in Recirculation Mode Transfer.

The evaluation concluded that additional back leakage to the RWST will not have a significant effect on on-site and off-site doses. However, local radiation doses may be higher in the vicinity of the subject piping. Existing post-accident HP practices will ensure increased radiological monitoring of potentially affected components. The probability of a large break LOCA will not be affected by the as-left leak rates. The as-left leakage is bounded by existing calculations. Based on a licensing design basis review, the check valve 2-81-25 may be used as single isolation for the RWST and its failure to open or close is not considered credible. Therefore, an unreviewed safety question does not exist.

e Surry Monthly .Operating Report No. 95-03 Page 14 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1995 SE 95-038 Safety Evaluation 3-18-95 Safety Evaluation 95-038 assessed the continued operation of Residual Heat Removal (RHR) System suction isolation valve 2-RH-MOV-2701-with its torque switch inoperable in the closing direction. This valve is a normally closed de-energized valve in series with 2-RH-MOV-2700 to provide isolation from the 'A' Loop Hot Leg. The operation of 2-RH-MOV-2701 is enabled on decreasing RCS pressure sensed by a pressure transmitter.

A jumper was installed around a limit switch contact and a torque switch contact to fully close the isolation valve, and then removed. No other limit switches were affected by this activity. The postulated malfunction for this valve is failure to open. Neither the capability of this valve to open, nor the pressure interlock which prevents the opening of this valve will be affected. The capability of the RHR system to perform its function is likewise not affected. Therefore, the reliable operation of the valve has been maintained, and an unreviewed safety question does not exist.

DCP 93-017 Design Change Package 3-21-95 (Safety Evaluation No.93-118)

Design Change Package 93-017 modified the Unit 1 and 2 condenser inlet circulating water motor operated valves (MOV) to qualify them for operation while submerged. The modifications are considered a plant design enhancement that will improve isolation capability during a postulated flood and will provide additional operational flexibility.

The modifications did not change the function, operation, or performance of the MOVs or the circulating water systems. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 95-03 Page 15 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1995 2-EPT-0903-01 Electrical Periodic Test 03-07-95 (Safety Evaluation No.95-030)

Temporary modifications will be implemented to facilitate testing of the containment fire detectors in each reactor coolant pump cubicle. The fire detector element leads and alarm output leads will be lifted and test equipment installed to test the circuit. The fire detector control module is tested by simulating the detector element and verifying the actuation of the alarm to the control box for annunciation in the control room.

System operation is verified upon removal of the test equipment by pushing the local test button on the control panel to ensure circuit continuity, and by monitoring the alarm response in the control room. To ensure that a fire in the RCP cubicles during the test would be detected, a Technical Specification limiting condition for operation will be entered that requires monitoring of the RCP pump bearing and motor temperature or containment RTDs during performance of the procedure on an hourly basis, or perform containment walkdowns once every eight hours. This will ensure a fire in the RCP cubicle will not go undetected. Therefore, an unreviewed safety question does not exist.

CH-31.940 Chemistry Procedure 03-23-95 (Safety Evaluation No.95-040)

To enable chemicals to be added to the Component Cooling System in a more efficient manner, a mobile chemical addition system will be attached to the component cooling heat exchangers outlet header drain valve 1-CC-1179.

The chemical addition system includes a pump, hose, tank and discharge check valve.

The pump is rated at a discharge pressure of 150 psig, which is well above normal CC operating pressure. The installed check valve prevents back leakage from the CC system and the procedure requires personnel to be at the pump during any pumping operations to ensure the pump does not lose suction. Condensate quality makeup water will be used to flush the chemical addition tank, which is normal makeup to the CC system. Therefore, an unreviewed safety question does not exist.

eSurry Monthly Operating Report No. 95-03 Page 16 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1995 None During the Reporting Period

e Surry Monthly Operating Report No. 95-03 Page 17 of 19 CHEMISTRY REPORT MONTH/YEAR: March, 1995 Unit No. 1 Unit No. 2 Primarv Coolant Analysis Max. Min. Avg. Max. Min. Avg.

Gross Radioactivity, uCi/ml 3.88E-1 1.99E-1 2.65E-1 2.21 E-1 6.20E-4 4.89E-2 Suspended Solids, ppm .:;:.0.01 .:;:.0.01 .:;:.0.01 0.075 .:;:.0.01 0.05 Gross Tritium, uCi/ml 2.36E-1 1.82E-1 2.01 E-1 6.71 E-2 1.42E-2 4.07E-2 1131, µCi/ml 6.35E-4 3.49E-4 5.30E-4 1.16E-4 1.58E-5 7.22E-5 113111133 0.08 0.04 0.07 - - -

Hydrogen, cc/ka 45.6 36.3 41.4 44.8 8.3 23.8 Lithium, oom 2.30 2.07 2.22 2.65 0.60 2.11 Boron - 10, oom* 91.7 73.9 83.2 483.7 63.3 240.6 Oxygen, (DO), ppm .:;:.0.005 .:;:.0.005 .:;:.0.005 6.0 .:;:.0.005 2.6 Chloride, ppm <0.050 <0.001 0.007 <0.050 <0.001 0.012 pH at 25 degree Celsius 7.64 7.08 7.26 6.59 4.69 5.55 Boron - 10 = Total Boron x 0.196 Comments:

None

e Surry Monthly Operating Report No. 95-03 Page 18 of 19 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: March, 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. 95-03 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: March, 1995 None During the Reporting Period