ML18153B181

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Monthly Operating Repts for Nov 1994 for Surry Power Station Units 1 & 2
ML18153B181
Person / Time
Site: Surry  Dominion icon.png
Issue date: 11/30/1994
From: Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
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ML18153B180 List:
References
NUDOCS 9412190221
Download: ML18153B181 (19)
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' l VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 94-11 Approved:

~ ~C..G.___ n-Station Manager 11--'i:1, Date 9412190221 941212 1 PDR ADOCK 05000280 / - - -- - - ---- _ l:QfL____ __ J

\ 1 e e Surry Monthly Operating Report No. 94-11 Page 2of 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. ........*..................................................................... 1O 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

' , e Surry Monthly Operating Report No. 94-11 Page 3 of 19 OPERATING DATA REPORT Docket No.: 50-280 Date: 12-02-94 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: ................................................. .. Surry Unit 1
2. Reporting Period: ........................................ .. November, 1994
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 192336.0
12. Number of Hours Reactor Was Critical .......... 652.4 6447.1 130254.3
13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5
14. Hours Generator On-Line ........................... 652.2 6409.7 128088.7
15. Unit Reserve Shutdown Hours ..................... 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 1535604.0 14954818.7 298122563.8
17. Gross Electrical Energy Generated (MWH) .... 510735.0 4963785.0 97503333.0
18. Net Electrical Energy Generated (MWH) ........ 492170.0 4775543.0 92602644.0
19. Unit Service Factor ................................... 90.6% 80.0% 66.6%
20. Unit Availability Factor............................... 90.6% 80.0% 68.5%
21. Unit Capacity Factor (Using MDC Net) ........... 87.5% 76.3% 62.1%
22. Unit Capacity Factor (Using DER Net) ........... 86.7% 75.6% 61.1%
23. Unit Forced Outage Rate ............................ 0.0% 0.4% 16.7%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Maintenance (Steam Generator Chemical Cleaning), November 28, 1994, 23 Days

25. If Shut Down at End of Report Period, Estimated Date of Start-up: December 20, 1994
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

' . e Surry Monthly Operating Report No. 94-11 Page 4of 19 OPERATING DATA REPORT Docket No.: 50-281 Date: 12-02-94 Completed By: D. Mason Telephone: (804) 365-2459 1 . Unit Name: .................................................. . Surry Unit 2

2. Reporting Period: ......................................... . November, 1994
3. Licensed Thermal Power (MWt): ...................... . 2441
4. Nameplate Rating (Gross MWe): ..................... .. 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 820
7. Maximum Dependable Capacity (Net MWe): ....... . 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YID Cumulative

11. Hours In Reporting Period .......................... 720.0 8016.0 189216.0
12. Number of Hours Reactor Was Critical .......... 720.0 7517.2 127593.5
13. Reactor Reserve Shutdown Hours ............... 0 0 328.1
14. Hours Generator On-Line ........................... 720.0 7507.5 125723.1
15. Unit Reserve Shutdown Hours ..................... 0 0 0
16. Gross Thermal Energy Generated (MWH) ...... 1757520.0 17778246.5 293453988.9
17. Gross Electrical Energy Generated (MWH) .... 585495.0 5891265.0 95836889.0
18. Net Electrical Energy Generated (MWH) ........ 565070.0 5676661.0 91008731.0
19. Unit Service Factor ................................... 100.0% 93.7% 66.4%
20. Unit Availability Factor............................... 100.0% 93.7% 66.4%
21. Unit Capacity Factor (Using MDC Net) ........... 100.5% 90.7% 61.7%
22. Unit Capacity Factor (Using DER Net) ........... 99.6% 89.9% 61.0%
23. Unit Forced Outage Rate ............................ 0% 0% 13.4%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling (10 Year ISi), February 3, 1995, 55 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. 94-11 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EOUAL To OR GREATER THAN 20%)

REPORT MoNTH: November, 1994 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12-03-94 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 941128 s 67.8 B NIA JB SG Maintenance Outage (Steam Generator Chemical Cleaning)

(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. 94-11 Page 6 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MoNTH: November, 1994 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12-03-94 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 016-1}

e e Surry Monthly Operating Report No. 94-11 Page 7of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: November, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) DaL (MWe- Net) 1 757 17 759 2 757 18 758 3 756 19 757 4 749 20 758 5 755 21 745 6 760 22 758 7 747 23 760 8 767 24 759 9 766 25 760 10 768 26 762 11 768 27 749 12 768 28 41 13 764 29 0 14 747 30 0 15 757 16 759 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. 94-11 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: November, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe- Net) 1 786 17 788 2 788 18 787 3 788 19 787 4 789 20 788 5 788 21 784 6 786 22 778 7 787 23 780 8 786 24 788 9 787 25 788 10 787 26 783 11 787 27 779 12 788 28 778 13 787 29 778 14 779 30 782 15 778 16 788 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. 94-11 Page 9of 19

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: November, 1994 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.

UNIJONE:

11/01/94 0000 The reporting period began with the unit operating at 97.5% power, 800 MWe, due to Steam Generator "C" level oscillations.

11/27/94 2130 Started power reduction in preparation for maintenance outage (steam generator chemical cleaning).

11/28/94 0413 Unit off-line.

0426 Reactor manually tripped.

11/30/94 2400 The reporting period ended with the unit shutdown for a maintenance outage.

UNIT Two:

11/01/94 0000 The reporting period began with the unit operating at 100% power, 815 MWe.

11/30/94 2400 The reporting period ended with the unit operating at 100% power, 820 MWe.

-Surry Monthly Operating Report No. 94-11 Page 10 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994 DCP94-45 Design Change Package 11-01-94 (Safety Evaluation No.94-133)

Design Change Package 94-45 temporarily replaced the existing fuel elevator basket with

.. one that is capable of accommodating Westinghouse fuel inspection equipment.

The replacement basket, which was functionally equivalent to the original basket, was installed to permit individual irradiated fuel rods to be examined. The modification did not affect other major components and the fuel handling was performed in accordance with the existing fuel handling procedures. Therefore, an unreviewed safety question does not exist.

TSl-018 Technical Specification Interpretation 11-07-94 (Safety Evaluation No.94-188)

Technical Specification Interpretation TSl-018 was developed to clarify the Technical Specification reference to the station batteries as having 60 cells as being descriptive and not technically significant. (Re: Technical Specification 4.6).

The TSI does not impact any system's ability to perform its design function and does not reduce the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

  • DCP77-50 Design Change Package 11-10-94 Design Change Package 77-50 installed motor operators on certain Unit 1 and 2 extraction steam manual isolation valves to protect the main turbine from potential water induction resulting from a backup on the feedwater heater shell side.

The modifications did not affect safety-related systems and did not reduce the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

DCP92-44 Design Change Package 11-10-94 (Safety Evaluation No.94-093)

Design Change Package 92-44 replaced the Unit 2 pressurizer safety valves (PSVs) with safety valves that are designed to seal tighter under pressurizer steam conditions and discharge pipe loads. A loop seal drain line was installed to allow the loop seal to continuously drain condensation, thereby allowing the removal of the loop seal ovens.

The new PSVs are like-kind replacements of the existing PSVs and the piping modifications were made in accordance with the system design criteria. Implementation of these changes eliminated the concern of Reactor Coolant System (RCS) over pressurization due to the PSV loop seals. Therefore, an unreviewed safety question does not exist.

-Surry Monthly Operating Report No. 94-11 Page 11 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994 FS 90-04 Updated Flnal Safety Analysis Report Change 11-10-94 (Safety Evaluation No.94-195)

UFSAR Change 94-04 deleted section 11.2.4.1.3, "Spent Resin Handling Operations," to reflect the relocation of the liquid waste processing ion exchangers from the station to the Surry Radwaste Facility.

This change was administrative in nature and was made to correctly reflect the previous relocation of the subject equipment. Therefore, an unreviewed safety question does not exist.

SE 94-193 Safety Evaluation 11-10-94 Safety Evaluation 94-193 was performed, as a result of a review of Information Notice 91-40, to evaluate the potential for unmonitored, uncontrolled radioactivity releases to the environment from the component cooling (CC) system.

The evaluation concluded that a CC system heat exchanger tube leak to the service water system would be required for a release to the discharge canal to occur. In the event of such a leak, minimal circulating water system flow would dilute contamination levels to well below the maximum release levels. Periodic sampling is performed to monitor system contamination levels. Therefore, an unreviewed safety question does not exist.

TM S2-94-16 Temporary Modification 11-10-94 (Safety Evaluation No.94-192)

Temporary Modification S2-94-16 installed a temporary oxygen analyzer on the main condensate discharge piping to verify the accuracy of permanently installed monitoring equipment.

The temporary oxygen analyzer will not adversely affect the operation of any component or system or reduce the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not eicist.

AC S1-94-1116 Administrative Control 11-17-94 (Safety Evaluation No.94-201)

Administrative control of Unit 1 containment sump pump discharge containment isolation valve, 1-DA-TV-1008, was established to permit the valve to be intermittently opened to maintain the containment sump level within acceptable limits. 1-DA-TV-1008 was deactivated in accordance with Technical Specifications due to the redundant isolation valve, 1-DA-TV-1 OOA, being inoperable.

The administrative controls require that an operator in direct communication with the control room be stationed at the valve when it is opened. Although 1-DA-TV-1008 is fully capable of performing its containment isolation function, the operator is a redundant measure to ensure the penetration can be isolated, when necessary. Therefore, an unreviewed safety question does not exist.

... *' -Surry Monthly Operating Report No. 94-11 Page 12 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994 DCP93-01 Design Change Package 11-17-94 (Safety Evaluation No.93-090)

Design Change Package 93-01 installed a test connection and isolation valve at the outlet

.of the pressure control valve for reagent gas to the Unit 1 and 2 containment hydrogen analyzers.

The test connections facilitate the use of test gauges during the performance of functional testing and calibration. The modifications did not affect the operation of the hydrogen analyzers or the ability to perform their design function. Therefore, an unreviewed safety question does not exist.

SE 94-200 Safety Evaluation 11-17-94 Safety Evaluation 94-200 was performed to evaluate the use of Westinghouse Corporation's Chemically Enhanced Pressure Pulse Cleaning Method to remove mineral deposits from the Unit 1 steam generators (SG).

The process is used when the unit is at cold shutdown. Evaluations of the cleaning method were performed by Virginia Power and Westinghouse Nuclear Safety. The evaluations concluded that the integrity of the SGs is not affected by pressure pulse cleaning. Therefore, an unreviewed safety question does not exist.

DR S-94-1949 Deviation Report 11-23-94 (Safety Evaluation No.94-202)

Safety Evaluation 94-202 assessed the condition identified by Deviation Report S 1949 concerning undersized roof decking on a plant yard storage building.

An evaluation of this condition concluded that the structure and its contents are not critical to plant operation and have no impact on nuclear safety. Building access has been limited until repairs can be effected. Therefore, an unreviewed safety question does not exist.

DR S-94-2053 Deviation Reports 11-23-94 DR S-94-2078 (Safety Evaluation No.94-203)

Safety Evaluation 94-203 assessed the conditions reported by Deviation Reports S 2053 and S-94-2078 concerning stroke problems with Unit 1 containment sump pump discharge containment isolation valves, 1-DA-TV-100A and 1-DA-TV-100B. As a result, the subject valves were closed/deactivated and the containment sump pumps were turned off. Sump in-leakage was allowed to overflow into the recirculation spray system (RS) sump.

An evaluation of this condition concluded that continued Unit 1 operation was acceptable until the upcoming scheduled maintenance outage (approximately one week). RS in-leakage was small and did not threaten RS component operability or present a containment flooding concern. With the subject valves closed, the containment isolation function was achieved. Therefore, an unreviewed safety question does not exist.

f}

-Surry Monthly Operating Report No. 94-11 Page 13 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994 TP-94-36 Temporary Power & Cable lnstallatlon Request 11-23-94 (Safety Evaluation No.94-205)

Temporary Power & Cable Installation Request TP-94-36 was implemented to supply temporary power from switchyard transformer No. 4 to equipment being used to clean the Unit 1 steam generators. Switchyard transformer No. 4 is an installed spare that is fully capable of supplying buses No. 5 and No. 6, if required.

An evaluation of TP-94-36 concluded that switchyard transformer No. 4 was capable of supplying its normal load, the temporary loads required by the steam generator cleaning equipment, and buses No. 5 or No. 6, if required. Therefore, an unreviewed safety question does not exist.

10 CFR 50, Appendix R Report 11-30-93 (Safety Evaluation 94-207)

The 10 CFR 50, Appendix R Report was revised to incorporate completed plant modifications and additional engineering evaluations that affect the Appendix R program.

The revision also removed Exemption Request No. 16 since the associated condition was addressed by a plant modification.

The plant modifications were evaluated independently, with respect to Appendix R compliance, prior to implementation as part of the design change process. The additional engineering evaluations were performed in accordance with Generic Letter 86-10. These changes document commitments which form part of the licensing basis for fire protection for Units 1 and 2. Therefore an unreviewed safety question does not exist.

TMS-94-37 Temporary Modification 11-30-94 (Safety Evaluation No.94-206)

Temporary Modification (TM) S-94-37 removed the roughing filter from the auxiliary ventilation system category II filter assembly to permit operation of filtered exhaust fan, 1-VS-F-59, with an acceptable differential pressure across the filter assembly.

The category II filter assembly remains capable of performing its design basis function of filtering contaminated air through the charcoal filters with the roughing filter removed. The HEPA filter portion of the assembly will be monitored and, if necessary, inspected for deterioration. The category II filter assembly does not perform any safety function to mitigate an airborne radioactive release during a LOCA or fuel handling accident.

Therefore, an unreviewed safety question does not exist.

... " -Surry Monthly Operating Report No. 94-11 Page 14 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994 1-TOP-4039 Temporary Operating Procedures

  • 11-04-94 1-TOP-4040 (Safety Evaluation No.94-187) 1-TOP-4041 1-TOP-4042 Temporary Operating Procedures 1-TOP-4039, "Installation of Temporary Connections for Unit 1 Steam Generator Chemical Cleaning Outage," 1-TOP-4040, "Removal of Temporary Connections Installed for Unit 1 Steam Generator Chemical Cleaning Outage," 1-TOP-4041, "Placing In Service and Removing From Service Aux Steam TM," and 1-TOP-4042, "Placing In Service and Removing From Service Condensate TM," were developed to provide instructions for the installation and operation of temporary connections to the Auxiliary Steam and Condensate Make-up Systems to facilitate the Unit 1 steam generator chemical cleaning processes.

The implementation of the subject procedures will not affect safety-related equipment, equipment important to safety, or the Technical Specifications margin of safety.

Therefore, an unreviewed safety question does not exist.

1(2)-MOP-EPH-008 Maintenance Operating Procedure 11-08-94 1(2)-MOP-EPH-009 (Safety Evaluation No.94-190) 1(2)-MOP-EPH-01 O 1(2)-MOP-EPH-011 Maintenance Operating Procedures 1(2)-MOP-EPH-008, "Removing 4160V Bus 1H, 480V Buses 1H and 1H-1, and 480V MCC 1H1-1 and 1H1-2 From Service," 1(2)-MOP-EPH-009, "Returning 4160V Bus 1H, 480V Buses 1H and 1H-1, and 480V MCC 1H1-1 and 1H1-2 to Service," 1(2)-MOP-EPH-01 O, "Removing 4160V Bus 1J, 480V Buses 1J and 1J 1, and 480V MCC 1J1-1 and 1J1-2 From Service," and 1(2)-MOP-EPH-011, "Returning 4160V Bus 1J, 480V Buses 1J and 1J1, and 480V MCC 1J1-1 and 1J1-2 to Service," were developed to provide detailed instructions for safely connecting and disconnecting the electrical leads on each station battery and for implementing temporary modifications (TM) to provide alternate power supplies for the radiation monitoring and fire detection equipment during the associated bus outages.

The procedures include the use of an electrical jumper to equalize the open circuit battery terminal voltage with the DC bus voltage when reconnecting the battery leads. This and other procedural controls minimize the potential of a dual battery short circuit and enhance the overall safety of the subject activity. During the bus outages, the radiation monitoring and fire detection equipment will be powered from the other unit's Class 1E electrical distribution system. The electrical load of the subject equipment is minimal and does not represent a significant addition to the distribution system. The affected equipment will be verified operable following the installation and removal of the TMs. The activity will only be performed when the affected unit is defueled. Therefore, an unreviewed safety question does not exist.

  • -Surry Monthly Operating Report No. 94-11 Page 15 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994 1-TOP-4045 Temporary Operating Procedures 11-23-94 1-TOP-4055 (Safety Evaluation No.94-178, Revision 1) 1-TOP-4056 Temporary Operating Procedures 1-TOP-4045, "Reactor Coolant Pump 1C Number 1 Seal

. Leakoff Bucket Check,w 1-TOP-4055, "Reactor Coolant Pump 1A Number 1 Seal Leakoff Bucket Check,w and 1-TOP-4056, "Reactor Coolant Pump 18 Number 1 Seal Leakoff Bucket Check,w were revised/developed to provide instructions for verifying the accuracy of the flow instrumentation for Unit 1 reactor coolant pumps (RCP) seal leak-off flow.

Implementation of these procedures, which involves the collection and measurement of RCP seal leak-off flow, will not affect the reactor coolant system pressure boundary and will not reduce the margin of safety as described by the Technical Specifications.

Therefore, an unreviewed safety question does not exist.

1-TOP-4057 Temporary Operating Procedure 11-23-94 (Safety Evaluation No.94-204)

Temporary Operating Procedure 1-TOP-4057, "Containment Sump Pump Down with 1-DA-TV-1008 Failed Closed,w was developed to provide instructions for establishing an alternate flowpath for pumping the contents of the Unit 1 containment sump.

  • The alternate flowpath, which involves the installation of a mechanical jumper, was established to bypass a deactivated containment isolation valve that lies in the normal flowpath. Procedural controls require double verification of jumper installation and removal and ensure containment integrity is maintained. Therefore, an unreviewed safety question does not exist.

. * -Surry Monthly Operating Report No. 94-11 Page 16 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994 None During the Reporting Period

-Surry Monthly Operating Report No. 94-11 Page 17 of 19 CHEMISTRY REPORT MONTH/YEAR: November, 1994 Unit No. 1 Unit No. 2 Primarv Coolant Analvsis Max. Min. Ava. Max. Min. Ava.

Gross Radioactivity, µ,Ci/ml 3.39E-1 1.86E-2 2.61 E-1 1.61E-1 9.29E-2 1.23E-1 Suspended Solids, ppm s_0.1 _s,0.1 _s,0.1 _s,0.1 s_0.1 _s,0.1 Gross Tritium, uCi/ml 3.07E-1 2.82E-1 2.90E-1 2.35E-1 1.64E-1 1.94E-1 1131, µ,Ci/ml 5.57E-4 2.74E-4 4.25E-4 2.02E-4 4.76E-5 1.11 E-4 113111133 0.08 0.06 0.07 0.10 0.04 0.07 Hydrogen, cc/kg 33.7 3.9 19.8 45.8 33.5 38.2 Lithium, oom 2.32 1.60 2.20 1.84 1.20 1.60 Boron - 10, oom* 140.9 24.9 96.0 43.7 25.1 34.7 Oxygen, (DO), ppm _s,0.005 .s,0.005 s_0.005 _s,0.005 s_0.005 s_0.005 Chloride, ppm 0.006 <0.001 0.003 0.003 s_0.001 s_0.001 oH at 25 deciree Celsius 7.02 6.14 6.86 7.54 7.29 7.43

None

7

' -Surry Monthly Operating Report No. 94-11 Page 18 of 19 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: November, 1994 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received ~rShiement Number Number Enrichment Cask Activi~

New Fuel Unit2 Batch 15 Receipt 5 11/01/94 12 OX3 LMOZWJ 3.8159 14.99Ci OX6 LMOZWM 3.8122 ox0 LMOZWP 3.8113 1XO LMOZWR 3.8277 3X1 LMOZXC 4.0088 3X4 LMOZXF 4.0055 3X7 LMOZXJ 4.0056 3X8 LMOZXK 4.0060 4X1 LMOZXN 4.0094 4X2 LMOZXP 4.0060 4X3 LMOZXQ 4.0050 4X5 LMOZXS 4.0193

-Surry Monthly Operating Report No. 94-11 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: November, 1994 None During the Reporting Period

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