ML18153B181
| ML18153B181 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/30/1994 |
| From: | Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18153B180 | List: |
| References | |
| NUDOCS 9412190221 | |
| Download: ML18153B181 (19) | |
Text
'
l VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 94-11 Approved:
~
~C..G.___ n-11--'i:1, Station Manager Date 9412190221 941212 1
PDR ADOCK 05000280
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1 e
Section TABLE OF CONTENTS e
Surry Monthly Operating Report No. 94-11 Page 2of 19 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.........*..................................................................... 1 O 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
OPERATING DATA REPORT e
Surry Monthly Operating Report No. 94-11 Page 3 of 19 Docket No.:
50-280 12-02-94 D. Mason Date:
Completed By:
Telephone:
(804) 365-2459 1. Unit Name:...................................................
- 2. Reporting Period:..........................................
- 3. Licensed Thermal Power (MWt):.......................
- 4. Nameplate Rating (Gross MWe):.......................
- 5. Design Electrical Rating (Net MWe):..................
- 6. Maximum Dependable Capacity (Gross MWe):....
- 7.
Maximum Dependable Capacity (Net MWe):........
Surry Unit 1 November, 1994 2441 847.5 788 820 781
- 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:
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION December 20, 1994 ACHIEVED
e Surry Monthly Operating Report No. 94-11 Page 4of 19 OPERATING DATA REPORT Docket No.:
Date:
Completed By:
50-281 12-02-94 D. Mason Telephone:
(804) 365-2459 1. Unit Name:...................................................
- 2. Reporting Period:..........................................
- 3. Licensed Thermal Power (MWt):.......................
- 4. Nameplate Rating (Gross MWe):.......................
- 5. Design Electrical Rating (Net MWe):..................
- 6. Maximum Dependable Capacity (Gross MWe):....
- 7. Maximum Dependable Capacity (Net MWe):........
Surry Unit 2 November, 1994 2441 847.5 788 820 781
- 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 INITIAL CRITICALITY ACHIEVED 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 (1)
(2)
(3)
(4)
(5)
Method Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12-03-94 Completed by: Craig Olsen Telephone: (804) 365-2155 Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No.
Code Code Prevent Recurrence 941128 s
67.8 (1)
F:
Forced S: Scheduled B
(2)
REASON:
Down Rx NIA A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction JB E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
(4)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
SG Maintenance Outage (Steam Generator Chemical Cleaning)
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
(5)
Exhibit 1 - Same Source.
(1) 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 (2)
(3)
(5)
Docket No.: 50-281 Unit Name: Surry Unit 2 Date:
12-03-94 Completed by: Craig Olsen Telephone:
(804) 365-2155 Duration Method of Reason Shutting Down Rx LER No.
(4)
System Code Component Cause & Corrective Action to Date Type Hours Code Prevent Recurrence (1)
F:
Forced S: Scheduled (4)
(2)
REASON:
None During the Reporting Period A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER} File (NUREG 016-1}
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 Other (Explain)
(5)
Exhibit 1 - Same Source.
e e
Surry Monthly Operating Report No. 94-11 Page 7of 19 AVERAGE DAILY UNIT POWER LEVEL MONTH:
November, 1994 Average Daily Power Level Day (MWe-Net) 1 757 2
757 3
756 4
749 5
755 6
760 7
747 8
767 9
766 10 768 11 768 12 768 13 764 14 747 15 757 16 759 INSTRUCTIONS DaL 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12-02-94 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level (MWe-Net) 759 758 757 758 745 758 760 759 760 762 749 41 0
0 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 MONTH:
November, 1994 Average Daily Power Level Day (MWe-Net) 1 786 2
788 3
788 4
789 5
788 6
786 7
787 8
786 9
787 10 787 11 787 12 788 13 787 14 779 15 778 16 788 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12-02-94 Completed by: Pat Kessler Telephone: 365-2790 Average Daily Power Level (MWe-Net) 788 787 787 788 784 778 780 788 788 783 779 778 778 782 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 11/27/94 11/28/94 11/30/94 UNIT Two:
11/01/94 11/30/94 0000 The reporting period began with the unit operating at 97.5% power, 800 MWe, due to Steam Generator "C" level oscillations.
2130 Started power reduction in preparation for maintenance outage (steam generator chemical cleaning).
0413 Unit off-line.
0426 Reactor manually tripped.
2400 The reporting period ended with the unit shutdown for a maintenance outage.
0000 The reporting period began with the unit operating at 100% power, 815 MWe.
2400 The reporting period ended with the unit operating at 100% power, 820 MWe.
DCP94-45 TSl-018 DCP77-50 DCP92-44 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994 Design Change Package (Safety Evaluation No.94-133)
-Surry Monthly Operating Report No. 94-11 Page 10 of 19 11-01-94 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.
Technical Specification Interpretation (Safety Evaluation No.94-188) 11-07-94 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.
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.
Design Change Package (Safety Evaluation No.94-093) 11-10-94 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.
FS 90-04 SE 94-193 TM S2-94-16 AC S1-94-1116 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994
-Surry Monthly Operating Report No. 94-11 Page 11 of 19 Updated Flnal Safety Analysis Report Change (Safety Evaluation No.94-195) 11-10-94 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.
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.
Temporary Modification (Safety Evaluation No.94-192) 11-10-94 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.
Administrative Control (Safety Evaluation No.94-201) 11-17-94 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.
DCP93-01 SE 94-200 DR S-94-1949 DR S-94-2053 DR S-94-2078 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994 Design Change Package (Safety Evaluation No.93-090)
-Surry Monthly Operating Report No. 94-11 Page 12 of 19 11-17-94 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.
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.
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.
Deviation Reports 11-23-94 (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}
TP-94-36 TMS-94-37 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1994
-Surry Monthly Operating Report No. 94-11 Page 13 of 19 Temporary Power & Cable lnstallatlon Request (Safety Evaluation No.94-205) 11-23-94 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 (Safety Evaluation 94-207) 11-30-93 The 1 O 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.
Temporary Modification (Safety Evaluation No.94-206) 11-30-94 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.
1-TOP-4039 1-TOP-4040 1-TOP-4041 1-TOP-4042 1 (2)-MOP-EPH-008 1 (2)-MOP-EPH-009 1 (2)-MOP-EPH-01 O 1 (2)-MOP-EPH-011
-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 Temporary Operating Procedures (Safety Evaluation No.94-187)
- 11-04-94 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.
Maintenance Operating Procedure (Safety Evaluation No.94-190) 11-08-94 Maintenance Operating Procedures 1(2)-MOP-EPH-008, "Removing 4160V Bus 1H, 480V Buses 1 H and 1 H-1, and 480V MCC 1 H1-1 and 1 H1-2 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 1 J, 480V Buses 1 J and 1 J 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 1 E 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.
1-TOP-4045 1-TOP-4055 1-TOP-4056 1-TOP-4057
-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 Temporary Operating Procedures (Safety Evaluation No.94-178, Revision 1) 11-23-94 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.
Temporary Operating Procedure (Safety Evaluation No.94-204) 11-23-94 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
CHEMISTRY REPORT MONTH/YEAR: November, 1994 Unit No. 1 Primarv Coolant Analvsis Max.
Min.
Ava.
Gross Radioactivity, µ,Ci/ml 3.39E-1 1.86E-2 2.61 E-1 Suspended Solids, ppm s_0.1
_s,0.1
_s,0.1 Gross Tritium, uCi/ml 3.07E-1 2.82E-1 2.90E-1 1131, µ,Ci/ml 5.57E-4 2.74E-4 4.25E-4 113111133 0.08 0.06 0.07 Hydrogen, cc/kg 33.7 3.9 19.8 Lithium, oom 2.32 1.60 2.20 Boron - 10, oom*
140.9 24.9 96.0 Oxygen, (DO), ppm
_s,0.005
.s,0.005 s_0.005 Chloride, ppm 0.006
<0.001 0.003 oH at 25 deciree Celsius 7.02 6.14 6.86 Boron - 1 O = Total Boron x 0.196 Comments:
None
-Surry Monthly Operating Report No. 94-11 Page 17 of 19 Unit No. 2 Max.
Min.
Ava.
1.61E-1 9.29E-2 1.23E-1
_s,0.1 s_0.1
_s,0.1 2.35E-1 1.64E-1 1.94E-1 2.02E-4 4.76E-5 1.11 E-4 0.10 0.04 0.07 45.8 33.5 38.2 1.84 1.20 1.60 43.7 25.1 34.7
_s,0.005 s_0.005 s_0.005 0.003 s_0.001 s_0.001 7.54 7.29 7.43
7 New or Spent Fuel Shipment Date Stored or Number Received New Fuel Unit2 Batch 15 Receipt 5 11/01/94 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: November, 1994 Number of Assemblies Assembly ANSI
~rShiement Number Number 12 OX3 LMOZWJ OX6 LMOZWM ox0 LMOZWP 1XO LMOZWR 3X1 LMOZXC 3X4 LMOZXF 3X7 LMOZXJ 3X8 LMOZXK 4X1 LMOZXN 4X2 LMOZXP 4X3 LMOZXQ 4X5 LMOZXS
-Surry Monthly Operating Report No. 94-11 Page 18 of 19 New or Spent Initial Fuel Shipping Enrichment Cask Activi~
3.8159 14.99Ci 3.8122 3.8113 3.8277 4.0088 4.0055 4.0056 4.0060 4.0094 4.0060 4.0050 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