ML18153D240
| ML18153D240 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/31/1993 |
| From: | Bowling M, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 93-064, 93-64, NUDOCS 9302180121 | |
| Download: ML18153D240 (20) | |
Text
- i.
e e
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 9, 1993 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.
NO/RPC:vlh Docket Nos.
License Nos.93-064 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of January 1993.
Very truly yours,
/11/t~
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 NRC Senior Resident Inspector Surry Power Station 9302180121 930f 3f --- -
'PDR ADOCK 05000280 R
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 93-01 Approved:
TABLE OF CONTENTS Section e Surry Monthly Operating Report No. 93-01 Page 2 of 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........................................... 12 Tests and Experiments That Did Not Require NRC Approval...................................................................... 15 Chemistry Report............................................................................................................................. 16 Fuel Handling - Unit No. 1................................................................................................................... 17 Fuel Handling - Unit No. 2................................................................................................................... 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications................................................................................................... 19
e Surry Monthly Operating Report No. 93-01 Page 3 of 19 OPERATING DATA REPORT
- 1. Un~ 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 January 1993 2441 847.5 788 820 781 Docket No.:
Date:
Completed By:
Telephone:
50-280 02-05-93 D. Mason (804) 365-2459
- 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..........................
744.0 744.0 176304.0
- 12.
Number of Hours Reactor Was Critical..........
682.6 682.6 116057.6
- 13. Reactor Reserve Shutdown Hours...............
0.0 0.0 3774.5
- 14. Hours Generator On-Line...........................
674.5 674.5 113949.9
- 15. Unit Reserve Shutdown Hours.....................
0.0 0.0 3736.2
- 16. Gross Thermal Energy Generated (MWH)......
1637364.2 1637364.2 265256643.3
- 17. Gross Electrical Energy Generated (MWH)....
553465.0 553465.0 86571718.0
- 18.
Net Electrical Energy Generated (MWH)........
526368.0 526368.0 82124228.0
- 19. Unit Service Factor...................................
90.7%
90.7%
64.6%
- 20.
Unit Availability Factor...............................
90.7%
90.7%
66.8%
- 21.
Unit Capacity Factor (Using MDC Net)...........
90.6%
90.6%
60.1%
- 22.
Unit Capacity Factor (Using DER Net)...........
89.8%
89.8%
59.1%
- 23.
Unit Forced Outage Rate............................
9.3%
9.3%
18.4%
- 24. Shutdowns Schedule 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):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED
)
e Surry Monthly Operating Report No. 93-01 Page 4 of 19 OPERATING DATA REPORT Docket No.:
Date:
Completed By:
50-281 02-05-93 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 January 1993 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:
11. Hours In Reporting Period..........................
- 12. Number of Hours Reactor Was Critical..........
- 13. Reactor Reserve Shutdown Hours...............
- 14. Hours Generator On-Line...........................
- 15. Unit Reserve Shutdown Hours.....................
- 16. Gross Thermal Energy Generated (MWH)......
- 17. Gross Electrical Energy Generated (MWH)....
- 18. Net Electrical Energy Generated (MWH)........
- 19. Unit Service Factor...................................
- 20.
Unit Availability Factor...............................
- 21.
Unit Capacity Factor (Using MDC Net)...........
- 22.
Unit Capacity Factor (Using DER Net)...........
- 23.
Unit Forced Outage Rate............................
This Month 744.0 744.0 0.0 744.0 0.0 1812413.2 606065.0 576513.0 100.0%
100.0%
99.2%
98.3%
0.0%
YTD 744.0 744.0 0.0 744.0 0.0 1812413.2 606065.0 576513.0 100.0%
100.0%
99.2%
98.3%
0.0%
Cumulative 173184.0 114430.9 328.1 112675.0 0.0 263143487.0 85801969.0 81366926.0 65.1%
65.1%
60.3%
59.6%
14.3%
- 24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each):
Refueling, March 6, 1993 -- 60 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 ACHIEVED
(1)
Date Type 930108 F
(1)
F:
Forced S: Scheduled (4) e Surry Monthly Operating Report No. 93-01 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: January 1993 (2)
(3)
(4)
Method (5)
Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02-05-93 Completed by: Anthony Xenakis Telephone: (804) 365-2145 Duration of LER System Component Cause & Corrective Action to Hours 69.6 Reason A
(2)
REASON:
Shutting No.
Down Rx 3
93-001 A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction Code Code JM RLY E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
Prevent Recurrence An automatic reactor trip (from 100% power) and safety injection resulted when a relay failure occurred during scheduled testing of a HI CLS instrument loop.
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
(5)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Exhibit 1 - Same Source.
(1) e Surry Monthly Operating Report No. 93-01 Page 6 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: January 1993 (2)
(3)
(4)
(5)
Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 02-05-93 Completed by: Anthony Xenakis Telephone:
(804) 365-2145 Duration Method of Reason Shutting Down Rx LER No.
System Component Cause & Corrective Action to Date Type Hours Code Code Prevent Recurrence (1)
F:
Forced S:
Scheduled (4)
(2)
REASON:
No entries for this reporting period.
A -
Equipment Failure (Explain) 8 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 0161)
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
(5)
Exhibit 1 - Same Source.
Month:
January 1993 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS e
Surry Monthly Operating Report No. 93-01 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 02-05-93 Completed by:
M.A. Negron Telephone:
(804) 365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net)
Day (MWe - Net) 786 17 786 786 18 772 786 19 786 787 20 787 785 21 786 786 22 786 785 23 786 572 24 785 0
25 773 0
26 786 175 27 786 785 28 786 786 29 786 787 30 786 783 31 786 784 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.
Month:
January 1993 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS e
Surry Monthly Operating Report No. 93-01 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 02-05-93 Completed by: M.A. Negron Telephone:
(804) 365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net)
Day (MWe - Net) 777 17 776 777 18 776 777 19 777 778 20 776 778 21 777 771 22 778 737 23 777 767 24 777 776 25 777 776 26 776 776 27 776 778 28 776 778 29 776 777 30 776 777 31 776 776 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. 93-01 Page 9 of 19
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: January 1993 Listed below in 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 01-01-93 01-08-93 01-09-93 01-11-93 01-31-93 UNIT TWO 01-01-93 01-07-93 01-08-93 01-31-93 0000 1730 0723 0701 This reporting period began with the Unit operating at 100% power, 825 MWe.
An automatic reactor trip (from 100% power) and safety injection resulted when a relay failure occurred during scheduled testing of a HI CLS instrument loop.
A train "A" safety injection occurred while testing the aforementioned HI CLS instrument loop prior to returning it to service.
Reactor critical.
1507 Unit on line.
2247 Unit at 100% power, 825 MWe.
2400 0000 1418 1549 1906 0445 2400 This reporting period ended with the Unit operating at 100% power, 825 MWe.
This reporting period began with the Unit operating at 100% power, 820 MWe.
Started Unit power reduction to perform 02-0PT-TM-001; 99.2% power, 805 MWe.
Stopped power reduction; 84.4% power, 700 MWe.
Started ramp up; 84.9% power, 710 MWe.
Stopped ramp; 100% power, 820 MWe.
This reporting period ended with the Unit operating at 100% power, 820 MWe.
e Surry Monthly Operating Report No. 93-01 Page 10 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: January 1993 DR S-92-1780 TM S2-93-01 TM S1-93-01 DCP 92-08 Deviation Report 01-05-93 (Safety Evaluation No.93-001)
This Safety Evaluation was performed to evaluate Deviation Report S-92-1780 concerning Unit 2 operation with the Victoreen manipulator crane area radiation monitor, 2-RM-RMS-262, out of service until repairs can be effected during the 1993 Unit 2 refueling outage.
The evaluation determined that the subject monitor is required to be operable only during refueling operations and is not used to assess plant conditions following an accident.
Furthermore, other containment radiation monitors are available. Therefore, an unreviewed safety question is not created.
Temporary Modification (Safety Evaluation No.93-002) 01-05-93 This Temporary Modification (TM) determinated annun~iator cables in the annunciator logic panel and in the instrument racks to facilitate "megger" testing of the subject cables.
A maximum of two annunciator cards with up to four windows were out of service at a time during this activity. The subject cables are part of the non-Technical Specification annunciator system and were isolated from any safety-related cables and equipment. Therefore, an unreviewed safety question was not created.
Temporary Modification (Safety Evaluation No.93-007) 01-08-93 This Temporary Modification (TM) installed an electrical jumper to maintain a train "A" Hi-CLS signal to the safety injection (SI) circuit during the replacement of failed Unit 1 reactor protection system train "A" relay, 3/4-CLS-1 A.
This TM was used to prevent the Hi-CLS signal from clearing (a SI had already occurred) and reinitiating during the replacement of the relay. The SI "8" train logic was not affected and the Unit was at hot shutdown. Therefore, an unreviewed safety question was not created.
Design Change Package 01-13-93 Design Change Package (DCP) 92-08 installed sheet metal deflectors to redirect the discharge of heated exhaust air from feedwater pump motors 1-FW-PM0-1 A 1 and 1-FW-PM0-1 A2 away from motor control center (MCC) 1 A 1-2.
The modification ensures that overheating of electrical components in MCC 1 A 1-2 due to the motor exhaust does not occur. Also, the modification does not affect the operation of the subject motors or other systems. Therefore, an unreviewed safety question was not created.
e Surry Monthly Operating Report No. 93-01 Page 11 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL WO 136561 TM S1-93-02 SE 93-012 MONTH/YEAR: January 1993 Work Order 01-14-93 (Safety Evaluation No.93-008)
Work Order 136561 installed a temporary blocking device to maintain the Unit 1 extraction steam isolation valve, 1-ES-24, in the open position until the actuator can be replaced.
The extraction steam system is nonsafety-related and is not required to function as part of any engineered safeguard for reactor protection features.
This modification maintains the subject maintenance isolation valve in its normal (open) configuration. The change does not reduce the margin of safety in the basis of any Technical Specification and is bounded by the UFSAR accident analyses. Therefore, an unreviewed safety question is not created.
Temporary Modification (Safety Evaluation No.93-010) 01-14-93 This Temporary Modification (TM) installed a filter to remove hydrazine from condensate polishing process waste water in the low conductivity (LC) and waste neutralization (WN) sumps. This TM enables the filter to be tested as an alternative to the chemical treatment of waste water for the removal of hydrazine.
The subject filter was installed on the sample lines of the nonsafety-related LC/WN sump pumps. The TM does not affect the operation of the condensate or other plant systems. Therefore, an unreviewed safety question was not created.
Safety Evaluation 01-19-93 This Safety Evaluation was performed to review previous safety evaluations performed for the Unit 2 Cycle 11 core reload in order to enhance the flexibility of operation following the end of full power reactivity (i.e.,
coastdown operation).
The review determined that the previous evaluations (which addressed a T avg/Power coast) were adequate to permit the plant to operate in a power only coastdown, except for two events. These. events (Rod Withdrawal from Subcritical and Main Steamline Break) were reevaluated using conservative assumptions that are bounding for a power only coast. It was concluded that continued operation and subsequent coastdown to the cycle burnup limit in accordance with the Technical Specifications would not violate the plant's design basis. Therefore, an unreviewed safety question does not exist.
O-OP-BS-005 1-0P-SA-006 O-EPT-1802-03 e
Surry Monthly Operating Report PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January 1993 Operating Procedure (Safety Evaluation No.93-005)
No.93-01 Page 12 of 19 01-07-93 Operating Procedure O-OP-BS-005, "Administrative Control of Unit 2 Emergency Switchgear Room Door to Unit 1 Turbine Building Basement," was developed to provide instructions for administratively controlling the subject door while hoses and equipment are routed through it.
Establishing administrative control of the subject door ensures the capability of rapidly restoring the main control room (MCR)/emergency switchgear room pressure envelope to required conditions, thus minimizing the potential for exposure of MCR personnel to radioactivity releases in the event of an accident. These controls will ensure that the operability requirements for the MCR/ESGR pressure boundary will be met. Therefore, an unreviewed safety question is not created.
Operating Procedure (Safety Evaluation No.93-006) 01-07-93 Operating Procedure 1-0P-SA-006, "Administrative Control of Unit 1 Service Air to the Emergency Switchgear Room Valve 1-SA-226," was developed to provide instructions for administratively controlling service air valve 1-SA-226.
Procedural control of the subject valve will ensure the capability of rapidly restoring the main control room/emergency switchgear room pressure envelope in the event of an accident.
Furthermore, administrative control of the valve will satisfy its operability requirements when it is open.
Therefore, an unreviewed safety question is not created.
Electrical Periodic Test Procedure (Safety Evaluation No.93-009) 01-14-93 Electrical Periodic Test Procedure, O-EPT-1802-03,. "Bus 1F Undervoltage Protective Relay Testing," was revised to provide instructions for installing electrical jumpers to maintain the Unit 2 auxiliary feedwater station blackout automatic start function during "F" transfer bus undervoltage relay testing.
This procedure is performed with Unit 1 off-line in a backfeed line-up and does not degrade the performance of any protective functions.
Installation and removal of the jumpers requires double verification and a circuit operability test is performed following jumper removal.
Therefore, an unreviewed safety question is not created.
GMP-M-161 2-MPT-1205-01 1-PT-18.9 2-PT-18.9 e
Surry Monthly Operating Report No. 93-01 Page 13 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES.
THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January 1993 General Maintenance Procedure 01-21-93 (Safety Evaluation No.93-013)
General Maintenance Procedure GMP-M-161, "Installation Of Recirculation Spray Heat Exchanger Service Water Flow Test Equipment," was revised to provide instructions for installing temporary instrumentation to support the performance of special test 2-ST-299, "Recirculation Spray Heat Exchanger Service Water Flow Test."
The temporary test equipment will be installed while the unit is in a condition during which service water flow to the recirculation spray heat exchangers is not required and will be removed prior to unit startup. Therefore, an unreviewed safety question is not created.
Mechanical Periodic Test Procedure (Safety Evaluation No.93-014) 01-21-93 Unit 2 Mechanical Periodic Test Procedure 2-MPT-1205-01, "Unit Two Containment Sump Inspection And Test Setup," was developed to provide instructions for relocating one of the Unit 2 containment sump pumps (2-DA-P-4A, 2-DA-P-4B) to the containment trough to permit the pumping of containment drains to the low level waste header while the containment sump is being inspected.
This procedure will be implemented while the Unit is at cold shutdown (CSD) and will not affect any safety-related system or component.
In addition, these pumps are not required to mitigate an accident while the Unit is at CSD.
Therefore, an unreviewed safety question is not created.
Periodic Test Procedures (Safety Evaluation No.93-015) 01-24-93 Periodic Test Procedures 1-PT-18.9 and 2-PT-18.9, "Boric Acid Transfer Pumps Operability and Performance Test," were revised to delete the requirement for entering a limiting condition for operation during boric acid transfer pump (BATP) performance testing.
The system alignments of the BATPs during operability testing do not affect the ability of the system to perform its design function. The BATP operability and flow path requirements specified in the Technical Specifications will continue to be met during this testing. Therefore, an unreviewed safety question is not created.
OP-23.2.11 e
Surry Monthly Operating Report No. 93-01 Page 14 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January 1993 Operating Procedure (Safety Evaluation No.93-016) 01-26-93 Operating Procedure OP-23.2.11, "Sampling Alignment for WGDT 1 A," was revised ("one-time only" change) to provide instructions for determining the operating characteristics of the waste gas system that are applicable to the waste gas decay tank oxygen analyzers.
This activity involved the installation of temporary transmitters on waste gas system piping to gather data. The modifications did not alter the operation or performance characteristics of the waste gas system.
Therefore, an unreviewed safety question was not created.
e Surry Monthly Operating Report No. 93-01 Page 15 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January 1993 No entries for this reporting period.
CHEMISTRY REPORT MONTH/YEAR: January 1993 Unit No. 1 Primarv Coolant Analvsis Max.
Min.
Ava.
Gross Radioact., u.Ci/ml 4.14E-1 1.45E-2 3.25E-1 Suspended Solids, oom
< 0.1
< 0.1
< 0.1 Gross Tritium, u.Ci/ml 3.39E-1 1.89E-1 2.38E-1 r131, µCi/ml 9.85E-4 1.05E-4 6.26E-4 1131/I133 0.11 0.07 0.09 Hydrogen, cc/ka 46.5 28.5 35.5 Lithium, oom 2.34 1.94 2.21 Boron - 10, oom*
249.5 145.4 180.9 Oxvaen, (DO), oom
< 0.005
< 0.005
< 0.005 Chloride, oom 0.007 0.003 0.004 pH at 25 deqree Celsius 6.80 6.36 6.61 Boron - 1 O = Total Boron x 0.196 Comments:
None.
Surry Monthly Operating Report No. 93-01 Page 16 of 19 Unit No. 2 Max.
Min.
Ava.
2.77E-1 9.99E-2 1.84E-1
< 0.1
< 0.1
< 0.1 1.36E-1 4.14E-2 7.60E-2 3.06E-3 2.88E-4 1.30E-3 0.19 0.07 0.13 47.8 29.1 39.8 1.34 0.58 1.01 20.4 1.2 10.9
< 0.005
< 0.005
< 0.005 0.010
< 0.001 0.002 8.29 7.26 7.57
Surry Monthly Operating Report No. 93-01 Page 17of 19 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: January 1993 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received eer Shiement Number Number Enrichment Cask Activity Unit2 Batch 14 Shipment 2 01-05-93 12 2W8 LMOX37 3.8 OW2 LMOX2F 3.8 1W5 LMOX2U 3.8 OW7 LMOX2L 3.8 1W6 LMOX2V 3.8 2W7 LMOX36 3.8 5W4 LMOX3V 4.0 OW1 LMOX2E 3.8 2W2 LMOX31 3.8 OW9 LMOX2N 3.8 1W8 LMOX2X 3.8 6WO LMOX41 4.0 Unit2 Batch 14 Shipment 3 01-07-93 12 1W9 LMOX2Y 3.8 5W5 LMOX3W 4.0 OW3 LMOX2G 3.8 5W7 LMOX3Y 4.0 1WO LMOX2P 3.8 OW5 LMOX2J 3.8 5W6 LMOX3X 4.0 5W9 LMOX40 4.0 OW4 LMOX2H 3.8 2W4 LMOX33 3.8 OW8 LMOX2M 3.8 1W4 LMOX2T 3.8
- s... "
Surry Monthly Operating Report No. 93-01 Page 18 of 19 FUEL HANDLING UNITS 1 & 2 MONTH/VEAR: January 1993 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received ear Shiement Number Number Enrichment Cask Activit~
Unit2 Batch 14 Shipment 4 01-12-93 12 3W4 LMOX39 4.0 3W3 LMOX38 4.0 3W7 LMOX3C 4.0 4WO LMOX3F 4.0 2W3 LMOX32 3.8 4W5 LMOX3L 4.0 4W1 LMOX3G 4.0 1W3 LMOX2S 3.8 5W8 LMOX3Z 4.0 4W7 LMOX3N 4.0 1W7 LMOX2W 3.8 1W1 LMOX20 3.8 Unit2 Batch 14 Shipment 5 01-14-93 8
5W2 LMOX3T 4.0 OW6 LMOX2K 3.8 2WO LMOX2Z 3.8 2W5 LMOX34 3.8 3W6 LMOX3B 4.0 2W1 LMOX30 3.8 2W6 LMOX35 3.8 1W2 LMOX2R 3.8 Unit2 Batch 14 Shipped off site 01-28-93 2
1W3 LMOX2S 3.8 OW9 LMOX2N 3.8
SUIT)' Monthly Operating Report No. 93-01 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: January 1993 None During This Reporting Period.