ML18153C871
| ML18153C871 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1991 |
| From: | Negron M, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 92-031, 92-31, NUDOCS 9201220150 | |
| Download: ML18153C871 (20) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January lS, 1992 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.92-031 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 December 1991.
Very truly yours,
- ~~
w.t~~~
Senior Vice President - Nuclear 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
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 91-12 Approved:
~,,.;;[)&(}L.z.
Station Manager 1-1l>-,~
Date
TABLE OF CONTENTS Section Surry Monthly Operating Report No. 91-12 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............................................................................... 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval........................................... 13 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
Surry Monthly Operating Report No. 91-12 Page 3 of 19 OPERATING DATA REPORT Docket No.:
Date:
50-280 1-8-92 Completed By:
Telephone:
M.A. Negron 804-365-2795
- 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 December 1991 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 1812061.0 610335.0 580655.0 100.0%
100.0%
99.9%
99.0%
0.0%
YfD 8760.0 8760.0 0.0 8760.0 0.0 20896766.4 6938365.0 6590937.0 100.0%
100.0%
96.3%
95.5%
0.0%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling, February 28, 1991, 64 days.
- 25. If Shut Down at End of Report Period Estimated Date of Start-up:
- 26. Unit In Test Status (Prior to Commercial Operation):
Cumulative 166776.0 108234.2 3774.5 106240.2 3736.2 247116676.7 80515188.0 76374066.0 63.7%
65.9%
59.1%
58.1%
19.3%
FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION
Surry Monthly Operating Report No. 91-12 Page 4 of 19 OPERATING DATA A,EPORT Docket No.:
Date:
50-281 1-8-92 Completed By:
Telephone:
M.A. Negron 804-365-2795
- 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 December 1991 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):
1 O.
Reasons For Restrictions, If Any:
This Month
- 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............................
744.0 574.3 0.0 553.1 0.0 1324560.5 442635.0 421229.0 74.3%
74.3%
72.5%
71.8%
25.7%
YTD 8760.0 6035.8 0.0 5890.3 0.0 12743213.8 4203735.0 3985213.0 67.2%
67.2%
58.3%
57.7%
17.0%
- 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):
Cumulative 163656.0 105208.1 328.1 103460.9 0.0 240878682.1 78433849.0 74363938.0 63.2%
63.2%
58.3%
57.7%
15.4%
FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION
(1) e Surry Monthly Operating Report No. 91-12 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: December 1991 (2)
(3)
(4)
(5)
Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
1-8-92 Completed by:
M. A. Negron Telephone:
804-365-2795 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:
None during this 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 0161)
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
(5)
Exhibit 1 - Same Source.
(1)
Surry Monthly Operating Report No. 91-12 Page 6 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: December 1991 (2)
(3)
(4)
(5)
Docket No.: 50-281 Unit Name: Surry Unit 2 Date:
1-8-92 Completed by:
M.A. Negron Telephone:
804-365-2795 Duration Method of Reason Shutting Down Rx LER No.
System Component Cause & Corrective Action to Date Type Hours 12-11-91 F
163.5 12-17-91 F
27.5 (1)
F:
Forced S: Scheduled A
A (2)
REASON:
NIA 3
NIA A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction Code Code Prevent Recurrence AB Fl JB FCV Leak at 2-RC-FE-2492, Repaired.
Failure of 'B' Feed Reg. Viv.,
Repaired.
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
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 (NU REG 0161)
(5)
Exhibit 1 - Same Source.
Month:
December 1991 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS e Surry Monthly Operating Report No. 91-12 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name:
Surry Unit 1 Date:
1-8-92 Completed by:
M.A. Negron Telephone:
804-365-2795 Average Daily Power Level Average Daily Power Level (MWe - Net)
Day (MWe-Net) 782.9 17 778.0 781.9 18 782.2 776.6 19 782.7 771.1 20 783.9 781.2 21 783.9 782.1 22 782.3 780.7 23 783.7 778.1 24 782.6 781.0 25 781.7 772.0 26 783.0 774.2 27 782.0 779.1 28 782.8 780.2 29 782.3 780.6 30 782.2 779.9 31 782.8 777.0 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.
Month:
December 1991 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS e Surry Monthly Operating Report No. 91-12 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date:
1-8-92 Completed by:
M.A. Negron Telephone:
804-365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net)
Day (MWe-Net) 768.1 17 0.0 775.5 18 0.0 774.4 19 486.5 772.0 20 776.8 766.8 21 776.9 768.5 22 777.0 778.2 23 776.5 778.8 24 775.7 779.8 25 775.8 753.8 26 772.8 23.4 27 777.2 0.0 28 778.7 0.0 29 779.3 0.0 30 779.6 0.0 31 779.5 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.
e Surry Monthly Operating Report No. 91-12 Page 9 of 19
SUMMARY
OF OPERATING EXPERIENCE MONTH/VEAR: December 1991 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 12-01-91 12-31-91 UNIT TWO 12-01-91 12-10-91 12-11-91 12-17-91 12-18-91 12-19-91 12-31-91 0000 2400 0000 2102 0317 0349 1304 2245 2254 1626 0222 This report period started with the Unit operating at 100% power, 820 MWe.
This report period ended with the Unit operating at 100% power, 820 MWe.
This report period started with the Unit operating at 1 00% power, 795 MWe.
Started Unit Ramp down to Cold Shutdown to repair a leak on 2-RC-FE-2492.
Unit off line.
Reactor manually tripped.
Reactor critical.
Unit on line.
Unit off line from an automatic reactor trip.
This was due to a failure of "B" main feedwater regulating valve to maintain a demand position, resulting in high "B" Steam Generator level.
Reactor critical.
Unit on line. Commence ramping to 100%.
1 7 53 Unit at 100% power, 815 MWe.
2400 This report period ended with the Unit operating at 1 00% power, 820 MWe.
e Surry Monthly Operating Report No. 91-12 Page 1 O of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL TM S2-91-50 TM S2-91-51 MONTH/YEAR: December 1991 Temporary Modification (Safety Evaluation No.91-255) 12-02-91 This Temporary Modification (TM) lifted an electrical lead to remove the undervoltage lockout for the Unit 2 Charging Pump "A" to prevent the potential loss of high head safety injection (assuming the active failure to be the "B" charging pump powered from the emergency bus "J" or emergency diesel generator number 3) in the event of a simultaneous design basis accident and emergency bus "H" undervoltage condition.
Each unit has three charging pumps with two required to be operable. One pump is normally operating and the other pump is in standby designed to start automatically upon receipt of an engineered safety feature (ESF) signal. One of the three pumps can be supplied from either emergency electrical bus ("H" or "J" bus).
The charging pump electrical supply breakers are equipped with interlock logic to ensure that only one charging pump can be supplied from an emergency bus at any given time. One such interlock for the "A" pump can stop the pump or prevent the pump from auto-starting in one operational configuration. This TM ensures that Unit 2 Charging Pump "A" will continue to operate or automatically start following receipt of an ESF signal coincident with a loss of offsite power. This TM does not affect Emergency Diesel Generator loading and assures the proper equipment response during accident conditions.
Therefore, an unreviewed safety question is not created.
Temporary Modification (Safety Evaluation No.91-263) 12-13-91 This Temporary Modification (TM) mechanically holds open damper 2-VS-F-60A on the Unit 2 control rod drive mechanism (CROM) shroud cooling fan to ensure adequate cooling is provided to the reactor head area.
This TM does not affect other systems and will ensure proper operation of the CROM shroud cooling fan until the subject damper can be repaired. Therefore, an unreviewed safety question is not created.
FS 91-40 e
e Surry Monthly Operating Report No. 91-12 Page 11 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December 1991
[continued]
UFSAR Change 12-26-91 (Safety Evaluation 91-273)
The Updated Final Safety Analysis Report (UFSAR) Figure 9.12-1 "Fuel Transfer System" was revised to correct errors associated with drawing references of plant elevations and dimensions of the fuel handling system inside Containment.
This change was administrative only. No physical changes to the station were made. Therefore an unreviewed safety question does not exist.
e e Surry Monthly Operating Report No. 91-12 Page 12 of 19 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL TM S2-91-52 AC S1-91-1231 DCP 87-031-2 MONTH/YEAR: December 1991
[continued]
Temporary Modification (Safety Evaluation No.91-274) 12-26-91 This Temporary Modification (TM) installed electrical jumpers to permit the replacement of Unit 2 "A" train Reactor Protection System relay, 02-RP-REL-PRBXA.
This TM was used to maintain downstream RPS "A" train relays energized during this activity.
Double verification of the jumper installation/removal and post maintenance testing were performed. The RPS "8" train logic was not affected. Therefore, an unreviewed safety question is not created.
Administrative Control (Safety Evaluation No.91-277) 12-31-91 Administrative Control of the Unit 2 Emergency Switchgear room (ESGR)/Turbine Building door is established to facilitate operations and maintenance activities. The controls include stationing a person at the door to the ESGR from the Turbine building. The person's duties are to immediately isolate and disconnect temporary hoses routed through the door and close the door in the event of a main control room (MCR) air bottle bank discharge. The person also performs the required fire watch responsibilities while the door is open.
The controls for the subject door ensure the capability of the MCR/ESGR pressure envelope to achieve the proper positive pressure for minimizing the potential for exposure of MCR personnel to radioactivity releases in the event of design basis accidents. Therefore, an unreviewed safety question is not created.
Design Change Package (Safety Evaluation No.91-017) 12-27-91 This Design Change Package (DCP) installs a new Unit 2 Chemical and Volume Control System (CVCS) Letdown line trip valve, 2-CH-TV-2204A (inside Containment).
The new trip valve, 2-CH-TV-2204A, performs the isolation function previously served by eves Letdown Flow Orifice isolation valves 2-CH-HCV-2200A, 8, and C and will improve leakage testing concerns, reduce personnel exposure and improve penetration design features.
The new trip valve and related limit switches were designed consistent with the original design basis criteria for containment isolation valves and the requirements of Regulatory Guide 1.97. eves operation is unchanged by these modifications. Therefore, an unreviewed safety question is not created.
O-MCM-1918-01 1-PT-18.1 MMP-C-FS-260 e
e Surry Monthly Operating Report No. 91-12 Page13of19 PROCEDURES OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December 1991 Mechanical Corrective Maintenance Procedure (Safety Evaluation No.91-256) 12-09-91 Mechanical Corrective Maintenance Procedure O-MCM-1918-01, "On-Line Leak Repairs" was implemented to correct a gasket leak from the Unit 2 Reactor Coolant system (RCS) flow element, 2-RC-FE-2492.
This repair involved the use of furmanite and installation of a clamp on RCS pipe spool, 3"-RC-4 77-1502.
Due to the nature of this application, furmanite was not injected into the RCS. Thus, RCS chemistry was not affected. An evaluation of the additional weight of the clamp was determined to not adversely impact the seismic qualification of the affected RCS piping.
Therefore, an unreviewed safety question is not created.
Operations Periodic Test Procedure (Safety Evaluation No.91-259) 12-12-91 Unit 1 Operations Periodic Test Procedure 1-PT-18.1, "Low Head Safety Injection Pump Test" was revised ("one-time only" change) to permit the use of temporary transmitters to enable the measurement of Low Head Safety Injection Pump pressure during the few seconds following pump start.
The use of the temporary transmitter does not affect the operation of the subject pump. As a precaution, however, the procedure change includes direction to isolate the transmitter if the Safety Injection system is required to perform its safety function.
Therefore, an unreviewed safety question is not created.
Corrective Mechanical Maintenance Procedure (Safety Evaluation No.91-262) 12-12-91 Corrective Mechanical Maintenance Procedure, MMP-C-FS-260, "Freeze Sealing - Liquid Nitrogen Method - Single Freeze" was performed on the Unit 2 Reactor Coolant System (RCS) "C" loop Resistance Temperature Detector (RTD) manifold return piping to isolate and allow flow element, 2-RC-FE-2492, to be repaired.
The Unit was at Cold Shutdown during the installation and special RCS pressure and temperature requirements were imposed.
Limiting conditions were established to limit potential RCS leakage, as a result of freeze seal failure, and to ensure the leakage would remain within the make-up capacity of the Safety Injection system. Contingency actions were also in place to minimize the consequences of a freeze seal failure.
In addition, Nondestructive Examination of the affected piping was performed prior to and following the seal installation.
Therefore, an unreviewed safety question does not exist.
MMP-C-FS-260 2-0P-5.2.1 e Surry Monthly Operating Report No. 91-12 Page 14 of 19 PROCEDURES OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December 1991
[continued]
Corrective Mechanical Maintenance Procedure (Safety Evaluation No.91-264) 12-13-91 Corrective Mechanical Maintenance Procedure, MMP-C-FS-260, "Freeze Sealing - Liquid Nitrogen Method - Single Freeze" was performed on the Unit 2 Reactor Coolant System (RCS) "B" loop Resistance Temperature Detector (RTD) manifold return piping to isolate and allow flow element, 2-RC-FE-2491, to be repaired.
The Unit was at Cold Shutdown during the installation and special RCS pressure and temperature requirements were imposed.
Limiting conditions were established to limit potential RCS leakage, as a result of freeze seal failure, and to ensure the leakage would remain within the make-up capacity of the Safety Injection system. Contingency actions were also in place to minimize the consequences of a freeze seal failure.
In addition, Nondestructive Examination of the affected piping was performed prior to and following the seal installation.
Therefore, an unreviewed safety question does not exist.
Operating Procedure (Safety Evaluation No.91-267) 12-16-91 Unit 2 Operating Procedure 2-0P-5.2.1, "Starting Any Reactor Coolant Pump" was revised ("one-time only" change) to permit lifting the lead to the malfunctioning Reactor Coolant system loop stop valve 2-RC-MOV-2593 stem switch.
This action circumvents the associated interlock with the "B" reactor coolant pump (RCP) starting circuit, enabling the pump to be started.
This change does not affect the protective functions of the RCP circuitry. The original purpose of the loop stop valve stem switch/RCP starting circuit interlock was to allow two loop operation, which is currently not allowed.
Therefore, an unreviewed safety question is not created.
e Surry Monthly Operating Report No. 91-12 Page 15 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December 1991 None during this reporting period.
CHEMISTRY REPORT MONTH/YEAR: December 1991 Unit No. 1 Primarv Coolant Analvsis Max.
Min.
Ava.
Gross Radioact., u.Ci/ml 1.08EO 5.19E-1 7.27E-1 Suspended Solids, ppm 0.0 0.0 0.0 Gross Tritium, µCi/ml 2.62E-1 1.76E-1 2.27E-1 1131, µCi/ml 1.57E-2 1.42E-3 3.45E-3 113111133 0.19 0.07 0.11 Hvdroaen, cc/ka 46.2 15.6 28.6 Lithium, oom 1.44 0.99 1.22 Boron - 10, oom*
27.2 11.2 19.2 Oxvaen, (00), oom
<0.005
<0.005
<0.005 Chloride, oom 0.004
<0.001 0.002 pH at 25 dearee Celsius 7.67 7.41 7.53 Boron - 10 = Total Boron x 0.196 e Surry Monthly Operating Report No. 91-12 Page 16 of 19 Unit No. 2 Max.
Min.
Ava.
2.98E-1 5.80E-3 1.31E-1 0.0 0.0 0.0 4.55E-1 2.27E-1 3.18E-1 6.88E-4 6.91 E-5 2.98E-4 0.16 0.06 0.09 38.7 26.3 31.4 2.99 1.26 2.17 455.3 218.9 308.5
<0.005
<0.005
<0.005 0.005 0.003 0.004 6.56 5.68 6.30 Comments:
Unit One:
RCS dissolved hydrogen concentration decreased to 15.6 cc/kg on 12-25-91 due to letdown isolation. The recommended limits for RCS dissolved hydrogen are 25-50 cc/kg. When letdown was returned to service on 12-27-91, the dissolved hydrogen concentration increased to 29.5 cc/kg. Dissolved hydrogen was low for a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and 20 minutes.
~~
e Surry Monthly Operating Report No. 91-12 Page 17of 19 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: December 1991 Units One and Two New or Spent New or Number for Fuel Shipping Spent Fuel Assemblies Assembly ANSI Initial Cask Activity Shi~ment No.
Date Stored
~er Shi~ment Number Number Enrichment Level LMO 12-3-91 12 OJ1 UY?
3.8 NIA LMO 12-3-91 12 OJ5 UYB 3.8 NIA LMO 12-3-91 12 1JO UYG 3.8 NIA LMO 12-3-91 12 OJ9 UYF 3.8 NIA LMO 12-3-91 12 1J1 UYH 3.8 NIA LMO 12-3-91 12 2J6 UYY 3.8 NIA LMO 12-3-91 12 1J8 UYQ 3.8 NIA LMO 12-3-91 12 OJ8 UYE 3.8 NIA LMO 12-3-91 12 1J9 UYR 3.8 NIA LMO 12-3-91 12 OJ2 UY8 3.8 NIA LMO 12-3-91 12 3J8 UZA 4.0 NIA LMO 12-3-91 12 4J3 UZF 4.0 NIA LMO 2
12-5-91 12 1J5 UYM 3.8 NIA LMO 12-5-91 12 1J6 UYN 3.8 NIA LMO 12-5-91 12 2J3 UYV 3.8 NIA LMO 12-5-91 12 5J5 uzr 4.0 NIA LMO 12-5-91 12 3J7 UZ9 4.0 NIA LMO 12-5-91 12 4J2 UZE 4.0 NIA LMO 12-5-91 12 4J1 UZD 4.0 NIA LMO 12-5-91 12 2J5 UYX 3.8 NIA LMO 12-5-91 12 2J4 UYW 3.8 NIA LMO 12-5-91 12 OJ?
UYD 3.8 NIA LMO 12-5-91 12 OJ4 UYA 3.8 NIA LMO 12-5-91 12 2J7 uvz 3.8 NIA
e Surry Monthly Operating Report No. 91-12 Page 18 of 19 FUEL HANDLING MONTH/YEAR: December 1991
[continued]
Units One and Two New or Spent New or Number for Fuel Shipping Spent Fuel Assemblies Assembly ANSI Initial Cask Activity Shiement No.
Date Stored eer Shiement Number Number Enrichment Level LMO 3
12-10-91 12 2JO UYS 3.8 NIA LMO 12-10-91 12 2J1 UYf 3.8 NIA LMO 12-10-91 12 1J3 UYK 3.8 NIA LMO 12-10-91 12 1J4 UYL 3.8 NIA LMO 12-10-91 12 1J7 UYP 3.8 NIA LMO 12-10-91 12 2J2 UYU 3.8 NIA LMO 12-10-91 12 OJ6 UYC 3.8 NIA LMO 12-10-91 12 6J2 vou 4.0 NIA LMO 12-10-91 12 3J6 UZ8 4.0 NIA LMO 12-10-91 12 3J9 UZB 4.0 NIA LMO 12-10-91 12 1J2 UYJ 3.8 NIA LMO 12-10-91 12 5J9 VOR 4.0 NIA LMO 4
12-17-91 12 OJ3 UY9 3.8 NIA LMO 12-17-91 12 5J7 VOP 4.0 NIA LMO 12-17-91 12 4J5 UZH 4.0 NIA LMO 12-17-91 12 5J2 UZQ 4.0 NIA LMO 12-17-91 12 4JO uzc 4.0 NIA LMO 12-17-91 12 4J8 UZL 4.0 NIA LMO 12-17-91 12 6J3 vov 4.0 NIA LMO 12-17-91 12 5J3 UZR 4.0 NIA LMO 12-17-91 12 5J8 VOQ 4.0 NIA LMO 12-17-91 12 4J7 UZK 4.0 NIA LMO 12-17-91 12 5J4 uzs 4.0 NIA LMO 12-17-91 12 5J6 VON 4.0 NIA
ti/
Surry Monthly Operating Report No. 91-12 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: December 1991 None During This Reporting Period.