ML18153D192
| ML18153D192 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/30/1992 |
| From: | BOWLING M L, MASON D, XENAKIS A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 92-780, NUDOCS 9212160171 | |
| Download: ML18153D192 (21) | |
Text
~.. . 0 !. I ' e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 11, 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.92-780 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 November 1992. Very truly yours, M. L. Bowling, Manager Nuclear Licensing
& Programs Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station -------------*--~
921216017t" 921130 PDR ADOCK 05000280 R PDR e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 92-11 Approved:
e TABLE OF CONTENTS Section tlurry Monthly Operating Report No. 92-11 Page 2of 20 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 ...........................................
16 Tests and Experiments That Did Not Require NRC Approval ......................................................................
17 Chemistry Report .............................................................................................................................
18 Fuel Handling -Unit No. 1 ...................................................................................................................
19 Fuel Handling -Unit No. 2 ...................................................................................................................
19 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified.
in Technical Specifications
...................................................................................................
20 4lurry Monthly Operating Report No. 92-11 Page 3 of 20 OPERATING DATA REPORT Docket No.: Date: Completed By: 50-280 12-07-92 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 1 November 1992 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 YfD Cumulative
- 11. Hours In Reporting Period ..........................
720.0 8040.0 174816.0 12. Number of Hours Reactor Was Critical ..........
720.0 6396.8 114631.0 13. Reactor Reserve Shutdown Hours ...............
0.0 0.0 3774.5 14. Hours Generator On-Line ...........................
720.0 6291.2 112531.4 15. Unit Reserve Shutdown Hours .....................
0.0 0.0 3736.2 16. Gross Thermal Energy Generated (MWH) ...... 1757402.8 14697863.7 261814540.4
- 17. Gross Electrical Energy Generated (MWH) .... 592010.0 4892690.0 85407878.0
- 18. Net Electrical Energy Generated (MWH) ........ 563146.0 4643135.0 81017201.0
- 19. Unit Service Factor ...................................
100.0% 78.2% 64.4% 20. Unit Availability Factor ...............................
100.0% 78.2% 66.5% 21. Unit Capacity Factor (Using MDC Net) ...........
100.1% 73.9% 59.8% 22. Unit Capacity Factor (Using DER Net) ...........
99.3% 73.3% 58.8% 23. Unit Forced Outage Rate ............................
0.0% 3.5% 18.5% 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):
FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION
- > e -urry Monthly Operating Report No. 92-11 Page 4of 20 OPERATING DATA REPORT Docket No.: Date: Completed By: 50-281 12-07-92 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 1992 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 720.0 720.0 0.0 720.0 0.0 1757520.0 585370.0 556730.0 100.0% 100.0% 99.0% 98.1% 0.0% YTD 8040.0 7734.8 0.0 7726.1 0.0 18647125.7 6159480.0 5853456.0 96.1% 96.1% 93.2% 92.4% 0.0% 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):
Cumulative 171696.0 112942.9 328.1 111187.0 0.0 259525807.8 84593329.0 80217394.0 64.8% 64.8% 59.9% 59.3% 14.4% FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION
.urry Monthly Operating Report No. 92-11 Page 5 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) REPORT MONTH: November 1992 (1) (2) (3) (4) (5) Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12-07-92 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)
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.
eurry Monthly Operating Report No. 92-11 Page 6 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) REPORT MONTH: November 1992 (1) (2) (3) (4) (5) Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12-07-92 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)
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.
Month: November 1992 Day 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS e -urry Monthly Operating Report No. 92-11 Page ?of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 12-07-92 Completed by: M.A. Negron Telephone:
(804) 365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net)
Day (MWe-Net) 782 17 785 783 18 784 781 19 784 781 20 784 779 21 783 780 22 782 782 23 782 783 24 782 784 25 779 783 26 782 782 27 783 782 28 780 780 29 785 776 30 785 784 31 784 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: November 1992 Day 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 INSTRUCTIONS e tlurry Monthly Operating Report No. 92-11 Page 8 of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 12-07-92 Completed by: M.A. Negron Telephone:
(804) 365-2795 Average Daily Power Level Average Daily Power Level (MWe-Net)
Day (MWe-Net) 773 17 774 773 18 774 769 19 774 764 20 775 772 21 773 773 22 774 774 23 773 774 24 773 774 25 774 774 26 774 774 27 774 774 28 773 774 29 774 774 30 774 774 31 774 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.
-urry Monthly Operating Report No. 92-11 Page 9 of 20
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR:
November 1992 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 11-01-92 11-30-92 UNIT TWO 11-01-92 11-30-92 0000 2400 0000 2400 This reporting period began with the Unit operating at 100% power, 820 MWe. 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. This reporting period ended with the Unit operating at 100% power, 825 MWe.
tlurry Monthly Operating Report No. 92-11 Page 10 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL SE 92-218 DCP 85-06-3 TM S1-92-38 MONTH/YEAR:
November 1992 Safety Evaluatlon 1 0-20-92 This Safety Evaluation was performed to evaluate a change in the bearing cooling (BC) system line-up to the instrument air (IA) compressors and after coolers. The modified line-up maintains the BC system solenoid operated valves, 1-BC-SOV-102 and 2-BC-SOV-201, open to allow a continuous flow through the IA compressors and aftercoolers.
This configuration removes residual heat following the shutdown of the IA compressors preventing a high discharge temperature lockout. This alignment change will not affect the operation of the BC system temperature control valves in maintaining proper IA compressor operating temperature.
Operation of the BC and IA systems is not affected by this change. Therefore, an unreviewed safety question is not created. Design Change Package 11-03-92 This Design Change Package (DCP) installed a comprehensive on-line steam generator secondary side water chemistry monitoring system on Units 1 and 2. The information gathered by the system is used as a basis for implementing actions to reduce the frequency and duration of outages caused by specification steam generator steam purity and water chemistry.
The modification did not affect the operation or the ability of equipment important to safety to perform its safety function.
Therefore, an unreviewed safety question was not created. Temporary Modification (Safety Evaluation No.92-225) 11-03-92 This Temporary Modification (TM) installed electrical jumpers to maintain electrical circuit continuity during the replacement of failed Unit 1 reactor protection system test switch, 01-RP-CS-151.
This TM enabled both trains of the Safety Injection (SI) system actuation circuitry to remain in service during the replacement of the test switch. Double verification was required for the installation and removal of the jumpers and post maintenance testing was performed.
Therefore, an unreviewed safety question was not created.
-urry Monthly Operating Report No. 92-11 Page 11 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL TM S1-92-39 EWA 90-330 AC S2-92-1109 MONTH/YEAR:
November 1992 Temporary Modification (Safety Evaluation No.92-226) 11-03-92 This Temporary Modification (TM) installed electrical jumpers to maintain electrical circuit continuity during the replacement of failed Unit 1 reactor protection system test switch, 01-RP-CS-144.
This TM enabled both trains of the Safety Injection (SI) system actuation circuitry to remain in service during the replacement of the test switch. Double verification was required for the installation and removal of the jumpers and post maintenance testing was performed.
Therefore, an unreviewed safety question was not created. Engineering Work Request (Safety Evaluation No.90-253) 11-04-92 This Engineering Work Request provided instructions for the inspection and cleaning of the Unit 2 recirculating spray heat exchanger service water supply piping. This activity was performed with Unit 2 at cold shutdown and with no fuel movement in process. The configuration or function of the subject piping was not modified.
Therefore, an unreviewed safety question was not created. Administrative Control (Safety Evaluation No.92-228) 11-09-92 Administrative control of Unit 2 main steam trip valve manual bypass valve 2-MS-155 was established to allow the valve to be opened and maintenance to be performed to correct a steam leak. The administrative controls were established for this maintenance activity to ensure that the manual valve would be closed promptly in the event of a safety injection signal. The administrative controls also ensured that the manual valve would be reclosed following the maintenance.
Furthermore, the probability of a steam line break during the maintenance period (approximately four hours) is insignificant and the radiological consequences remained bounded by the existing design basis. Therefore, an unreviewed safety question was not created.
e aurry Monthly Operating Report No. 92-11 Page 12 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL EWR 90-332 AC S1-92-1112 FS 92-39 MONTH/YEAR:
November 1992 Engineering Work Request (Safety Evaluation No.90-332) 11-09-92 This Engineering Work Request provided instructions for the inspection and cleaning of the Unit 2 48-inch service water (SW) headers and the 30-inch and 36-inch SW piping. The 48-inch SW headers supply water to the control room habitability chillers.
To ensure the control room envelope temperatures remained within the analyzed limits during this activity, compensatory actions were implemented as directed by a Justification for Continued Operation.
The configuration or function of the SW system was not modified.
Therefore, an unreviewed safety question was not created. Administrative Control (Safety Evaluation No.92-229) 11-12-92 Administrative control of service water valves 1-SW-263, 1-SW-265, and 1-SW-303 was established to permit strainer 1-VS-S-1A to be removed from service for maintenance.
The administrative controls maintained service water flow to control room chillers and charging pump service water pumps and ensured compliance with Appendix R fire protection requirements.
Therefore, an unreviewed safety question was not created. UFSAR Change 11-12-92 (Safety Evaluation 92-231) The Updated Final Safety Analysis Report (UFSAR) Section 4.1, "Reactor Coolant System Design Bases," was revised to reflect Surry's participation in the Babcock and Wilcox Owner's Group (B&WOG) Master Integrated Reactor Vessel Surveillance Program (MIRVSP).
The change is administrative in nature. No procedures are affected and no physical modifications are involved.
The change involves only a modification to the reactor vessel materials surveillance capsule withdrawal schedule.
Therefore, an unreviewed safety question was not created.
aurry Monthly Operating Report No. 92-11 Page 13 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL FS 92-46 FS 92-48 DR S-92-1839 MONTH/YEAR:
November 1992 UFSAR Change 11-12-92 (Safety Evaluation 92-234) The Updated Final Safety Analysis Report (UFSAR) Section 11 A.3, "Plant and Animal Census," was revised to clarify the purpose of the plant and animal census and to identify the station program which documents the census information.
Table 11A-9, "Distance to the Nearest Residence, Garden, Milk Cow, Milk Goats, and Beef Cattle Within 5 Miles of the Surry Plant," was deleted to eliminate the need to revise the UFSAR to reflect changes in the annual plant and animal census. The change is administrative in nature. No physical modifications are involved.
Therefore, an unreviewed safety question is not created. UFSAR Change 11-12-92 (Safety Evaluation 92-232) The Updated Final Safety Analysis Report (UFSAR) Section 9.10.2.2.1, * "Water Storage Tanks," and Table 15.2-1, "Structures, Systems, and Components Designed for Seismic and Tornado Criteria," were revised to delete incorrect statements regarding the use of the intake canal as a backup source of water for the fire protection system. The change is administrative in nature. No procedures are affected and no physical modifications are involved.
The existing ]fire protection system meets regulatory requirements and provides adequate fire suppression capability to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. Therefore, an unreviewed safety question was not created. Deviation Reports 11-17-92 (Safety Evaluation No.92-238) This Safety Evaluation was performed to evaluate Deviation Report S-92-1839 concerning the operation of the mechanical equipment rooms 3 and 4 service water supply piping with valve 1-SW-301 fixed in the open position with a cracked yoke. It was determined that the cracked yoke does not affect the integrity of the valve or plant operation.
Therefore, an unreviewed safety question is not created.
&rry Monthly Operating Report No. 92-11 Page 14of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL TSl-015 DCP 90-02-03 MONTH/YEAR:
November 1992 Technical Specification Interpretation (Safety Evaluation No.92-237) 11-17-92 Technical Specification Interpretation TSl-015 was developed to clarify the operability status of a station battery and associated chargers while testing is being conducted pursuant to Technical Specification (TS) 4.6.C.1.d.
An evaluation of the applicable TS concluded that turning off a battery charger during testing merely places the respective battery in its design operating condition for a brief period of time. Furthermore, sufficient margin exists in station battery capacity to remain fully capable of its design basis duty cycle following the completion of the subject testing. Therefore, an unreviewed safety question is not created. Design Change Package (Safety Evaluation No.90-128) 11-20-92 This Design Change Package (DCP) increased the storage capacity of the main control room bottled air system by installing additional air bottles in mechanical equipment room 3 and a new bottle bank in the switchgear area stairwell.
This modification was made to ensure the compressed air storage capacity is adequate to maintain the control room pressure envelope at a positive pressure for one hour consistent with the design criteria.
The change did not affect the operation of the main control room bottled air system. Therefore, an unreviewed safety question was not created. 10 CFR 50, Appendix R Report (Safety Evaluation 92-241) 11 92 The 1 o CFR 50, Appendix R Report was revised to incorporate completed plant modifications that affect the Appendix R program and additional/revised engineering evaluations.
The plant modifications were evaluated independently, with respect to Appendix R compliance, prior to implementation as part of the design char,ge process. The additional engineering evaluations were performed in accordance with Generic Letter 86-10. The revised engineering evaluations resulted from walkdowns of fire area boundaries to assess current plant configurations.
These changes document commitments which form part of the licensing basis for fire protection for Units 1 and 2. No physical changes to the plant were made. Therefore, an unreviewed safety question was not created.
e aurry Monthly Operating Report No. 92-11 Page 15 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL AC S2-92-1130 MONTH/YEAR:
November 1992 Administrative Control (Safety Evaluation No.92-242) 11-30-92 Administrative control of the Unit 2 emergency switchgear room/cable tunnel door was established to permit an air hose to be temporarily routed through the doorway. A continuous fire watch was stationed at the door while it was open. The fire watch was responsible for disconnecting the temporary air hose and closing the door in the event of a safety injection, main control room air bottle bank discharge, fire, or a carbon dioxide discharge.
This control action ensured the capability of rapidly restoring the main control room/emergency switchgear room pressure envelope to its required accident condition.
Therefore, an unreviewed safety question was not created.
t* e tlurry Monthly Operating Report No. 92-11 Page 16 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL 1-IPT-FT-RC-T-412 1-IPT-FT-RC-T-422 1-IPT-FT-RC-T-432 1-PT-18.1 2-PT-18.1 MONTH/YEAR:
November 1992 Instrument Periodic Test Procedures (Safety Evaluation No.92-233) 11-12-92 Instrument Periodic Test Procedures 1-IPT-FT-RC-T-412, "Delta T and TAVG Protection Set I Loop T-412 Channel Calibration," 1-IPT-FT-RC-T-422, "Delta T and TAVG Protection Set II Loop T-422 Channel Calibration," and RC-T-432, "Delta T and TAVG Protection Set Ill Loop T-432 Channel Calibration," were revised to provide instructions for gathering additional data from the respective spare resistance temperature devices to determine inherent process noise and streaming effects associated with the operation of these instrument loops. This activity is a test only and will not involve any modifications, setpoint changes, or impact on plant operations.
The additional testing will be performed in conjunction with the normal monthly functional test of the three delta T and T average protection loops and involves only gathering additional data within the provisions established for the monthly testing. Therefore, an unreviewed safety question is not created. Operations Periodic Test Procedure (Safety Evaluation No.92-230) 11-12-92 Operations Periodic Test Procedures 1/2-PT-18.1, "LHSI Pump Test," were 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 safety-related transmitters does not affect the operation of the subject pumps or the ability of the safety injection system to perform its required safety function.
Therefore, an unreviewed safety question was not created.
- J* e tlurry Monthly Operating Report No. 92-11 Page 17of 20 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
November 1992 None during this reporting period.
e CHEMISTRY REPORT MONTH/YEAR:
November 1992 Unit No. 1 Primarv Coolant Analvsis Max. Min. Ava. Gross Radioact., u.Ci/ml 3.57E-1 2.52E-1 2.99E-1 Suspended Solids, oom < 0.1 < 0.1 < 0.1 Gross Tritium, J.LCi/ml 3.51E-1 3.32E-1 3.45E-1 1131, J.LCi/ml 8.15E-4 5.03E-4 6.82E-4 113111133 0.12 0.07 0.09 Hvdroaen, cc/ka 40.7 30.7 36.7 Lithium, oom 2.30 2.02 2.22 Boron -10, oom* 194.4 171.7 179.4 Oxygen, (DO), oom < 0.005 < 0.005 < 0.005 Chloride, nom 0.006 0.002 0.005 oH at 25 dearee Celsius 6.79 6.62 6.70 Boron -1 O = Total Boron x 0.196 Comments:
None. tlurry Monthly Operating Report No. 92-11 Page 18 of 20 Unit No. 2 Max. Min. Ava. 2.42E-1 1.45E-1 1.78E-1 < 0.1 < 0.1 < 0.1 3.02E-1 2.78E-1 2.90E-1 6.17E-4 2.69E-4 3.85E-4 0.14 0.07 0.09 45.2 34.9 39.9 2.18 1.67 1.99 58.6 40.2 49.3 < 0.005 < 0.005 < 0.005 0.003 < 0.001 0.001 7.39 7.23 7.32
., New or Spent Fuel Shipment Date Stored or Number Received CASTORVt21 11-10-92 500-11-017 e FUEL HANDLING UNITS 1 & 2 MONTH/YEAR:
November 1992 Number of Assemblies Assembly ANSI per Shipment Number Number NIA 084 LMOSLR 089 LM08M7 OLS LM06ET 180 LMOSLJ 182 LMOSLN 2C3 LM08M6 3C1 LMOSMN 3C3 LMOSMV 3C8 LMOSME 4C7 LM08N5 4C8 LMOSND 4C9 LM08N9 5C1 LMOSMX 5C2 LMOSNJ 5C3 LM08N2 5C5 LM08N4 5C6 LM08M5 J10 LM034G J40 LM035R J41 LM035L J49 LM034T tlurry Monthly Operating Report No. 92-11 Page 19 of 20 New or Spent Initial Fuel Shipping Enrichment Cask Activity 3.22 NIA 3.22 3.13 3.22 3.22 3.40 3.40 3.40 3.40 3.40 3.40 3.40 3.40 3.40 3.40 3.40 3.40 2.90 2.90 2.90 2.90
. * .,. ,., . e tllurry Monthly Operating Report No. 92-11 Page 20 of 20 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR:
November 1992 None During This Reporting Period.