ML18153A996

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Monthly Operating Repts for June 1994 for Surry Power Station Units 1 & 2.W/940712 Ltr
ML18153A996
Person / Time
Site: Surry  Dominion icon.png
Issue date: 06/30/1994
From: Mason D, Ohanlon J, Olsen C
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
94-403, NUDOCS 9407180248
Download: ML18153A996 (19)
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Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 12, 1994 U. S. Nuclear Regulatory Commission Serial No.94-403 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of June 1994.

Very truly yours, J. P. O'Hanlon 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 NRC Senior Resident Inspector Surry Power Station

~q ',

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 94-06 Approved:

  • TABLE OF CONTENTS

.Surry Monthly Operating Report No. 94-06 Page 2of 18 Section Page Operating Data Report - Unit No. 1 .........................................................................................................3 Operating Data Report - Unit No. 2 .........................................................................................................4 Unit Shutdowns and Power Reductions - Unit No. 1....................................................................................5 Unit Shutdowns and Power Reductions - Unit No. 2 .................................................................................... 6 Average Daily Unit Power Level - Unit No. 1.............................................................................................. 7 Average Daily Unit Power Level - Unit No. 2 .............................................................................................. 8 Summary of Operating Experience - Unit No. 1 ......................................................................................... 9 Summary of Operating Experience - Unit No. 2 ......................................................................................... 9 Facility Changes That Did Not Require NRC Approval. .............................................................................. 10 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 ................................................................................................... 18

  • .Surry Monthly Operating Report No. 94-06 Page 3of 18 OPERATING DATA REPORT Docket No.: 50-280 Date: 07-02-94 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: ..............................*.**..*.............. Surry Unit 1
2. Reporting Period: ........*.........................***.*... June, 1994
3. Licensed Thermal Power (MWt): ...*.*................. 2441
4. Nameplate Rating (Gross MWe):....**.*.**............ 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 820
7. Maximum Dependable Capacity (Net MWe): ....... . 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, HAny (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period ......................... . 720.0 4343.0 188663.0
12. Number of Hours Reactor Was Critical ........ .. 720.0 2841.7 126648.9
13. *-Reactor Reserve Shutdown Hours .............. . 0 0 3774.5
14. Hours Generator On-Line .......................... . 720.0 2804.5 124483.5 15 .. Unit Reserve Shutdown Hours.................... . 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... . 1757461.4 6251602.5 289419347.6
17. Gross Electrical Energy Generated (MWH) .. .. 584510.0 2091050.0 94630598.0
18. Net Electrical Energy Generated (MWH) ....... . 561987.0 2009204.0 89836305.0
19. Unit Service Factor .............*..................... 100.0% 64.6% 66.0%
20. Unit Availability Factor...........***................. 100.0% 64.6% 68.0%
21. Unit Capacity Factor (Using MDC Net) .......... . 99.9% 59.2% 61.4%
22. Unit Capacity Factor (Using DER Net) ......... .. 99.1% 58.7% 60.4%
23. Unit Forced Outage Rate ........................... . 0.0% 0.9% 17.1%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

  • OPERATING DATA REPORT
  • Surry Monthly Operating Report No. 94-06 Page 4 of 18 Docket No.: 50-281 Date: 07-02-94 Completed By: D. Mason Telephone: (804) 365-2459 1 . Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . June, 1994
3. Licensed Thermal Power (MWt): ...................... . 2441
4. Nameplate Rating (Gross MWe): ...................... . 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 820
7. Maximum Dependable Capacity (Net MWe): ........
  • 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, HAny (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YID Cumulative

11. Hours In Reporting Period .......................... 720.0 4343.0 185543.0
12. Number of Hours Reactor Was Critical .......... 221.2 3844.2 123920.5
13. Reactor Reserve Shutdown Hours ............... 0 0 328.1
14. Hours Generator On-Line ........................... 211.5 3834.5 122050.1
15. Unit Reserve Shutdown Hours..................... 0 0 0
16. Gross Thermal Energy Generated (MWH) ...... 432133.2 8830556.5 284506298.9
17. Gross Electrical Energy Generated (MWH) .... 140290.0 2952705.0 92898329.0
18. Net Electrical Energy Generated (MWH) ........ 134216.0 2843880.0 88175950.0
19. Unit Service Factor ................................... 29.4% 88.3% 65.8%
20. Unit Availability Factor............................... 29.4% 88.3% 65.8%
21. Unit Capacity Factor (Using MDC Net) ........... 23.9% 83.8% 61.0%
22. Unit Capacity Factor (Using DER Net) ........... 23.7% 83.1% 60.3%
23. Unit Forced Outage Rate ............................ 0% 0% 13.7%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

  • Surry Monthly Operating Report No. 94-06 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: June, 1994 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 07-01-94 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx None During the Reporting Period.

(1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

  • Surry Monthly Operating Report No. 94-06 Page 6of 18 UNIT SHUTDOWN AND POWER REDUCTION (EaUAL To OFI GREATER THAN 20%)

REPORT MONTH: June, 1994 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 07-01-94 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 940604 s 508.5 B NIA SJ SG Unit taken off line for chemical cleaning of steam generator secondary sides.

(1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative .

G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

  • .Surry Monthly Operating Report No. 94-06 Page 7of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 07-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: June, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 787 17 783 2 786 18 780 3 785 19 772 4 785 20 770 5 788 21 767 6 788 22 763 7 788 23 758 8 787 24 767 9 788 25 774 10 788 26 777 11 789 27 780 12 788 28 781 13 788 29 780 14 785 30 781 15 783 16 782 INSTRUCTIONS On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.
  • .Surry Monthly Operating Report No. 94-06 Page 8of 18 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit2 Date: 07-02-94 Completed by: Pat Kessler Telephone: 365-2790 MONTH: June, 1994 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 1 641 17 0 2 649 18 0 3 628 19 0 4 17 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 144 10 0 26 453 11 0 27 726 12 0 28 779 13 0 29 778 14 0 30 779 15 0 16 0 INSTRUCTIONS On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.

SUMMARY

OF OPERATING EXPERIENCE

  • Surry Monthly Operating Report No. 94-06 Page 9of 18 MONTH/YEAR: June, 1994 UNIT ONE:

06/01/94 0000 The reporting period began with the Unit operating at 100% power, 820 MWe.

06/30/94 2400 The reporting period ended with the Unit operating at 100% power, 815 MWe.

UNtTTWO.i, 06/01/94 0000 The reporting period began with the Unit operating at 86.5% power, 700 MWe, due to Steam Generator "C" level oscillations.

06/03/94 2100 Commence ramp down in preparation for U2 Steam Generator Chemical Cleaning (SGCC) outage.

06/04/94 0236 Unit taken off line, began SGCC outage 06/24/94 2125 Reactor made critical in preparation for startup.

06/25/94 0706 Unit placed on line, commence power escalation.

0758 Stop ramp at 32%, 240 MWe, for chemistry hold & calorimetric calculation.

06/26/94 0037 Commence power escalation 0612 Stop ramp at 67%, 515 MWe.

06/27/94 0048 Commence power escalation.

0555 Stop ramp at 95%, 755 MWe.

2230 Commence final power escalation.

2300 Unit at full power, 815 MWe.

06/30/94 2400 The reporting period ended with the Unit operating at 100% power, 815 MWe.

J

  • FACILITY CHANGES THAT DID NIOT

.Surry Monthly Operating Report No. 94-06 Page 10 of 18 REQUIRE NRC APPROVAL MONTH/YEAR: June, 1994 SE 94-115 Safety Evaluation 06-01-94 Safety Evaluation 94-115 was performed to evaluate the use of Westinghouse Corporation's Chemically Enhanced Pressure Pulse Cleaning Method to remove mineral deposits from the Unit 2 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.

TMS2-94-07 Temporary Modification 06-02-94 (Safety Evaluation No.94-117)

Temporary Modification (TM) S2-94-07 mechanically fixed the Unit 2 condensate polishing compressor cooling tower dampers in the open position and provided an alternate source of cooling water.

The TM was implemented to permit continued cooling tower operation while maintenance was being performed. The modification was made to nonsafety-related equipment and did not affect accident analyses or the margin of safety as defined by the Technical Specifications and Updated Final Safety Analysis Report (UFSAR). Therefore, an unreviewed safety question did not exist.

TM S1-94-33 Temporary Modification 06-08-94 (Safety Evaluation No.94-118)

Temporary Modification (TM) S1-94-33 installed an electrical jumper to maintain power to certain Unit 1 Reactor Protection (RP) s*ystem Train "8" circuits during the replacement of relay AFP1-X8.

The "8" reactor trip breaker was open, the "8" by-pass breaker was closed, and the motor-driven auxiliary feedwater pumps were in "pull to lock" during the implementation of this TM. The activity did not affect RP System Train "A". Double verification -of jumper installation/removal and post-maintenance testing were performed. Therefore, an unreviewed safety question did not exist.

TMS2-94-08 Temporary Modification 06-09-94 (Safety Evaluation No.94-119)

Temporary Modification (TM) S2-94-08 installed a one-inch diameter piping branch with a chemical injection quill to the discharge header of the Unit 2 condensate polishers.

The TM was implemented to permit the injection of ethanolamine on a trial basis to help control secondary system pH and corrosion. The modification was made to nonsafety-related equipment and did not affect accident analyses or the margin of safety as defined by the Technical Specifications and UFSAR. Therefore, an unreviewed safety question did not exist.

  • FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL
  • Surry Monthly Operating Report No. 94-06 Page 11 of 18 MONTH/YEAR: June, 1994 TMS2-94-09 Temporary Modification 06-10-94 (Safety Evaluation No.94-121)

Temporary Modification (TM) S2-94-09 installed a temporary exhaust fan in the center of the missile shield of the Unit 2 Main Steam Valve House roof to help remove paint fumes while painting was being performed.

The TM was installed while the unit was at cold shutdown and did not affect the cross-connect (to Unit 1) capability of the Unit 2 motor-driven auxiliary feedwater pumps or the operability of other plant equipment. The TM was removed before the unit left cold shutdown. Therefore, an unreviewed safety question did not exist.

TM S2-94-10 Temporary Modification 06-16-94 (Safety Evaluation No.94-125)

Temporary Modification (TM) S2-94-10 installed electrical jumpers to maintain power to certain Unit 2 Safety Injection (SI) System Train "A" circuits during the replacement of relay Sl-2A.

The TM was implemented while Unit 1 was at cold shutdown when the SI System was not required to be operable. The TM was installed to prevent unwanted ESF actuations to maintain the Daisy Chain of wire continuity to adjacent relays. The TM did not affect SI System Train "8". Double verification of jumper installation/removal was performed.

Therefore, an unreviewed safety question did not exist.

FS92-113 Updated Final Safety Analysis Report Change 06-28-94 (Safety Evaluation No.94-127)

UFSAR Change 94-127 revised Section 9.14, "Decontamination Facility," to reflect the removal of decontamination equipment from the decontamination facility.

The equipment was replaced by other decontamination components in the radwaste facility. Removal of the nonsafety-related equipment did not impact the operation of the plant. Therefore, an unreviewed safety question did not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES

  • Surry Monthly Operating Report No. 94-06 Page 12 of 18 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1994 O-OPT-VS-002 Operations Periodic Test Procedure 06-08-94 (Safety Evaluation No. 94-117A)

Operations Periodic iest Procedure, O-OPT-VS-002, "Auxiliary Ventilation Filter Train Test" was revised to minimize the required operator actions for opening the charging pump motor-operated dampers and returning them to service when performing the subject testing. The procedure revision also deleted the requirement to perform continuity checks for the damper fuses.

The subject testing will be performed on each filter train independently and procedural controls will ensure that the required damper alignment will be obtained during a design basis event. The fuse continuity checks were replaced by steps to verify that the dampers stroke closed. Therefore, an unreviewed safety question does not exist.

SE 94-120 Safety Evaluation 06-10-94 Safety Evaluation 94-120 assessed the resumption of Unit 2 operation for the balance of cycle 12 at the original Reactor Coolant System operating pressure of 2235 psig following the replacement of the pressurizer safety valves.

The evaluation concluded that this change is acceptable since 2235 psig is the nominal RCS operating pressure specified in the Technical Specifications. Furthermore, the design basis of the reactor and plant systems assume an RCS steady state pressure of 2235 psig. Therefore, an unreviewed safety question does not exist.

1/2-IPT-FT-RP-Sl-001A Instrument Periodic Test Procedures 06-14-94 1/2-IPT-FT-RP-Sl-001 B (Safety Evaluation No.94-123)

Instrument Periodic Test Procedures 1[2]-IPT-FT-RP-Sl-0001 A, "Train A Safeguards Actuation Logic Functional Test", and 1[2]-IPT-FT-RP-Sl-00018, "Train B Safeguards Actuation Logic Functional Test " were revised to delete the requirements to perform coil continuity checks for certain slave relays due to the high risk nature of the testing.

The subject relays are normally de-energized, do not have a history of failure, and are functionally tested each refueling outage. The testing circuitry was not configured to support slave relay testing or coil continuity measurement. Such testing is not required by Technical Specifications. Furthermore, this testing change is consistent with the recommendations of Generic Letter 93-05, "Line Item Technical Specification Improvements to Reduce Surveillance Requirements for Testing During Power Operation."

Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES

.Surry Monthly Operating Report No. 94-06 Page 13of 18 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1994 1-GOP-1.3 General Operating Procedures 6-15-94 2-GOP-1.3 (Safety Evaluation No.94-124)

Unit 1 Operating Procedures 1[2]-GOP-1.3, ftUnit Startup, RCS Heatup !From 345° F to HSDft were revised to provide instructions for installing a temporary modification (TM) that removes the seal-in function for the Safety Injection System accumulator isolation valves when the Reactor Coolant System pressure is s. 1000 psig. This TM removes the seal in relay which allows the stroke of the subject motor-operated valves to be controlled. The controlled opening of the Safety Injection System accumulator isolation valves minimizes the potential for pressure transients when returning the accumulators to service during startup activities.

  • These procedurally controlled TMs do not affect the integrity of the valves or their ability to be opened or closed. The accumulators are not required to be operable when the RCS pressure is s 1000 psig. Therefore, an unreviewed safety question does not exist.

DR S-94-1243 Deviation Report 06-21-94 DR S-94-1293 (Safety Evaluation No.94-126)

Safety Evaluation 94-126 assessed the condition reported by Deviation Reports S 1243 and S-94-1293 concerning the continued operation of Unit 2 with a small hole in the riser barrel of the "B" and "C" steam generators (SG).

An evaluation of the hole in the "C" SG was performed by Westinghouse. This evaluation, which is also applicable to the hole in the "B" SG, concluded that it is acceptable to continue operation for the remainder of the fuel cycle since the holes will not affect the thermal performance of the SGs or increase the internal loading on the SG components.

Therefore, an unreviewed safety question does not exist.

1[2]-EPT-0902-01 Electrical Periodic Test Procedures 06-28-94 1[2]-EPT-0902-02 Electrical Preventive Maintenance Procedure O-EPM-0902-01 (Safety Evaluation No.94-045, Revision 1)

Electrical Periodic Test Procedures 1[2]-EPT-0902-01, "Fire Protection Low Pressure CO2 System Puff Test," and 1[2]-EPT-0902-02, "Fire Protection Low Pressure CO2 System Equipment Test," were revised to provide instructions for administratively controlling the low pressure carbon dioxide tank manual isolation valves to facilitate the performance of Technical Specification required surveillance flow testing. Electrical Preventive Maintenance Procedure O-EPM-0902-01, "Fire Protection Low Pressure CO2 System Turbine Generator Enclosure Protection Tests," was developed to provide instructions for performing similar testing of the turbine generator low pressure CO2 system.

Appropriate administrative controls are provided in the procedures to ensure that the Low Pressure Carbon Dioxide fire suppression systems remain capable of performing their design function during testing. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES

-urry Monthly Operating Report No. 94-06 Page 14 of 18 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: June, 1994 1-FP-VPA-Fl1 Vendor Procedure 6-30-94 (Safety Evaluation No.94-132)

Vendor Procedure 1-FP-VPA-Fl1, "Fuel Inspection for Surry Unit 1" was developed to delineate the tasks and evolutions required to perform fuel inspections of some fuel assemblies discharged from Surry Unit 1 Cycle 12.

Implementation of this procedure will not alter the handling or storage characteristics of any fuel assemblies. The assumptions used in the analysis for the fuel handling accident in the Fuel Building remain bounding for the handling and inspection of irradiated fuel.

Therefore, an unreviewed safety question does not exist.

  • .Surry Monthly Operating Report TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL No. 94-06 Page 15 of 18 MONTH/YEAR: June, 1994 None During the Reporting Period
  • .Surry Monthly Operating Report No. 94-06 Page 16 of 18 CHEMISTRY REPORT MONTH/YEAR: June, 1994 Unit No.1 Unit No. 2 Primarv Coolant Analvsis Max. Min. Ava. Max. Min. Avo.

Gross Radioactivity, u.Ci/ml 3.56E-1 1.78E-1 2.59E-1 2.95E-1 6.20E-4 8.31E-2 Suspended Solids, ppm <0.1 .s,0.1 .s,0.1 .s,0.1 .s,0.1 .s,0.1 Gross Tritium, u.Ci/ml 3.0SE-1 2.82E-1 2.91E-1 4.12E-2 4.12E-2 4.12E-2 1131, u.Ci/ml 4.12E-4 2.63E-4 3.37E-4 2.74E-4 3.68E-5 7.52E-5 113111133 0.08 0.06 0.07 0.08 0.06 0.07 Hvdroaen, cc/ka 42.9 33.4 37.9 41.1 2.2 14.6 Lithium, oom 2.30 2.09 2.18 2.34 0.51 1.41 Boron - 10, oom* 209.9 198.4 204.2 328.3 119.2 252.0 Oxygen, (DO), ppm <0.005 .s,0.005 <0.005 6.0 <0.005 0.47 Chloride, ppm s.0.050 0.003 0.014 .s,0.050 0.003 0.014 pH at 25 degree Celsius 6.89 6.50 6.62 6.95 5.81 6.24

None

  • FUEL HANDLING

.Surry Monthly Operating Report No. 94-06 Page 17 of 18 UNITS 1 & 2 MONTH/YEAR: June, 1994 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity No Fuel Received or Stored During the Reporting Period.

  • .urry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED No. 94-06 Page 18 of 18 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: June, 1994 None During the Reporting Period.
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