ML18153A295
| ML18153A295 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/31/1998 |
| From: | Marshall G, Mason D, Steinert J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 98-192, NUDOCS 9804170215 | |
| Download: ML18153A295 (18) | |
Text
e e
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April.8,1998 United States 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.
SPS Lie/JCS Docket Nos.
License Nos.98-192 RO 50-280 50-281 DPR-32 DPR-37 The Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of March 1998, is provided in the attachment.
If you have any questions or require additional information, please contact us.
Very truly yours,
~~cc_
D. A. Christian, Site Vice President Attachment Commitments made by this letter: None cc:
U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, S. W.
Suite 23T85 Atlanta, Georgia 30303 d._, I
/*l'/7,'~.
- l
~~ i;--*@"
Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station 9804170215 980331 PDR ADOCK 05000280 R
I VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 98-03 Approved:
Site Vice President Date
TABLE OF CONTENTS Section
-Surry Monthly Operating Report No. 98-03 Page 2 of 17 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 Nos. 1 and 2............................................................................................. 9 Facility Changes That Did Not Require NRG Approval............................................................................................ 10 Procedure or Method of Operation Changes That Did Not Require NRG Approval................................................. 13 Tests and Experiments That Did Not Require NRG Approval.................................................................................. 15 Chemistry Report..................................................................................................................................................... 16 Fuel Handling - Unit Nos. 1 and 2............................................................................................................................ 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications....................................................................................................................... 18
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
OPERATING DATA REPORT Unit Name:............................................................
Reporting Period:..................................................
Licensed Thermal Power (MWt):..........................
Nameplate Rating (Gross MWe):..........................
Design Electrical Rating (Net MWe):....................
Maximum Dependable Capacity (Gross MWe):....
Maximum Dependable Capacity (Net MWe):........
Surry Unit 1 March, 1998 2546 847.5 788 840 801
-Surry Monthly Operating Report No. 98-03 Page 3 of 17 Docket No.:
50-280 Date:
04/02/98 Completed By:
D. K. Mason Telephone:
(757) 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 Year-To-Date Cumulative
- 11.
Hours in Reporting Period 744.0 2160.0 221544.0
- 12.
Hours Reactor Was Critical 493.9 1859.3 155885.1
- 13.
Reactor Reserve Shutdown Hours 0.0 0.0 3774.5
- 14.
Hours Generator On-Line 481.2 1839.5 153439.0
- 15.
Unit Reserve Shutdown Hours 0.0 0.0 3736.2
- 16.
Gross Thermal Energy Generated (MWH) 1206302.9 4654401.7 360899417. 3
- 17.
Gross Electrical Energy Generated (MWH) 403900.0 1559994.0 118375748.0
- 18.
Net Electrical Energy Generated (MWH) 390464.0 1508543.0 112742764.0
- 19.
Unit Service Factor 64.7%
85.2%
69.3%
- 20.
Unit Availability Factor 64.7%
85.2%
70.9%
- 21.
Unit Capacity Factor (Using MDC Net) 65.5%
87.2%
65.4%
- 22.
Unit Capacity Factor (Using DER Net) 66.6%
88.6%
64.6%
- 23.
Unit Forced Outage Rate 0.0%
3.0%
14.6%
- 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):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
OPERATING DATA REPORT Unit Name:............................................................
Reporting Period:..................................................
Licensed Thermal Power (MWt):..........................
Nameplate Rating (Gross MWe):..........................
Design Electrical Rating (Net MWe):....................
Maximum Dependable Capacity (Gross MWe):....
Maximum Dependable Capacity (Net MWe):........
Surry Unit 2 March, 1998 2546 847.5 788 840 801
-Surry Monthly Operating Report No. 98-03 Page 4 of 17 Docket No.:
50-281 Date:
04/02/98 Completed By:
D. K. Mason Telephone:
(757) 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:
- 11.
Hours in Reporting Period 744.0
- 12.
Hours Reactor Was Critical 744.0
- 13.
Reactor Reserve Shutdown Hours 0.0
- 14.
Hours Generator On-Line 744.0
- 15.
Unit Reserve Shutdown Hours 0.0
- 16.
Gross Thermal Energy Generated (MWH) 1891107.7
- 17.
Gross Electrical Energy Generated (MWH) 633365.0
- 18.
Net Electrical Energy Generated (MWH) 612967.0
- 19.
Unit Service Factor 100.0%
- 20.
Unit Availability Factor 100.0%
- 21.
Unit Capacity Factor (Using MDC Net) 102.9%
- 22.
Unit Capacity Factor (Using DER Net) 104.6%
- 23.
Unit Forced Outage Rate 0.0%
- 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):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST 2160.0 218425.0 2160.0 153310.3 0.0 328.1 2160.0 151293.5 0.0 0.0 5495754.9 357029322.2 1842315.0 116967923.0 1783495.0 111426646.0 100.0%
69.3%
100.0%
69.3%
103.1%
65.2%
104.8%
64.7%
0.0%
11.8%
ACHIEVED
(1)
Date Type 03/08/98 F
03/20/98 s
(1)
F:
Forced S:
Scheduled (4) e
-Surry Monthly Operating Report No. 98-03 Page 5 of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: March, 1998 (2)
Duration Hours Reason 16h14m A
10d22h B
(2)
REASON:
(3)
Method of LER No.
Shutting Down Rx N/A NONE 1
NONE A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction (4)
System Code LE N/A Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
04/03/98 Completed by:
G. N. Marshall Telephone:
(757) 365-2465 (5)
Component Cause & Corrective Action Code to Prevent Recurrence FAN N/A
'(3)
METHOD:
Broken iso-phase fan belt replaced Scheduled Preventive Maintenance Outage 1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
E Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
(5)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Exhibit 1 - Same Source
(1)
Date Type 03/14/98 F
(1)
F:
Forced S:
Scheduled (4)
(2)
UNIT SHUTDOWN AND POWER REDUCTION (EQUAL TO OR GREATER THAN 20%)
REPORT MONTH: March, 1998
.urry Monthly Operating Report No. 98-03 Page 6 of 17 Docket No.:
50-281 Unit Name:
Surry Unit 2 Date:
04/03/98 Completed by:
G. N. Marshall Telephone:
(757) 365-2465 (3)
(4)
(5)
Method Duration of LER No.
System Component Cause & Corrective Action Hours 11 Reason B
(2)
REASON:
Shutting Down Rx N/A NONE A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction Code SB E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
Code to Prevent Recurrence V
(3)
METHOD:
Freedom Valve Test 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
eurry Monthly Operating Report No. 98-03 Page 7 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
04/03/98 Completed by:
J. C. Steinert Telephone:
(757) 365-2834 MONTH:
March, 1998 Average Daily Power Level Average Daily Power Level Day (MWe - Net)
Day (MWe - Net) 830 17 829 2
828 18 826 3
827 19 825 4
824 20 701 5
823 21 0
6 823 22 0
7 826 23 0
8 676 24 0
9 824 25 0
10 826 26 0
11 826 27 0
12 826 28 0
13 826 29 0
14 828 30 0
15 828 31 17 16 829 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.
MONTH:
March, 1998 Day 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 INSTRUCTIONS
.urry Monthly Operating Report No. 98-03 Page 8 of 17 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)
Day 828 17 829 18 826 19 825 20 824 21 826 22 826 23 825 24 824 25 825 26 826 27 826 28 827 29 791 30 829 31 828 Docket No.:
50-281 Unit Name:
Surry Unit 2 Date:
04/03/98 Completed by:
John C. Steinert Telephone:
(757) 365-2837 Average Daily Power Level (MWe - Net) 829 828 825 825 817 821 822 828 825 827 822 821 822 822 821 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 MONTH/YEAR: March, 1998
.urry Monthly Operating Report No. 98-03 Page 9 of 17 The following chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.
UNIT ONE:
03/01/98 0000 03/08/98 0941 03/08/98 1246 03/08/98 2136 03/09/98 0155 03/20/98 1717 03/20/98 2254 03/21/98 0259 03/21/98 0307 03/31/98 1314 03/31/98 2141 03/31/98 2400 UNIT Two:
03/01/98 0000 03/14/98 0630 03/14/98 1216 03/14/98 1313 03/24/98 1530 03/31/98 2400 Unit 1 operating at 100%, 855 MWe.
Commenced ramp down to self-cooling rating of iso-phase bus.
Stopped ramp at 65%, 540 MWe.
Commenced ramp up at 64%, 540 MWe.
Unit 1 operating at 100%, 855 MWe.
Commenced unit shutdown from 100%, 855 MWe.
Unit off line. Reactor power 4%.
Tripped main turbine.
Manually tripped reactor.
Reactor Critical Unit on line, commence ramp up.
Unit 1 operating at 50%, 414 MWe.
Unit 2 operating at 100%, 855 MWe.
Commenced Ramp Down for Unit Freedom Valve Test Stopped ramp at 74%, 650 MWe Commenced ramp up Unit operating at 100%, 855 MWe Unit 2 operating at 100%, 855 MWe.
JCO SC-97-006 SE 98-0027 FS 98-04 FS97-044 FS 98-05 9surry Monthly Operating Report No. 98-03 Page 10 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1998 Justification for Continued Operation (SE 97-0152 Rev. 1) 03/26/98 The purpose of this revision to the JCO is modify the method of monitoring eighteen containment Radiant Thermal Detectors (RTDs). The RTD high alarm limits will be set 15 degrees above the existing containment temperature. The revision provides the formal tracking mechanism and on shift training of Operations personnel to provide the necessary instructions for operator response to alarms received on the P-250 printer through operations procedures.
The RTDs will be monitored and a weekly review of RTD temperatures will be performed in accordance with a periodic test for any temperature shifts. A design change will be completed for each unit during the next refueling outage to correct the radiant energy shield deficiency.
Safety Evaluation 03/05/98 The Safety Evaluation was performed because two heat trace circuits on Unit 1 had been inoperable for greater that thirty days due to a low wattage output ratio. One heat trace circuit is on the boron injection flow path and one is in the charging discharge flow path.
The heat trace circuits are designed to prevent solidification of boric acid in the associated piping and components by maintaining boric acid solution temperature at greater than technical specification limits.
There are redundant heat trace circuits for the affected piping and they are verified operable daily by operator logs and a Main Control Room annunciator alarms whenever the temperature of the heat trace circuits are within the same temperature band as required by the logs.
UFSAR Change Request (Safety Evaluation No. 98-0029) 03/12/98 UFSAR Change Request FS 98-04 documents Quality Assurance (QA) Program organizational responsibilities for the Independent Spent Fuel Storage Installation (ISFSI) in Chapter 17. The changes to the UFSAR are administrative in nature and do not reduce the effectiveness of the QA Program or reduce commitments in the program.
UFSAR Change Request (Safety Evaluation No. 98-0030) 03/12/98 UFSAR Change Request FS97-004 documents an alternative to ANSI/ANS 3.1 (Draft 12/79) by stating that the requalification training requirements for Shift Supervisor, Senior Reactor Operator, Reactor Operator, and Shift Technical Advisor, are located in Technical Specifications (TS). This change was made to ensure consistency between the Quality Assurance Topical Report and TS in stating that the above referenced requalification program is in accordance with 10CFR55.59(c).
UFSAR Change Request (Safety Evaluation No. 98-0031) 03/12/98 UFSAR Change Request FS 98-05 documents the elimination of the position of Supervisor Administrative Services from the QA Topical Report and administrative procedures. This change is administrative in nature and re-assignes the responsibilities of the eliminated position to other positions within the organization.
This change does not reduce the commitments in the QA Program.
FS 98-08 TM S1-98-06 SE 98-0037 SE 98-0038 9surry Monthly Operating Report No. 98-03 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1998 UFSAR Change Request (Safety Evaluation No. 98-0033) 03/19/98 UFSAR Change Request 98-08 incorporates a sensitivity evaluation to Section 6.3 to account for the impact of flow through vents and drains in the Recirculation Spray (RS)
Subsystem. The evaluation of this change confirms the ability of the RS subsystems to meet the containment analysis acceptance criteria considering the flow diverted from the spray headers by the vents and drains while crediting expected RS subsystem flow. The safety evaluation assessed the effect of this change upon the existing accident analysis and accounts for the diverted flow impact until the flow through the vents and drains is reduced and Outside Recirculation Spray minimum flow is restored to the value explicitly used in the core uprate analysis.
Temporary Modification (Safety Evaluation No. 98-0034) 03/23/98 This Temporary Modification installs a jumper across the switch in the "C" service water line of the ultrasonic level sensors for the High Level screens. The purpose of the TM is to allow the alarm circuit to function for the remaining three lines thus allowing the Main Control Room to monitor the High Level screens with the "C" line out of service without having the indicator light locked in.
Safety Evaluation 03/24/98 Safety Evaluation 98-0037 was performed because one heat trace circuit on Unit 2 had been inoperable for greater that thirty days due to a low wattage output ratio. The heat trace circuit is on the boron injection flow path.
The heat trace circuit is designed to prevent solidification of boric acid in the associated piping and components by maintaining boric acid solution temperature at greater than technical specification limits. There is a redundant heat trace circuit for the affected piping and it is verified operable daily by operator logs. A Main Control Room annunciator alarms whenever the temperature of the heat trace circuits are not within the temperature band required by technical specification.
Safety Evaluation 03/24/98 Safety Evaluation 98-0038 documents how the fire barriers separating the Unit 1 and Unit 2 Normal Switchgear Rooms (NSGRs) from their respective Mechanical Equipment Rooms (MERs) are adequate as they exist with ventilation dusts between the two areas not completely sealed. The evaluation will also be added to Chapter 1 O of the Appendix R Report.
The evaluation was performed in accordance with Generic Letter 86-10, Interpretation #4, allowing engineering evaluations of fire area boundaries. The NSGRs both contain smoke detectors for early warning of fires the annunciate in the Main Control Room and each area is equipped with a total flooding CO2 system. The MERs are large open areas with a limited amount of combustibles. If a fire were to occur in the MERs, it would not be expected to impinge on the ventilation duct penetrations due to the limited amount of combustibles in the room, the lack of combustibles in the pipe chase, and the open room design would dissipate the heat quickly.
TM S1-98-07 9surry Monthly Operating Report No. 98-03 Page 12 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: March, 1998 Temporary Modification (SE 98-0040) 03/26/98 TM S1-98-07 installed a seal weld plug in a leaking reactor coolant pump Resistance Temperature Detector (RTD) thermowell found during a scheduled maintenance outage.
The RTD was removed and the seal weld plug installed and will remain in place until a future refueling outage when it will be replaced with a wet RTD insert. Normal operating procedures were revised to provide guidance on available indications for pump bearing seal water temperature. The failure of the plug and weld are no different than those postulated for the failure of the thermowell and the potential bearing degradation as a result of a loss of seal cooling water flow. The condition is bounded by previous UFSAR analysis.
1/2-LPT-FP-017 & 018 O-LPT-FP-010 & 022 O-LPT-FP-026 & 027 O-LSP-FP-010 & 011 O-LSP-FP-029 & 030 O-LSP-FP-033 & 034 O-LSP-FP-035 & 036 O-LSP-FP-038 & 039 O-LSP-FP-042 PT-24.35 GOP-1.1 1-TMOP-RH-3047 e Surry Monthly Operating Report No. 98-03 Page 13 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1998 Loss Prevention Periodic Test Procedures (Safety Evaluation No. 98-0026) 03/03/98 Loss Prevention Periodic Test Procedures 1/2-LPT-FP-017 & 018 "Emergency Switchgear Room Halon System," O-LPT-FP-101 & 022 "Fuel Oil Pump House High Pressure CO2 System," and O-LPT-FP-026 & 027 "Emergency Service Water Diesel Fuel Oil Tank Room High Pressure CO2 Sysyem," were permanently changed by adding a Temporary Modification to facilitate testing.
The procedures will allow the lifting of the solenoid operating valves (SOV) from each pilot valve on the Halon gas* and CO2 gas cylinders during testing thus preventing the trip of the systems and the release of suppression gas into the affected area.
Loss Prevention Surveillance Procedures (Safety Evaluation No. 98-0036) 03/24/98 Loss Prevention Surveillance Procedures O-LSP-FP-010 & 011 "Administrative Building High Pressure CO2 System," O-LSP-FP-029 & 030 "Training Center Computer Room Halon System," and O-LSP-FP-033 & 034 "Training Center Simulator Halon System," O-LSP-FP-035 & 036 "Security Halon System," O-LSP-FP-038 & 039 "LEOF Halon System," O-LSP-FP-042 "TSC Vent Filters High Pressure CO2 System," and O-PT-24.35 "TSC Vent Filter Test,"
were permanently changed by adding a Temporary Modification to facilitate testing. The procedures will allow the lifting of the solenoid operating valves (SOV) from each pilot valve on the Halon gas and CO2 gas cylinders during testing thus preventing the inadvertent trip of the systems and the release of suppression gas into the affected area.
General Operating Procedure (Safety Evaluation 98-0041) 03/27/98 General Operating Procedure 1-GOP-1.1 "Unit Startup, RCS Heat-up From Ambient to 190° F," was revised to procedurally control a temporary modification to allow the installation and removal of a Passive Autocatalytic Recombiner (PAR) in Unit 1 containment. The PAR will be used and the current method of "feed and bleed" using the containment vacuum pumps will remain available for the control of the hydrogen concentration in containment.
Temporary Maintenance Operating Procedure (Safety Evaluation 98-0042)
Temporary Maintenance Operating Procedure 1-TMOP-RH-3047 "Draining and Flushing the RHR System," was developed to procedurally control the temporary installation of a hose between the containment Nitrogen Header and the Residual Heat Removal System (RHR).
The nitrogen gas will be used to assist in draining the RHR system while precluding the introduction of oxygen in the RHR and Reactor Coolant Systems (RCS). The RHR system will be isolated from the RCS and declared inoperable for the evolution and pressure will be controlled at less than 100 psig.
tlurry Monthly Operating Report No. 98-03 Page 14 of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: March, 1998 None During the Reporting Period
e CHEMISTRY REPORT MONTH/YEAR: March, 1998 Unit No. 1 Primary Coolant Analysis Max.
Min.
Avg.
Gross Radioactivity, µCi/ml 5.20E-1 1.90E-2 2.44E-1 Suspended Solids, ppm 0.500
~0.010 0.17 Gross Tritium, µCi/ml 3.79E-1 3.43E-1 3.60E-1 1131, µCi/ml 2.01 E-1 6.95E-4 1.55E-2 113111133 0.23 0.11 0.15 Hydrogen, cc/kg 33.0 0.8 12.1 Lithium, ppm 2.42 1.31 2.06 Boron - 10, ppm*
324.2 108.4 228.8 Oxygen, (DO), ppm 0.200
~0.005 0.012 Chloride, ppm
~0.050 0.002 0.007 pH at 25 degree Celsius 6.99 6.08 6.59 Boron - 10 = Total Boron x 0.196 Comments:
None 9urry Monthly Operating Report No. 98-03 Page 15 of 17 Unit No. 2 Max.
Min.
Avg.
2.17E-1 1.12E-1 1.66E-1
~0.010
~0.001
~0.001 8.65E-1 8.21 E-1 8.48E-1 5.39E-5 2.59E-5 4.27E-5 0.10 0.05 0.08 40.2 31.6 35.1 2.34 2.06 2.21 214.4 200.7 208.4
~0.005
~0.005
~0.005 0.005 0.005 0.005 6.68 6.48 6.56
New Fuel Shipment or Cask No.
Date Stored or Received FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: March, 1998 Number of Assemblies per Shipment Assembly Number ANSI Number None During the Reporting Period 9urry Monthly Operating Report No. 98-03 Page 16 of 17 Initial Enrichment New or Spent Fuel Shipping Cask Activity
.rry Monthly Operating Report No. 98-03 Page 17 of 17 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: March, 1998 None During the Reporting Period