IR 05000220/1985018
| ML17055A794 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/18/1985 |
| From: | Nimitz R, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17055A792 | List: |
| References | |
| 50-220-85-18, 50-410-85-32, NUDOCS 8511260432 | |
| Download: ML17055A794 (40) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-220-85-18 50-410/85-32 Docket No.
50-220 50-410 License No.
DPR-63 CPPR-112 Pri ority Category C
B Licensee:
Nia ara Mohawk Power Cor oration 300 Erie Boulevard West S racuse New York 13202 Facility Name:
Nine Mile Point Unit 1 and
Inspection At:
Oswe o
New York Inspection Conducted:
October 14-18 1985 Approved by:
Inspectors:
R.
L. N'tz Senior Radiation pecialist W. J.
sciak, Chief BWR, Radiation Protection Section dat l& k&
date Ins ection Summar:
Inspection conducted October 14-18, 1985 (combined Report 50-220/85-18; 50-410/85-32)
Areas Ins ected:
Routine, unannounced radiological controls inspection of routine operation at Unit 1 and preoperational testing at Unit 2.
The following areas were reviewed at Unit 1:
personnel training and qualification; posting, barricading and access control; and previous findings.
The following areas were reviewed at Unit 2:
organization and staffing; training and quali-fications; previous findings; bulletins, circulars, and information notices; fuel receipt planning and preparation; preoperational testing of radiation/
radioactivity monitoring systems, liquid, solid gaseous processing systems, HVAC; shield survey program.
The inspection involved 41 inspector hours at Unit 2 and 3 inspection hours at Unit 1.
85it260432 851l20
'"'DR ADO'5000220,.
(
Q PDR
Results:
No violations or deviations were identified.
The licensee has not completed preoperational testing of radioactive waste processing systems or of the process and effluent monitoring systems.
Additional licensee attention is needed in the area of IE Bulletin and Circular closur ~
I
DETAILS 1.0 Individuals Contacted N
k
"M.D. Jones, Superintendent, Operations
"L. D. Kassakatis, Start-up
- 0. Henderson, Radwaste Supervisor
- R. G. Randall, Superintendent Technical Support
- J. N. Duell, Supervisor, Chemistry and Radiation Protection
- E.
W. Leach, Superintendent, Chemistry and Radiation Protection Management
- M. J.
Ray, Manager, Special Projects
"T. E.
Lempges, Vice President Nuclear Generation
"T. J
~ Perkins, Generation Superintendent
"M. T. Boyle, Nuclear Compliance and Verification
- R. Gerlig, Radiation Protection Supervisor
- P. Volza, Supervisor Radiological Support
"WE Drews, Technical Support
- D. Barcomb, Supervisor, Radiation Protection
"W. Connally, Supervisor, QA Nuclear Operations 1.2 Nuclear Re viator Commission
- S. Hudson, Senior Resident Inspector (SRI), Unit
~R.
Gramm, SRI, Unit 2
~denotes those individuals attending the exit meeting on October 18, 1985 The inspector also contacted other individuals during the inspection.
2.0
~Per oee The purpose of this routine inspection was to review the following program elements:
Unit
~
previous findings review
~
Radiological Controls Personnel Training/Qualification
~
Posting, Barricading and Access Control
II I'
Unit previous findings review Organization and Staffing Training and Qualification Bulletins, Circulars, Information Notices Fuel Receipt Preparation and Planning
~
Preoperational Testing:
Process, Area, Effluent Monitors Liquid Radwaste System Gaseous Radwaste System HVAC Systems Shield Surveys 3.0 Previous Findin s Review 3.1 3.2 3.3 3.4 (Open)
Follow-up Item (50-220/84-22-01)
NRC to review licensee close out action of SRAB radiological control audit findings.
The inspec-
.
tor review of licensee close out of the findings indicated that:
1)
the findings are tracked via computer, 2) reports of the status of the findings are periodically provided to upper management, and 3)
the findings are resolved in a technically acceptable manner.
How-ever, the inspector review of the finding closure summaries indicated that, in some instances, the summary did not provide a clear basis for closure of the finding.
Additional inspector review found that acceptable corrective action was taken to close the audit finding but had not been included in the closure summary.
The licensee should clearly indicate in the closure summary the basis for closure of the findings.
The licensee was unable at the time of the inspection to provide closure summaries for audit findings in the area of radio-logical controls training and qualifications.
The closure of find-ings in this area will be reviewed during a subsequent inspection.
(Open)
Follow-up Item (50-410/85-20-01)
NRC to review licensee preoperational testing of Liquid Radioactive Waste Processing Systems.
The licensee has completed about 25% of the Preliminary Testing.
The Preoperational testing has not commenced.
(Open)
Follow-up Item (50-410/85-20-02)
NRC to review licensee preoperational testing of the solid Radioactive Waste Processing System.
This matter is discussed in Section 9 of the report.
(Open)
Follow-up Item (50-410/85-20-03)
NRC to review licensee preoperational testing of safety related ventilation system testing.
This matter is discussed in Section 9 of this repor.5 (Closed)
Follow-up Item (50-410/85-20-04)
NRC to review preopera-tional testing of area, process, and effluent monitoring system.
This item is closed for administrative purposes.
A separate item for area, process, and effluent monitor testing review will be opened to provide for better tracking of each system.
See Section 9 of this report.
3.6 (Open)
Follow-up Item (50-410/85-20-05)
Licensee to determine capa-bilityy of his process and effluent monitoring system to collect representative samples.
The licensee is currently reviewing this matter.
This item remains open.
3.7 (Closed)
Follow-up Item (50-410/85-20-06)
NRC to review training and qualification of start-up test personnel.
Inspection reviews during Inspection 50-410/85-20 could not substantiate adequate selection, training and qualification of start-up test personnel.
Resumes for certain individuals were not available.
Also no apparent evaluation of acceptability of contractor provided written exam was performed.
The licensee subsequently performed a comprehensive audit of the selection, training, and qualification of start-up personnel in the questionable areas, and documented the evaluation of the accepta-bilityy of written exams.
The licensee found that all personnel reviewed were properly trained and qualified.
No major findings were identified.
An evaluation of the acceptability of the exams was performed but had not been docu-mented.
This matter is closed.
The following items for improvement were identified:
~
Ensure that appropriate uniform controls are inplace to verify the previous experience of start-up test personnel.
~
Provide general guidance for performance of oral exams of start-up test personnel.
4.0 Or anization and Staffin Unit 1 and
The inspector reviewed the organization and staffing of the Radiological Controls Organization with respect to criteria contained in the following:
Final Safety Analysis Report (FSAR), Section 13, "Organization,"
AP-1. 1, "Composition and Responsibility of Site Organization,"
"Composition and Responsibility of Unit Organization,"
and AP-1.3,
"Personnel Responsibilities and Authority."
Within the scope of this review, the following was noted:
The licensee has established a defined Radiological Controls Organization to support dual unit operation.
~
The licensee has adequate staff to support fuel receipt and fuel load activities.
~
The licensee is actively recruiting to fill several vacancies in the organization.
These vacancies are primarily needed to support dual unit full power operation.
Within the scope of this review, the following matter needing licensee attention was identified:
~
The licensee has established a
new supervisory position in the dosi-metry records group.
The responsibility and authority of this position should be identified and included in applicable administra-tive documents.
5.0 Trainin and ualification Unit 1 and
The inspector reviewed the training and qualifications of Radiological Controls personnel.
~Findin s
The licensee has established a documented program to select, train, qualify, and retrain personnel.
The program was considered generally acceptable.
However, the following matters requiring licensee attention were identified:
(50-220/85-18-01);
(50-410/85-32-01)
~
Establish a method to ensure the, appropriate personnel (e.g.,
Radio-logical Controls Technicians)
are cognizant of changes to procedures or new procedures prior to tasks associated with those procedures.
Establish and implement a program, as necessary, to verify the previous experience of contractor Radiological Controls personnel.
The inspector review of the qualifications of personnel filling back shift Radiological Controls Technician positions found that excluding the above issues, the technicians were adequately trained and qualified.
6.0 Bulletins Circulars and Information Notices Unit 2 The inspector reviewed the licensee's action on (as appropriate)
and the status of a number of Bulletins and Circulars.
Information Notices were also discusse I
Some of the Bulletins and Circulars reviewed were as follows:
~
"Contamination of Nonradioactive System and Resulting Potential for Unmonitored, Uncontrolled Release of Radio-activity to Environment"
~
IE Circular No. 77-10,
"Vacuum Conditions Resulting in Damage to Liquid Process Tanks"
~
IE Circular No. 77-14,
"Separation of Contaminated Water Systems from Uncontaminated Plant System"
~
IE Circular No. 79-21, "Prevention of Unplanned Releases of Radioactivity"
~
IE Circular No. 80-18,
"10 CFR 50.59 Safety Evaluation for Changes to Radioactive Waste Treatment System" The inspector also reviewed the licensee's action on NRC Generic Letter 81-38,
"Storage of Low Level Waste at Power Reactor Sites,"
The licensees performance in the area was based on discussion with personnel and review of documentation.
The following was identified:
~
The licensee has not completed action on the bulletins and circulars.
~
Procedures to implement the guidance contained in the bulletins and circulars have yet to be developed.
~
The action taken by the licensee to address the bulletins and cir-culars should be reviewed to determine if it remains acceptable.
The licensee is uncertain as to whether the action taken on some of the circulars remains acceptable due to possible plant system changes.
No apparent, comprehensive, unified program to address the matters discussed in Generic Letter 81-38.has been established.
A program to address the matters discussed in Generic Letter 81-38 should be established on a site wide basis.
The inspector noted that the licensee has, in some instances, ceased action on some circulars as a result of NRC indication that a particular circular is closed.
The inspector informed the licensee that a detailed review of the implementation of the guidance contained in these circulars should be performe II
The attachment to this inspection report provides a listing of applicable bulletins, circulars, and information notices whose receipt and implemen-tation (as appropriate)
by the licensee will be reviewed during subsequent inspection (50-410/85-32-02).
7.0 Postin Barricadin and Access Control Unit
The inspector toured the Unit 1 Radiological Controlled Area.
The following matters were reviewed:
~
posting and barricading of radiation and high radiation areas
~
access control to locked high radiation areas
~
performance of radiological surveys
~
control and posting of radioactive and contaminated material.
Within the scope of this review, no violations were identified.
The licensee was properly posting, barricading and controlling access to radiation and high radiation areas.
Radioactive and contaminated material areas were properly posted and controlled.
The following item for improvement was identified:
The source used to check operability of Mini-Rad Survey instruments does not provide for verification of the operability of the high range of the instruments.
8.0 Pre aration for Fuel Recei t Unit 2 The inspector reviewed the licensee's radiological controls planning and preparation for the receipt and inspection of new fuel.
The review was with respect to criteria contained in the following:
Letter, R.
M. Rader (for Niagara Mohawk) to J.
G. Davis (NRC), dated June 12, 1985.
Subject:
Application for Amendment to Special Nuclear Material License SNM1895.
Letter, Merri Horn (NRC), to A.S. Zllnick (Niagara Mohawk), date July 29, 1985, Subject:
Request for Additional Information
'll Letter, M. J. Wetterhahn (for Niagara Mohawk) to J.
G. Davis (NRC),
dated September 27, 1985, Subject:
Amendment to the Application to Amend Special Nuclear Material License 1895.
CFR 20, "Standards for Protection Against Radiation"
CFR 50, "Domestic Licensing of Production and Utilization Facilities"
~
CFR 70, "Domestic Licensing of Special Nuclear Material" The evaluation of the licensee's performance in the area was based on:
~
review of documentation
~
discussions with cognizant individuals inspector observations of fuel receipt, storage, and handling locations.
The following matters were reviewed/discussed;
~
establishment and implementation of procedures for performing receipt radiological controls inspections/surveys of transport vehicle, cask, fuel and components
~
types and acceptability of equipment to be used to perform radio-logical control surveys
~
performance of calibration and periodic operability checks of the instruments
~
establishment and implementation of procedures for calibration and
'peration of the radiological controls survey instrumentation
~
acceptability of cri ter ia for use in determining if components are or are not contaminated
~
training and qualification of personnel performing radiological controls surveys
~
training and qualification of personnel handling/inspecting new fuel
~
emergency procedures for fuel handling accidents
~
airborne radioactivity sampling
~
dosimetry use (e.g. criticality dosimetry)
~
fixed/portable gamma radiation monitoring system of areas
~
personnel contamination monitoring.
Fuel Recei t In general, the licensee has performed acceptable radiological controls planning and preparation for fuel receipt/inspectio I
~
t
%i Ep
Within the scope of this review, the following was identified:
(50-410/85-32-03):
~
The licensee has not established and implemented a number of procedures for fuel receipt radiological controls.
These include:
calibration/operation of radiological instrumentation (cog. portable survey meters).
~
The licensee has not performed an evaluation of the acceptability of the beta/gamma and alpha contamination limits to be used for determining if new fuel/equipment is or is not contaminated.
~
The licensee has not established emergency/accident procedures (rela-tive to fuel handling in Unit 2) and trained personnel in their response to the emergency/accidents.
~
The licensee has not established a procedure for portable ARMs/ARM alarm setpoints and response thereto.
~
The licensee has not established airborne radioactivity monitoring requirements/action levels.
9.0 Preo erational Testin Unit 2 The inspector reviewed the licensee's preoperational testing of the following systems:
~
area, process and effluent radiation monitoring systems;
~
safety related ventilation systems;
~
liquid radwaste system;
~
gaseous radwaste system;
~
solid radwaste system; The review was with respect to criteria contained in the following:
Final Safety Analyses Report (FSAR), Chapter 14, "Initial Tests Program;"
Regulatory Guide 1.68, November 1978, "Preoperational and Initial Start-up Test Program for Water Cooled Power Reactors";
Procedure N2-SAP-100, "Start-up and Test Program description and Organization";
Procedure N2-SAP-101,
"Preparation and Control of Start-up Administration Procedures";
~
Procedure N2-SAP-102, "Joint Test Group";
~
Procedure N2-SAP-106A, "Test Procedure Format";
~
Procedure N2-SAP-106B,
"Test Procedure Review, Approval and Revision";
~
Procedure N2-SAP-107A,
"System Turnover".
The following matters were reviewed:
status of construction, release, and/or turnover of systems;
~
status of start-up test procedure establishment;
~
status of testing;
~
adequacy of test procedures; The evaluation of licensee performance in the above areas was based on:
~
independent inspector walk down (commensurate with degree of construction) of the above systems;
~
'eview of procedures;
~
discussions with cognizant licensee representatives.
9. 1 Area Process and Effluent Radiation Monitorin S stems Unit 2 Documents Reviewed General Final Safety Analysis Report, (FSAR) Section ll.S, "Radiation Monitoring Systems;"
FSAR, Section 12.3, Radiation Protection Design Features ANSI N42. 18-1980, "Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents;"
ANSI N13. 1-1969,
"Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities;"
"Location and Design Criteria for Area Radiation Monitoring Systems for Light Water Nuclear Reactors."
9. 1. 1 Area Radiation Monitors Documents Reviewed FSAR, Section 12.3.4, Area Radiation and Airborne Radioactivity Monitoring Instrumentation Various Loop Calibration Reports (LCRs)
Procedure IE.Gene 024, Kaman Instrumentation Model KEM-A/KEM-P Radiation Monitors, Revision
~Findin n
All Area Radiation monitors are installed.
However, no testing/
calibration of the instruments have been performed.
The monitors have not yet been supplied with permanent power.
There are five ARMs located on the Refueling Floor.
The licensee has placed priority on testing/calibration of these monitors.
Two of the monitors (Inside Fuel Vault and Refuel Platform) are Technical Specification required monitors.
Based on the results of the review, the following matters requiring licensee review/attention were identified:
(50-410/85-32-04)
FSAR Table 12.3-1 indicates that two ARMs are located on the Spent Fuel Refueling Platform.
These ARMs are not located on the Platform, rather they are located on the Operating Floor.
The licensee should update his FSAR accordingly.
Also a review should be conducted to deter-mine if all ARMs are in their proper location.
FSAR up-dates should be made where appropriate.
The ARMs have not been subjected to Preliminary Testing The ARMs have not been subjected to Preoperational Testing.
Procedure N2-POT-BOA-1 has not been approved.
Procedure IE Gene 024 does not provide for calibration of the ARMs in mR/hr or R/hr, but in counts per minute.
Con-sequently, it is not clear that the procedure provides for calibration of the ARM over range of anticipated use.
Also, the traceabi lity of the beta sources used for checking of the ARMs is not clearly indicated.
The licensee should calibrate the ARMs'eeded to support fuel receipt and inspectio.1.2 Gaseous Effluent Monitors GEMS SAI Document Reviewed FSAR, Section 12.3', Area Radiation and Airborne Radioactivity Monitoring Instrumentation
~
FSAR Section 11.5 Process and Effluent Radiological Monitoring and Sampling System General The Gaseous Effluent Monitoring System (GEMS) consists of the Plant Stack and Reactor Building Yent Monitors.
The purpose of these monitors is to monitor/quantify effluent releases from these two discharge paths.
Within the scope of the review, the following matters requiring licensee attention were identified:
(50-410/85-32-05):
~
Complete Preliminary Testing of System
~
Complete Preoperational Testing of System (N2-POT-BOA-2).
Testing is 0% complete.
~
Install insulation on Stack Sampling line
~
Supply uninterrupted power to monitor 9. 1.3 Process Monitorin S stem Di ital Radiation Monitorin S stem Kaman)
Documents Reviewed FSAR Section 12.3.4, Area Radiation and Airborne Radioactivity Monitoring Instrumentation
~
FSAR Section 11.5, Process and Effluent Radiological Monitoring and Sampling Systems General The function of the ORMS is to measure, evaluate and report radioactivity in process streams, in liquid and gaseous efflu-ents and in selected plant locations.
With the scope of this review, the following matters requiring licensee attention were identified (50-410/85-32-06)
l
~
Preliminary test of the DMRS has not been completed.
Completion status is less than 5%.
~
Preoperation Testing of the DMRS has not started.
The pre-operational Test procedure is in draft form.
9.2 Solid Radioactive Waste S stem Documents Reviewed Documents Reviewed
~
Final Safety Analysis Report.(FSAR) Section 11.2, "Solid Waste Management";
~
ANSI/ANS-55. 1, 1979, "Solid Radioactive Waste Processing System for Light Water Cooled Reactor Plants";
~
Applicable Stone and Webster, F-SK Piping and Instrumentation Drawings (P&IDs).
~Findin s
~
The licensee has initiated Preliminary Testing of the Solid Radioactive Waste System.
The licensee has not established/
approved the system preoperational tests.
The licensee approved the procedure for operation of the Solid Radioactive Waste System (IOP-41).
~
The licensee has established draft procedures for performance of solid radioactive waste handling/shipment activities.
The following matter requires licensee attention:
(50-410/85-32-07)
~
Approve the necessary radwaste handling procedures to support fuel receipt/fuel load as appropriate.
9.3 Main Steam Line Monitors General Electric General There are four ion chambers physically located near the main steam lines.
These monitors provide channel trip signals to the Reactor Protection System, containment isolation, and reactor vessel isola-tion control systems to initiate protective action.
The monitors are used for detecting failed fuel.
Within the scope of this review, the following matters requiring licensee attention were identified:
(50-410/85-32-08)
~
The main steam line monitors are not yet installed.
~
The system has not been released for testin t pr
~
The preoperational test procedure has not been established.
~
preliminary testing is not complete.
10.0 Shield Surve s
Unit 2 The inspector reviewed the licensee's preparation and planning for per-formance of plant shield surveys.
The licensee's performance in this area was based on discussions with licensee representatives and review of documentation
~Findin s
The licensee is currently establishing his shield survey program.
This area will be reviewed during a subsequent inspection (50-410/85-32-09).
The inspector met with licensee representatives (denoted in Section 1)
at the conclusion of the inspection on October 18, 1985.
The inspector summarized the purpose, scope and findings of the inspection.
No written material was provided to the licensee by the inspecto ATTACHMENT UNIT 2 Bulletins, Circulars, and Information Notices In The Area of Radiological Controls A.
General The following Bulletins, Circulars, and Information Notices should have been received by the licensee and action (as appropriate) initiated to address the matters described therein.
B.
~List i n Item Recommended Action As A ro riate *
IE Bulletin No. 80-10,
"Contamination of Non-Radioactive System and Potential for Unmonitored, Uncontrolled Release to Environment."
IE Circular NO. 77-10,
"Vacuum Conditions Resulting in Damage to Liquid Process Tanks," July 15, 1977.
IE Circular No. 77-14, "Separation of Contaminated Water Systems from Uncontaminated Plant Systems,"
November 22, 1977.
IE Circular No. 79-21, "Prevention of Unplanned Releases of Radio-activity," October 17, 1979.
IE Circular No. 80-18,
"10 CFR 50.59 Safety Evaluations for Changes to Radioactive Waste Treatment Systems,"
August 22, 1980.
IE Circular No. 81-09,
"Containment Effluent Water that Bypasses Radioactivity Monitor," July 10, 198 <<,p
~Listin Recommended Action As A ro riate IE Circular No. 80-14,
"Radioactive Contamination of Plant Demineralized Mater System and Resultant Internal Contamination of Personnel,"
June 24, 1980.
IE Circular No. 81-07,
"Control of Radioactively Contaminated Material,"
May 8, 1981.
IE Circular 76-03, "Radiation Exposures in Reactor Cavities,,"
dated September 15, 1976.
IE Information Notice No. 79-09,
"Spill of Radioactively Contaminated Resin,"
March 30, 1979.
IE Information Notice No. 82-43,
"Deficiencies in LWR Air Filtration/Ventilation Systems,"
November 16, 1982.
IE Information Notice No. 82-49, Correction for Sample Conditions for Air and Gas Monitoring,"
December 16, 1982.
IE Information Notice No. 83-14,
"Dewatered Spent Ion-Exhange Resin Susceptibility to Exothermic Chemical Reaction,"
March 21, 1983.
IE Information Notice No. 80-22, Breakdown in Contamination Control Programs,"
May 22, 198 ~Listin Recommended Action As A ro riate *
IE Information 'Notice No. 82-32,
"Contamination of Reactor Coolant System by Organic Cleaning Solvents,"
August 19, 1982.
IE Information Notice No. 82-49,
"Correction for Sample Conditions for Air and Gas Monitoring,"
December 16, 1982.
IE Information Notice No. 83-0S,
"Obtaining Approval for Disposing of Very-Low-Level Radioactive Waste - 10 CFR 20.302,"
February 24, 1980.
IE Information Notice No. 83-33,
"Nonrepresentative Sampling of Contaminated Oil," May 26, 1983.
IE Information Notice No
~ 79-07,
"Rupture of Radwaste Tanks,"
March 26, 1979.
IE Bulletin No. 79-19,
"Packaging, Transport, and Burial of Low-Level Radioactive Waste," August 10, 1979.
-operator Tr aining Program C-remaining aspects H
IE Bulletin No. 79-20,
"Packaging, Transport, and Burial of Low-Level Radioactive Waste," August 10, 1979.
IE Circular No. 78-03,
"Packaging Greater Than Type A Quantities of Low Specific Activity Radioactive Material for Transport,"
May 12, 1978.
IE Information No. Notice 79-21,
"Transportation and Commercial Burial of Radioactive Materials,"
September 7,
1979 (Supplement to IE Bulletin Nos.
79-19 and 79-20).
h
~Listin IE Information Notice No. 80-32,
"Clarification of Certain Requirements for Exclusive-Use Shipments of Radioactive Materials," August 29, 1980.
Recommended Action As A ro riate IE Information Notice No. 80-32, Revision 1, "Clarification of Certain Requirements for Exclusive-Use Shipments of Radioactive Materials,"
February 12, 1982
"Clarification of Several Aspects Relating to Use of NRC-Certified Transport Packages,"
March 11, 1983.
IE Notice 80-24 "Low-Level Waste Burial Criteria," May 30, 1980 IE Information Notice No. 82-18,
"Assessment of Intakes of Radioactive Material by Workers,"
June 11, 1982.
IE Information Notice No. 81-26, Part 2, "Placement of Personnel Monitoring Devices for External Radiation Exposure,"
August 28, 1981 and Supplement 1,
July 19, 1982.
IE Information Notice No. 83-59,
"Dose Assignment for Workers in Non-Uniform Radiation Fields,"
September 15, 198 *Recommended Action Com letion A
Fuel Receipt
Fuel Loading C
Initial Criticality G
Receipt Verification and personnel awareness of information H
First shipment of Radioactive Waste