Text

Insp Rept 50-382/85-26 on 851007-11.Violations & Deviation Noted:Failure to Conduct Specified Training Courses,Failure to Provide Proper Storage for Shipping Containers & Use of Addl Low Level Radwaste Storage Areas
	ML20137W986
Person / Time
Site:	Waterford
Issue date:	11/29/1985
From:	Chaney H, Murray B, Spitzberg D; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20137W961	List: ML20137W954; ML20137W962; ML20137W975; ML20137W986;
References
	50-382-85-26, IEB-79-19, NUDOCS 8512100391
	Download: ML20137W986 (17)
	v • d • e

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APPENDIX C

U.S. NUCLEAR REGULATORY COMMISSION

,

REGION IV

-[ NRC Inspection Report: 50-382/85-26 License: NPF-38

. Docket: -50-382

Licensee: Louisiana Power & Light Company (LP&L)

ATTN: R. S. Leddick, Senior Vice President

Nuclear Operations

142 Delaronde Street

4

New Orleans, Louisiana 70174

Facility Name: Waterford Steam Electric Station, Unit 3 (Wat-3)

Inspection At: Taft, St. Charles Parish, Louisiana (Wat-3 site) and

Generai Office in New Orleans, LA

. Inspection Conducted: October 7-11, 1985

'

Inspectors; n[- , / #-27-86

H.Chan'e9~,IT(did.igfSpecialist, Facilities Date

Radiological Prot %ction Section

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D. B. Spitzberif, ifadfation Specialist, - Date

Facilities Radiolobical Protection

-Section

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p proved: [//c 1/11tztd ///BW65

B. Murray, Chief,' Facilit/tes Radiological

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Protection Section /

Inspection Summary

Inspection Conducted October 7-11, 1985 (Report 50-382/85-26)

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, Areas Inspected: Routine, unannounced inspection of the licensee's radioactive

material (RAM) shipment program, solid radioactive waste (radwaste) management

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program, and activities involving onsite storage of low-level ' radioactive

waste (LLRW). The inspection involved 75 inspector-hours onsite and

7 inspector-hours offsite by two NRC inspectors.

Results: Within the areas inspected, two violations, (see paragraphs 4 and 5),

and one deviation (see paragraph 7) were identified.

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DETAILS

1. Persons Contacted

LP&L-

-R.-Barkhurst, Plant Manager

S. Alleman, Assistant Plant Manager

.

R. Kenning, Radiation Protection Superintendent

L. Simon, Radwaste Engineer

K. Brewster, Licensing Engineer

R. Cornell, Independent Safety Engineering Group, Engineer

D._.'Stevens, Radwaste Supervisor

M. Moe, Radwaste Supervisor

D.~ Landeche, Health Physics (HP) Supervisor

R. Pittman, Operation Quality Assurance (QA) Supervisor

J. Woods, Quality Control (QC) Manager

'*D. Rieder, Radwaste Associate Engineer

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'J. Etheridge,' LP&L General Office (GO), Radiation Control Unit,

Radwaste Engineer -

E. Fields, Engineering Nuclear' Safety, Engineer

J. Messina, QA-Representative

'G. Wuller, Onsite Licensing Coordinator

W. Perry, Chemistry and Radwaste Training Instructor

~J. O'Hern, General Training Superintendent

" Denotes those present at the exit interview on October 11, 1985.

The NRC inspector also interviewed several other licensee and contractor

personnel.

2. Licensee Actions on Previously Identified Inspection Findings

.(Closed).0 pen Item (382/8512-02): Pre-use Response Check for Radiation #

-Measurement Instruments --This item was previously discussed in NRC

Inspection Report 50-382/85-12 and_ involved the licensee's7 1ack of a

suitable pre-use response check for the Eberline teletector high range

probe. The licensee had implemented a revision to HP Directive 83-1 which

provided for response checking the high range probe of the teletector

prior to use. Several teletectors were inspected for documentation of the

required response check. This item is-considered closed.

3. Organization and Management Controls

The NRC inspectors reviewed the licensee's onsite and offsite organiza-

tions that were involved with RAM transportation, radwaste operations and

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management to determine compliance with the commitments contained in the

Final Safety Analysis Report (FSAR), Sections 11,12, and 13; and the

requirements of the facility operating license Technical Specifications

(TS), Section 6; NRC Inspection & Enforcement (I&E) Bulletin 79-19, and

the recommendations in NRC Branch Technical Position (BTP) concerning

waste classification and characteristics.

The NRC inspectors determined that th radwaste organization agreed with

the organizational chart depicted in Figure 6.2-2 of the TS. The licensee

had developed position descriptions for personnel functional assignments-

and designated a specific individual as being responsible for LLRW and the

transportation of RAM.

The NRC inspectors reviewed procedures and a computerized program for LLRW

classification, characterization, and shipping document preparation. The

procedures reviewed are listed in the Attachment I to this report.

The NRC inspectors reviewed the licensee's Process Control Program (PCP),

the vendor's solidification PCP, and operating procedures. The NRC

inspectors discussed with the licensee the apparent lack of positive

control over vendor procedures used for solidification operations. This

item was also noted as a finding in a recent licensee QA audit

(SA-W3-QA-85-12). The licensee stated that actions were being taken to

place vendor procedures under their change and revision control. The

licensee was noted to have developed a special scope QA document (Nuclear

Operations Management Manual-NOMM,Section VI, Chapter 5) for general

radwaste management and the establishing of specific QA/QC policies for

compliance with 10 CFR Part 71, Subpart H requirements.

The NRC' inspectors reviewed the licensee's program for appraisals and

audits of transportation and radwaste activities. Recent audits and

appraisals (SA-W3-QA-84-47, SA-W3-0A-85-12, and RCU Appraisal 85-2) of

radwaste and transportation activities, including management and training

aspects w~re reviewed. The NRC inspectors noted that the licensee's

auditor checklists and audit notes were not of a sufficient depth to

ensure that all of the NOMM's directives had been implemented in the

radwaste program. The NRC inspectors also reviewed responses to audit

findings and the program for ensuring audit findings were resolved in a

timely manner. The NRC inspectors noted to the licensee at the exit

meeting that, currently, there are no personnel in the operations- QA audit

group with technical expertise in the field of radwaste and transportation-

activities. .The licensee stated that they are considering recruiting

personnel with HP,-radwaste/ transportation experience and that future

audits of radwaste activities would evaluate implementation of the

radwaste program.

No violations or deviations were identified.

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4. Training and Qualification

The NRC inspectors reviewed the licensee's training and qualification

program for perscnnel assigned transportation and radwaste duties to

determine compliance with commitments contained in the FSAR, Section 13;

and the requirements of TS 6.3, 6.4; and I&E Bulletin 79-19, and the

recommendations of industry standards ANSI /ANS 3.1-1978 and

ANSI N18.1-1971.

.

The NRC inspectors reviewed course' descriptions, lesson plans, personnel

training records, QA audits, and held discussions with training department

personnel. The NRC inspectors were informed by training department

personnel that the Institute of Nuclear Power Operation's (INPO)

accreditation program for training of plant personnel did not specifically

include radwaste activities involving transportation or the handling of

LLRW (compaction and solidification), and that current performance based

training development did not provide for task analysis in radwaste

functional areas. The NRC inspectors noted to the licensee that the NRC

would expect the licensee to maintain the training and retraining program

for radwaste activities.

The NRC inspectors reviewed the training qualifications of several rad-

waste group personnel that performed compaction of LLRW to determine

compliance with IE Bulletin 79-19 and licensee procedures. Radwaste

Technical Procedure RW-02-200, " Packaging Radioactive Solid Waste (DAW)

for Disposal," specifies that personnel performing compaction using the

B-100 compactor (large box type compactor) must have completed training in

the following areas:

General Employee Training,

Redwaste Training in accordance with UNT-03-018, "Radwaste Helper and

Radwaste Technician Training Procedure,"

-* Instruction in the operation of the B-100 waste compactor,

The handling of radwaste in accordance with procedure RW-02-200, and

Qualification training for forklift truck operation, including

demonstrating operating ability.

The NRC inspectors determined on October 10, 1985, that a contracted

employee had compacted DAW using the-B-100 compactor approximately 18

times,.during the period July 18 through September 5, 1985. Contrary to

the above requirements, licensee training records showed that out of the

five specific training courses referenced above, the contractor employee

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had only received the General Employee training. Failure to conduct the

specified training is considered a violation of TS 6.8.1 (382/8526-02).

.The NRC inspectors reviewed Nuclear Training Department radwaste course

descriptions, lesson plans of completed courses, attendance rosters, and

tests. The NRC inspectors noted that, with the exception of the employee

noted above, all other employee's inspected (including contractor.

. personnel) were qualified for their functional area assignments.

No deviations were identified.

5. Radioactive Material Transportation Program

The NRC inspectors reviewed the licensee's transportation program for

compliance with the requirements of 10 CFR Part 71, and DOT regulations

49 CFR Parts 171 through 178, the NRC I&E Bulletin 79-19, commitments

contained in Sections 11.4.4 and 12.5.1.3 (K) and (1) of the FSAR, the

recommendations in I&E Notices 83-10, 84-14, and 84-50, NRC Regulatory

Guides (RGs) 7.1 through 7.10, and the guidance contained in NUREG-0923

and the licensee's commitments.

The NRC inspectors determined that since receiving their operating license

in December 1984 the licensee had not shipped any radioactive material

other than low specific activity (LSA) waste that did not exceed Type A

quantities. Therefore, only strong, tight containers have been used by

the licensee.for seven such shipments.

a. Quality Assurance Program and Audits

The NRC inspectors reviewed the licensee's QA program for compliance

with the requirements of 10 CFR Part 71, Subpart H. QA attributes

governing the procurement of packaging, use of packaging, and ship-

ment of RAM is set forth in Attachment I to Chapter 5 of Section VI

to the NOMM (see paragraph 3 above). This quality program satisfies

the requirements of 10 CFR Part 71.101(b). The licensee has also

notified the NRC concerning the requirements of 10 CFR Part 71.101(f).

A review of licensee procedures for the shipment of RAM showed the

extensive use of independent QC verifications and checklists for .

container loading and closing. The licensee's audits to date had

been conducted prior to the licensee shipping any RAM. However, the

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licensee's radwaste contractor'had conducted an appraisal of RAM

shipping during June of this year and reviewed the radwaste

activities associated with one shipment and noted no deficiencies.

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b. Procedures .

The licensee's procedures for selection of packaging, preparation for

shipment, marking / labeling / placarding, mcnitoring for radiation and

contamination, and criteria for disposal site acceptance were

reviewed and found to be satisfactory except for the form used in

.RW-02-500, _.for determining the dose rate from a package for curie

content estimation. The NRC inspectors noted that the instructions

on the form were confusing and that values for average container dose

rates were in error on a majority of the shipments reviewed. The

. licensee's representatives stated that HP personnel filling out the-

-forms were making the errors due to the complexity of the forms and

insufficient training. The licensee representative further stated

that the data from the forms were not used to estimate the curie

content of containers previously shipped since the computerized RAM

shipping program for waste containers, utilized shipment specific

radicchemistry analysis results for determining each container's

curie content. The licensee stated at the exit meeting that the

subject form would the revised to make it simpler to use.

c. Procurement and Selection of Packagings

The licensee was found to have implemented detailed instructions on

the. procurement and receipt inspection of shipping con-

tainers /packagings. This included both DOT specification and NRC

certified packages.

The NRC inspectors noted during the period October 7 through 10 that

the licensee had stored approximately eight steel liners, used for

the solidification or dewatering of LLRW resins / wetted solids and as

LSA shipping containers, in an area which was not protected from

inclement weather. These containers / liners had been stored outside

of the security fence opposite the Services Building on the west side

of the plant. These storage conditions are contrary to the

requirements in procedure RW-02-300, " Receipt, Storage and Loading of

Shipping Containers," paragraph 6.1.1, which requires that all DOT

specification, strong, tight, and certified shipping containers shall

be stored to minimize exposure to inclement weather conditions.

Failure to provide proper storage is considered a violation of

TS 6.8.1 (382/8526-01).

d. Determination of Package Activity and Radionuclides

The NRC inspectors reviewed the licensee's methodologies for deter-

mining the curie content of packages. The licensee's computerized

radwaste management program (RADMAN) provides for establishing a

,

containers curie content by either direct input of quantitative

radiochemistry analyses or by a default program using generic PWR

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waste stream radionuclide concentrations and a dose rate to curie

estimation based on Rockwell International shielding methodologies.

-The licensee currently uses the method of directly inserting quantita-

tive radiochemistry analyses into the data base of each shipment. As

noted in paragraph 5.b above, the licensee is reevaluating the

current dose rate averaging method for packages.

e. Preparation of Packages for Shipping

The NRC inspectors reviewed the licensee's procedures for the receipt

inspection, opening, loading and closure of shipping containers and

casks. The NRC inspectors discussed with licensee representatives

the QC inspections set forth in shipment preparation procedures and

the expected degree of-QC involvement in each shipment.

Plant proc.edure RW-2310, Revision 1, " Storage of Loaded Shipping

Containers," paragraph 6.2, requires all loaded shipping containers

to be stored in weather tight buildings or enclosures. The NRC

inspectors determined on October 10, 1985, that the licensee had

stored approximately 114 filled LSA strong, tight shipping containers

(22 solidification liners and 92 steel, B-25 shipping containers)

outside in an area exposed to ambient whether conditions. This is a

second example.of failure to provide proper storage for materials

important to quality and is an apparent violation of T.S. 6.8.1 and

station procedures (382/8526-01-see paragraph 5.c above).

The NRC inspectors noted that many of the containers (B-25 steel

boxes) were filled with condensate polisher resins, which involved

low-level radioactive contamination for which the licensee is

petitioning the NRC to allow onsite burial per-10 CFR Part 20.302

criteria. The NRC inspectors also noted that the B-25 containers

have been accumulating since the April 1985 incident involving a

primary to secondary leak, Licensee Event Report No. 85-13, and that.

there was no program / procedure for the periodic inspection of the

containers' physical condition.

f. Delivery of Packages to Carriers

The NRC inspectors reviewed the licensee's shipping documents for the

eight RAM shipments made by the licensee since the start of facility

operations. The documents were reviewed for content and accuracy

concerning DOT proper shipping name, hazard classification, hazard

identification number, listing of radionuclide inventory, description

of contents (physical and chemical), curie content, category of

labels applied to the package, determination of DOT transport index

val ~ue, placarding applied to the transport vehicle, and whether any

chelating agents were present in LLRW. The licensee's shipping

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documents indicate that past packages delivered to carriers satisfied

the requirement of 49 CFR Parts 100 through 177, and those of 10 CFR

Part 20.311.

g. Receipt of Packages

The NRC inspectors reviewed the licensee's procedures and records for

receipt of radioactive material and determined that the requirements-

of 10 CFR Part 20.205 and recommendations of RG 7.'s were being met.

h '. ' Transportation Incidents.

The NRC inspectors determined,'by discussions with licensee representa-

tives, that none of LP&L's RAM shipments had been involved in accidents

or incidents. Also, no violations have been noted on RAM received.

i. Records, Reports, and Notifications

The NRC inspectors reviewed the licensee's procedures and records for

RAM shipments. The NRC inspectors noted to the licensee that there

appeared to be insufficient independent review of the entire shipping

document package prior to package shipment. The licensee stated that

this aspect of the program would be looked into for possible improve-

ment. The licensee's shipment notification program appears to

satisfy the requirements of 10 CFR Part 71.89.

No' deviations'were noted.

6. Low-Level Radioactive Waste Management Program

The NRC inspectors reviewed the licensee's program for the control,

classification, characterization, and shipment of low-level radioactive

waste to' determine compliance with the commitments contained in

-Section 11.4 of the FSAR; and the requirements contained in 10 CFR

Parts 20.301, 311, 61.55, and 61.56; and TS 6.5.1.6.n, 6.8.1.1, 6.13,

and 6.15; and the recommendations of NRC BTP papers on LLRW classification

and waste form,

a. Procedures

The NRC inspectors reviewed the licensee's process control program

procedure, implementation of the RADMAN computerized LLRW management-

system (including the internal programs for LLRW shipment tracking,

waste manifest preparation, waste classification, and curie content

estimation), QA and G0 audits of LLRW activities, plant waste stream

sampling and analysis procedures, and implementation of the LDCL

Special Scope QA program for radwaste activities.

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b. Sampling and Analysis

The NRC inspectors reviewed the licensee's scaling factors program

for the inventory of radionuclides. This generic model is based on

several Combustion Engineering type pressurized water reactors. The

NRC inspectors discussed with licensee representatives the licensee's

future plans on periodic sampling of waste streams and the developing

of plant specific scaling factors. The licensee's planned program

includes semiannual sampling of waste streams with analyses by an

offsite laboratory in conjunction with quarterly samples analyzed by

the onsite radiochemistry group.

c. Effluent Release and Controls

The NRC inspectors reviewed the licensee's controls over the release

of RAM to unrestricted areas. The licensee had implemented personnel

training (general employee and radiation worker), and detailed

procedures for the handling, control and surveying of potentially

contaminated material. The licensee's controls, equipment, and

procedures were reviewed, as well as actual processing of potenti-

ally contaminated materials by HP personnel. The NRC inspectors

discussed with licensee representatives the NRC's position on use of

state-of-the-art radioactivity measurement equipment for evaluating

the radiological status of materials being released from licensee

control. The NRC inspectors emphasized to the licensee the restrict-

ions placed on 10 CFR Part 50 licensees concerning release of

radioactive material as discussed in NRC I&E Information Notice

No. 83-05.

The licensee informed the NRC inspectors that they were pursuing a

petition to the NRC for establishing an onsite waste burial facility

for the disposal of very low-level radioactively contaminated con-

densate polisher resins per 10 CFR Part 20.302 and the guidance

contained in the above noted I&E Information Notice.

d. Operations and Maintenance of Facilities and Equipment

lhe NRC inspectors determined that the licensee had elected not to

use the installed plant solidification system, but was using a vendor

provided and operated solidification system. The vendor's PCP and

procedures have been accepted by the NRC as meeting the requirements

of 10 CFR Part 61.56. Due to the licensee's nonradiological

limitations on boron in discharged liquids from the plant, the

licensee is utilizing a supplemental demineralizer system (vendor

provided and operated) for treatment of waste liquids. The licensee

had provided for the continuous monitoring of airborne radioactivity

within the temporary solidification facility and specific work area

grab sampling during solidification activities; also the licensee had

provided monitoring instrumentation and HEPA filtered ventilation

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system for the waste segregation and compaction facility. The

licensee also stated that revisions to the FSAR, Section 11.4.8.1

were being planned to resolve the description inaccuracies concerning

the ventilation system on the DAW waste compactor. The licensee's

actions noted above resolve the NRC's. concerns about the temporary

solidification facility and the waste compaction building which were

discusseo in NRC Inspection Report 50-382/84-38.

e. Reports

The NRC inspectors reviewed the licensee's semiannual Radioactive

Effluent Release Report, documented changes to the solid radwaste

system, and PCP procedure changes submitted to the NRC per TS 6.9.1.8

for the period March 4 (initial criticality) through June 30, 1985.

Since issuance of an operating license in December 1984 the

licensee's LLRW inventory has been:

LLRW in

Shipments LLRW to be Long Term

Types of LLRW To Burial Shipped Storage

DAW 950 ft' 190 ft2 none

Wetted Wastes 3094 ft' 1092 ft' 8155 ft'*

Denotes waste being held pending 10 CFR Part 20.302 determination.

7. Onsite Low-Level Radioactive Waste Storage

The' licensee's onsite low-level radioactive waste storage facilities were

reviewed for agreement with the guidance provided in NRC Generic

Letter 81-38, and the licensee's commitments contained in Sections 11.4.6

and 11.4.7 of the FSAR.

The NRC inspectors determined that the licensee had developed. plans and

selected a building site for an interim LLRW storage and DAW compaction

facility of approximately 24,000 square feet. The scheduling for start'of

construction is being held in abeyance pending the outcome of state burial

site compact negotiations and federal legislation'on keeping existing

burial sites open. The licensee's plans appear to incorporate all the

design aspects discussed in the NRC Generic Letter, and NRC BTP-ETSB'11-3.

The FSAR in Sections 11.4.6, 11.4.7, and 11.4.8 identifies LLRW storage

areas in the following locations:

a. Reactor Auxiliary Building Solidification Facility (11.4.6),

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b. An outside lay down area (concrete slab) on the east side of the dry

cooling towers (11.4.7), and

c. Interim Dry Compacted Waste Facility (11.4.8).

The NRC inspectors determined on October 10, 1985, that the licensee had

established approximately four additional LLRW storage areas other than

those referenced in the FSAR. The licensee had established storage for

a;. proximately 114 filled LLRW shipping containers in 4 additional areas of

the plant as follows:

West side of the turbine building (approximately 71 containers),

Southwest corner of the switchyard fence (approximately 19

containers),

East side of the switchyard fence (approximately 2 containers), and

. East side of the turbine building (approximately 22 containers).

The use of additional LLRW storage areas is considered a Deviation of

Commitments in the FSAR (382/8526-01).

8. Exit Interview

The NRC inspectors met with the licensee's representatives identified in

paragraph 1 of this report at the conclusion of the inspection on

October 11, 1985. The NRC inspectors summarized the scope and the results

of the inspection. In response to the inspectors comments and concerns

the licensee provided the following commitments:

a. More positive control will be exercised over vendor procedures used

in the LLRW processing program,

b. The forms and methodologies for determining dose rate information

used in RAM shipment curie estimation will be reevaluated.

c. An independent review program will be implemented concerning the

completed RAM shipment dccument packages.

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ATTACHMENT 1

TO NRC INSPECTION REPORT

50-382/85-26

DOCUMENTS REVIEWED

TITLE REVISION DATE

Nuclear Operations Management Manual (NOMM)

Foreword and Policy Statement 0 3/18/85

Section I - Introduction 0 3/18/85

Section II - Mission and Goals 0 3/18/85

Section III - Management Documentation 0 3/18/85

Section IV - Quality Requirements Matrix 0 3/18/85

Section V - Nuclear Safety Quality Policies 0 3/18/85

Chapter 1 - Organization 0 3/18/85

Chapter 2 - Quality Assurance Program 0 3/18/85

Appendix B - Nuclear Safety Quality

Policy Compliance With

10 CFR 50, Appendix B 0 3/18/85

Section VI - Special Scope Quality Policies 0 3/18/85

Chapter 5 - Radioactive Waste Management 0 3/18/85

Attachment 1 - QA Program for

Transport Packaging 0 3/18/85

Chapter 9 - ALARA Program 0 3/18/85

Chapter 10 - Radiation Protection 0 3/18/85

Quality Assurance Procedures (QAP)

QAP-000, Quality Assurance Charter 0 6/10/85

QAP-001, Quality Assurance Group

Requirement Matrix 0 6/10/85

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QAP-003, Preparation and Revision of NOMM

Sections IV, V, and VI 0 6/10/85

QAP-012, Corrective Action Requests 0 6/10/85

QAP-200, Scheduling of Vendor Quality

Assurance Section Audits 0 6/10/85

QAP-302, Scheduling and Performing Operations

, Surveillance Audits 0 6/10/85

QAP-303, Technical Specifications

Surveillance Audits 0 6/10/85

Nuclear Services Procedures (NSP)

NSP-241, Radiation Control Unit Organization

and Responsibilities 1 4/11/85

NSP-246, Radiation Control Unit Plant

Appraisals 2 6/10/85

NSP-247, Radiation Control Unit Radwaste

Review 0 3/30/84

Health Physics Group Procedures (HP)

HP-01-152, Marking, Handling, and Storage

of Radioactive Material 3 2/26/85

HP-01-214, RCA Control Point Operation 2 10/10/84

Radioactive Waste Management Procedures (RW)

RW-01-100, Radioactive Waste Reduction 1 1/9/85

RW-01-200, Record Preparation, Filing, & Storage 0 11/19/84

RW-01-210, Process Control Program 1 6/5/85

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RW-01-400, Radioactive Waste Reduction

Cost-Benefit Analysis 0 2/25/83

RW-02-100, Handling Dry Active Waste (DAW)

and Used Protective Clothing 1 12/17/84

RW-02-110, Waste Sample Collection and

Isotope Evaluation 1 10/16/84

RW-02-200, Packaging Radioactive Solid Waste

(DAW) for Disposal 3 11/23/84

RW-02-210, Radioactive Waste Solidification 3 6/19/85

RW-02-220, Radwaste Filter Disposal 1 3/8/85

RW-02-230, Dry Waste Segregation 0 2/13/84

RW-02-231, Granulating Material for Disposal 0 3/16/84

RW-02-300, Receipt, Storage and Loading of

Shipping Containers 1 7/16/85

RW-02-310, Storage of Loaded Shipping

Containers 1 7/10/83

RW-02-320, Packaged Radioactive Waste Control

and Inventory 2 12/7/84

RW-02-330, Radioactive Waste Tracking 0 11/19/84

RW-02-500, Radioactive Material Shipment 2 6/20/85

RW-02-800, Dose to Curie Conversion 0 1/8/85

RW-02-810, Waste Classification 0 1/7/85

RW-02-570, Receipt of Radioactive Material 1 7/10/83

Nuclear Training Department

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UNT-3-018, Radwaste Helper and Radwaste

Technician Training Procedure 1 5/1/84

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TE-RW-01, Course Description - Radwaste

l Helper Training 1 11/1/84

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Radwaste Department Course Catalog 10/10/85

Lesson Plans:

Dry Waste Segregation

Radwaste Regulatory Awareness (CHEM NUC)

Radwaste Program Overview

Radioactive Solid Waste Compaction

Radwaste Solidification

Radwaste Helper Training Course

Radioactive Material Packaging

Marking, Labeling and Placarding

Requirements for Radioactive Material

Shipments

Radioactive Shipping Papers

Decontamination

Radwaste Material Handling

Radwaste Shipments

,

RADMAN Computer Software

ML20137W986

Text

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