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| {{Adams | | {{Adams |
| | number = ML20137W986 | | | number = ML20153F109 |
| | issue date = 11/29/1985 | | | issue date = 02/19/1986 |
| | title = 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 | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/85-26.Revs to Procedure RW-2-200 Understood to Not Result in Decreased Controls Re Processing/Packaging of Radwaste |
| | author name = Chaney H, Murray B, Spitzberg D | | | author name = Gagliardo J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Leddick R |
| | addressee affiliation = | | | addressee affiliation = LOUISIANA POWER & LIGHT CO. |
| | docket = 05000382 | | | docket = 05000382 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-382-85-26, IEB-79-19, NUDOCS 8512100391 | | | document report number = NUDOCS 8602250314 |
| | package number = ML20137W961 | | | title reference date = 01-03-1986 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | package number = ML20153F112 |
| | page count = 17 | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | | page count = 2 |
| }} | | }} |
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| APPENDIX C U.S. NUCLEAR REGULATORY COMMISSION
| | , FEB I 91986 |
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| ==REGION IV==
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| -[ NRC Inspection Report: 50-382/85-26 License: NPF-38
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| . Docket: -50-382 Licensee: Louisiana Power & Light Company (LP&L)
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| ATTN: R. S. Leddick, Senior Vice President Nuclear Operations 142 Delaronde Street
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| New Orleans, Louisiana 70174 Facility Name: Waterford Steam Electric Station, Unit 3 (Wat-3)
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| Inspection At: Taft, St. Charles Parish, Louisiana (Wat-3 site) and Generai Office in New Orleans, LA
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| . Inspection Conducted: October 7-11, 1985
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| Inspectors; n[- , / #-27-86 H.Chan'e9~,IT(did.igfSpecialist, Facilities Date Radiological Prot %ction Section
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| du Ma,, //-Z7-d5 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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| i Dage /
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| Protection Section /
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| 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 i
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| 8512100391Bj0 ADOCK O
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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.
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| Results: Within the areas inspected, two violations, (see paragraphs 4 and 5),
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| and one deviation (see paragraph 7) were identifie s
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| DETAILS Persons Contacted LP&L-
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| -R.-Barkhurst, Plant Manager
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| *S. Alleman, Assistant Plant Manager
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| *R. Kenning, Radiation Protection Superintendent
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| *L. Simon, Radwaste Engineer
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| *K. Brewster, Licensing Engineer
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| *R. Cornell, Independent Safety Engineering Group, Engineer
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| *D._.'Stevens, Radwaste Supervisor
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| *M. Moe, Radwaste Supervisor
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| *D.~ Landeche, Health Physics (HP) Supervisor
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| *R. Pittman, Operation Quality Assurance (QA) Supervisor
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| *J. Woods, Quality Control (QC) Manager
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| '*D. Rieder, Radwaste Associate Engineer
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| 'J. Etheridge,' LP&L General Office (GO), Radiation Control Unit, Radwaste Engineer -
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| E. Fields, Engineering Nuclear' Safety, Engineer J. Messina, QA-Representative
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| 'G. Wuller, Onsite Licensing Coordinator W. Perry, Chemistry and Radwaste Training Instructor
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| ~J. O'Hern, General Training Superintendent
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| " Denotes those present at the exit interview on October 11, 198 The NRC inspector also interviewed several other licensee and contractor personnel. Licensee Actions on Previously Identified Inspection Findings
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| .(Closed).0 pen Item (382/8512-02): Pre-use Response Check for Radiation #
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| -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. 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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| | In Reply Refer To: |
| | Docket: 50-382/65-26 Louisiana Power & Light Company ATTN: R. S. Leddick, Sr. Vice President Nuclear Operations 142 Delaronde Street New Orleans, Louisiana 70174 Gentlemen: |
| | Thank you for your letter of January 3,1986, in response to our letter and Notices of Violation and Deviation dated December 5, 1985. Based on telephone conversations between your Mr. G. E. Wuller and Mr. H. D. Chaney of this office on January 22 and 23, 1986, cencerning your response to violation 382/8526-02, we understand that the revisions being made to station procedure RW-2-200 will not result in decreased controls regarding the processing / packaging of solid radioactive wast Based on a review of your written reply and the above discussions, we have determined that you have been responsive to the Notices of Violation and Deviation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine |
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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 characteristic The NRC inspectors determined that th radwaste organization agreed with the organizational chart depicted in Figure 6.2-2 of the T The licensee had developed position descriptions for personnel functional assignments-and designated a specific individual as being responsible for LLRW and the transportation of RA The NRC inspectors reviewed procedures and a computerized program for LLRW classification, characterization, and shipping document preparatio The procedures reviewed are listed in the Attachment I to this repor The NRC inspectors reviewed the licensee's Process Control Program (PCP),
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| 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 requirement The NRC' inspectors reviewed the licensee's program for appraisals and audits of transportation and radwaste activitie 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 progra No violations or deviations were identifie .
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| 5 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 N18.1-197 .
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| 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)
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| 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 activitie 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)
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| for Disposal," specifies that personnel performing compaction using the B-100 compactor (large box type compactor) must have completed training in the following areas:
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| * General Employee Training,
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| * Redwaste Training in accordance with UNT-03-018, "Radwaste Helper and Radwaste Technician Training Procedure,"
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| -* Instruction in the operation of the B-100 waste compactor,
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| * The handling of radwaste in accordance with procedure RW-02-200, and
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| * Qualification training for forklift truck operation, including demonstrating operating abilit 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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| | J. E. Gagliardo, Chief Reactor Projects Branch cc: (continued on next page) < |
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| | \'- jf s RIV:FRPT HDChaney C:FRPS BMurray D: |
| | 0f.hS RLBaNyart C;RPSC Gl%rrstable |
| | :RPB EGagliardo y / /86 y / /86 g/pg/86 2./G/86 A/[3/86 |
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| | ADOCK 05000382 PDR o PDR ,lf . |
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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).
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| .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 contracto . personnel) were qualified for their functional area assignment No deviations were identifie . 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 commitment 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 quantitie Therefore, only strong, tight containers have been used by the licensee.for seven such shipment 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).
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| A review of licensee procedures for the shipment of RAM showed the extensive use of independent QC verifications and checklists for .
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| 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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| 7 Procedures .
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| 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
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| .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
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| . licensee's representatives stated that HP personnel filling out the-
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| -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 us 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 package 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 condition Failure to provide proper storage is considered a violation of TS 6.8.1 (382/8526-01). 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
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| 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 methodologie 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 package 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 shipmen 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)
| | Louisiana Power & Light Company -2-cc: Louisiana Power & Light Company ATTN: G. E. Wuller, Onsite Licensing Coordinator P. O. Box B Killona, Louisiana 70066 Louisiana Power & Light Company ATTN: R. P. Barkhurst, Plant Manager P. O. Box B Killona, Louisiana 70066 Middle South Services ATTN: Mr'. R. T. Lally P. O. Box 61000 New Orleans, Louisiana 70161 Louisiana Power & Light Company ATTN: K. W. Cook, Nuclear Support and Licensing Manager 142 Delaronde Street New Orleans, Louisiana 70174 Louisiana Radiation Control Program Director bec to DMB (IE06) |
| 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).
| | bcc distrib. by RIV: |
| | | RPB D. Weiss, LFMB (AR-2015) |
| 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 tha there was no program / procedure for the periodic inspection of the containers' physical conditio 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
| | Resident Inspector R. D. Martin, RA Seccion Chief (RPB/C) DRSP R&SPB RSB MIS SYSTEM H. D. Chaney RSTS Operator B. Murray RIV File |
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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 20.31 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 me h '. ' Transportation Incident 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 receive Records, Reports, and Notifications The NRC inspectors reviewed the licensee's procedures and records for RAM shipment 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 71.8 No' deviations'were noted. 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, 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 activitie '
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| 10 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 grou 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. 83-0 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 Notic 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 syste 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 facilit The licensee also stated that revisions to the FSAR, Section 11.4. 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 50-382/84-3 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. for the period March 4 (initial criticality) through June 30, 198 Since issuance of an operating license in December 1984 the licensee's LLRW inventory has been:
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| 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'*
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| * Denotes waste being held pending 10 CFR Part 20.302 determinatio . 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. and 11.4.7 of the FSA 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 fee 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- The FSAR in Sections 11.4.6, 11.4.7, and 11.4.8 identifies LLRW storage areas in the following locations: Reactor Auxiliary Building Solidification Facility (11.4.6),
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| 12 . An outside lay down area (concrete slab) on the east side of the dry cooling towers (11.4.7), and Interim Dry Compacted Waste Facility (11.4.8).
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| 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:
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| West side of the turbine building (approximately 71 containers),
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| * Southwest corner of the switchyard fence (approximately 19 containers),
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| East side of the switchyard fence (approximately 2 containers), and
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| . East side of the turbine building (approximately 22 containers). | |
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| The use of additional LLRW storage areas is considered a Deviation of Commitments in the FSAR (382/8526-01). 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 inspectio In response to the inspectors comments and concerns the licensee provided the following commitments: More positive control will be exercised over vendor procedures used in the LLRW processing program, The forms and methodologies for determining dose rate information used in RAM shipment curie estimation will be reevaluate An independent review program will be implemented concerning the completed RAM shipment dccument package _ _ - _
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| ATTACHMENT 1 TO NRC INSPECTION REPORT 50-382/85-26 DOCUMENTS REVIEWED TITLE REVISION DATE Nuclear Operations Management Manual (NOMM)
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| 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)
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| QAP-000, Quality Assurance Charter 0 6/10/85 QAP-001, Quality Assurance Group Requirement Matrix 0 6/10/85 i
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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
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| , Surveillance Audits 0 6/10/85 QAP-303, Technical Specifications Surveillance Audits 0 6/10/85 Nuclear Services Procedures (NSP)
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| 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)
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| 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)
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| 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)
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| 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:
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| Dry Waste Segregation Radwaste Regulatory Awareness (CHEM NUC)
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| 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
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| RADMAN Computer Software Other Documents Resume' of J. Etheridge 8/9/83 Position Description - Radwaste Engineer 0 4/3/84 Position Description - Radwaste Assocatte Engineer II/I 0 4/3/84 Position Description - Radwaste Supervisor (Support Services) 0 4/3/84 Position Description - Radwaste Supervisor (Transportation) 0 4/3/84
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| Position Description - Radwaste Technician 0 4/3/84 Position Description - Radwaste Helper 0 2/16/84 Letter, from LP&L Wuller, to file, Subject:
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| Agreement on Generic Correspondence Between LP&L and Region IV NRC 9/25/85 i
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| QA Audit Report SA-W3-QA-84-47 - HP and Radwaste Technician / Helper Training 1/16/85 QA Audit Report SA-W3-QA-85-12 - Radioactive Waste Management and Shipping 4/30/85 Nuclear Services Radiation Control Unit Appraisal of the WAT-3 HP and Radwaste Programs 7/18/85 Letter, from LP&P Kenning, to LP&L Rollins Subject: Response to HP and Radwaste Appraisal 85-2 9/25/85 Operations QA Audit Schedule for March 1985 through February 1987 8/21/85 Radioactive Waste Packaging Logs for 1985 LP&L Semiannual Radioactive Effluent Release Report 8/29/85
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