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C1.40 NSdE?sNU OVERVIEW 1.0 SCOPE i.1 This procedure is applicable to Waterford 3 Nuclear Project Support Group (NPSG) personnel in the Radiation Control Section (RCS).
1.2 This procedure describes the functions, responsibilities, interface requirements and' organization of the RCS.
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2.0 REFERENCES
2.1 NUREG 0761 Radiation Protection Plans for Nuclear Power Reactor Licensees.
2.2 P :D-GO-013 Program Description for ALAPA.
2.3 PMD-GO-020, Program Description for Radiological Environmental Monitoring (REMP).
2.4 PMD-RW-001, Program Description for Radioactive Waste.
2.5 PMD-EP-001, Program Description for Management of the E.diation Protection Plan.
2.6 NAP-004. Waterford 3 Project Support Group Organization and Responsibilities.
2.7 Nuclear Operations Project Suppert Group Position Description Manual.
2.8 NAP-001, Preparation and Revision of Nuclear Administrative Procedures.
2.9 PMD-RW-002, Program Description for Transportation of Radioactive Material.
2.10 PMD-TR-015, Program Description for Radwaste Training Program.
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4.2 Organization j
4.2.1 The RCS organization is depicted in Reference 2.7.
i 4.2.2 The RCS division of responsibilities is shown in'.1.
l 4.2.3 The RCS staff reports to the TSSG Supervisor and has the
.esponsibilities as delineated in this procedure.
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4.2.4 RCS responsibilities (Attachment 5.1) are divided into Exposure Control and Laboratory Services Subsections to l
facilitate the smooth functioning of support efforts.
NOTE: This is a functional division (as opposed to administrative) and in no way constitutes total separation of activities as cross-training and qualification of personnel are emphasized.
4.2.5 The Radiation Control Engineer-Nuclear reports to the TSSG Supervisor who in turn reports to the Project Support Manager-Nuclear.
4.3 Duties 4.3.1 The Radiation Control Section provides technical support to the Waterford 3 Health Physics and Radvaste organizations and has the following seneral duties.
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I 4.3.1.1 Coordinate FSAR updates for health physics and radvaste aspects.
4.3.1.2 Conduct special technical analyses, such as unreviewed radiation related safety questions _(10CPR50.59).
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s 4.3.1.11 Provide appropriate management liaison, such as establishment of corporate policy relating to the health physics and radwaste prograes, establishment and maintenance of controlled documents such as ALARA Manual and Realth Physics Manual.
4.3.1.12 Provide appropriate technical support to the Waterford 3 Safety Review Committee (SRC) and Plapt Operations Review Connittee (PORC) in radiation related matters.
4.4 The following responsibilities are specific to the Exposure Control Subsection in addition to general responsibilities listed in 4.3.1:
4.4.1 ALARA 4.4.1.1 Review design changes and plant modifications from a radiological standpoint.
4.4.1.2 Provide assistance in outage planning and scheduling for personnel exposure control.
4.4.1.3 Prepare long-term collective (person-rem) dose evaluations / projections to determine dose trends for ALARA planning and analyze the success of prior ALARA objectives.
4.4.1.4 Provide a voting member on the Waterford 3 ALARA Co'emittee to ensure Project Support Group ALARA representation.
4.4.1.5 Coordinate the implementation and maintenance of LP&L's ALARA program.
FOR INFORMAT10N ONi.Y 4
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NUCLEAR ADMINISTRATIVE PROCEDURES NO:
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EEsQ OVERVIEW RADIATION CONTROL SECTION'S DIVISION OF RESPONSIBILITIES RADI/. TION CONTROL ENGINEER - NUCLEAR Laboratory Exposure Service Subsection Control Subsection Utility Utility Engineer-Nuclear Engineer-Nuclear Engineering Engineering Technician-Nuclear Technician-Nuclear
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Dosimetry ALARA Program Internal Dosimetry Design Reviews CEPADAS Radvaste Radiological Effluent Tech Specs Respiratory Environ = ental Program Exposure Control Counting Room (site)
Emergency Plan Counting Room (G.O.)
Contracts Administration Byproduct Licensing Equipment Evaluations Procedures Review Vendor Files Appraisals / Audits Procedures Review Training Interface Appraisals / Audits Special Projects Special Projects NRC Effluent Reports INP0/ANI Criteria Equipment Evaluations Notepad /NOMIS Regulations (Reviev.. Comment)
ALARA/ Exposure Licensing Activities Support NRC Exposure / Monthly Operating Reports NRC Bulletin, Circular Notice Review NRC Bulletin, Circular Notice Reviev Other Plant Infor=ation Other Plant Information Review / Prepare LER's Review / Prepare LER's Maintain F.ealth Physics Reference Library Maintain Health Physics Manual NAP-220 Revision 0.1 FOR INFuriiunure um.y 1
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l OUISIANA P O W E R & L i G H T / INTER-OFFICE COR AESPONDENCE V'
OLE SOUTH UNT;ES SvSTEM August 25, 1984 W3K84-2001 Q-3-A35.02.01 TO: Distribution I..fi * ] G ' Cqr FROM:
W. M. Morgan 3 Nuclear Operations Quality Assurance Manager
SUBJECT:
Waterford SES Unit No. 3 Exit Interview Notes NRC Review of Radiation Protection. Radvaste Program Inspection 84-38 August 20-24, 1984 In attendance:
NRC LP&L H. D Chaney R. P. Barkhurst K. A. Whittlesey S. A. Alleman K. W. Kenning W. M. Morgan J. Woods L. R. Simon R. E. Allen G. E. Wuller K. L. Brewster E. M. Rollins J. L. Etheridge D. L. Hoel D. Landeche D. W. Herrin D. E. Adams C. B. Hawkins A. R. Roberts Other N. E. Dubry - MSS fotf-$V'20 Rhy
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NRC Exit Interview Notes Review of Radiation Protection, Radvaste Programs Inspection 84-38 t
1.
Inspection conducted August 20-24-1984 Inspection report will be 50-382/84-38.
Mr. Chaney opened the meeting by stating that as a result of this inspection there were no open items left in the Rad protection /Radwaste area that required closure prior to fuel' load.
Mr. Chaney stated that as a result of his inspection there would be an apparent violation issued for failure to post NRC Form-3 in accordance with 10CFR19.11.
Mr. Chaney stated he specifically followed personnel on their way to work in Chemistry lab, Health Physics lab and-control and did not see a posted NRC-3 Form. Also, he stated he could not locate one posted in the turbine building.
Mr. Barkhurst, Mr. Alleman, and Mr. Woods engaged in a conversation with 4
Mr. Chaney regarding the location of posting of the NRC-3 Form and the fact that all employees received instruction regarding the form in GET.
However, Mr. Chaney stated that the regulations required the form to be posted in the enployees' work area and he could not locate one in the turbine building, the +21 level or elevator, etc., of the plant. He stated it would remain as an apparent violation, tentative level 5.
r Mr. Chaney stated the FSAR 11.4.8.1, Interim Dry Compacted Waste Facility Description described the system as having a "self-contained closed loop ventilation system". He stated it is obvious to him this is not so and
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suggest we may want to make a change to the FSAR.
4 Mr. Chaney stated he had discussed the Portable Solidification System with Radwaste and Health Physics personnel. He noted that there is a possibility of a release path in the system and that General Design Criteria 64 requires continuous monitoring in this situation. He had been assured by Radvaste personnel that continuous monitoring would be performed by ARM's and/or CAM's.
However, he noted that neither the equipmant nor the procedures were in place for this monitoring.
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2.
Comments on Previous Inspection Findings:
.Open Item (382/822-02): Caseous and Licuid Radwaste Systems ALARA Reviews - This item was closed as a result of licensee action.
Open Item (382/8211-14): Procedures - This item was closed as a result i
of licensee action.
Open Item (382/8211-11): Technical Specifications - This item was closed as a result of licensee action.
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y Inspection 84-38 Page 2 2.
Open Item (382/8211-09): Air Cleaning Svstems - Mr. Chaney stated he would close out a portion of this item.
The portion that would remain open involved the area of loading and testing of the RAB normal ventilation and reactor containment airborne radioactivity re= oval units' EEPA filters and charcoal adsorbers. The licensee had requested that this testing be delayed until just before reactor criticality due to possible degradation of the filters and adsorbers by ongoing construction activities.
Open Item (382/8405-02): NuReg-0737 - PASS item would remain open pending demonstration of PASS capability which is scheduled to be performed during 5 power tests.
Open Item (382/8211-10): Instrumentation - This item vill remain open pending the completion of calibration procedures on a number of Radwaste systems.
Open Item (382/8211-12): Radwaste T'rnnsportation Activities - This item will remain open pending the updating of procedures to reflect the latest changes to 10CFR61.
3.
There were no new items opened as a result of this inspection.
4.
Mr. Chaney asked for any questions or comments. There were none and he dismissed the meeting.
WMM:ARR:VBR cc:
R. S. Leddick, R. P. Barkhurst, F. J. Drummond, T. F. Garrets, D. E. Dobson, N. S. Carns L. Storz, S. A. Alleman, J. Woods, R. F. Burski, C. J. Decareaux L. L. Bass, K. R. Iyengar, R. S. Savoie',
M. I. Meyer, R. W. Lailheugue. H. J. Williams, Jr., T. Smith, R. W. Kenning, L. Simon, B. Marshall, O. D. Hayes, D. Clark, Z. A. Sabri, W. J. Baldwin, Project Files, Nuclear Records NRC - G. L. Constable
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