IR 05000458/1985073: Difference between revisions

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{{Adams
{{Adams
| number = ML20151N671
| number = ML20210C666
| issue date = 12/03/1985
| issue date = 03/10/1986
| title = Insp Rept 50-458/85-73 on 851028-1101.Deviation Noted:Senior Radiation Protection Technicians Not Provided W/Proper Training.Violation Noted:Qualification Matrix for Technicians Not Updated for Period in Excess of 8 Months
| title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/85-73
| author name = Chaney H, Murray B
| 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 = Cahill W
| addressee affiliation =  
| addressee affiliation = GULF STATES UTILITIES CO.
| docket = 05000458
| docket = 05000458
| license number =  
| license number =  
| contact person =  
| contact person =  
| case reference number = RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-2.F.2, TASK-TM
| document report number = NUDOCS 8603260091
| document report number = 50-458-85-73, NUDOCS 8601030049
| title reference date = 01-28-1986
| package number = ML20151N659
| package number = ML20210C669
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE
| page count = 15
| page count = 2
}}
}}


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APPENDIX C U. S. NUCLEAR REGULATORY COMMISSION
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MAR.I0.1986'
In Reply' Refer.To:
Docket: '50-458/85-73 Gulf States Utilities ATTN: William J. Cahill, J Senior Vice-President River Bend Nuclear Group P. O. Box 2951
  . Beaumont, Texas 77704 Gentlemen:    g ..
Thank you:for your letter of January 28, 1986, in response to our letter
. and ' Notices of Violation'and Deviation dated December 30, 1985. We have
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reviewed your reply and find it responsive to the concerns raised in our Notices of Violation and Deviation. We will review the implementation of your corrective actions during a. future inspection to determine that full compliance


==REGION IV==
has been achieved and will be maintained.
NRC Inspection Report: 50-458/85-73 License: NPF-40 Docket: 50-458 Licensee: Gulf S'tates Utilities (GSU)
,
ATTN: William J. Cahill, J Senior Vice President River Bend Nuclear Group (RBNG)
P.O. Box 2951 Beaumont, Texas 77704 Facility Name: River Bend Station (RBS)
Inspection At: River Bend Station, St. Francisville, Louisiana Inspection Conducted: October 2 through November 1, 1985 Inspector: h #
H. Chaney( ladiation Speciali 12.!3kI Date Facilities Radiological Protection Section Approved: 9
  ~
E  #&[J[f3 B. Murray, Chief, Fac ities Radiological Protection Date Section Inspection Summary Inspection Conducted October 28 through November 1, 1985, (Report 50-458/85-73)
Areas Inspected: Routine, unannounced inspection of the licensee's radiation protection (RP) program, including: organization and management controls, RP staff training and qualifications, and the ALARA program; actions on previous inspection findings; and implementation of certain NUREG-0737 requirement The inspection involved 41 inspector-hours onsite by one NRC inspecto Results: Within the areas inspected, two violations and one deviation were identifie (see paragraph 4).


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8601030049 851230 48 DR ADOCK O


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Sincerely, i
Nsul Signed bypf J. E. Gagliardo, Chief Reactor Projects Branch cc:
Gulf States Utilities ATTN: J. E. Booker, Manager-Engineering, Nuclear
:  Fuels & Licensing    -
P. O. Box 2951 Beaumont, Texas 77704 i
Louisiana State University, Government Documents Department Louisiana Radiation Control Program Director bec: (see next page).


DETAILS Persons Contacted GSU
RIV:FRPS C:FRPS D:[ S
* Cahill, Jr. , Senior Vice President', RBNG
    -
*J. Deddens, Vice President, RBNG
C: PS/A C:RPB l b HDChaney/jt~ Murray 'A RLE ng/rt JPJaudon JEGag rdo ''/
*T. Plunkett, Plant Manager
p /f /86 / /86 g/f/86 f/Ll/86 ) /ft t/
*T. Crouse, Manager, Quality Assurance (QA)
8603260091 860310 PDR. ADOCK 05000458
* Tomlinson, Director, Quality Services
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* Graham, Assistant Plant Manager
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* Cargill, Radiological Programs Supervisor
G  PDR    e
* Hey, Licensing Engineer
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* Desai, Chemistry Group Engineer
* Coppo, Senior Projects Mechanical Engineer
* Horn, Nuclear Training Department (NTD) Representative
* Spivey, QA Engineer
* Suhrke, Manager, Projects Planning and Coordination
*D. Seymour, Compliance Analyst J. Cadwallader, Emergency Planning (EP) Supervisor S. Marino, NTD Training Assistant D. Gipson, Assistant Plant Manager C. Rohrman, RP/ Chemistry Training Coordinator C. Edwards, Senior Radiation Protection Technician (RPT)
T. Sloan, Senior RPT K. Varnado, RPT R. White, RPT Others
*D. Chamberlain, NRC Senior Resident Inspector J. Grant, Test Engineer Consultant T. Loudenslager, EP Consultant D. Simpson, EP Consultant
  * Denotes those present at the exit interview on November 1, 198 The NRC inspector also interviewed several other licensee employees including QA/QC, training, chemistry, and RP personne . Licensee Actions on Previous Inspection Findings (Closed) Open Item (458/8406-25): NUREG-0737, Item II.F.1-2, Plant Effluent Sampling - This item has been previously discussed in NRC Inspection Reports 50-458/84-06, 85-05, and 85-53. Based on the licensee's completion of sample line deposition studies for the Fuel Building, Radwaste Building, and Main Plant Stack Ventilation airborne radioactivity samplers, this item is considered close . .
3 RP Program Organization and Management Controls The NRC inspectors examined the organization and staffing of the licensee's RP organization to determine compliance with the Final Safety Analysis Report (FSAR) Sections 12.5.1.1, 13.1.2.1.3, and 1 commitments; and the requirements of 10 CFR Parts 20 and 50, and the Facility Operating License Technical Specifications (TS) 6.2.1, 6.5.1.2, 6.8.1, and 6.11.1; and the recommendations of NRC Regulatory Guides (RG) 1.33, 1.8, 8.8, and NUREG-073 The NRC inspector reviewed the current organization assignments and staff positions for compliance with the FSAR and T Recent staff changes within the licensee's RP program were reviewed. The NRC inspector also reviewed position descriptions contained within the plant operating procedures, RP staff resumes', conducted interviews with selected RP staff members, and observed conduct of operations involving RP supervisors, technicians and staff specialist Recent changes to RP program implementing procedures were reviewed. The licensee's assignment of responsibilities for RP program implementation and conduct of RP operations were reviewed. The NRC inspector discussed with the Supervisor of Radiological Programs (SRP) (equivalent to RG 1.8 Radiation Protection Manager - RPM) the qualifications of the RP Supervisor to function as the backup SRP/ RPM. The NRC inspector determined the RP Supervisor's qualifications satisfied the FSAR commitments in Section 12.5. The NRC inspector reviewed RP group shift logs and observed RP supervisors making tours of work areas. The NRC inspector reviewed Station Administrative procedures, RP program procedures, QA procedures, and the Station Support Manual. Procedures / documents reviewed are listed in Attachment 1 to this repor The NRC inspector reviewed QA procedures for licensee audits, corrective action tracking, qualification of audit personnel, and reporting of audit findings to management. The latest QA audits of RP and NTD activities were reviewed. The response to audit findings appeared to be timel The NRC inspector reviewed the licensee's RP organization, including staffing for the backshift, and the Radwaste grou The NRC inspector discussed with licensee representatives the day-to-day supervision of the radiation protection technicians (RPT) assigned to the radwaste group and the controls over them to ensure that their knowledge of general plant conditions and training is kept up to dat The NRC inspector noted to the licensee that the total number of RPTs (approximately 22) appeared to be marginal in that there appeared to be no margin for RPT retraining time or coverage for unexpected jobs. The NRC inspector determined that routine use of overtime would be necessary for accomplishing routine RP duties during plant start-up and power range testin Licensee representatives indicated that personnel were aware of the overtime needs and that necessary work would be accomplished without exceeding TS 6. requirements involvic.g the use of overtim No violations or deviations were identifie , .
4 RP Organization Staff Qualifications and Training The NRC inspector examined the qualifications of the licensee's RP organization to determine compliance with commitments in the FSAR Section 12.5, 13.3-7, and 13.5; and the requirements of 10 CFR Part 19.12, TS 6.3.1, and 6.4.1; and the recommendations of RGs 1.8, 8.2, 8.8, 8.27, and those of NUREG-076 The NRC inspector reviewed the licensee's RP staff's qualifications based on personnel resumes', interviews, and training record The licensee's training facilities were inspected, lesson plans and training procedures were reviewed, and requalification training was observe NTO staffing and instructor qualifications / training were reviewed. The NRC inspector reviewed the qualifications of a newly hired instructor that will be responsible for RPT and chemistry technician training programs. The NRC inspector discussed with licensee representatives the current status of Emergency Preparedness training for RPTs and the cross training of radiochemistry personnel in certain RP fundamentals so the radiochemistry technicians could perform limited RPT duties during radiological emergencie Qualification of RPTs has been previously discussed in NRC Inspection Reports 50-458/84-06, 85-05, and 85-35. TS 6.8.1.a and 6.11.1 establish the requirements for development and adherence to the aforementioned procedure The NRC inspector was given the names of eight RPTs, on October 28, 1985, that the licensee considered to be qualified as Senior RPTs, and therefore satisfied established qualification criteria. The NRC inspector determined that the eight Senior RPTs satisfied the ANSI /ANS 3.1, paragraph 4.5.2 criteria for RPT. However, licensee records (RBS -
Radiological Programs Section Technician Qualification Matrix print-out) as of October 28, 1985, indicated that all eight Senior RPT were deficient in completion of the training required by RSP-0003, paragraph 5.2.4, which states: "An employee is designated as a Senior Radiation Protection Technician after completion of the requirements listed for Junior and Senior Technician. . . ." Attachment 3 to RSP-0003 contains a detailed listing of the necessary training for both Junior RPT and Senior RPT. The licensee indicated that some of the apparently missed training was due to a backlog of completed training that needs to be entered into the matrix data files. The NRC inspector selected one Senior RPT for review of completed trainin The NRC inspector determined on October 31, 1985, that neither the RP Section's nor the NTD records could provide verification that the Senior RPT had comoleted Drywell Entry training as required by Attachment 3 to RSP-0003. This is an apparent violation involving failure to provide specified training (458/8573-01).


RSP-0003 also requires that RP Section maintained training records contain specific documents and that these documents be maintained current by the Radiological Engineering Supervisor or his designee (paragraph 7.3.1).
, i Gulf States Utilities -2-bec to DMB (IE06)
bcc distrib. by RIV:
RPB  DRSP Resident Inspector R. D. Martin, RA Section Chief (RPB/A) D. Weiss, LFMB (AR-2015)
MIS System RSB RSTS Operator H. D. Chaney R&SPB  B. Murray RIV File R. L. Bangart


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The NRC inspector determined on October 31, 1985, that the training records for the eight Senior RPTs were not being kept current, in that documentation of completed training, physical exams, and dosirretry records referenced on Attachment 1 to RSP-0003 were missing for personnel that had been employed at RBS for upward of 9 months. Also, NTD records showed that training had been completed for certain lesson plans, but the RP Section's records indicated no training had been received. This is an apparent violation involving the failure to comply with procedures (458/8573-02).
 
The FSAR Section 13.2.1, " River Bend Station Staff Training Program,"
establishes the licensee's commitment to provide certain training as matrixed in Figure 13.2-1 of the FSAR to RPTs. The FSAR commits the licensee to provide initial plant staff and subsequent plant staff training in Boiling Water Reactor (BWR) technolog This BWR training is described in Section 13.2.1.3.3 of the FSAR, and consists of a four week long course (designated B7) on the design and operating details of components and systems at RB The NRC inspector determined on October 31, 1978, by a review of NTD records, that out of the eight Senior RPT
! previously referenced, only one had been provided the BWR technology course referenced in the FSAR. This is an apparent deviation from commitments to the NRC (458/8573-01).
 
Licensee representatives indicated that the subject training was thought to have been satisfied by an internal RP Section training module involving plant systems walk downs. The subject plant systems walk-downs did not appear to involve the comprehensiveness of the FSAR course description and therefore did not appear to the NRC inspector to be a suitable alternative to the FSAR committed to training. The NRC inspector noted to the licensee at the exit meeting that a similar FSAR training deficiency was identified during a May 1985 Operations QA Group audit (GSUS/HPRP-85/05)
and addressed in QA Finding Report number P-85-06-011-D. This audit finding involved the failure of the RP Group to initiate training waivers for committed training for personnel based on experience or equivalent training. The NRC inspector noted to the licensee that evidently the corrective action was not comprehensive enough to identify similar deficiencies or prevent future deficiencies of this natur . ALARA Program The NRC inspector reviewed the licensee's ALARA Program to determine compliance with the requirements of 10 CFR Part 20.1(c); the commitments in the FSAR Section 12.1.1 and 12.5.1.1; and the recommendations of NRC RGs 8.8, 8.10, 8.19, and NUREG-076 The NRC inspector noted that since RBS had just recently received their low power operating license and had nc,. performed any work involving significant radiation exposure, there was very little in the way of actual ALARA program implementatio The NRC inspector reviewed the ALARA program administrative procedure, implementing procedures, GSU management ALARA policies, ALARA staff
 
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qualifications, RBNG design engineering interface with RBS ALARA staff, outage planning, proposed trending of ALARA concerns, ALARA reports to RBNG managers, ALARA committee meeting minutes, ALARA committee membership, assignment of ALARA program responsibilities, ALARA training for nuclear engineers and outage planners, radiation worker ALARA training, and general RBS staff ALARA training. The NRC inspector noted that the ALARA program, as set forth in the FSAR, appeared to be implemented. The NRC inspector discussed with licensee representatives the proposed exposure goals for RBS power ascension testing and the basis for the 6.5 man-rem goal for 1985. The NRC inspector noted that the ALARA staff was establishing a photographic library of system components and areas for use in planning work operations. The NRC inspector noted to the licensee at the exit meeting that there appeared to be very little training provided, other than that provided in GET I & II, to plant engineers and planners on the effective implementation of ALARA criteria during system engineering and job review. ALARA staff members indicated that specific ALARA training for nuclear engineers and other plant staff personnel was being considere The NRC inspector discussed with licensee representatives the interface of the RP group personnel with outage coordinators early in the planning stages of scheduled outages and also emergency outages for equipment repai No violations of deviations were identifie . Post Accident Sampling System (PASS)
The NRC inspector reviewed the current status of the PASS in regards to satisfying Operating License Attachment 1 conditions for exceeding five percent rated power. Licensee's representatives stated that the PASS system had been acceptance tested and the results reviewed by the Joint Test Group. However, the PASS system had not been turned over to the plant operating sta'ff as of this time. The NRC inspector determined that one portion of the acceptance testing (obtaining of a reactor coolant sample) had not been performed due to a lack of pressure on the primary coolant system. This portion of the acceptance testing will be completed when suitable plant pressure is obtained during low power testing in the near future. The NRC inspector emphasized to the license at the exit meeting the importance the NRC is placing on the operability of PASS during full power license considerations. The licensee stated that PASS would be turned over to the plant staff and that a demonstration of PASS operability would be provided to NRC Region IV personnel during the week of November 11, 198 The NRC inspector reviewed the licensee's progress to eliminate the numerous uncontained mechanical joints in the PASS system (see NRC Inspection Report 50-458/85-70, Open Item 458/8422-05). General Electric
 
. .  . _ _ _ _ _ _ _ . _ . _ . _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ . _ _ _
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is providing a redesigned sample cooling and isolation valve module that will eliminate some mechanical fluid boundaries. The licensee reaffirmed the scheduled completion date of within 100 effective full power day No violations or deviations were identifie . Reactor Startup Radiation Shielding Surveys The NRC inspector reviewed the licensee's activities for conducting the radiation survey of the reactor biological shield and other plant areas during reactor startup and power ascension testing to determine compliance with FSAR Section 14 commitmants and the recommendations of NRC RG 1.6 The licensee had completed the zero power surveys and is awaiting further reactor power increases to allow completion of the startup survey procedure. During this inspection period, reactor power was less than one percen No violations or deviations were identifie ' Exit Interview The NRC inspector met with the licensee's representatives and the NRC resident inspector identified in paragraph 1 of this report at the conclusion of the inspection on November 1, 1985. The NRC inspector summarized the scope and the results of the inspection.
 
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ATTACHMENT 1 TO NRC INSPECTION REPORT 50-458/85-73 DOCUMENTS J,EVIEWED IIILE  REVISION Q81E Biver Bend Naclear Procedures Manual (RDNP)
RDNP-001, Preparation, Revision, Approval and Control of Procedures and Manuals  0 10/12/84 RDNP-OO2, Responsibilities and Authority O 10/12/84 RDNP-OO4, Reporting Requirements  0 10/12/84 RDNP-OO5. Training Procedure and Respon-sibilities  0 10/12/84 RDNP-010, Design and Modification Control 1 05/17/85 RDNP-014, Radiological and Industrial Safety  0 10/12/84 RBNP-016, Resolution of Audit Findings and Inspection Reports  0 10/12/84 RDNP-018, Outage Planning and Management O 10/12/84 RDNP-020, Policy Statements and Management Directives  0 10/12/84 PS/MD 1, Gulf States Utilities ALARA Policy Statement  03/07/85 PS/MD 2, River Bend Station Respiratory Protection Program Policy Statement  03/07/85 PS/MD 3, Responsibility for Overall River Bend Station Operations  04/12/85 PS/MD 6, Promulgation of RDNG Performance Parameters  10/07/85 RDNP-024, Radiation Protection Plan  1 06/10/85 RDNP-025, Posting of Regulatory Matter  O 05/29/85 RDNP-028, River Dend Station Performance Monitoring Program  O 10/02/05
 
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IIILE  GEy1SION DGIE
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()per a t i onal DA Manual  ,
' Oual i ty Assurance Directi ve-10 Audits 2 09/10/8 ;
Operations Quality Proced.ures and In s t ruc t i_on s (OAP/OAI)
OAP-1.2, OA/OC Organization. Responsibilities and Duties  0 02/17/84 OAP-1.3, Indoctrination, Training Qualification and Certification of Duality Assurance Audit / Surveillance Personnel  3 05/07/05 OAP-1.D, Procencing Corrective Action Reports to Nanagement  1 07/03/84 OAP-1.10, Reporting of Status of Open Items to Management  2 07/24/85 OAP-1.14, Quali ty Assurance Tracking of Ouality Concerns  1 09/24/85 OAP-1.15, Processing of Quality Assurance Finding Reports  0 07/03/84 OAI-2.1, Audit Performance and Reporting  2 10/30/85 OAI-2.3, Planning. Scheduling, and Reproting OA Garveillances of Plant Activities 0 08/15/84 QAI-2.10 Inupection Planning  2 09/03/85 Gtatinn Operatino Manual GdM11Ls_t t .g t i ve Procedures (ADM).
 
ADM- OOO 1, Station Staff Organizatio Responsibilities and Authorities 2 05/03/05 ADM-OOO3, Development, Control and Use of Procedures  7 09/07/05 ADM-0007, Selection. Training, Qualification and Evaluation of Plant Staff Personnel  2 04/20/85 ADM-0024, Conduct of Technical Gtaff Acti vi ti es 1 12/21/84 ADM-0025. Conduct of Radi at 2 on Prot ection Gervices  2 07/20/85 ADM-0039 ALARA Program  1 05/25/85
 
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i IIILE  BEYISION 901E [
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Radiation Protection Section Procedures (RSP)
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i 1 RSP-0001, Tracking and Trending Radiological I  Occurrences  O 06/02/85 ;
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l RSP-0003, Personnel Qualification for the
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Radiation Protection Section 3 08/12/85 -
RSP-0004, Preparation of Radiation Protection  ;
Department Reports  0 07/13/85
.RSP-0200, Radiation Work Permits  1 06/11/85 RSP-0201, Respiratory Protection Program for  l Radiological Areas  1 06/27/85 t RSP-0202, Radiation Protection Calibration Program  1 06/09/85
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RSP-0203, Personnel Monitoring  1 08/02/G5 >
PSP-0206, Prenatal Radiation Exposure Policy 2 06/21/85
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RSP-0209, Control and Calibration of Radiation  !
Protection Equipment  2 06/07/85 l RSP-0212, Drywell Entry  1 07/02/05 PSP-0213, Control and Handling of Radioactive  I Materials  1 06/21/85 i I
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Radiation Protection Procedures (RPP)
RPP-0003, Control & Leak Test of Radioactive Sources  2 06/27/85
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RPP-0005, Posting of Radiologicall y  !
Controlled Areas  2 06/11/85 l l
RPP--0006, Radiological Surveys  2 07/05/85 ;
l RPP-0007, Dasic Radioactivity Counting  1 07/02/85 l
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RPP-OO13. Survey Instrument Response Testing 1 06/18/85 RPP-0018, Personnel Decontamination  1 08/24/85 RPP-0020, Selection and Use of Protective  ;
Clothing  1 07/14/85 !
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RPP-0023, Radiological Precautions for  ,
CRDM Removal and Maintenance 1 05/19/85 l i
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IIILE  REVISION DOIE RPP-0024, . Radi ol ogi cal Precaution for Underwater Operations  1 07/02/85 RPP-0033, Setup and Operation of General Atomics' Portable Continuous Atmospheric Monitor  0 07/12/85 RPP-0034, Operation of the General Atomics Digital Radiation Monitoring System CRT Display Terminals  0 02/16/85 = _ _ .
RFP-0035, Calibration of Digital Radiation Monitoring Process Monitors 0 03/11/85 RPP-0049, Emergency Equipment Inventory 1 06/28/85 RPP-0050, Response to Abnormal Radiological Conditions  2 07/14/85 RPP-0064, Use of Lapel Air Samplers  1 06/19/95 RPP-0065, Use of. Multiple Dosimetry Devices 1 07/24/85 RPP-OOO9, Operation and Calibration of the Eberline RO-2/2A  1 07/05/85 RPP-0091, Operation and Calibration of the Teletector - 6112 B/D  1 07/25/85 RPP-0092, Calibration of the RADECO Model H-809  1 07/13/85 Radiation Health Physics Procedures (RHP)
RHP-0001, Operation of the Panasonic Automatic TLD Reader  2 06/17/85 RHP-0008, Dose Determination and Reporting 2 07/28/85 RHP-0012, Issue and Use of the Pocket Dosimeter  1 07/02/85 RHP-0015, Operation of the Helgeson Do-It-Yourself In-Vivo Counting System  1 07/13/85 RHP-0017, Calculation of Internal Doses 1 07/22/85 RHP-0018, Dicassay Sample Analysis  1 07/05/85 RHP-0019 Quantitative Mask Fit Testing 1 07/05/85
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IIILG      BEMISION  DOIE i'
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RHP-OO25, Dicassay Sample Collecti'an      1 06/23/85
 
  . RUP-OO27, Occupation Exposure Records i    and Reports      1 07/01/85 i-RHP-OO40, ALARA Cost Benefits Evaluation      2 06/15/85
  - RHP-OO42, ALARA Pre-Job Review      2 06/25/85 RHP-OO43, ALARA Post-Job Review      2 06/15/85
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RHP-OO44, ALARA Exposure Tracking      2 06/24/85
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RHP-OO45, ALARA Design Review      2 06/15/85 l
RilP-OO46, ALARA Reports        2 06/24/85 RHP-OO47, ALARA Committee        2 06/27/85  i
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RHP-0107,-Spirometry Testing        O 06/25/84
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Station SupJort Manual          l
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I  Training _ Administration Procedures (TAP). Section 5        t
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4  T A P - 5 -- O O i , Training Department Organization      O 01/16/85 TAP-5-OO2, Training and Qualification of
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Training Department Instructors    O 06/18/85 TAP-5-OO3, Training Facilities and Equipment      O 01/29/85
;  TAP-5-OO4, Training Library and Reference Materials      O 01/29/85  i-TAP-5-OO7, Teaining Records and Documentation      O 01/16/85  >
TAP-5-OO9, Training Interfaces      O 01/29/85
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. Trainino Methodolooy Procedures (TMP). Section 6 TMP-6-OO2, Design and Development of Training j    Programs and Instructional Materi al s    O 01/29/85
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TMP-6-OO3, Training Program Implementation      O 01/14/85 i
TMP-6-OO4, On-The-Job Training      O G1/16/85  r
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TMP-6-OO5, Student Evaluation      O 03/07/85
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IIIL_q  OE$IS100  DGIE Tr a i n ij331 Prooram Procedures (TPP), Section 7 TPP-7-013, tiech an i c a l Training Program O  O2/07/85 TPP-7-Ot6, Radiation Protection Personnel Training  O  O2/07/85 TPP-7-018, General Employee Training  1  09/23/05 TPP -7-026, General Gystems Training  O  O2/07/85 General Emplnvee Trainino Lesson Plans (GET)
Qr ipn t a t i on GE T-OO 4--2, Radiation Protection Training 2  11/11/83 GET-OO7-2, Overview of Plant Operating Procedures  2  11/11/83 GET Level I GET-010-1, Introduction to River Dend Station  1  08/28/85 GET -015-0, Emergency P1an  O  09/17/04 GET-016HJ', Dasic Radiation Training  O  09/21/84 GET Level II GET-020-1, Administrati ve Radiological Controls 1  OG/26/G5 (Gite Specific)
GE T--021 - 1, Practicol Application  1  08/28/85 GET Level III GET-030-1, Respiratory Protection  1  09/06/G5 GET Regttal i fi ca t i on Trainino (GETR)
GETR-100-0, GET-I Requalification Trainiog  O  09/16/05 GETR~200-0, GET-II Requalification  O  09/16/05 GETR-30a-0, GET-III Requalification  O  09/17/G5
 
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IIIl=E  BEMISION D6IE
  -
Spec _iltl Pur_ pose TratAiAq GET-050-0, Site Specific Training for Select Personnel  O 06/25/05 Radiation Protection _Techni_cian Lesson Plans (RPT)
RPT-011, Dosimetry  1 06/21/G4 RPT-012, Dosimetry Laboratory  0 09/27/83 RPT-024, Air Sampling  O 11/15/83 RPT-025, Air Sampling Laboratory  0 11/15/03 RPT-026. Radiation Surveys  1 07/23/84 RPT-027, Radiation Survey Laboratory  0 11/17/93 RPT-032, Radiological Work Coverage  0 10/26/93 Olhor Documents Reviewed Memorandum (Draft), KES-560- 05, Subject: River Bend Outage Management Goals and Objectives,.cAted September 4, 1985
  .
General Employee Training Tetts:
.GETR-I, 10-R1  0 09/27/85
.GETR-II, 20-R1  O 09/27/85
.GETR-III, 30-R1  O 09/27/GS
.GET-II, 02-05  0 09/18/85 GET I, II and III Student Manual Training Records of:
. Maintenance Department Personnel (2)
. Radiation Department Personnel (15)
Training Department Instructor Resumes: 3
. Contracted Employees RDS Radiological Programs Section Technician Dualification Matrix  10/28/85 Radiation Protection Section Personnel Resumes: 36
. Supervisor-Radiological Programs
. Radiation Protection Supervisor
. Radiological Health Supervisor
. Radiological Engineering Supervisor
.Gr. Health Physicist
. Health Physicist (2)
 
. . . .
IlILE  SEYISIOtj D61C
  ~
. Radiation Protection Specialist (2)
.ALARA Coordinator
. Radiation Protection Foreman (4)
. Radiation Protection Technician (22)
ALARA Recordu:
.ALARA Suggestions
.Open ALARA Committee Action Items and Engineering Evaluation Action Requests (EEAR)
.05-070 (EEAR 85-207)
.G5-071 (EEAR 85-209)
.85-074 (CEAR 85-0215)
.85-075 (EEAR G5-0214)
ALARA Photographic Library of Plant Systems and Areat Rivr-r Bend Statico Final Safety Analysis Report Amendment 16 RDS Operations 04 Audits:
.GSUS/HPRP-05-05, File Codo 015.2. /17/05
.GSUO TRNG-85/07, File Code G15. /31/05
}}
}}

Latest revision as of 15:09, 4 December 2021

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-458/85-73
ML20210C666
Person / Time
Site: River Bend Entergy icon.png
Issue date: 03/10/1986
From: Gagliardo J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: William Cahill
GULF STATES UTILITIES CO.
Shared Package
ML20210C669 List:
References
NUDOCS 8603260091
Download: ML20210C666 (2)
v • d • e


Text

1 .

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,. ..

MAR.I0.1986'

In Reply' Refer.To:

Docket: '50-458/85-73 Gulf States Utilities ATTN: William J. Cahill, J Senior Vice-President River Bend Nuclear Group P. O. Box 2951

. Beaumont, Texas 77704 Gentlemen: g ..

Thank you:for your letter of January 28, 1986, in response to our letter

. and ' Notices of Violation'and Deviation dated December 30, 1985. We have

} .

reviewed your reply and find it responsive to the concerns raised in our 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 maintained.

J

Sincerely, i

Nsul Signed bypf J. E. Gagliardo, Chief Reactor Projects Branch cc:

Gulf States Utilities ATTN: J. E. Booker, Manager-Engineering, Nuclear

Fuels & Licensing -

P. O. Box 2951 Beaumont, Texas 77704 i

Louisiana State University, Government Documents Department Louisiana Radiation Control Program Director bec: (see next page).

RIV:FRPS C:FRPS D:[ S

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C: PS/A C:RPB l b HDChaney/jt~ Murray 'A RLE ng/rt JPJaudon JEGag rdo /

p /f /86 / /86 g/f/86 f/Ll/86 ) /ft t/

8603260091 860310 PDR. ADOCK 05000458

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, i Gulf States Utilities -2-bec to DMB (IE06)

bcc distrib. by RIV:

RPB DRSP Resident Inspector R. D. Martin, RA Section Chief (RPB/A) D. Weiss, LFMB (AR-2015)

MIS System RSB RSTS Operator H. D. Chaney R&SPB B. Murray RIV File R. L. Bangart

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