IR 05000285/1988030

Insp Rept 50-285/88-30 on 880829-0902.No Violations or Deviations Noted.Major Areas Inspected:Licensee Radiation Protection Program for External & Internal Radiation Exposure Control Programs & Surveys

ML20154S535
Person / Time
Site:	Fort Calhoun
Issue date:	09/21/1988
From:	Baer R, Chaney H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20154S521	List: IR 05000285/1988030 ML20154S515
References
50-285-88-30, NUDOCS 8810050091
Download: ML20154S535 (15)

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, APPENDIX L

U.S. NUCLEAR REGULATORY COWi!SSION

REGION IV

i NRC Inspection Report: 50-285/88-30 Operating License: OPR-40 Docket: 50-205 ,

Licensee: Omaha Public Power District (OPPD) l

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1623 Harney Street Omaha, Nebraska 68102 Facility Name: Fort Calhoun Station (FCS) l Inspection At: FCS, Fort Calhoun, Washington County, Nebraska Inspection Conducted: August 29 through September 2, 1988 h

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Inspector: [ V6 ,7 H. D. Opahey, Radiatio 4pecialist, facilities 7 2/!

Date Radiological Protec)onSection

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Approved: / AL NN R. E. Baer, Chief. Facilit'ies Radiological Uate 8//

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Protection Section Inspection Sumary l

Inspection Conducted August 29 through September 2,1983 (Report 50-285/88-30) l Areas Inspected: Routine, unannounced inspection of the licensee's radiation ,

protection program for external and internal radiation exposure control [

programs surveys, monitoring and control of radioactive materials,

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radiologIcalfacilities,andpreparationfortheforthcomingreactoerefueling outage.

I Results: Within the areas inspected, no violations or deviations were !

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DETAILS  :

i Persons Contacted OPPD

• W. Gates, Manager, FCS

• R. Jawerski, Manager, Station Engineering F. Franco, Section Manager, Radiological Health and Emergency Preparedness

• Kellogg, Supervisor, Special Services

• J. Gasper, Manager, Training

• S. Gebers, Supervisor, Radiological Services K. Stultz, Supervisor, Technical Services A. Bilau, Radioactive tlaste Coordinator D. Jacobson, Supervisor, Chemistry and Radiation P otection Training R. Cords, Radiation Protection Technician J. Fisicaro, Supervisor, Nuclear Regulatory and Industry Affairs C. Crawford, Respiratory Protection Specialist C. Williams, Senior ALARA Technician

• D. Matthews, Supervisor, Nuclear Licensing

• L. Gundrum, Nuclear Licensing Engineer G. Krieser, Supervisor, Corporate Quality Assurance (QA) Audits

• A. Richard, Manager. QA and Quality Control (QC)

K. Steele, Radiation Protection Group Special Services Coordinator

"A. Christensen, Field Health Physicist (HP)

H. Hawes, Dosimetry Specialist Others D. Neely, Radiation Protection Program Consultant Hydro Nuclear Services. In "P. Harrell, NRC Senior Resident Inspector

• J. Bobba, Consultant, Temporary Radiation Protection Manager The NRC inspector also inte %ed other licensee and contractor employees including operations, adminurative, security, maintenance, and QA/QC personne "Denotes those individuals present during the exit interview on Stpter.ber 2, 198 . Followup on Previous Inspection findings (Closed) Violation (285/8716-01): Testing of Friskers and Xetex Monitors - This item was previously discussed in NRC Inspection Report 50-285/87-16 and involved the licensee's failure to perform the required daily response check of the instruments. The NRC inspector l

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examined the licensee's implementation of the corrective actions committed to in their September 15, 1988, (LIC-87-628) response to the violatio The licensee's corrective actions appear to be adequate to prevent a recurrence of the violation in the future. This item is considered close (Closed) Violation (285/8716-02): Failure to Report Inoperable Radiation Monitors - This item was previously discussed in NRC Inspection Report 50-285/87-16 and involved the licensee's failure to submit a ino special requiredreport to the NRC by Technical concerning(TS)perable Specification 2.21. The NRCnoble inspector gas monitors, examined as the licensee's implementation of the corrective actions committed to in thir September 15, 1988 (LIC-87-628) response to the violation and Licensee Event Report (LER) 87-23. The licensee's corrective actions appear to be adequate to prevent a recurrence of the violation in the future. This item is considered close (Closed) Violation (285/8721-01): Failure to Control Access to a Very High Radiation Area (VHRA) - This item was previously discussed in NRC Inspection Reports 50-285/87-21 and 88-05 and involved the licensee's failure to properly control access to VHRAs per the requirements of TS 5.1 The NRC inspector reviewed the licensee's corrective actions comitted to in their February 18, 1988 (LIC-88-116) response to the violation and those in LER 87-26. The licensee's ccrrective actions appear to be adequate to prevent a recurrence of the violation in the future. The licensee's more comprehensive corrective actions to their VHRA problems are being tracked via corrective actions to the similar VHRA violations (285/8805-02 and -03) and the corrective actions referenced in LER 88-01. This is item is considered close (Closed) Violation (285/8721-04): Failure to Report Very High Radiation Area Door Incident - This item was previously' discussed in NRC Inspection Report 50-28378F21 and involved the licensee s failure to submit an LER on an incident involving an unlocked VHRA door (TS 5.11.2). The licensee submitted LER 87-26 in response to the violation. The NRC inspector examined the licensee's corrective actions comitted to in their February 18, 1988 (LIC 88-116) response to the violation. The licensee's corrective actions appear to be adequate to prevent a recurrence of the violation in the future. This item is considered close (Closed) Violation (285/8805-04): Failure to Observe the Two-Man Rule -

This item was previously discussed in NGC Inspection Report 50-285/88-05 and involved the licensee's failure to effectively implement VHRA controls that were designed to prevent the reoccurrence of a previous VHRA violation (285/8721-01). The NRC inspector interviewed personnel and examined training records to verify the implementation of the corrective actions committed to in the licensee's June 3, 1988 (LIC-88-393) response to the violation. This item is considered close (Closed) Violation (285/8805-05): Failure to Properly post a Contaminated Area - This item was previously discussed in NRC Inspection

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Report 50-285/88-05 and involved the licensee's failure to maintain 1 j radiological posting required by plant procedures. The NRC inspector i

! examined the licensee's corrective actions committed to in their June 3,

) 1988 (LIC-88-393) response to the violation. The NRC inspector also  ;

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inspected existing contaminated area posting and observed work related l identification of contaminated areas and the subsequent posting of those '

j areas. The licensee's corrective actions appear to be adequate to prevent i a recurrence of the violation in the future. This item is considered i

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(Closed) Violation (285/8805-06): RespiratoryProtectionEqujpmentUse l Policy - This item was previously discussed in NRC Intpection f f Report 50-285/88-05 and involved the licensee's failure to implement a  ;

i management policy concerning the use of respiratory protection I equipment (RPE) as required by 10 CFR Part 20.103(c)(3). The NRC inspector interviewed personnel and examined training records to verify  ;

! the implementation of the corrective actions committed to in the i licensee's June 3, 1988 (LIC-88-393) response to the violation. The l 1 licensee's corrective actions appear to be adequate to prevent a t

] recurrence of the violation in the future. This item is considered  ;

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I (Closed) Violation (285/8813-02): Portal Alarm Response - This item was previously discussed in NRC Inspection Report 50-285/88-13 and involved g l the licensee's failure to implement procedures, required by TS 5.8.1, for

! the radiological monitoring of personnel and equipment leaving the site 1 and the subsequent control of personnel found contaminated by such j 1 monitoring. The NRC inspector examined procedures, policies, and training I

! documents to verify the licensee's implementation of the commitments f I contained in the licensee's July 25, 1988 (LIC-88-580) response to the [

violation. The licensee's corrective actions appear to be adequate to j prevent a recurrence of the violation in the futuie. This item is

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considered close +

(Closed) Open Item (285/8734-01): Semiannual Effluent Release Reports - ,

This item was previously discussed T6 NRC Inspection Report 50-285/87-34 (

and involved excessive technical and editorial errors in the TS 5.9. required Semiannual Effluent Release Report The NRC inspector reviewd the licensee's corrective actions in regard to the NRC identified concerns

and consider them to be satisfactory. This item is considered closed, f .

j (Closed) Open Item (285/8805-11): Backup Radiation Protection  !

4 Hanager (RPM) - This item was previously discussed in NRC Inspection l l Report 50-285/88-05 and involved the NRC's concern regarding t.he I qualiff ons of the person selected as the backup to the Supervisor, l Chemistr> "1 Radiation Protection (NRC Regulatory Guide 1.8, RPM l

equivalent). The licensee has established a list of "Designated

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Alternates" for backup to selected key individuals, including the RPM, within the FCS Radiological Protection Group (Memorandum OPPD FC-C-260-88, t

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i dated August 10,1988) that resolves the NRC concerns in this are This I l

item is considered close . Open Items Identified During This Inspection An open item is a matter that requires further review and evaluation by I the NRC inspector. Open items are used to document, track, and ensure !

adequate followup on matter of concern to the NRC inspector. The i following open item was identified- '

1 L l Open Item Title See Paragraph l l t 285/8830-01 Dosimetry System Reliability 5 i Organization and Management Controls - Radiation Protection f 183522/83722)

l The licensee's organization and staffing of the radiation protection group !

! was examined to determine agreement with: commitments in Section 12 of i l the Updated Safety Analysis Report (USAR); compliance with the i I requirements of Operating License Technical Specifications; and the !

j recommandations of NUREG-0731 and 076 t i The NRC inspector examined the licensee's organization, staffin l l

assignment of responsibilities, and radiation protection arogram l implementing procedures. The licensee had made several c1anges to the :

staffing of the radiation protection gNup since the last inspection of this area in February 1988 (50-285/88-05). These changes involved the reassignment of tt s former Supervisor of Chemistry and Radiation .

Protection (RPH) tc a corporate office support group and the hiring of a i consultant to fill the vacant RPM position. The licensee had also I appointed an individual to the position of field HP and added positions of l Special Services Coordinator and Respiratory Protection specialist to the Radiation Protection Group. The licensee had contracted with a consultant [

to provide an Assessment of the FCS radiation protection program, the e development of new radiation protection program implementing procedures, ;

and other activities aimed at strengthening the FSC radiation protection .

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The NRC inspector examined audits and surveillances of the FSC radiation protection program. The licensee's corrective action for identified {

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deficiencies appeared to be timely. The NRC inspector also noted that the l licensee's QA departreent audit group had undergone a significant reduction l of personnel with HP experience. The licensee had hired a consultant with j HP experieace to maintain the quality of the audits involving the i radiation protection progra Procedures and documents examined are listed in the Attachment to this l repor l

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No violations or deviations were identifie [ External Exposure e.ontrol and Personal Dosimetry (83524/83724)

i j The licensee's external radiation exposure control program was examined to i determine agreement with: the commitments in Section 12 of the USAR; i j compliance with the requirements contained in the TS, 10 CFR Parts 19.12, !

i 19.13, and 20.101, 20.102, 20.104, 20.105, 20.202, 20.203, 20.205, 20.206, !

20.405, 20.407, 20.408, and 20.409; and the recommendation of NRC !

j Inspection and Enforcement Information Notices (IEIN) 86-23 87 39, 88 63, !

NRC Regulatory Guides (RGs) 8.8,8.13,8.14,and8.28,andIndustry l l

standard ANSI N13.11-198 j i

The NRC inspector reviewed personnel exposure records, record storage

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facilities, expos m ;vntrol procedures, dosimetry processing procedures,

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dosimetry QC md nods, data processing and report generation. Emergency preparedness instructions on radiation exposure r;ontrol were examined and

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found to be in agreement with industry standards Training and f j qualification programs for both licensee and con.ract personnel were j examined, National Voluntary Laboratory Accredit 0 tion of the licensee's

dosimetry processing program was verified. The licencee's on hand stock (

i of extremity dosimeters and spare thermoluminescent dosimeters (TLD) !

personnel monitoring devices was inspecte !

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, Ouring the end-of-the-month preparations for exchanging FCS personal !

l dosimeters (TLDs), the licensee's TLD processing equipment experienced a i j failure and almost caused the required monthly changeout to be cancelled, j The licensee's TLD processing system has experienced numerous failures ;

during the past year due to its age. According to licensee  ;

j representatives during the period of August 22-30, 1988, repair personnel !

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responded to TLD system equipment failures five times.. The NRC inspector [

, discussed, with licensee representatives, the need to review their '

! maintenance program involving the TLD system and evaluate whether a {'

{ suitable preventative maintenance program has br.en implemented for the TLD -

j processing system. This is considered an Lo en item pending licensee j actions to improve the reliability of the T W processing system J (285/8830-01).

l The NRC inspector noted that the licensee has adopted the use of the 1 VARSKIN computer program for calculation of skin doses from hot particles and that a revised and updated hot particle control program was teing t

, developed by onsite consultants. The licensee's hot particle program was !

J previously discussed in NRC Inspection Report 50-285/87-16 and found !

i deficient in several areas. The NRC inspector discussed with licensee ;

I representatives the need to inform radiation workers of the industry's hot i j particle problems and what the worker can do to minimize exposure to hot i 3 particle !

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Facility inspections and independent measurements were conducted of posted ;

hot spots and high radiation areas. The licensee's very high radiation l

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area controls, including locking, escorts, and control of keys, were '

) examined. The NRC inspector discussed with licensee representatives the l l l

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controls to be used in handling incore detectors and cables during the i upcoming refueling outage. The licensee was currently evaluating the !

information on personnel exposure problems encountered by other utilities l during incore detector work, as referenced in IEIN 88-6 No violations or deviations were identifie . Internal Radiation Exposure Control and Assessment (83525/83725)

The licensee's internal radiation exposure control program was examined i

t for agreement with: commitments in Section 12 of the USAR; compliance !

with the requirements contained in the TS, 10 CFR Parts 19.13, and 20.103, 20.108, 20.203, 20.206, 20.401 and the recommendations of NRC RGs8.8,8.13,8.15,8.20,8.2d,20.405:

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and 8.28, NUREG 0041, and industry standards ANS! 13.1-1969 and N343-1978, (

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The NRC inspector reviewed the licensee's implementing procedures, !

management policies governing use of RPE, programs and activities j involving the routine and emergency aspects of the internal dosimetry, air i sampling and analysis and posting of airborne radioactivity areas. The I licensee'splansforImplementingaprogramformonitoringandevaluation [

of tritium uptakes were discussed with the licensee. The licensee i discharges approximately 225 curies of tritium per year in liquid i effluents. The NRC inspector noted that in preparation for the upcoming (

refueling outage, the licensee had leased an additional whole body counter i to speed the processing of personnel during the outage. The licensee's i inventory of RPE was examined and personnel responsible for training and !

issuance of RPE were interviewed. The NRC inspector noted that the j licensee had obtained a technical expert in respiratory protection and ,

industrial hygiene programs to provide the licensee guidance in the !

development of their own industrial and radiological respiratory [

protection programs. The licensee appears to have initiated actions to !

resolve the NRC concerns regarding the respiratory protection program at FCS which were identified in NRC Inspection Report 50 285/88-05. The licensee assigned one person as the FCS respiratory protection expert, provided professional RPE program training to selected HP and Training j Department staff members, and hired a consultant to help revise and update i the respiratory protection progra !

No violations or deviations were identifie . Control of Radioactive Materials (RAM) and Contamination, Surveys, and (

Monitoring (83526/83726) *

The licensee's programs for the control of RAM and contamination, radiological surveys, and monitoring were examined for agreement with:

comitments in Section 12 of the USAR; compliance with the requirements of TS 3.13, 10 CFR Parts 19.12, 20.5, 20.201. 20.203, 20.205, 20.207, 20.301, ,

20.401, 20.402, and NUREG-0737, Item !!!.0.3.3; and the recomendations of t IEINs 86-23, 86-43, 87-39, and 88-63, f

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The NRC irspector toured FCS facilities, conducted independent gamma

radiation dose rate measurements and lonse surface contamination survey ;

) Licensee work operations, within the reactor and turbine buildings, were i j reviewed. Radiation Work Permits, radiatinn, airborne, and surface i

! contamination surveys were examined for accuracy and supervisory revie :

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The NRC inspector noted that the licene,ee's smear and air sample survey L l analyses equipment provides for now level beta and alpha radioactivity I l analysis, and that air samples were evaluated for iodine and other fission  !

j products when a significant indication of airborne activity was present, a

] The NRC inspector examined the licensee's procedures for the control of '

l radioactive material, monitoring of radiation levels within and outside of l j the radiologically controlled facilities, source inventory and survey (

practices, air sample analysis and reporting of results, and posting of radiological areas. The licensee QA surveillances of radioactive material

receipt inspections had identified licensee prucedural compliance  ;

violations. Corrective actions appear to be satisfactory to prevent a  !

i recurrence. No violations of 10 CFR Part 20.205 were identifie !

r i The licensee has not identified any significant hot particles in  !

] contamination surveys of facility waste streams or internals surfaces of f

majorreactorsystemcomponents. The NRC inspector discussed with  !

! licensee representatives the need to maintain a vigilance in the form of

,1 special loose surface contamination surveys, especially during the i upcoming refueling outage, to ensure that areas requiring increased j radiological controls due to a potential for hot particle exposure are i j promptly idenHfie l t

l No viola',fons or deviations were identifie . Radiological Control Facilities and Equipment / Instruments The licensee's facilities for radiological protection activities during j routine and emergency situations were reviewed for agreements with the comitmeats contained in Section H of the Radiological Emergency Response

! Plan (RERP) - FCS, and the recommendations of RGs 8.8 and 8.25, NUREG-0041, and NUREG-0654/ FEMA-REP-1, a

! The NRC inspector reviewed: training facilities; respirator

! decontamination and maintenance facilities; counting laboratories; j the calibration facility; the radioactive source storage; locker and toilet

facilities for workers; the radioactive controlled area access control

point; first aid facilities; the machine shop for radioactive materials; decontamination facilities for personnel and equipment; and emergency equipment inventories such as radiation protection survey equipment, respiratory protection equipment, and protective clothing at the onsite

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Operations Suppurt Center and Technical Support Center. Selected j equipment referenced in FCS Surveillance Test ST-RM-3 was verified to be

! present and operational, Operation of the portal monitors at the exit to

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the protected area was verifie Instructions were posted as to actions to be taken if the portal monitors were to alar No violations or deviations were identifie . Scheduled Outage Advance Planning and Preparations (83529)

The NRC inspector examined the licensee's preparations for a 77-day refteling outage, tentatively scheduled to start on September 24, 198 Licensee advanced staffing personnel selection criteria and testing, site specifictrainingandqualIficationofHP and radwaste workers were reviewed. Thelicensee's;ontractorquallficationprogramensures contract HP and radwaste technicians are properly qualified to perform specific tasks. The NRC inspector examined licensee organizational staffing for the outage and HP coverage cf selected areas and jobs. The licensee has established an ALARA goal of approximately 2?.7 person-rem for the outage. The licensee's procurement of additional radiation protection instrumentation and expendable supplies was examined. The NRC inspector noted that the licensee was revising their dosimetry issuance procedures for extremity and multiple whole body monitoring into for the outage and establishing an onsite dosimetry processing capabilit The licensee has scheduled steam generator primary side eddy current inspections, secondary side sludge lancing, and inspection of the reactor vessel thermal shields after full fuel off-load, among other activities, during this outag No violations or deviations were identifie . Followup on Licensee Event Reporting (92700)

(Closed) LER 285/87-26: Failure to Control a Very High Radiation Area - The event the LER describes involves the failure of a licensee employee to properly lock a door to a VHRA as required by TS 5.1 Subsequent to this LER, the licensee has experienced several other incidents involving VHRA control (LERs 88-01 and 88-03) that have resulted development o* a comprehensive plan on modification door locking systems and revisions to the VHRA control procedures. The licensee's corrective actions for this incider.t were examined and found to have been implemented. Further licensee actions concerning modification of locking systems for VHRA doors will be tracked via licensee commitments in their response to Notice of Violation 285/8805 03 and LER 88-0 (Closed) LER 285/88-03: Inadequate Key Control to a VHRA - The event described in the LER was addressed as a Notice of Violation in NRC Inspection Report 50-285/88-05 (285/8805-03) and involved the licer.see's failure to adequately control issuance of keys to YhRAs. The licensee has implemented a new key control program that satisfies the commitments contained in the LER. Long term corrective actions involving the

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1 modification of all door locking hardware and VHRA key control will be

, monitored via the licensee's commitments contained in LER 88-0 ,

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1 Exit Interview (

j The NRC inspector met with licensee representatives identified in I i paragraph I at the conclusion of the inspection on September 2, 1988. The l j NRC inspector summarized the scope and findings of the inspectio I i

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l ATTACHt1EtiT TO t4AC IN5PECTIOtl REPORT I

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50-285/88-30 $

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09CUMEHIR. REY.lEWED t

T I.T L F rey!S!QU D/)T E i standino_orde. , i

f G-41, Station First Aid 06 04-21-88 O -- 50. ALARA Radiation Exposuro Prooram 07 07-25-09 >

G-52. Plant Staff Workino Hours 02 07-25-88 I G-57, Installation of Tempor rv Lead Shielding 05 -07-25-88 i G-64, tiedical Examin tion Frogram f or '

Worker Dualificatton 12 07-25-88 !

G-76 Use of Gamma-10 Portal Monitors 00 04-29-R8 i t

T-01. Radiation Froceduro Manual 04 07-25-88 !

T-10, Personno! Exposuro Records 31 07-25-88 i T-11, Reepiratorv Frotection Program

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Poltcv Statoment 01 07-25-88 ;

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R-03. Reportable Occurrences 09 03-18-87 i R-04 Operatino Incident Reports 16 C6-09-88 l l

Radlet190_Ergtectigo_Upogal t t

Euct1on 2 Personnel Pratection and Contral 38 04-28-88 Personne! Exposure Monitorino f and Ruceros >

2.4. Radaation Exposuro Reotstration 2.5, TLD !ssuance  ! ' TLD/Dosimetrv Dascropancy Compar1 sons O.15. Fort Calhoun Administrative i Enposure t.tmits k"

2.10 Radtetion WerA Peratts 2,27 ftF C Hour Accountabi11tv 2.30 Use of Respiratory Equipment  !

i section 3. Area Control 22 [

08-17-G8 6

, D.*i n n s t t on e 3 . .' . h d t t 1 ori Centrain 7. 3 At r tior ne Rad t cac t 1 w a t v Contrata pct 1on 6 Redtonctive thtesa.s1 Contr01 22 08-17-6S f 6.1, Rece1v1nc Radtoactave Nateraal 6.2, S t or a o e of Radtcactave Materael hec u t v a rio God t oac t t v6- Mat er t al Tratler Shipaients

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. o TIT (E REVISION DAIE Section 7. ' Operational ALARA Program 08 07-01-88 Section 8. Radfation Protection Procedures (RPP) 07 08-17-88

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RPP-1. Contro11e1 Area Emergencies 09 08-17-88 RPP-6, Protective Clothing and Respiratory Equipment Monitoring 13 04-22-88 RPP-6A. Rad Clean Dev Cleaners 00 08-27-87 RPP-6 Laundry W mher and Dever 00 08-27-87 RPP-6 Respiratory Washer and Dryer 00 08-24-87 RPP-1 Recharging SCBA Cylinders 01 09-18-79 RPP-1 Radioactive Source Log Maintenance and Use 04 08-17-88 RPP-18. Instrument Selection 07 07-07-88 RPP-20. Radiation Work Permits (RWP) 10 08-17-88 RPP-21. Use of Mul tiplo Whole Body and '

E>t t r emi t v TLD with Direct i Reading Dosimeters 02 v3-09-87 l RPP-22. Control ard Use of Respiratory

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Equipment 01 02-23-87 Section 9. Operating Procedures +or Heal th P.)vsi cs Personnel (HP)

, HP-01 Whole Body Countino 07 05-05-88

HP-01A. Whole Body Count Evaluations 02 08-10-8 HP-02. Respirator Fit Test Quantitative j Polydinnersed Aerosol Test 07 07-21-88

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HP-04. Radioactive Source Control Loo 02 09-23-83 '

HP-05. Col 1ection and Analvsis of Air Samples 06 09-19-85 j

HP-07 Vitalograph Testing and Operation 08 07-25-88

HP-08. Labelino and Baoging of Radioactive

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Materials 04 12-17-87 HP-09. Area Contamination Cont rol 04 06"29-88 HP-11. Whole Bodv Friskina 01 09-27-8S HP-13. Cont 2nuous Air Mcoitorino Inutrument

Operation 03 04-27-88 .

, h>-14. Countino Instrument Operation 06 05-25-88 l j HP-15. Portable Dose Instrument Opser at i c i 06 08-13-85

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HP-16. Selection of Contract Health Phvsics T ec hn i c i etn 01 07-13-83

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HP-1G. Personnel Decontamtnation 04 04-28-88 hA-20 Compressed 6reathino Air Qualitv Survei11ance 01 02-28-84

, HP-23. Iontral1ed Area Visitor Br1efino 01 12-14-87 HP-25. Rad 1ation Hot Spot Verifacation/

Updato 01 03-29-88 I

l Emptgeoc v .Pl a*L_ I mp1.pmen t t ng , Pt:ocetjur os (EPIP)

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EPIP-OSC-13. Onsite Radioloolcal Monitorino 02 03-12-87 EPIP-OSC-16 Emeroencv foam 06 07-06-87 i

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TITLE REVISION DATE EPIP-EDF-03. Emercency Operation Facility Emergency Instruments and Equipment 09 10-28-87 fiP I P-EOF-1 1. Dosimetry and Records 06 02-12-88 EPIP-RR-03. Re-entrv into Evacuated Area 02 04-30-86 EPIP-RR-09. Re-entry and Recoverv Equipment Procurement 05 01-07-88 Cal _ib t etigo_Ptgceduces _ _tieal.tlLEbvel.cn HP-22. Fast Scan Whole Body Counter 02 07-02--87 HP-23. Personnel Contamination Monitor 00 07-01-85 HP-25. Canberra HF ~Go System 01 07-07-88 Radi at,.i pg,_Mggi tgt og.f gylpmeat,,Cel. i 2 Cat 190_8C9Gedut!!L b L109ttumeQt E-530 Portable Radiation Monitor 05 03-02-87 RO-2, Portable Radiation Monitor 06 01-05-87 RO-2A, Portable R-adiation Moni tor 05 01-05-87 RO-4A. Portable Radiation Monitor 04 02-09-84 RO-7 Digital Ion Chamber Portable Radiation Monitor O2 02-04-87 RM-14. Portable Radiation Monitor GC, 02-22-88 RAS. Portable Air sampling Pump 04 01-21-87 SAM-2. Portabin Radiation Monitor 03 05-07-85 SAS-1. Stapl ex Air Samp 1 ter 01 11-03-83 091A. Containment High Range tionitor 05 05-04-87 Chemi sitv Udgual _P ggechttes_JCrjP1 t

CMP-2.8. Asbestos Air Samplinn 00 03-25-87

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CMP-3.10. Determination of Radioactive Particulates and Iodine in Air Samples 04 12-09-86 CMP-3.75. Comoressed Air Analvsis for Oil. Water and Particulate Content 01 03-20-84 CMP-3.77. Determ'. nation of Selected Gases and Vapors Usino Mine Safotv Apolian.e Detettor Tubes 01 09-30-85 Ct1P-3. 78. Determination of Combustible anrf T o:< i c Gaws in S a mp l e= d I Atmospherec 00 04*06-84 i

niidi t s SF;B] AL ,N DATE

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He,a 1 t h Phvnics and ALARA 50 11-02-87

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Surye111ance_Foports Wasto Gas Release 03-88-1 03-09-88 i Personnel Enposuro Rocards 03-88-2 03-21-88 i Radtation Pratoction/dhF 03-88-3 03-21-88 l Rouniratory Fousoment 04-88-7 04-14-88 l

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. . e T Ilh REVISION D8TE ALARA' C4-88-4 05-03-88 Ridi ation Protection Surveill ance Tour C5-88-1 05-23-88 Contamination Control C5-88-5 06-07-88 Controlled Area Surveillance Tour C6-88-1 06-20-88 l HP Counting Instrument Operations C7-88-1 07-18-88 S9C VHil. I J!nc e_ f est l

ST-Rti-3. Emergency P1an Radiation

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Instruments and Equipment 37 06-22-87 >

ID far pa t.Jommug i.g a t i on s ( Memor a n r*u Orders, etc..)

Proper TLD Placement FC-C-252-88 08-05-88 Status of 1988 ALARA Goals FC-C-229-88 07-20-88 Synopsi s of Staam Generator No :le Dam Inuta11ation FC-381 Sup1. 03-21-87 RRD 870442 Response (NRC-TLD Concern) TS-FC-87-549 09-22 87 Desianated Altornates (RP Group Order 88-RP-01) FC-C-260-88 C8-10-88 Control of Very High Radiation Area Access (Group Order 88-01) FC-C-093-88 03-10-88 Use of Junior Technician in the Field Heelth Physics Area (Group Order 88-4) FC-C-213-88 06-29-88 sponse to NOV 50-285/8813-02 LIC-88-580 07-25-88 Securitv Bul1ettn 88-11 04-13-88 Standing Order No. G-76 (Nemorandum) FC-818-88 04-29-88 OEED _ Tectjo i c el . Setviges _Opetet i og_Ecggeduces RWISJON D8IE N-190P-3. Calibration of thee Cesium 137 Source 07 08-87 N-TSDP-4 Calibration of the Ha shaw

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riodel 2271 TLD Reader 01 07-87 N-TSUP-5 Dosimetrv T9chnician Tr ainino

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Guidelinos 02 04-88 h-TSDP - 12. Qualitv Con trol / Tent Badoes 03 06-87 N- I SOP-- 13. Enit er.a i n i nu ILD Gamma Sensitivities 03 06-87 N- T S O P-- 1 Dow Calculation for TLD Specials 02 06-87 N-TbOP-15. Readino TLD Cardu 04 06-87 tJ-TSOP-16. Monthly Encosure Ponort 03 06-87 N- l bt)P -! Initial Duality Check of New TLD 00 07-87 N-TSOP-20. Hand Calculat1on War F shee t On 07-87 Ir.inino Dop er_ t men t Jjandou t *, , at_ul _ Dno inpn ty Course Ha st or v for Selectod Students (47)

C/RP Traintins for s Relocted HP/RW inchnician-4 -

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Tl]LE REVISION DOIE Rr;s p i r'a t or y Protectiote Training Lesson Plan 10-27-31 05-31-88 Respiratory Protection Training Handout 00 05-19-88 Sonior Contract Radwaste Tect.ai ci an Qualification Guide 01 08-04-88 Junior Contract Radwaste Technician

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Qualification Guide 01 08-04-88 Senior Contract Health Physics Field Technician Qualification Guide 01 08-04-88 Junior Contract Health Physics Field Technician Qualification Guide 01 08-04-0E Senior Contract ALAR 4 Technician Qualification Guide 01 08-04-88-l r

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