IR 05000498/1986029
| ML20214N538 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 11/10/1986 |
| From: | Chaney H, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20214N478 | List: |
| References | |
| 50-498-86-29, 50-499-86-26, NUDOCS 8612030667 | |
| Download: ML20214N538 (32) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-498/86-29 Construction Permits: CPPR-128 50-499/86-26 CPPR-129 Expiration Date: December 31, 1987 Dockets: 50-498 50-499 Licensee: Houston Lighting & Power Company (HL&P)
P. O. Box !.700 Houston, Texas 77001 Facility Name: South Texas Project Electric Generating Station, Units 1 and 2 (STP)
Inspection At: STP Site, Matagorda County, Texas Inspection Conducted: September 15-19, 1986 Inspector: / // /
H. Chaney, TadTation Spe list, Facilities Date Radiological Protectio Section
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Approved: 76t[Yldbil(fl-/
B. Murray, Chief ~, Facilities Radiological
////hhD Date Protection Section Inspection Summary Inspection Conducted September 15-19, 1986 (Report 50-498/86-29; 50-499/86-26)
Areas Inspected: Routine, announced inspection of the licensee's radiation protection (RP) program, including: management controls and organization; training and qualification; external radiation exposure control; internal radiation exposure control; respiratory protection; radiological posting; radiological surveys; ALARA and radiation work controls; radiation protection instrumentation and calibration; radiation protection facilities; radiation protection equipment and expendable supplies; radiation protection program audits and reviews; and the post-accident sampling system (PASS).
Results: Within the areas inspected, no violations or deviations were identifie PDR O
ADOCK 05000498 PDR
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-2-DETAILS Persons Contacted HL&P ~
W. H. Kinsey, Plant Manager J. W. Loesch, Plant Superintendent M. A. Ludwig, Maintenance Manager D. J. Cody, Nuclear Training Manager
- M. A. McBurnett, Supervising Engineer, Site Licensing
- J. D. Green, Operations Quality Assurance (QA) Manager
- G. L. Jarvela, Health & Safety Services (H&SS) Division Manager
- R. C. Craft, Radiological Protection Supervisor (RPS)
- W. C. Parish, Radiological Support Supervisor
- B. A. Franta Nucl
- S. Head, Engineer,earTrainingDepartment(NTD),StaffTrainingManager ProjectComplianceGroup
- D. Bednarczyk, Operations QA Supervisor
- B. N. Woolweber, Engineer, Operations Technical Support
- J. O. Bettle, Engineer, Operations QA
- C, R. Beavers, Lead Engineer
- K. E. Nemec, Engineer Operations Technical Support
- T.E.Underwood,ChemIcalOperations&AnalysisManager
- M. F. Rejcek, Chemical Operations Supervisor
- J. C.~ Dierickx, Chemical Support Supervisor M. Smith, Outage Manager W. G. Isereau, QA Audit / Surveillance Supervisor R. E. Bilbrey, Health Physicist (HP)
J. D. Lindsay, HP R. K. Piper, HP V. A. Smith, Lead Radiation Protection Technician (RPT)
Others
- B. Murray, Chief, FRPS, NRC, Region IV
- R. Baer, NRC Inspector
- R. Wahlheim Engineer, Operations Technical Support - NOVA
- Phillips, Licensing Engineer - Westinghouse
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D. Garrison, NRC Resident Inspector l H. F. Bundy, NRC Inspector
- Denotes those present during the exit intervie The NRC inspector also contacted other STP personnel, including reactor operators and NTD personne . - . - - . . - - - . . . . _ . _- . . . - . - - - _ . . - .
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-3-2. Open Items Identified During This Inspection Open items are matters that require further review and evaluation by the NRC inspector or the licensee. Open items are used to document, track, and ensure adequate follow-up on matters of concern to the NRC inspecto Open Item Description Paragraph 498/8629-01 Organization and Management 3 Controls 498/8629-02 Organization Staff Qualifications 4 498/8629-03 General Employee Training /8629-04 Radiological Worker Training /8629-05 Radiation Protection Staff Training 498/8629-06 External Radiation Exposure Control 6 498/8629-07 Internal Exposure Control and Assessment 498/8629-08 Respiratory Protection /8629-09 Radiological Posting 8 498/8629-10 Radiological Surveys 9 498/8629-11 ALARA and Radiological Work Controls 10 498/8629-12 RP Instrument and Equipment 11 Use/ Calibration 498/8629-13 Radiological Control Facilities 12 498/8629-14 RP Equipment and Expendable 13 Supplies 498/8629-15 Audits and Reviews 14 498/8629-16 Post-Accident Sampling System 15 3. Program Organization and Management Controls The NRC inspector examined the organization and staffing of the licensee's radiation protection organization to determine agreement with the commitments in the Safety Evaluation Report (SER, NUREG-0781) and the I
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-4-Final Safety Analysis Report (FSAR) Sections 12.5.1.1, 13.1.2., and 13.5; and the recommendations of NRC Regulatory Guides (RG) 1.33, 1.8, 8.8, and NUREG-0731,Section I The NRC inspector reviewed the licensee's organization of the radiation protection staff (Health & Safety Services Division). The majority of the-H&SS staff is located onsite (Radiological Support Section, Radiation Protection Section, and the Emergency and Safety Services Section). The Radiation Laboratory Section is located at HL&P offices in Houston, Texas (Energy Development Center-ELC). The licensee's organization agrees with the SER and FSAR descriptions. Staff assignments, position descriptions, and personnel qualifications were reviewed. Work load allocations for the staff and the Manager of H&SS were reviewed. The NRC inspector reviewed the H&SS manager's involvement in the implementation of the Industrial Safety, Environmental Monitoring, and Emergency Preparedness program These three separate programs do not appear to adversely impact on the H&SS managers attention to development and implementation of the STP radiation protection program. The licensee's turnover rate of personnel in the RP Division was reviewe The NRC inspector reviewed the licensee's administrative programs for procedure development and revision, personnel evaluations, conduct and reporting of supervisory tours of work areas, notifications and reports to the NRC, review of NRC and industry correspondence, and proposed management oversight of radiation protection activities. The NRC inspectur noted that the licensee did not have any corporate staff dedicated to oversight of the STP radiation protection program. Oversight of management control resides primarily within the onsite Radiological Support and offsite Radiation Laboratory Sections of the H&SS. Oversight will also be provided by the HL&P Nuclear Safety Review Board and the onsite Independent Safety Engineering Group, both of which were not organized at the time of this inspection. The NRC inspector noted that the licensee's equivalent to the Radiation Protection Manual referenced in NUREG-0761, Plant Group Procedure 03-ZR-0001, " Radiation Protection Program," had been issued. This procedure established the responsibilities for certain plant personnel, but did not identify the responsibilities of radiological workers or the stop work authority of the RPTs in regard to radiological work activities. The licensee had not issued a policy statement from HL&P senior management regarding the implementation, authorities of personnel, and compliance with the radiation protection program, as referenced in RG 8.1 The NRC inspector reviewed other STP organizations interfaces and operational philosophies concerning the radiation protection programs with the Plant Manager, Plant Superintendent, Maintenance Manager, Outage Manager, QA Manager, and the Nuclear Training Department Manage The NRC inspector reviewed licensee programs for the control of contracted employee activities and the identification of radiological control infractions, trending, and tracking. The licensee had developed and issued approximately 200 of approximately 235 scheduled procedures that
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implement the RP program. The NRC inspector noted that only a few critical procedures remained to be issued and these were either under staff review or in the development stage. Many of the procedures reviewed were noted to contain reference to the regulations of the Texas State Bureau of Radiation Control, which is no longer the controlling authority for STP RP and radioactive materials licensing activities. Several procedures were noted to be lacking supervisor review provisions for data sheets and survey forms. The licensee's complement of procedures satisfy the criteria of RG 1.33 concerning procedures that should be developed and issue This item is considered op,en (498/8629-01) pending:
o NRC review of program for reports and notifications to the NR o Revision of procedures to eliminate erroneous regulatory agencies references and provide for supervisory review of survey and technical document o Issuance of a policy statement from senior HL&P management concerning the RP progra o Include the responsibility of the entire STP staff, regarding RP activities in PGP 03-ZR-000 . Organization Staff Qualifications The NRC inspector examined the qualifications of the licensee's RP organization to determine agreement with the commitments in FSAR Sections 12.5 and 13.1.3 and with the recommendations of RGs 1.8, 8.2, and 8.8, and NUREG-076 The NRC inspector reviewed the qualifications of the RP staff, including supervisory personnel, against the criteria of industry standard ANSI N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel."
Licensee position descriptions require experience and qualifications that exceed the ANSI standard. The NRC inspector informed the licensee's representatives during the inspection and at the exit meeting regarding the apparent lack of Radiation Protection Technicians with commercial reactor operating experience. Even though many RPTs had participated in RP activities during outages at other utilities, very few had much experience (approximately 1 to 2 days) at an operating reactor plan The NRC inspector noted that the H&SS manager and two staff HPs possess operating experience, and that the RP staff possesses experience and training in RP activities involving nuclear utility corporate support or non power reactors. The licensee was informed at the exit meeting that a written response would be requested to address actions that would ensure that radiation protection technicians in responsible positions possess adequate operational commercial power reactor experienc .
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-6-This item is considered open (498/8629-02) pending:
o Providing a sufficient number of RPTs with operating commercial power reactor plant experienc . Radiation Protection Training The licensee's RP training programs for general employees and H&SS Division personnel were reviewed to determine agreement with the commitments in the SER and FSAR Sections 12.5.3.8, 13.2.1.1, 13.2.2, and Emergency Plan Section 8.1; the requirements of 10 CFR Parts 19.12 and 20.103; and the recommendations of NRC Inspection and Enforcement (IE)
Information Notice 85-88, and RGs.l.8, 8.2, 8.8, 8.13, 8.15, 8.27, NUREG-0041, NUREG-0761, and ANSI N1 The NRC inspector reviewed H&SS Division and NTD administrative procedures, training records, lesson plans, classroom handout materials,
', attendance rosters, testing materials, instructor qualifications, training facilities, (including the classroom monitoring of radiation worker, GET Category 2, training and practical factors demonstrations) for training STP personnel in R General Employee Training (GET, Category 1)
GET-1 was determined to provide staff employees that would not be entering radiological area basic RP guidance that satisfied 10 CFR Part 19.12 and Emergency Plan commitment The licensee had completed training the majority of the STP staff and is about to commence annual retraining of personne This item is considered open (498/8629-03) pending:
o NRC review of GET-1 presentation and training record Radiological Worker Training (GET, Category 2)
The NRC inspector determined that the licensee's radiological worker training, including respiratory protection equipment (RPE) training, satisfied, for the most part, FSAR commitments and the recommendations of NUREG-0761 and RG 8.1 The NRC inspector noted to licensee representatives that training did not include:
(1) handouts regarding HL&P policies for RPE, ALARA, and the RP program; (2) stop work authority of the H&SS staff; and (3) instruction on the selection, use and care of RPE chemical cartridges (filters /adsorbers). The NRC inspector also noted that NTD personnel providing RPE training (GET, Category 3) did not possess current technical training in federal and industry standards for respiratory protection programs, and that the practical experience level of one of the two instructors that present this course appeared i
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-7-to be limite NUREG-0041, paragraph 8.1, recommends that personnel presenting RPE training possess a thorough knowledge of the application and use of RP This item is considered open (498/8629-04) pending:
o Inclusion of the RP staff's stop work authority into GET-2 and GET- o Provide GET-3 instructors with appropriate technical trainin o Evaluate the completeness of GET-3 training in regards to all RPE available at ST o Provide HL&P policies associated with the STP RP program to all personnel that attend GE c. Radiation Protection Staff Training The licensee's training program for RPTs and HS&S supervisory personnel was reviewed and found to agree with SER/FSAR commitments and industry standard The NRC inspector noted during a review of licensee training records and resumes' that personnel had been exempted for certain FSAR commitments based on previous training or experience. However, these records did not provide documentation or the required approval for the waivers by the NTD in accordance with the requirements of STP Interdepartmental Prucedure 8.5, " Training Waiver Repcrts." Several of the training records reviewed also contained duplicate course entries and apparent incorrect entries. Several of the apparently incorrect entries involved RPT qualification to use/ wear respiratory protection equipment. These RPE courses were recorded as being given by the manufacturer of the equipment, when in fact the training was provided by ST These aforementioned entries were made under the heading of "Section III, Professional Registration / Certification,"
which could lead to some confusion as to the whether the person was qualified to inspect and repair respiratory protection equipment when the entry only referred to the person's qualification to wear RP Section 13.2.2.2 of the FSAR states that RPTs will as a minimum be
provided training in the following five areas:
o Pressurized Water Reactor (PWR) Familiarization o RP Practices and procedures o RP equipment and use o Applicable Administrative Procedures o Special course presented by NTD or vendors
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-8-Computerized printouts documenting training for the majority of the ANSI qualified RPTs showed that several of the RPTs had not been given PWR Familiarization Trainin '
This item is considered open (498/8629-05) pending:
o Proper documentation of training waivers for H&SS Department personnel, o Verification that all training addressed in the FSAR had been
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complete . External Radiation Exposure Control The licensee's external radiation exposure control program was reviewed for agreement with the commitments in the SER, and Section 12.5, of the FSAR, and Sections 6 and 7 of the Emergency Plan; the requirements in 10 CFR Parts 19.12, 19.13, and 20.101, 20.102, 20.104, 20.105, 20.202, l 20.203, 20.205, 20.206, 20.405, 20.407, 20.408, and 20.409; and the recommendations of NRC IE Information Notices 81-26, 82-42, 83-59, 84-19,
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84-40, 84-59, 84-61, 85-42, and 86-23, RGs 8.2, 8.4, 8.7, 8.8, 8.13, 8.14,
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and 8.28, and industry standards ANSI N13.11-1983, N13.5-1972, and N13.27-1981.
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The NRC inspector reviewed personnel exposure records, records storage
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facilities, exposure control procedures, dosimetry processing procedures, dosimetry quality control methods, data processing, and report generation.
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The licensee's personnel dosimetry system for control of personnel
- exposures consists of a four-element thermoluminescence dosimeter (TLD)
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badge and a computerized self-reading pocket dosimeter (SRD) system. The licensee is participating in the National Voluntary Laboratory
- Accreditation program for their TLD system. The licensee had not obtained
- accreditation for the beta or neutron components of the TLD syste The NRC inspector reviewed the licensee's TLD and its filters. NRC Form 5,
" Current Occupational External Radiation Exposure," states, " Dose to the whole body" shall be deemed to include any dose to the whole body, . . .
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head and trunk, or lens of eye. Unless the lenses of the eyes are i protected with eye shields, dose recorded as whole body dose should include the dose delivered through a tissue equivalent absorber having a
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thickness of 300 mg/cm2 or less. When the lenses of the eyes are protected i with eye shields having a tissue equivalent thickness of at least 700 mg/cm2, dose recorded as whole body dose should include the dose delivered through a tissue equivalent absorber having a thickness of 1,000 mg/cm2 or less." The licensee's TLD processing algorithms for
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determining penetrating gamma radiation dose appear to use data from one of the four TLD elements of the badge that is shielded by greater than
. 300 milligrams per square centimeter of material. The NRC inspector
- determined that licensee representatives did not know what controls were i to be used to prevent exposures to the lens of the eyes or whether assigned I
whole body dose would be based on one of the TLD elements with less than i 300 mg/cm 2 filtering.
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-9-The NRC inspector noted that the licensee had adequately addressed the quality control problems associated with their TLDs as referenced in NRC IE Information Notice 85-42. The NRC inspector also noted that the licensee's procedures referenced a maximum ambient temperature limitation on personnel TLDs of 120 F. The NRC inspector also noted to the licensee that there are areas within the plant, such as the certain locations within the reactor containment and steam turbine driven pump rooms, that personnel must enter that may exceed this temperature limitatio The NRC inspector inspected plant areas and discussed the licensee's proposed program for controlling dosimetry issue and collection, and personnel access to radiological areas. The licensee had not completed development and issuance of all procedures for implementation of the radiation exposure control progra The licensee had identified an accessible area adjacent to the spent fuel transfer tube in between the fuel handling building and the reactor containment. The licensee was developing corrective action for isolating this area. The licensee was reminded of the requirements contained in NRC '
IE Bulletin No. 78-08, " Radiation Levels from Fuel Element Transfer Tubes."
The licensee had not procured and stocked emergency kits with the high range SRDs in the 100 R exposure range, as referenced in Appendix B to the Emergency Pla The licensee's TLDs/ system and emergency exposure guidelines (internal and external) satisfies federal standards for emergency preparedness program This item is considered open (498/8629-06) pending:
o Evaluation of the TLD algorithm used to measure official whole body radiation exposure to satisfy 10 CFR Part 20.40 o Establish accreditation for the beta and neutron radiation monitoring aspect of the TLD syste o Complete development and issuance of implementing procedures for the personnel exposure monitoring progra o Procure suitable SRDs for satisfying commitments in the Emergency Pla o Complete development of corrective actions for controlling access to areas adjacent to the Unit 1 spent fuel transfer tub o Evaluate the temperature limitations of personnel TLD . Internal Radiation Exposure Control The licensee's internal radiation exposure control and dosimetry program, including airborne radioactivity monitoring / sampling and respiratory
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-10-protection, was reviewed for agreement with the commitments in the SER and Sections 12.1.2.2, 12.3, 12.5, of the FSAR; the requirements of 10 CFR Parts 19.12, 19.13, and 20.103, 20.201, 20.203, 20.405, 20.407, 20.408, and 20.409; and the recommendations of NRC IE Information Notices 81-26, 83-68, 84-24, 84-34, 84-60, 85-06, 85-60, 85-87, and 86-24, industry standards ANSI 13.1-1969, Z88.2-1980, N343-1978, and NUREG-0041, and RG 8.2, 8.7, 8.8, 8.9, 8.15, 8.20, and 8.2 Internal Exposure Control and Assessment The NRC inspector reviewed the licensee's programs, implementing procedures, equipment involving routine and emergency aspects of the internal radiation exposure and dose assessment. Licensee in-vivo and in-vitro bioassay programs, and implementing procedures were reviewed. Calibration sources are traceable to primary standard The licensee's in-vitro sampling procedures were determined to lack the specificity for sampling recommended by ANSI N343-1978, and that the WBC dose assessment procedures did not provide for the determination of regulatory compliance (maximum permissible concentration-hours (MPC-hr) of uptake) when elevated in-vivo bicassay results were encountered. The NRC inspector reviewed a portable computer based program used by the licensee for the evaluation and assessment of radioactive material uptakes that utilizes International Commission on Radiation Protection (ICRP)
Publication 30 methodology. The NRC inspector reminded the licensee of the recommendations of RG 8.26 and NRC I&E Information Notice 82-18, " Assessment of Intakes of Radioactive Material by Workers," that addresses the NRC's position relative to use of ICRP 30 methodologies for determining regulatory complianc This item is considered open (498/8629-07) pending:
o Development of in-vitro bioassay sampling procedure o Develop MPC-hr back calculation methodologies for evaluation of elevated bioassay result Respiratory Protection Program The NRC inspector reviewed the licensee's documents establishing and implementing the respiratory protection program. The NRC inspector determined that the licensee had not issued a policy frois, senior HL&P management on the use of RPE as recommended by RG 8.15 and NUREG-004 Also, the licensee had not designated, in writing, a specific person as the site contact for respiratory protection matters as recommended by federal and industry standard The NRC inspector reviewed implementing procedures, airline breathing system, maskfit test systems, and equipment inventory. The licensee's inventory of the fullface respirators and Self Contained Breathing Apparatus appears to be marginal when outage and emergency
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-11-preparedness requirements are considere The licensee's procedures for evaluation of airborne radioactivity do not adequately address worker breathing zone sampling protocols and provide guidance on where, how, and when to implement breathing zone sampling. The licensee had not established areas for the storage, issuance, and maintenance of RP This item is considered open (498/8629-08) pending:
o Issuance of a Respiratory Protection polic o Designating in writing, the specific site contact for respiratory protection program matter Evaluate the minimum inventory requirements for RPE to support outage and emergency preparedness activitie . 3adiological Posting The licensee's radiological posting program was reviewed to determine agreement with commitments in the SER and Section 12.5.3.3 of the FSAR; the requirements of 10 CFR Part 20.203; and the recommendations of NUREG-076 The NRC inspector reviewed licensee issued procedures for the identification, posting, and controlling of:
o radiation and high radiation o radiation hot spots o oxygen deficient areas o airborne radioactivity areas o loose surface contamination areas o areas containing radioactive materials The NRC inspector noted that the licensee had not implemented a program for the periodic review of posting and maintenance of barriers for very high radiation areas. The licensee stated that such programs would be considered along with the controls to be implemented over the accessible areas adjacent to the spent fuel transfer tube referenced in paragraph 6 of this repor This item is considered open (498/8629-09) pending:
o Development of program to periodically review posting applicability and access controls statu . Radiological Survey Program The licensee's radiological survey program was reviewed to determine agreement with commitments in the SAR and Sections 12.3.4.2, 12.5.2.2.5, and 12.5.3.1; the requirements of 10 CFR Parts 20.103, 20.201, 20.205, and
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-12-20.401; and the recommendations of NRC IE Information Notices 83-05, 83-51, 82-49, 80-22; RGs 1.97, 1.68, 1.101, 8.2, 8.8, 8.15, NUREGs 0654, 0737, 0761, and industry standards 13.1-1969, N13.12-Draft, 13.2-1969, N18.9-1972, and ANS 6.3.1-198 The NRC inspector reviewed the licensee's implementing procedures for the radiological survey programs. The NRC inspector noted that the licensee's emergency preparedness procedures referenced routine plant operating procedures when discussing inplant radiation / contamination / airborne radioactivity surveys during reactor accidents. The routine plant procedures for these activities do not adequately address specialized aspects of radiological monitoring during such abnormal situations as reactor accidents. The licensee had not developed specific instructions for compliance with NUREG-0737 Item III.D.3.3, " Improved Inplant Iodine Instrumentation Under Accident Conditions." The licensee had also not issued a startup radiation survey program for verifying reactor plant radiation shielding as recommended by federal and industry standard The NRC inspector also noted that the licensee's proposed limits for fixed radioactivity on materials to be released for unrestricted use is higher than the values recommended by the NRC in NRC IE Information Notice 85-9 This item is considered open (498/8629-10) pending:
o Development of an inplant airborne sampling program for iodine radioactivity during reactor accident o Deveiopment of a reactor shield survey program that satisfies the recommendations of ANSI /ANS 6.3.1-198 o Implementation of radioactive material release limits that meet current NRC recommendation o Provide routine operating procedures that are cross referenced in emergency preparedness procedures (for use during reactor accidents)
with specific emergency response instruction . ALARA Program The licensee's ALARA Program was reviewed to determine agreeiaent with the commitments in the SAR and Sections 12.1 and 12.5.3.2 of the FSAR; the requirements of 10 CFR Part 20.1(c); and the recommendations NRC IE Informaticn Notice 83-64; RGs 8.8, 8.10, 8.27; and NUREG-076 The NRC inspector reviewed the licensee's ALARA program and radiological work control program (Radiation Work Permit-RWP). The NRC inspector reviewed the ALARA committee charter, procedures, meeting minutes, suggestion program, and draft ALARA preplanning and post-job review procedure for jobs expected to exceed one person-rem. Procedures for implementing the RWP program, trending of radiological performance data, and restricted access area control have not been either fully developed or implemented. The NRC inspector reviewed inhouse developed ALARA training
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-13-programs for the STP staff and performance of reactor plant system ALARA reviews. The ALARA policy from senior HL&P management was reviewed and found to satisfy RG 8.8 guidanc This item is considered open (498/8629-11) pending:
o Development of a RWP progra o Completion of ALARA program support procedure . Radiation Protection Instrument and Equipment Use/ Calibration Program The licensee's instruments / equipment for radiological pro $.ction activities during routine and emergency situations were reviewed for agreement with the commitments contained in Section 12.5.2.2, 12.5.2.3, and Table 12.5-1 of the FSAR, and the STP Emergency Plan; and the recommendations of RG 1.97, 8.4, 8.5, 8.6, 8.12, 8.25, 8.28, NUREG-0041, NUREG-0761, NUREG-0737, NUREG-0654/ FEMA-REP-1, and NRC IE Information Notices 86-22, 86-30, 85-52, and 81-2 The NRC inspector reviewed the licensee's on hand inventory of radiation protection instruments (portable, fixed, and laboratory), use and calibration procedures, pre-use response check program, traceability of calibration sources, and calibration facilities. The licensee had not completed procurement /taken delivery of all instruments committed to in the FSAR and Emergency Plan. Specific equipment noted to be lacking in the licensee's inventory were:
o Portable beta / gamma radiation survey meters - 1 millirad / hour to 5,000 rad / hour range - 20 eac o Portal monitors for surveying personnel exiting radiologically
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controlled areas for radioactive contamination - amount to be determined by licensee o The special gamma radiation measuring device referenced in Table 12.5-1 of the FSAR - 1 R/ hour to 10,000 R/ hour rang o High range 0-100 R SRD The licensee's proposed inventory of RP instruments appears to be satisfactory for routine use and emergency kit inventorie The NRC inspector discussed with the licensee the reason why approximately 48 beta / gamma ion chamber type portable radiation measuring instruments were returned to the manufacturer. The licensee stated that they returned the instruments to the manufacture for modification to eliminate instrument indicating needle lockup when used in proximity to unshielded rotating electrical motors. The NRC inspector was contacted by the manufacturer of the instruments following the inspection and was informed
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on how the manufacturer was testing the instruments and whether or not
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-14-this was a potential 10 CFR Part 21 problem. Evidently, initial tests at STP by the manufacturer's engineers using rotating electrical machinery within Unit 1 and devices to measure magnetic field strengths disclosed that the instruments only exhibited the lockup anomaly when brought into contact with a portable gasoline powered electrical generator and while held in a specific orientation. There appears to be no problem associated with the large electrical motors within the plant as Tong as they do not radiate greater than 10 gauss at the meter's internal vibrating reed switch. This anomaly is apparently generic and can affect other radiation detection instruments of different manufacturers that use the vibrating reed switch to internally switch ranges. The manufacturer is modifying the STP instruments to eliminate the proble The NRC inspector determined that a industry standard regarding specifications on testing the performance of portable RP instruments is currently in draft form, and addresses this anomaly and the testing for it. The draft industry standard N42-17A, references a threshold limit of less than 6 gauss. The manufacturer and the licensee had not decided whether or not this problem constituted a reportable matter under 10 CFR Part 2 The NRC inspector determined that the licensee had not completed development of use and calibration procedures for the several portable RP instruments, such as the high range extendible probe gamma dose rat measuring, lapel air samplers, and neutron dose rate measurin This item is considered open (498/8629-12) pending:
o Procurement of remaining RP instrumentatio o Completion of use and calibration procedures for RP instrumentatio . Radiological Control Facilities The licensee's facilities for conducting radiological protection activities during routine and emergency situations were reviewed for agreement with the commitments in the SAR, and Section 12.5.2.1 of the FSAR, and Section 7 of the STP Emergency Plan; and the recommendations of RG 1.97, 8.8, 8.25, NUREG-0041, and NUREG-0654/ FEMA-REP- The NRC inspector inspected the proposed facilities to be used by the RP staff in carrying out their function The facilities inspected included:
o Ingress and egress to plant radiologically controlled areas o Worker change / dress / shower areas within the plant o Protective clothing laundry facility o RPE decontamination, sanitizing and maintenance area o Radioactive material / equipment decontamination / maintenance shops
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- o Emergency response facilities
Technical Support Center-TSC a Control Room-CR
Emergency Operations Facility-EOF o Training Facilities
o RP instrument calibration facilities i
o RP staff inplant offices o RP counting rooms The training and E0F facilities were the only facilities completed and turned over to the licensee from the contractor at the time of this inspection. The facilities inspected appear to agree with the descriptions provided in the FSAR and SA This item is considered open (498/8629-13) pending:
o Completion of RP facilities and turnover to the RP staf . RP Equipment and Expendable Supplies The NRC inspector reviewed the licensee's planned procurement and inventory control program for RP equipment and expendable supplies to determine agreement with the commitments in the SAR, and Section 12.5. of the FSAR, and Section 7 and Appendix B of the STP Emergency Pla I The licensee is currently procuring equipment and expendable supplies to
- support Unit 1 start up and operation. The licensee had not put in place
! or stocked emergency kits containing equipment / supplies referenced in the STP Emergency Plan. As noted in paragraph 7.b of this report, the licensee's proposed inventory of RPE does not appear to be sufficient to support reactor operations and also provide a dedicated supply of RPE c..-
emergency facilitie This item is considered open (498/8629-14) pending:
o Completion of procurement of RP equipment and expendable supplies for Unit 1.
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o Stocking and placement of emergency kits to support the STP Emergency
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Pla . Audits and Reviews The licensee's internal audit and review program regarding the RP program was reviewed to determine agreement with the commitments in the SAR, and l
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-16-Sections 13 and 17 of the FSAR; and the requirements of Appendix B to 10 CFR.Part 50; and the recommendations of ANSI /ANS 3.2-1982, and RGs 1.33, 1.144, and NUREG ^76 The NRC inspector determined that the Operations QA Department would conduct comprehensive audits of RP activities on a proposed yearly frequency, and periodic surveillances of selected RP speciality areas as often as conditions warrant. The Operations QA had conducted a limited scope audit of RP program activities in June 1986. The NRC inspector reviewed department procedures, audits plans (there was no specific audit plan for the STP RP Program), auditor qualifications, audit checklists, audit reports, and the audit finding tracking system. The licensee intends on completing a comprehensive audit of the STP RP Program prior to fuel loading of Unit The NRC inspector noted that RP supervisory personnel had not developed a program for the periodic walkthrough and review of work areas to ensure the effectiveness of the RP program and employee RP trainin The NRC inspector discussed with QA Department personnel the qualifications of audit personnel assigned to perform RP audits and provisions to assure that the audit team included a team member with expertise in commercial reactor health physics. The licensee had not, at the time of this inspection, implemented the FSAR referenced Nuclear Safety Review Board (NSRB) or the Independent Safety Engineering Group (ISEG). The NRC inspector noted that the FSAR commits to having an NSRB that is capable of reviewing technical matters related to radiological safet This item is considered open (498/8629-15) pending:
o Development of audit plans for the STP RP progra o Defining the specific audit and review functions of the NSRB and ISEG in regard to the review / audit of RP program activities at ST o Conducting a comprehensive audit of the STP RP program.
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15. Post-Accident Sampling System l
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The licensee's post-accident sampling system (PASS) for Unit I was reviewed to determine compliance with the requirements of Item II.B.3 of l NUREG-0737, " Clarification of TMI Action Plan Requirements". The PASS was l evaluated as to it's ability to function, and allow reactor coolant samples to be obtained, during a reactor accident involving severe degraded core condition The NUREG-0737 reactor coolant source term concentration of approximately 1 to 10 curies per gram was used in this evaluatio The NRC inspector performed a review of the licensee's installed PASS system in Unit 1. Licensee procedures for the operation and preventative maintenance of the PASS were also reviewed. Personnel hands-on training l
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-17-for use of the PASS had not been initiated as of this inspection. The NRC inspector noted that the PASS did not reduce reactor coolant pressures prior to reaching the PASS sample pane The NRC inspector noted to licensee representatives the following two apparent design deficiencies in the PASS facility:
o There are 50 or more mechanical joints (mostly swage-lok type fittings) used on sample inlet and recirculation lines that are not provided any containment for potential leakage from the mechanical joint o The remote area radiation monitor (ARM) for the facility is located in such a position that it will not provide useful dose rate information to either the operator at the control panel (instrument panel-IP) or a person obtaining a sample at the sample panel (liquid and gas sample panel-LGSP).
The PASS facility consists of three cubicles separated by labyrinth shield walls that share a common open ceilin The LGSP is in one end cubicle and the IP in the far cubicle. A ventilated work station is located in the middle cubicle. The NRC inspector determined that if any one of the reactor coolant sample lines outside of the LGSP were to develop a leak (even a minor one) the resultant airborne and whole body radiation levels (considering the NUREG-0737 source term) would cause all three cubicles to be uninhabitable, and thus preventing the operation of the PASS and obtaining of reactor coolant or reactor containment atmosphere sample The ARM is located on a shield wall within the shielded cubicle between the LGSP and the IP cubicles, thus making its readings not representative of-the conditions at the IP or the LGSP, which are the primary work stations of the PASS. There are also no remote ARM readouts for personnel operating the PASS system to view from their work stations. Due to the similarity between Unit 1 and 2's design and construction these concerns are applicable to Unit 2 als This item is considered open (498/8629-16) pending:
o Developing corrective action for the elimination of or containment of exposed sample line mechanical joints outside of the LGS '
o Evaluate relocation of the ARM servicing the PASS cubicles, including the locations of any existing remote readouts. Consideration should ;
be given to increasing the number of ARMS in the PASS facilit . Exit Interview
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The NRC inspector met with NRC personnel and licensee representatives identified in paragraph 1 at the conclusion of the inspection on September 19, 198 The NRC inspector expressed his concern regarding the lack of commercial nuclear power plant operating experience among the licensee's personnel at the RPT level. Also, the NRC inspector solicited a commitment from the licensee's representatives concern the resolution of
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-18-the deficiencies noted with the PASS. The licensee indicated that they would provide a written response to the experience concern and conduct an evaluation of the PASS deficiencies noted by the NRC inspector. The licensee was apprised that open items addressed in this report would be used to track areas requiring either further inspection or completion of licensee action; and that these items will need to be satisfactorily resolved prior to a recommendation that STP be issued an operating licens _ _
e ATTACHMENT TO NRC INSPECTION REPORT 50-498/86-29 APPENDIX A DQGUMENIS_BEVIEWED IIILE BEyISigN DOIE SOUTU_IEX6S_EBQgEGI_ELEGIBIG_ GENE 8611NG_SI611gN_fSIEEGSl_NyGLE68_GBQUE EgLIGIES Sgctigq_2OO_gtggnizgtige NGP 210, Organization Charts 1 08-31-86 Sectige_600_6ggellLigengigglEgblic_6figitg NGP 640, Posting Specified Documents O Unknown Section. ZOO _Eggineetigg_ggd_Iecbgicgi_Sugggtt NGP 705, ALARA Program O 04-01-85 Sgg t i..gq_ GOO _Nuc legt_85gycggce NGP 820, Nuclear Safety Review Board 1 08-01-85 1UIERDEP6BIDENIOL_EBOGEDUBES_IIEl Odmiot9tEetive 1.10 Interdepartmental Procedures 1 12-03-84 1.6, Licensing Commitment Management Administration 0 10-07-85 UUGLOMC_99ECgtiggg 2.20. Operations Experience In-House Experience Review 2 10-01-85 2.30, ALARA Program O 07-29-86 2.50. Radioactive Waste Packaging, Handling, Storage, and Shipping O 11-08-85 IMGtlDiGM I 3.10 Mcdifications O O2-27-86 3.20. Expendable Material Control Program 2 09-03-86 Dua!_1ty_O;"3yr_enge_1 gel 4 . _7 0 . Corrective action System 1 11-25-85
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IIILE BEVISION QOIE 4.40, Performance of OA Audits and Surveillance Activities 1 06-10-86 4.00, OA Program for Radioactive Waste Management O 11-05-84 4.60, QA for Radiological, Chemical and Thermal Effluent, Meteorological and Non-radiological Ecological Monitoring Program O 11-12-84
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Treigieg 8.1, Technical Training Advisory Councils 2 09-12-86 B.30, Training Interface O 04-04-86 8.40, Training Records Documentation System O 06-15-86 0.5, Training Waiver Reports 1 09-05-86 0.18 Conduct of On-The-Job-Training 1 03-11-86 8.21, Emergency Management Plan Training Program 1 07-01-86 8.22. General Employee Training Program 1 08-01-86 uuCLeeB_IB01u1NG_QEEGBINENI_EBQCEDUBES_dGNy@6_JNIEl j NTP-101, Preparation & Control of Procedures 1 03-28-85 NTP-105, Training Program Evaluation 1 08-29-86 NTP-106, Individual and Training Program f<ecordn O 08-11-86 NTP-ill, Lesson Plan-Development & Control 2 04-04-86 NTP-112. Course / Instructor Evaluation O 06-27-86 NTP-il7 Conduct of Training Programs O 07-15-85 NTP .I14, Control & Administration of Written E s a m es 3 04-10-86 NTP-115, Certi fication of Instructors O 06-03-85 Emergencv Plan Training Handout General Employee Training Category I, II, & III
! Course Outlines for Students eIE_EL601_EBOCEQUBES t. e g e n d :
PGP - Plant General Procedure PRP -- Plant Radiological Services Procedure EPP - Emergency Plan Procedure PCP - P1 ant Chemical Procedure IRP -- T o m p o r c4r s Plant General Procedure POP Flant Operations Procedure EF pii! / an X.G . Rtid i al agi ca l Controls O 03-11-86 FF Ptr! Zu-inns 'earch and Rescue / Contaminated
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1:. m i r O 03-06-86
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111l,E REVISIOLJ DATE EPPoi-zA-OOOB, Dose Calculations and Protective Action Recommendations O 05-14-86 EPPO1-ZA-OO11, Recovery Operations O 05-05-86 PAPO5-ZA-OOO7, Resumes 0 12-23-85 PAPO5-ZO-OOO5, Bulletin Boards and Posting 1 09-04-86 PGPO1-ZA-OOO1, Nuclear Plant Operations Department Organization Policy 1 09-10-86 PGPO2-ZA-OO35, Employee Check In/ Check Out Process O 08-02-85 PGPO2-ZA-OO37, Bulletin Boards and Posting O 09-05-84 PGPO2-ZA-OO44, Organizational Charts 0 11-20-84 PGPO2-ZA-OO53. Management Action Tracking System (MATS) 1 08-07-86
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PGPO2-ZA-OO55, Daily Work Activity Schedule Policy 0 09-27-85 PGPO3-ZA-OOO1, Plant Manual Description 5 07-13-86 PGPO3-ZA-OOO2, Plant Procedures 5 07-13-86 PGPO3-ZA-OOO3, License Compliance Review 4 02-28-86 PGPO3-ZA-OOO4, Plant Operations Review Committee 1 10-03-85 PGPO3-ZA-OOO7, Classification of Procedures 1 03-28-84 PGPO3-ZA-OO10, Plant Procedure Compliance, Implementation, and Review 2 02-28-86 PGPO3-ZA-OO39, Plant Procedures Writers Guide 3 06-24-86 PGPO3 -ZE-OOO6, Chemistry and Health and Safety Services Laboratorv Management Program i 11-27-85 FGPO'-ZI-OOO4, Industrial Gafety Evaluation Procram O 03-03-86 P Gf i.C - Z I - O O O 7 , Confined Space Entry Program 1 06-23-86 P O r- ' ' ui-0010 Industrial Sa6oty Accidiant/
In edent inwe ti oet i on O 06-10-86
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IIILE BO_/ISIQN D6IE PGPO3-ZR-OOO1, Radiation Protection Program O 09-05-85 PGPO3-ZR-GOO 6, Personnel Exposure Extension i Authorization 0 10-02-85 PGPO3-ZR-OOO8, Operational ALARA Program 1 08-04-86 I PGPO3-ZR-OO11, Exposure Investigations O 08-04-86
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jt PGPO3-ZR-OO12, Radioactive Material Control Program i 08-29-86 i
PGPO3-ZR-0017, Radiological Monitoring for New Fuel Receipt O 04-13-84 c l
j PGPCG- Z R-OO 18, Disposal and/or Transfer of -
Radioactive Sources O 01-09-85 l l PGPO3-ZR-OO21, Respiratorv Protection Program O 08-20-85 PGP03-ZR-OO25, Use of Protective Clothing i and Respi ratory Equipment O 08-04-86 f PGPO3-ZR-OO26, Personnel Exposure Guides and l Ltmitn O 08-25-86 PGPO3-IR-OO27, Internal Dosimetry Program 1 09-05-86 l ,
P GPO3 - Z R--OO 28, STPEGS ALARA Review Committee O 08-04-86 i
- P Gi >O3 -- Z R-OO33, ALARA Engineering & Procedure i Review 1 08-04-86 ,
l PGPO3-ZR-OO35, ALARA Suagestion Program O 08-04-86 i
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- PGi 03-ZR-OO39. Preoperational Radiological j Environmental Moni toring Pragram O O2-22-85 i
l IGPo3-ZR-OnO3, ALARA Engineering h Design
{' Resiow ALaPA Walkdowns 0 10-16-85
i i PReot-ZA-OOOi, Health and Safety Services
! Doitnitionn 2 07-22-85 t
I PHPo l -- Z A-OOOS, Radiation Protection Personnel l l r ai ni nq O 12-04-85
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PRPo l -- Z r, - OO 10. Heulth and Gaicaty Services i di v i _,i on Routine last Schedules 1 07-22-85 i
! miol-Zm ">Iz, r Na i r:t en an c e of feet Banks 0 10-02-85
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i-i IIILE rey 1SION D8IE l PRPot-IA-OU14. Preparation, Grading, and j An.nlyuis of Radiation Protection Exams 0 10-03-85
} PRPo l --l A -OO 15, Radiological Controls ( Deficiency Reporting 2 01-17-86 PRPO1-Z A -0016, Preparation and Revision of j Plant Radiation Protection Procedures 3 05-15-85 i
!j i PRPO1-ZA-UO27, Practical Factor Training O 01-22-86 i i
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PRPO1-ZA-OO28, Health and Safety Services ;
I General Procedure Wr i ter's Guide O 06-01-85 !
i PRPO1-ZA-GO29. Celanese Plant Access
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FRPO1-ZA-OO31, Accessing Supercomp Twenty
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H&SS Division Filen 0 10-18-85 t
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PRPO2-ZD-OOO2. Biological Sample Collecting 1 05-13-85 PHP02-ZD-OOO4, Radioactive Contamination .h Airborne Radicactivity Guides .% Limits O 03-09-84 i
PRP.E-ZB-OOOS, Internal Donimetry 0 01-31-84 PRPC.w ZX-OOO1 External Dosimetry Program O O2-15-85 FFPo 2-Z A--OOO2. Use of A Direct-Peading r j Dosimeter 1 07-22-85 l i
PRPo?-ZX-OOG'5 Use of Integrating Dostmetry ,
Devices 1 10-11-85 PRr02-ZX-OOO5. Special Dosimetry for Personnel O 07-17-85 PRPG2-ZX-OOO7. Radiological Posting and Warning Devices 2 01-30-86
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PRPO2 -Z BOO l l . Use of Thermoluminescence l Dncimeters tTLD) 3 01-31-86 L
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P F P O .' - Z X - O O 1 2 . Special Danimetry for Area *
Itooitoring 1 07-22-85 '
F RPO Z - Z X --OO 14. Storage and Handlino of
'wreonnel r TLDs 4 01-23-86 F >RPO2 c , -0015. Qualitv Control Checks for the l Uif ~! e nutomatic 'ILD Reader 3 01-17-86 P
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PRPO2-ZX-OOl6, Quality Control Checks for .
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Panasonic TLDS and TLD Holders 2 01-22-86 l PRPO2-ZX-OO17, Personnel Radiation Exposure !
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Records 1 05-20-86
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l PRPO2-ZX-OO18, Annual Statistical Reporting ( of Personnel Radiation Monitoring Results 0 11-16-85
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- PRPO3-ZM-OOO1, Inventory and Leak Testing of
- Radioactive Sources 0 - 07-03-86---- j
PRPO3-ZM-OO11, Receipt of Radioactive Material O 08-22-85 PRPO3-ZM-v912 Storage of Radioactive Material O 07-12-85 i FRPO3-ZM-OO13. Transfer of Radioactive Material 1 09-16-85 '
PRPO3-ZM-oO14, Movement of Material Out of l
Radiologically Controlled Areas O 08-19-85 PRPo3-ZM-OO15. H&SS Use of Radioactive Sources O 09-16-85 PRPt>4-ZS-UOO1, Radiological Survey Program 1 08-20-85'
PRPO4- ZS-ooO2, Radiation Survey Methods 1 12-11-85 ,
PRP< >4--Z S- Ov03, Contamination Survey Methods 1 08-07-85
PRPO4-ZS-OOO4, Airborne Radioactive Material !
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Survey Methods 1 08-08-85
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l PRPO4-7S-OOO7, Selection and Use of Portable l Radiation Survey Instruments 1 07-25-85 ,
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) PEPO 4-ZS-OOOB, Smear Counting and Evaluation 1 07-23-85 !
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PRPO4-ZS-OOO9, Air Sample Evaluation 1 07-22-85 PFPO5-ZI-0001. Portable Radtation Detection l Instrument Calibration Program 2 08-19-86 i PRPOS- Z I- 0u02, Calibration af the Eber1ine i RM-14 Count Rat.e Meter 1 09-16-8S t
PRFOS-Zf-0003. Cal ibration of Eberline Model 6112 Tetelector 2 06-25-86 j psw,'i- 21 - ca..ie r d . Cai t br c.t t on of Eberline PIC-6A 1 07-22-85
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j ,+ p e s ' 1, n n .' ~r , Cel ibra ti on of the Victoreen
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j 4. .il a m it E b ,>r 1 i n e RO -1 Ion Criambers
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IIILE REVISION DAIE PRPOS-ZI-OOO7. Calibration cf Eberline PNR-4 Neutron Survey Meter and PRS-2P/NRD-1 Neutron Counter 1 07-15-85
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PRPOS-ZI-OOO9, Calibration of the Ludlum 2200 O 10-01-85 PRPO5-Zl-OO10, Calibration of the Ludlum 12-4 Neutron REM Survey Instrument O 08-19-85 PRPO5-ZI-OO11, Calibration of the Bicron
" Analyst" O 10-01-85 PRPO5-ZI-OO12, Calibration of the Bicron RSO-5 or the Bicron RSO-50 Portable Survey Meter 1 06-20-86 PRPO5-ZI-OO13, Calibration of Vane F' ump Air Samplers O 01-31-86 PRPOS-ZI-OO14, Calibration of the Radeca H-809V. H-809V1, H-809C, and the F & J HV-1 Air Samplers 2 01-31-86
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PRPO5-71-OO15, Calibration of the Eberline AMS-3 1 12-12-85 PhPO5-Zl-OOl6, Standardization of the ORTEC Spectroscopy Systcm O 04-08-86
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PRPO5-ZI-OO10, Calibration of the Tennelec Proportional Counter O 04-01-86 PRPO5-ZI-OO19, Calibration Check of the Eberline Model MS-3 Mini Scaler 4 01-30-86 PRPO5-ZI-OO20, Calibration of the Ludlum 333 0 03-26-86 PPPOS-ZI-OO22, Maintenance of the Respirator Fit Iest System 2 07-22-85
FHF05-21-oO23, Standardization of the RL
. Beckman LS-1000C Liquid Scintillation System 1 07-07-86 PFPO5-Z I--OO25, Recertification of the Eberline Model 10008 Calibrator 1 01-22-86 PRP05-2I-0028, Calibration of the Beta-Gamma f:nincidence Svetem 1 02 28-86 i s p m ,-. i l - 4,0 3 1 . Calib>ation of the Gamma
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Indostriea bi!AC 3 08-01-86
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l PRPO5-ZI-OO32, Standardization of the RL !
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Tennelec Counter LB1000 and LB5110 Systems 2 07-28-86
l PRPO5-ZI-OO33, Calibration of Eberline RO-2 i l Portable Ion Chamber 2 06-20-86 !
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l PRPO5-ZI-OO34, Calibration of Dositet DOS 501
! Digital Alarm Dosimeter 2 12-17-85 l l PRPO5-ZI-OO35, Calibration of the Ludlum Model i 177 Alarm Rate Meter 3 01-30-86 !
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! PFPOS-ZI-OO36, Calibration of the Ludlum Model I
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3 Geiger Counter 2 02-13-86 1 l
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j PRPO5-ZI-OO37, Calibration of the Eberline ,
} PRM-7 MicroR Meter 1 12-16-85
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PHPO5-ZI-OO38, Calibration of Victoreen CDV-700 !
i Civil Defense G-M Survey Instrument 1 09-16-85 i
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PRPOS-ZI-OO40. Calibration of the Panasonic '
LJD-710A Automatic TLD Reader 2 08-29-86 i i
PRPO5-ZI-OO41, Standardization of GE(Li) and/or l Intrinsic Germanium Detectors 1 04-07-86 l
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FRPOS-Z1-OO42, Counting Equipment Operating !
Voltage, Background and Efficiency ;
Determinations 2 10-03-85 ;
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PRPO5-ZI-OO43, Direct Reading Pocket Dosimeter l Response and Drift Checks 2 06-20-86 j
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PRPO5-ZI-OO44, Response Check of Personnel f Inteorating Alarm Dose Devices 2 07-22-85 i
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PRPOS-Zl-0045. WBC-6000 Organ Burden f Cal i br ati on 0 11-14-83 j l
PEPOS-11-oO47, Standardi:ation of the TRACOR }
Analvtic Liquid Scintillation Svutem 1 01-22-86
PRPOS-ZI-oO49, Calibration of the Panasonic !
, UD- 702D Manual FLD Reader 1 01-23-86 i
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i PRPifn - Z 1 -00$' 5 Determinat1on of TLD E!ement l Calibrat inn Facters 1 01-29-86 f l
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\ .y O5-Zl-OO57, Calibration of E-120/E-140/
L372[J/E-530 GM Survey Instruments 2 07-25-85 PRPO5-ZI-OO2. Recertification of the Open Air Ir r ad i ator 1 12-11-85 PRPO5-ZI-OO61. Standardi~ation and Set-up of the Canberra Series to tortable 3 MCA for Iodine Analvsis O 08-07-85 FRPUS-ZI-0063, Calibration of the Eberline RM-20 Count hate Meter 1 03-26-86 F fsPO5-Z O-OOO 1, Health and Safety Services Division Instrument Operation Program 1 06-10-85 PRPO5-ZO-OOO2. Operation of Eberline RM-14 C or in t Rate Meter 1 05-22-85 PHP' e5 -ZO -OOO3. Operation of Eberline 6112 feletector 1 11-04-85 PPPub-ZO-nOO4. Operation of the Eberline PIC oA 2 03-03-86 PRPori- Z O -OOOS . Operation of the Victoreen 40-F and Eberline R O--3 1 10-23-85 PHirn-?O-000/, Operation of Eberline PNR-4 Neutron Survey Instrument 2 10-18-85 PFP8 r5 -ZO-UOu8, Operatton of Eberline PRS-2F'/
t tR D-- I Neutron Counter 2 09-12-85 PRP O b - Z O --OOO9, Operation of the Ludlum 2200 Portable Scaler Rate Meter O 11-11-85 PRPuS-ZO-OO10 Operation of the Ludlum 12-4 Neutron REM Survey Instrument O 08-21-85 PhPdi- Z O-OO 1 1, Operation of the Bicron
" An a 1 e=_ t " O 09-13-85 E RP. .S- Z O-n .12. Operation af the Bicron R50-5 or the fil c r on RSO- 50 Portable Survey Meter O 08-21-85 Pop,m .;p-.")i Doeratton of the Ludlum Model
.., i'.it w r O 10-02-85 f! os ,: , f(; &J14, Opaation mp P HDE C O l{-8u9t/1 4i r epier 1 08-20-85
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PRPOS-ZO-OO15, Operation of the Beta Air Monitor 2 03-14-86
PRPOS-ZO-OO17, Grab Sample Collection on the *
j (PIG) and (PI) Continuous Atmospheric
- Monitors 0 12-26-85 I
PRPOS-ZO-0018. LJse of the Tennelec Proport-
! iona1 Counter O 04-15-86 ,
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PRPOS-ZO-OO19, Caeration of the Eberline MS-3 j Mini Scaler 1 07-12-85
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! FRPO5-ZO-OO20. Operation of Eberline FC-2 l
Proportianal Counter 2 11-21-85 PRPO5-ZO-OO21, Operation of Eberline RD-13
, Detector 1 07-08-85
! PRPO5-ZO-OO22, Operation of the Respirator
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Fit Test System 2 08-21-85 ,
FRPO5-ZO-OO23, Operation of the Beckman LS-1000C Liquid Scintillation System 1 10-18-85
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PRPO5-ZO-OO24, Operation of the Victoreen l Model 570 Condenser R-Meter 2 11-19-85 PRPO5-ZO-OO25. Operation of the Eberline Model
, 10000 ralibrator 1 09-18-85
f' RPO5 - ZO-OO26, Operation of Eberline MP-1 Mini Pulser 1 07-09-85 i
PRPob -Z u -OO2 7, Operation of the Environmental Madiation Monitar, Model RSS-111 1 08-26-85 PR P OS-- Z O - O O 28, Operation of the RL Beta-Gamma
{ Caioc1dence System 1- 09-10-86 l FRPOb-ZOm)O29, Use of the RADECO Model C-828 l and C-8528 Air Flow Calibrators 2 11-08-85
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PRPOS-ZO-OO3L. Doeration of Gamma Industries Model 2520 Survey Meter and Dosimeter Charger
- mMr,C > 2 07-15-85
F Ri >0' - Z O-003 2. Operation of fennolec LD5100 Auto 9 / B t;oon t er 1 02-28-86 i
! 6 WO5 20 a n i~' , Operation of Etwrline RO- 2 P rtmhte ion thamber 7 10-15-85 l
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IIILE BEVISigN DATE PRPO5-ZO-OO34, Operation of Dositec Model DOS 501 Digital Alarm Dosimeter 1 12-30-E5 PRPO5-ZO-OO35, Operation of the Ludlum Model 177 Alarm Rate Meter 2 01-22-96 PRFUS-ZO-OO36, Operation of the Ludlum Model 3 Geiger Counter 2 10-23-85 PRPOS-ZO-OO37, Operation of Eberline Model PRM-7 Micro-R Survey Meter 2 09-18-85 PRFOS-ZO-OO40, Operation of Panasonic UD-710A Automatic TLD Reader 3 01-23-86 PRPOS-ZO-OO41, Acquisition of GE(Li) Spectra Using the ND66 MCA 1 04-07-86 PRPO5-ZO-OO42, Operation of GM Counting Systems 1 11-08-85 PRPO5 -ZO-OO45. Spectra Acquisition Using the WBC-6000 3 08-18-86 PRPO5-ZO-OO47 Operation of the TRACOR Analytical Liquid Scintillation System 2 06-19-86 PRPa5-ZO-Oo48, i;ounting Statistics 1 01-07-86 PRF05-ZO-OO49, Operation of the Panasonic UD-702D Manual TLD Reader 2 01-22-86 PRP05-ZO-OO50, Irradiation of Dosimeters 1 11-11-85 PRPOS-ZO-OO51. Operation of the Self-Reading nostmeter Charger 1 10-11-85 PRPOS-20-0052, Operestion af Tennelec LB1000 Manual Alpha /Deta Counter O '03-26-84 PHPOS-ZO-OO54 ' Routine Performance Chacks for the WBC-e3OOO 1 08-19-86 PfiPO5 - Z U-OObc3 Operation of the Radiological Leboratciv Data Analvsis System 1 01-24-86 PRPO5 -l O--04 67, Operatton of the Eberline E-120 E-14v. E ---5 20, and E-520 Portable GM Survev i nn t n vn.>n t r, 1 10-23-85 rRtOh-in-> C D. Um at the PRIHA I II! Gamma Monitnr 1 10-11-85
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TITLE BEVISION D61E PRPOS-ZO-OO59. TLD Dose Estimating and Nonthly Dose Reporting 3 12-26-85 PRPQ5-ZO-OO60, Operation of the Portable Electric Generator 1 10-30-85 PRPOS-ZO-00el, Operation of the Canberra Series 10 Portable MCA Iodine Analysis O 05-06-85 i
PRPO5--ZO-OO62, Acquisition of Spectra Using the Canberra Series 10 Portable MCA O 08-09-85 PRPO5-ZO-OO63, Operation of the Eberline RM-20 Count Rate Meter O 08-16-85 PRPQ5-ZO-OO64, Rebooting the WBC Computers After Power Interruption 1 02-18-86
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PRPO5- Z O-- Q O65, Routine Performance Checks for the Helgeson WBC 1 08-06-86 F R P O S - Z O - G O 6 6 ., Spectra Acquisition using the He1geeon WBC 1 08-06-86 PRFOS-ZU-OO70, Operation of the Spirameter O 07-22-85 PRPOS-ZO-OO72. Operation of tne (WRGM) Contin-uous Atmospheric Monitor O 12-26-85 P PP o5 - Z O-- Oif74 , Filter Replacement on the (PIG)
and (P1) Continuous Atmospheric Monitors 0 12-26-85 PRPo6-20 -000 7. Ouaiity Assurance for the PadioIaalcal Laboratory 2 01-29-86 PRPn6-ZG-Oi)OB, festing of Radiological Laboratory Computer Programs 1 09-05-86 FNFti6- ?G-Oo 11, Routine Performance Checks for the L1 quid ScinLiilation Counters 1 02-28-86 PRF v S -iG-Ou t .:, Quality Assurance Program for Enternal Dosimetrv 1 01-24-86 PFPOo-ZG-OOt3. Rottt i ne Performance Checks and UA E-ercise=, for RL GE(Lt) Gystems 1 09--12-86 FRPv 6 - ZG- UO 14, Instrument Retention Evaluation 1 10-11-85 c ia .;, , J r . n .. > He>atth and Sa f of v T~ond Analynic 0 09-05-85 epi , s /r .o Lant eu n-. tion Contrel Pr o g r a cn 1 07-17-86 i _ . . - _ _ . . . . _ . . _ . _ . _ _ _ .
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. 1 I.ITL_E REVISION DAIE PRPo8-ZC-OOO2, Personnel Decontamination 2 11-14-85 PRPOH-ZC-OOO3, Tool and Equipment Decontamination i 10-11-85 PRPO8-ZC-OOO6, Laundering of Protective Clothing i 40-17-85 PRPO8-ZC-OOO7, Area Decontamination 1 09-12-85 P R P O 8 - l.R - O O O 2 , Respiratory Protection Equipment Control 1 11-11-85 PRPOB-ZR-OOO4, Charging Self-Contained Dreathing Air Battles 1 05-22-86 PRPO8-ZR-OOOS, Routine Inspection of Self-Contained Breathing Apparatus 1 06-04-86 PRPOS-ZR-OOO6, Cleaning and Sanitizing Hospirator Masks 2 09-15-86 Arkij t wital Proced_ures Scheduled for Devel_p_pment that Support or Implement t h e- S f PEGS _. Rad t a_t_i on. Pro tec_ti on Proqr_am III!=E EPPO2-ZA-OOO2, Emergency Equipment P SPU8-- Z R-OOO 1, Ecurce Surveillance Program PRrol-1A-0011, Health and Safety Services Records Management PRPO1-ZA-OOl3, Radiological Dose Reporting FRPol-ZX-OOO8, Emergency Entrance Into Radiologically Controlled Areas FRPO2 -Z X -0019, tJan-Routine TLD Evaluations PRPO9-Z Z -0016, Operation of the Gilian Air Sampler PRF09-ZZ-OO17, Calibration of the Gilian Air Sampler PRPon - Z I --OOe, Ca l t beati on of the Helgeson WBC i
PRPO*i - Z 0-007 4, Cootinuous Atmospheric Monitar (CAM) Detector Subassembly Roo 1 er.emen t
!Rf:OS-zu-0.OH J.e n t l eiv o u t Atmospheric fianitar (CAN) Deta Detector Window Faplacoment P6. poS .. * a- o.JC 7, Ut of the Radioloqical Evaluation Vehicle
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IIILE PRPOS-ZO-OO90, Operation of the Computerized Interface Dosimetry System j PGPO3-ZE-OO29, Contaminated System Leakage, Test Program i
PGPO3-ZH-OOO1, HEPA Filter /HVAC Test Program Description PGPO3-ZH-OOO2, Charcoal Filter Contaminant Control i
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PGPO3-ZI-OOO1, Industrial Safety Program i
PGPO3-ZI-OOO5, Heat Stress PGPO3-ZI-OOOB, Control of Expendable Mate-ials
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j FGPO3-ZP-OOO6, Contract Services Control PGPO 3- Z R--OOO 1, Radiation Work Permit
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PGPO3-ZR-OOO3, Radiation Worker Medical '
i PGPO3-ZR-OOO4, Radiological Incident Reporting
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PGPO3-ZR-OOO9. Restricted Area Access Control Pt3PO3-ZR-OO10, Responsibilities of the Radiation Safety Committee PGPO3-ZR-OOL4, Receipt of Radioactive Material j
PGPO3-ZR-OO19, Use of Sealed Sources and Standards PG PO3 - Z R --O O 20, Shipment of Radioactive Material i
PGPO3-ZR-OO24
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Radi ol ogi cal Services Trend Analysis Program
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PGPO3-ZR-OO30, ALARA Pre-Job Planning and Post-Job Review FGPO3-ZR-OO3D. Shield Verification
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PGPOJ-ZX-OOO6, Theft or Loss of Licensed Material j PGPo3-Zy-ooO7, Semi -Annital Radioactive Effluent Release Report
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