ML20149F880
| ML20149F880 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 08/10/1994 |
| From: | Bentley B, Femreite B, Maas L SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| To: | |
| Shared Package | |
| ML19304C543 | List: |
| References | |
| EMF-30, NUDOCS 9409280087 | |
| Download: ML20149F880 (69) | |
Text
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Siemens Power Corporation i
EMF-30, Chapter 2 Revision 16 issue Date:
8/10/94 i
SIEMENS POWER CORPORATION SAFETY MANUAL CHAPTER TWO RADIATION PROTECTION STANDARDS O
PREPARED BY REGULATORY COMPLIANCE i
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EMF-30, Revision 16 G
Chapter 2 Siemens Power Corporation Safety Manual - Chapter Two j
Radiation Protection Standards Mt.
W I> l N Prepared by:
(f J. Maas, Manager Date
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Regulatory Compliance bbb 3Nd Accepted by:
B. F. Bentley, ManagdrJ Date Plant Operations ff Aj d b r (kh M. K. Valeritine, Manager Date Manufacturing Engineering BYrin m3 hr-9614 D. J. liill,' Manhger Date Quali trol i
A 08W R. L'Feuerbacher, Manager Date Materials and Scheduling
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/A. hepardyd,,Manapr Date Product Mecharu' cal, Engineering Concurred by: M I
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R EVaughan Ma er Cate Safety Secu
, and Li nsing SbYW A& cu m J.W. Morgan, Vice President Date Engineering
/xAtd; eli/91 R. K. Burklin Date H
Physicist i
af bu~ dnJi 0f8fiY Approved by:
%. N. Femreite, Ddte
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Richland Plant Manager
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i EMF-30, Chapter 2 Revision 16 Issue Date:
8/10/94 SIEMENS POWER CORPORATION t
SAFETY MANUAL CHAPTER 1WO I
RADIATION PROTECTION STANDARDS i
UST OF EFFECTIVE PAGES S.ection Revision i
Title Page, Signature Page, Table of Content & Distribution....................... 16 i
1.0 I NTRO D U CTIO N....................................
15 2.0 G E N E RAL...........................
16 3.0 VENTILATION SYSTEMS........................................... 15 4.0 AREAS......................................................... 15 5.0 EX P O S U R E..................................................... 15 6.0 TRAI N I N G........................................................ 15 7.0 SHIPPING AND RECEIVING RADIOACTIVE MATERIALS.....
15 8.0 IN CID ENT REPORTS.............................................. 16
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f Appendix Pagg Revision 1
All......................................
15 2
All.......................................................
15
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EMF-30, Chapter 2 Revision 16 Pagei SIEMENS POWER CORPORATION - NUCLEAR DIVISION SAFETY MANUAL CHAPTER TWO RADIATION PROTECTION STANDARDS TABLE OF CONTENTS Section Pace 1.0 I NTR O D U CTIO N................................
1 1.1 ALARA P o licy.....................................................
1, 2.0 G E N E RA L.......................................
2 2.1 Radiation Work Procedures......................................... 2 2.2 On-Site Transfers and Storage of Radioactive Material....
3 i
i 2.3 U q ui d...................................
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2.4 Solid Waste..................................
4 2.5 Instruments and Equipment.................
4 2.6 Sealed Sources - Ucense No. WN-1062-1 6
2.7 Emergency Electrical Power.....................
8 O
2.8 Audits / inspections................................................. 8 O
2.9 ALARA/ Radiation Safety Committee...................
10 2.10 industrial Radiographic Operations and Analytical X-Ray Equipment........... 11 2.11 La u n d ry........................................................ 12 3.0 VENTILATION SYSTEM S............................................ 16 3.1 Equipment Ventilation.............................................. 16 3.2 Room Ventilation................................................. 16 3.3 M onito rin g...................................................... 17 3.4 Exhaust Ventilation................................................ 17
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4.0 AREAS......................................................... 18 4.1 Cle an Are as..................................................... 18 4.2 Intermediate Areas................................................ 20 4.3 Contamination Controlled Area........................................ 21 1
1 4.4 Low Surface Contaminated Area...................................... 23 4.5 Radioactive Materials Area (10 CFR 20.1902(e))..............
24 4.6 Radiation Area (10 CFR 20.1003(b)(2) and 10 CFR 20.1902(a)).
25 l
4.7 High Radiation Area (10CFR20.1003) and (10CFR20.1601).................. 25 4.8 Airborne Radioactivity Area (10 CFR 20.1003(d))............
27 1
5.0 EX P O S U R E..................................................... 31 5.1 Nonoccupational Exposure (Off-Site) (10 CFR 20.105) and (40 CFR 190.10(a))... 31 5.2 Occupational Exposure (10 CFR 20.1201).............................. 31 nlC) 5.3 Internal Exposure................................................ 36 5.4 Records and Reports.................................
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EMF-30, Chapter 2 Revision 16 Page li 6.0 TRAINING................
45 6.1 New Employee Orientation.......
45 6.2 Radiation Worker Training.........................
45 6.3 Prenatal Exposure Training..........
47 6.4 Radiation-Producing Devices.
47 6.5 Health and Safety Technician Training....
48 7.0 SHIPPING AND RECEIVING RADIOACTIVE MATERIALS......
49 8.0 REPORTING OF INCIDENTS................
50 8.1 Responsibility................
50' 8.2 Evaluation and Documentation............
50 8.3 Notification of Safety, Security and Ucensing.......
51 8.4 Reporting to NRC............................
52 8.5 Reporting to the State of Washington..
58 O
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EMF-30, Chapter 2 Revision 16 Page iii-r LIST OF TABLES 1
Table Eggt TABLE 2.1 RADIATION SAFETY INSTRUMENT CAPABILITIES..................... 5 i
TABLE 5.1 OCCUPATIONAL EXPOSURE LIMITS.................
....... 32 '
l TABLE 5.2 AIRBORNE RADIOACTIVITY EXPOSURES........................... 37 TABLE 5.3 RESTRICTED AREA AIRBORNE RADIOACTIVITY CONCENTRATION ACTION LEVELS AN D ACTION S......................................... 38 LIST OF EXHIBITS Exhibits Paae f
EXH I B IT A............................................................. 13 i
EX H I B IT B............................................................ 14 l
EX H I B IT C............................................................ 15 1
LIST OF APPENDICES j
i Appendix Eggt i
1 RADIATION INCIDENT CORRECTIVE ACTION REPORT.................... 62 2
EXAMPLES OF INCIDENTS REQUIRING IMMEDIATE AND 24-HOUR NOTIFICATION 64
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EMF-30, Chapter 2
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Revision 16 Page 2 2.0 GENERAL
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2.1 Radiation Work Procedures All handling, processing, transporting, or storage of radioactive material shall be covered by Radiation Work Procedures (RWP) which shall govern the radiological safety of all work. The RWPs shall be immediately available to personnel working with radioactive material. It is the responsibility of the individual worker to know, understand, and follow the RWP requirements for the activity being performed. If there is uncertainty, the Supervisor, or a Radiological Safety 5
Health and Safety Technician (HST), should be called for assistance.
RWPs shall contain the following information and requirements:
1.
A unique identification number.
2.
The location of the work.
3.
A description of the nature and extent of the work.
4.
A description of types and levels of radiation exposures that may be encountered, and instructions for self-monitoring.
5.
A description of the types and levels of contamination that may be encountered, cnd instruction for personal survey.
6.
Protective clothing requirements.
7.
Personal dosimetry requirements.
8.
A statement of any special equipment, instructions, or controls required.
All RWPs shall be prepared by Radiological Safety, approved by Health Physics, and l
accepted by the section manager (s) responsible for the work and the facility. All RWPs shall be reviewed and reissued every two years.
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EMF-30, Chapter 2 Revision 16 Page 3 Violations of an RWP shall be immediately brought to the attention of appropriate operations personnel and Radiological Safety. The corrective action for a violation shall be immediate, or the offending action shall be shut down until corrective action can be taken.
Action to prevent recurrence shall be determined by the responsible area management, with the concurrence of the Supervisor, Radiological Safety. Radiological Safety shall document and maintain a record file of the RWP violations and corrective actions.
2.2 On-Site Transfers and Storsoe of Radioactive Material Radioactive material to be transferred between facilities on-site or placed into storage shall be packaged in containers designed to provide containment of radioactive contamination by providing at least one barrier for contamination control.
The accessible surface of the outer container used to transport radioactive material 2
outside of a contaminated, radioactive materials area shall survey to <200 dpm/100 cm a, or 2
<500 dpm/100 cm p-y removable contamination, and shall be posted with either a tag, label, or stencil bearing the standard radiation ephol (unless under constant attendance). The posting shall be durable and clearly visible. N posting requirement does not pertain to off-site shipping containers.
Radioactive powder shall be transferred from one container to another within ventilated l
hoods. Transfer containers shall be designed to contain the radioactive material insofar as 2
practicable. The outer surfaces of such containers shall be maintained at <10,000 dpm/100 cm 2
a, or <60,000 dpm/100 cm p-y removable contamination when outside of hooded area in a contamination controlled area.
2.3 Llauid Process cooling water shall be isolated from a liquid process environment by two physical barriers prior to discharge to the sanitary sewer system. Process cooling water used in a dry process requires only one physical barrier prior to discharge to the sanitary sewer.
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EMF-30, Chapter 2 Revision 16 6
Page 4 j
i 2.4 Solid Weste There shall be no on-site disposal of radioactive-contaminated materials unless specifically authorized by Manager, Regulatory Compliance.
l Uranium-contaminated solid material awaiting recovery or disposal shall be stored within 2
a designated area, and outer package surfaces shall be <200 dpm/100 cm a or <500 dpm/100
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cm p-y of removable contamination as verified by HST survey. Containers used for this purpose, l
2 shall be an engineered, strong-tight container.
2.5 Instruments and Equipment The Su?orvisor, Radiological Safety, is responsible for providing proper radiation safety instruments. The Manager, Plant Engineering, is responsible for the maintenance and calibration of radiation safety instruments and equipment. The maintenance and use of these various
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instruments is outlined be!ow. A typical listing of instruments and their capatilities is displayed in Table 2.1.
l 1.
All radiation detection and dose rate instruments shall be inspected and calibrated per Regulatory Guide 8.24 at least semiannually.
2.
Instruments shall be calibrated following any maintenance on them before they are put back into routine service.
l 3.
Personnel contamination, survey instruments, used at step-off pads, shall be source-checked prior to each use, and shall be located in an operating background sufficiently low so as to allow personnel to perform an effective survey.
4.
Portable dose rate survey instruments shall be source-checked by HST prior to the conduct of area radiation level surveys.
j 5.
Calibration sources shall be traceable to NIST.
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Airborne radiation monitoring instrumentation systems shall be calibrated at least i
semiannually.
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i EMF-30, Chapter 2 Revision 16 Page 5 TABLE 2.1 RADIATION SAFETY INSTRUMENT CAPABILITIES i
Lower Approx.
Radiations Type of instrument Range Detedon Emciency
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Detected Level Ranges 8
Air Sample Analyzers a
0-16 cpm 1 cpm
.24.35 3
Air Concentration Monitors a
0-5x10 cpm 5 cpm
.25.35 8
AC-Operated Survey Meters a
0-10 cpm 20 cpm 8
Portable Survey Meters a
0-5x10 cpm 20 cpm
.08.25 4
Portable Survey Meters p,y 0-5x10 cpm 20 cpm Portable Low Energy Dose p,y,x 0-300 0.1 mrem /hr Rate Survey Meters mrem /hr Portable Dose Rate Meters p,y,x 0-25 Rem /hr 0.5 mrem /hr 0-100 Rem /hr 1.0 mrem /hr 0-300 Rem /hr 0.1 mrem /hr 0-500 Rem /hr 0.2 mrem /hr Portable Dose Rate Meters n
0-2 Rem /hr 0.01 mrem /hr Direct-Reading Dosimeters y,x 0-200 mrem 10 mrem y
0-10 Rem 500 mrem y
0-600 Rem 20 mrem x,y,n 0-200 mrem O
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EMF-30, Chapter 2 i
Revision 16 Page 6 1
7.
" Laboratory-type" air sample analyzers shall be source and background checked
'l oach day before use.
If source-checks are outside procedural limits, as determined by Radiological Safety, Maintenance shall be notified.
Following maintenance, a new chi square test shall be run.
8.
The emergency equipment repository shall be inspected and inventoried monthly by the Safety Section of the Safety, Security, and Ucensing Department.
j 9.
Radiation detection instrument maintenance and calibration records shall be retained by Plant Engineering.
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2.6 Sealed Sources - License No. WN-1062-1
- i The possession of sealed sources is authorized by license on an individual source basis.
Prior to purchase of a radioactive source, license review for such authorization should be requested from Manager, Regulatory Compliance. WAC-402-12 The replacement of any l
sealed source fastened to or contained in a radiographic exposure device and leak testing, repair, tagging, opening, or any other modification of any sealed source shall be performed only
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' by persons specifically authorized by the SPC State Ucense.
-I Radiological Safety shall conduct a physical inventory of all sealed sources and_ perform leak tests at 6-month intervals, on all sources containing >100 pCi p-y, or >10 pCi a activity.
The following information shall be recorded during the inventory:
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1.
Name of responsible custodian.
2.
The date of the inventory / leak test.
3.
The location of the source.
l 4.
Identity of the principalisotopes.
j 5.
Estimate of (as applicable) pCl, pg, dpm, and dose rate.
l 6.
Result of leak test in units of pCl.
l 7.
Identity of source by identification number (if possible).
8.
Name of person performing leak test.
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EMF-30, Chapter 2 Revision 16 Page 7 Upon receipt of a source, and in the absence of a certificate from the transferor that a test has been made within the 6-month period prior to receipt, the sealed source shall not be put into use untii tested.
Any test which reveals the presence of 0.005 pCi or more of removable radioactive material shall be considered evidence that the sealed source is leaking. Any source found to be leaking shall be withdrawn from service and reported immediately to the Manager, Regulatory, Compliance. Records of leak test results shall be maintained by Radiological Safety for two years.
Within five days after determining that any sealed radioactive material source has leaked, Regulatory Compliance shall prepare and submit a detailed report describing the equipment involved, the laak test results, and corrective action taken. Copies of all such reports shall be distributed to:
1.
External distribution (for source and byproduct material sources):
Supervisor, Radiation Control Section i
Department of Social and Health Services P. O. Box 1788 Olympia, WA 98504 2.
Internal distribution (all sources)
Supervisor, Safety Manager, Safety, Security, and Ucensing Each radiographic exposure device shall have, permanently and conspicuously attached 2
to it, a durable label at least 2 in bearing the prescribed radiation caution symbol in conventional colors (magenta or purple on a yellow background), and the instructions,
- DANGER -
RADIOACTIVE MATERIAL - DO NOT HANDLE - NOTIFY CIVIL AUTHORITIES IF FOUND.*
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EMF-30, Chapter 2 Revision 16 Page 8 A sealed source which is not fastened to, or contained in a radiographic exposure device 2
shall have permanently attached to it a durable tag at least 1 in bearing the prescribed radiation caution symbol in conventional colors (magenta or purple on a yellow background), and the instructions: " DANGER - RADIOACTIVE MATERIAL - DO NOT HANDLE - NOTIFY CML AUTHORITIES IF FOUND."
2.7 Emergency Electrical Power it is the responsibility of Plant Maintenance to assure that emergency power systems are maintained for critical safety systems. Operational tests of emergency generators shall be conducted monthly. Functional tests, consisting of loading the generators to normal emergency loads, shall be performed at least annually. Test results shall be retained by Plant Engineering.
The following equipment and systems shall be tied into both normal and emergency power *:
1.
Process off-gas systems exhausters.
2.
Exhaust duct deluge systems.
3.
HVAC control panels.
4.
Air sampling vacuum pumps.
5.
Air recirculation system radiation monitors.
6.
Laboratory-type smear and air sample counters.
7.
Criticality detection / alarm system.
8.
2.8 Audits / Inspections 2.8.1 Purpose Health Physics audits and inspections are conducted on a regular schedule to confirm that operations are being conducted to maintain radiation exposure A1. ARA, and within the requirements of the NRC and State regulations and licenses, SPC Standards and RWPs, and that appropriate regard has been given to Regulatory Guides and sound industrial practices.
For additional requirements, see Chapter 1. " Industry Safety."
EMF-30, Chapter 2 Revision 16 Page 9 2.8.2 HST Inspections HSTs shall perform inspections as they go about their daily activities such as collecting air samples, and performing radiation and contamination surveys. Detected infractions of radiation protection procedures, exposure controls, and sound radiation protection practices should be corrected on-the-spot by the HST as part of their continuing personnel educational responsibility. Minor infractions shall be recorded on observation of weakness from serious infractions and acts of noncompliance shall be documented (see Exhibit A) and distributed by, the Supervisor, Radiological Safety, to the respective facility / operational managers.
2.8.3 Audits - Safety. Security, and Licensino The Health Physics Component shall perform audits monthly to confirm that operations are being conducted so as to maintain radiation exposure ALARA, and within the scope of the NRC and State regulations and licenses, EMF-30 Standards, and SPC RWPs. The major subjects of the audit are listed on the audit cover sheet (Exhibit B). Subjects to be audited in any given month will be described in an annual audit plan. Reports of all audits shall be made orally ASAP to the manager of the facility audited, and submitted, in writing, within five working days. If possible, infractions should be corrected immediately during the audit. If immediate corrective action cannot be taken or agreed to, the offending operation may be shutdown. In addition to the full audit report, each audit finding shall be stated on a Corrective Action Request Form (Exhibit C) which is submitted to the manager responsible for corrective action. The audit report shall have the following minimum distribution:
Richland Plant Manager Manager, Manufacturing Engineering Manager, Safety, Security, and Ucensing Manager, Regulatory Compliance Supervisor, Radiological Safety Manager, Plant Operations Manager, Plant Engineering Vice President, Engineering Manager, Fuel Services Manager, Product Development and Testing
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EMF-30, Chapter 2 Revision 16 Page 10 A response to audit findings using the Action Request Form shall be returned within 10 working days from the date on the Audit Report. The audit response must identify the cause of the infraction, the immediate corrective action, and action to prevent future occurrence, including a schedule for those actions. Action to prevent reoccurrence should normally be scheduled for completion within 30 days of the audit date. The audit response should be sent to the auditor.
2.8.4 Radiation Protection Proaram Audit An annual audit of the Radiation Protection Program content and implementation shall be conducted by the Supervisor, Safety per 10 CFR 20.1101(c) to determine that the Radiation Protection Program is conducted in compliance with regulatory requirements, license conditions and formal procedures.
2.9 Al. ARA / Radiation Safety Committee SPC has a functioning ALARA Radiation Safety Committee as a subgroup of the Health and Safety Council. The membership of the Committee shall be as follows:
Manager, Regulatory Compliance - Chairman Health Physics Component - Secretary Manager, Safety, Security, and Ucensing Supervisor, Safety Supervisor, Radiological Safety Manager, Fuel Services Manager, Plant Operations Manager, Plant Engineering Manager, Process Engineering 1
1 Normally, the Committee will convene twice each year as a minimum (the dates to be scheduled by the Chairman). The Committee shall issue a formal report at least annually to the Health and Safety Council, reviewing employee exposures and effluent release data to determine:
EMF-30, Chapter 2 Revision 16 Page 11 1.
If there are any upward trends developing in personnel exposures for identifiable categories of workers or tvpes of operations, total effluents or concentrations of effluents in environmental samples.
2.
If exposures and effluents might be louered under the concept of ALARA.
3.
If equipment for effluent and exposure control is being properly used, maintained, and inspected.
Committee reports shall be retained by the Chairman of the Committee.
In order to have a basis for comparison and judgment, the following information and data shall be reviewed by the Committee.
1.
Airborne contamination levels.
2.
Bioassay data (urinalysis and in-vivo examinations).
3.
External radiation exposure data.
4.
Effluent data.
5.
Environment sampling / monitoring data.
6.
Integrity of waste lagoon liners and "between-liner" sampling data.
7.
Operational history of effluent treatment and measurement systems.
8.
Documentation of incidents, unusual occurrences, etc., for facilities, equipment, systems, etc., which deal with personnel exposure to radioactive material.
9.
Documentation of facilities, equipment, procedures, etc., put in place to reduce personnel exposures, or to reduce environmental impact of plant operations.
10.
Documentation of pertinent audits and inspections.
[ni ustrial Radioaraphic Operations and Analytical X-Ray Eauipment td 2.10 i
All radiographic and analytical X-ray operations shall comply with State of Washington Chapters WAC 402-36 and WAC 402-40, respectively.
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E'viF-30, Chapter 2 Revision 16 Page 12 2.11 Laundry Protective clothing shall be cleaned to minimize contamination so that resuspension of radioactive material and direct exposure to the skin /whole body are maintained Al. ARA.
2 Removable contamination on fresh laundry shall be <1000 dpm/100 cm a, and <22,200 2
dpm/100 cm p-y. Samples of fresh laundry shall be surveyed for removable contamination by HST weekly. Fixed p-y contamination on fresh laundry shall not exceed that which could ' result in skin exposure greater than the Company Guide (3 rem per quarter). This value is conservatively estimated using LA-4558-MS as a basis, to be approximately 2,500 cpm on the i
laundry monitoring instrument. All fresh laundry shall be surveyed for fixed contamination by laundry personnel prior to release for use.
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EMF-30, Chapter 2 Revision 16 Page 13 EXHIBIT A Siemens Power Corporation - Nuclear Division VIOLATION OF RADIATION SAFETY DATE:
TIME.
HPT:
NAME:
LOCATION OF VIOLATION.
DESCRIPTION OF VIOLATION.
O CORRECTIVE ACTION T AKEN. (To be completed by responsible Manager or Supervesor)
DATE BY:
W.NAGE R OR SUPERVISOR O
SPCAD 3r2 Ht A (R-202/ Bit)
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EMF-30, Chapter 2 ReviSlon 16 Page 14 EXHIBIT B HEALTH PHYSICS AUDIT REPORT Distribution:
Audit Date:
BF Bently (3)
SR Lockhaven Facilities Audit:
RA Busch LJ Maas RE Collingham JN Morgan BN Femreite TC Probasco Auditor:
RL Feuerbacher A. Reparaz EL Foster /HST MK Valentine JW Hetton RE Vaughan DC Kilian LD Weaver MA Law File /LB-94-002 CHECKLIST OF OBSERVATIONS YN
- 1... Area boundary, container identifications, and postings are satisfactory.
- 2... Radiation Work Procedures and teir implementation are satisfactory.
- 3.,, The frequency and accuracy of radiation surveys are satisfactory.
4.
Radioactive material containment is satisfactory.
5.
Radioactive material packaging and shipping programs are satisfactory.
6.
Personnel, exhaust, and recirculation air sampling and monitoring are satisfactory, i
- 7. N/C* In-Vivo and urinalyses programs are satisfactory.
8.
Process, room, and building containment; HEPA filters Ap measurements and air flows are satisfactory.
- 9.,,, Radiation detection instruments, their calibration, emergency equipment, emergency power systems are satisfactory.
10.
Environmental surveillance; liquid effluent, lagoon integrity, air, soi!, and vegetation sampling programs are satisfactory.
11,,, Radioactive protection training program is satisfactory.
- 12.,, Sealed source inventory and leak test are satisfactory.
- N/C Not checked Date of Report Auditor's Signature Page Audit Report No.
1 of 2 I
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i EMF-30, Chapter 2 Revision 16 Page 15 EXHIBIT C Siemens Power Corporation HEALTH PHYSICS CORRECTIVE Nuclear Division ACTION REQUEST auper part-aupricwrs smaanse met mustn AUDIT FINDINGS:
IMMEDIATE CORRECTIVE ACTON:
CORRECTIVE ACTON g TAKENBV w CORRECTIVE ACTIONS: (Managers of Operatens where mtrectons were oscusseo snan repay watun to worming oays of the avait cate)
MANAGER RESPONSIBLE FOR RESPONSE CAUSE; Cor'ective actuis plarmed to prevent recurrence, meludeg a schedu6e for those actors:
O r.
6PCMD 3W2 950m (R 197%)
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EMF-30, Chapter 2
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ReWsion 15 Page 16 i
3.0 VENTILATION SYSTEMS SPC is required to control ventilation systems such that releases of radioactive materials in gaseous emuents are within license and regulatory limits. This Section pertains to those controls necessary to maintain concentrations of radioactive materials in air to within limits for j
restricted areas. EMF-30, Chapter 4, discusses controls for releases to unrestricted areas.
i 3.1 Eautoment Ventilation Process equipment ventilation provides confinement of radioactive materials while they l
are being processed. Differential pressures shall be maintained by Plant Maintenance such that room-air flows into the hoods er processing equipment. The average linear face velocities of f
openings in process equipment, or enclosures that contain readily dispersible forms of uranium, l
shall be maintained nominally at 1125 LFPM with no individual velocity being <100 LFPM.
i 3.2 Room Ventilation
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The ventilation systems for contaminated, radioactive material areas shall be operated by.
l Plant Maintenance to provide:
1.
Pressures. negative with respect to atmosphere (0.05 inch of water minimum).'
i Airlocks shall be provided, where necessary, to insure maintenance of the proper air pressure differential.
i 2.
Directional airflows from areas of least potential contamination to areas of greater i
contamination potential.
j 3.
A minimum of seven air changes per hour in contaminated, radioactive materials areas (see Section 4.3).
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Vacuum cleaning units operated outside of a ventilated enclosure in contaminated, radioactive material areas (defined in Section 4.3) shall, when purchased and annually thereafter, j
I be tested to assure approximately 99.95% efficiency for the removal of 0.8 micron particles.
HEPA filters to be installed in the vacuum cleaners shall be individually tested and certified by i
the manufacturer to be at least 99.97% efficient for the removal of 0.3 micron particles.
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l EMF-30, Chapter 2 Revision 15 Page 17 3.3 Monitorina 1.
The recirculated air shall be continuously, isokinetically monitored prior to final HEPA filtration. An indication of >40 DAC-hr shall automatically divert the ventilation system from the recirculation mode to a once-through exhaust mode.
Recirculation air HEPA filtration shall be equipped with continuous pressure differential measuring and monitoring systems which are read and recorded at least monthly. Records shall be maintained by Plant Engineering.
2.
Contaminated area pressure with respect to atmosphere shall be recorded at least monthly and reported to the building manager, and Supervisor, Radiological Safety, if readings 2 -0.05 inch of water are found. These records shall be maintained by Plant Engineering.
3.
Smoke tests for proper directional airflow in process areas shall be performed and recorded weekly by Plant Maintenance, improper directional flow shall be reported to the building manager, and Supervisor, Radiological Safety, Regulatory Compliance. These records shall be maintained by Plant Engineering.
4.
The face velocities of openings in process equipment enclosures shall be measured and recorded monthly by Plant Maintenance. These records shall be retained by Plant Engineering.
3.4 Exhaust Ventilation Exhaust slacks shall extend at least 20 feet above air intakes in order to minimize the possibility of recycling contaminated air into the buildings in the event of a stack release.
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EMF-30, Chapter 2 Revision 15 Page 18 4.0 AREAS Various plant areas are defined below based upon their radiological characteristics, and pertinent limits and requirements are noted.
4.1 Clean Areas Definition
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Areas where radioactive material, if present, is either completely contained and/or contamination levels are extremely low on the floors or accessible surfaces.
Postino
. Safety, Security, and Ucensing shall provide posting of notices to workers in compliance with WAC 402-48-020 and 10 CFR 19.11.
Survev Recuirements Clean areas in the vicinity of contaminated, radioactive material areas shall be surveyed by an HST at least weekly. Lunchrooms and break areas shall be surveyed by HST daily.
Contamination Umits (Fixed and Smearable)
The survey shall be performed to help insure the Company guidelines specified in the Table 4.1 are not exceeded. The Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Ucenses for Byproduct, Source, or Special Nuclear Material (EMF-2, Chapter 3, Appendix A) which are less conservative, may be used upon written authorization by the Manager, Safety, Security, and Ucensing.
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TABLE 4.1 ACTION LEVELS AND MONITORING FREQUENCIES Action Level Removable Action Level Minimum l
Contamination on Floors Removable Contamination on Monitoring Area Equipment
- Frequency l
For Alpha Emitters 1.
Contamination Controlled Area 10,000 dpm/100 sq cm or 10,000 dpm/100 sq cm or visible Weekly I
visible contamination contamination 2.
Low Surface Contamination Area 200 dpm/100 sq cm 200 dpm/100 sq cm Weekly i
3.
Intermediate Area 50 dpm/100 sq cm 50 dpm/100 sq cm Daily 4.
Clean Area 50 dpm/100 sq cm 50 dpm/100 sq cm Monthly 5.
Lunch Rooms Adjacent to Radioactive 50 dpm/100 sq cm 50 dpm/100 sq cm Daily M terials/ Radiation Areas i
For Beta-Gamma Emitters 1.
Contamination Controlled Area 60,000 dpm/100 sq cm 60,000 dpm/100 sq cm Weekly i
2.
Low Surface Contamination Area 500 dpm/100 sq cm 500 dpm/100 sq cm Weekly 3.
Intermediate Area 500 dpm/100 sq cm 500 dpm/100 sq cm Daily 4.
Clean Area 200 dpm/100 sq cm 200 dpm/100 sq cm Monthly 5.
Lunch Rooms Adjacent to Radioactive 200 dpm/100 sq cm 200 dpm/100 sq cm Daily Mrterials/ Radiation Ar eas For Plutonium Alpha Semiannually 1.
Clean Radioactive Materials Storage Areas 20 dpm/100 sq cm mE 7'
h Equipment is reference to those not in containment.
EO Decontarr.ination shall be required within the shift if the contamination exceeds the appropriate action level. Immediate decontamination shall be ygg 2
2 required if the contamination for a clean area is greater than 200 alpha dpm/100 cm or 500 beta-gamma dpm/100 cm. Immediate decontamination tg g R 2
2 shall be required if the contamination for an intermediate area is greater than 500 alpha dpm/1,00 cm or 2000 betagamma dpm/100 cm. If the R
2 contamination levelin a clean or intermediate area is in excess of 2000 (aipha or beta-gamma) dpm/100 cm as or S the area shall be posted as a S
- F0 Contamination olled Area untilit is cleaned up.
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EMF-30, Chapter 2
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Revision 15 Page 20 Protective Clothina None required. Protective clothing approved for work in contaminated areas shall not be worn in clean areas without the specdic approval of the Supervisor, Radiological Safety.
Personnel dosimeters are required for all employees.
i Trainina New employee orientation (Section 6.1).
i 4.2 Intermediate Areas O
Definition Intermediate Areas are buffer areas between contaminated, radioactive material areas and clean areas. A potential exists for low levels of radioactive material contamination in Intermediate Areas. Radioactive material is not to be process i
ed or permanently stored in an intermediate Area.
Postina t
,The boundaries and entrances into Intermediate Areas from clean areas (other i
than walls) should be identified by yellow and green tape. The entrance from a contamination controlled area shall be at a step-off pad.
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i EMF-30, Chapter 2 Revision 15 Page 21 Survey Recuirements a
Intermediate Areas shall be surveyed for contamination daily (normal working days) by an HST.
Contamination Umits (Smearable)
The survey shall be performed to help ensure company guidelines specified in Table 4.1 are not exceeded.
Protective Clothina Protective clothing is not required. Fresh (laundered) protective clothing is allowed (see Section 2.11). Used protective clothing may be worn after personal survey discloses it meets the contamination requirements for a area (see intermediate Section 4.1).
Trainina New employee orientation (Section 6.1).
4.3 Contamination Controlled Area Definition Area where uncontained radioactive materials are processed and the probability of contamination on floors and accessible surfaces is high.
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-es EMF-30, Chapter 2 Revision 15 Page 22 Postina The boundaries and entrances into contamination controlled areas shall be l
identified by yellow and magenta (purple) tape.
Survey Reauirements Contamination controlled areas will be surveyed by an HST at least weekly.
Contamination Umits (Smearable)
The survey shall be performed to help ensure the company guidelines in Table 4.1 are not exceeded.
'I Personnel are not released to eat or leave the facility, except with the approval of the Supervisor, Radiological Safety, and the respective facility manager, if their 2
personal clothing or skin is contaminated in excess of 200 dpm/100 cm s, or -
2 l'
200 dpm/100 cm p.y, Equipment, materials, or samples shall be surveyed and released by an HST prior -
to leaving the area.
Dose rate surveys shall be performed by an HST monthly.
Protective Clothina Personnel working in a contamination controlled area, performing hands-on work, _
shall wear a full set of protective clothing as specified in RWPs.
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EMF-30, Chapter 2 Revision 15 Page 23 During the workday, protective clothing in a contaminated area will be changed 2
if removable contamination is visible and/or exceeds 10,000 dpm/100 cm a on survey.
Trainina
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Persons who process or handle radioactive materials in any manner shall have received radiation worker training.
Persons not required to process or handle radioactive materials shall receive radiation worker training, or be escorted by a person who has received radiation worker training while in a contaminated, radioactive material area.
4.4 Low Surface Contaminated Area O
Definition
+
Process or laboratory areas where uncontained radioactive materials are processed / assayed and the probability and/or level of contamination on floors and accessible surfaces is low.
Survey Reauirement Low surface contaminated areas will be surveyed by an HST at least weekly.
Personnel surveys are required when exiting area.
Contamination Umits The survey shall be performed to help ensure the company guidelines in Table 4.1 are not exceeded.
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Q EMF-30, Chapter 2 V
Revision 15 Page 24 Protective Clothino 4
Protective clothing requirements may range from full protective clothing to personnel clothing. RWPs specify the protective clothing requirements.
Trainino Same as a for contamination controlled area personnel.
4.5 Radioactive Materials Area (10 CFR 20.1902(e))
Definition An area, room, or compartment where radioactive materials are used or stored in an amount exceeding 10 times the quantity of such material specified in Appendix C to 10CFR 20.1001-20.2401.
Postino The boundaries and entrances of radioactive materials areas (other than walls or permanent fence) shall be identified by yellow and magenta tape, rope or chain; they shall be posted with signs bearing the standard radiation symbol and the words ' CAUTION RADIOACTIVE MATERIAL (S) or DANGER RADIOACTIVE MATERIAL (S)." If containers within an area are not identified when containing radioactive material, then each entrance shall also have a sign stating, "EVERY CONTAINER OR VESSEL IN THIS AREA, UNLESS OTHERWISE IDENTIFIED, MAY CONTAIN RADIOACTIVE MATERIAL" U
t EMF-30, Chapter 2 Revision 15 Page 25 4.6 Radiation Area (10 CFR 20.1003(b)(2) and 10 CFR 20.1902(a))
Definition A Radiation Area is an area accessible to personnel in which radiation exists at such levels that a person could receive, in one hour, a dose equivalent in excess of 5 mrem, in one hour at a distance of 30 centimeters from the source (s).of radiation or from any surface that the radiation penetrates.
Postina Areas meeting the definition of radiation area shell be posted with a sign bearing the words " CAUTION RADIATION AREA".
Survey Recuirements HST shall survey radiation areas to help keep exposures low. Surveying shall be in accordance with EMF-1507,5.1.
Dos! metry Personnel dosimetry is required for all personnel entering radiation areas.
4.7 Hiah Radiation Area (10CFR20.1003) and (10CFR20.1601)
Definition A High Radiation Area is'an area accessible to personnelin which radiation levels could result in an individual receiving a dose equivalent in excess of 100 mrem in O 4
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EMF-30, Chapter 2
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Revision 15 l
Page 26 one hour at 30 centimeters from the source or from any surface that the radiation penetrates.
i Posting i
Signs shall bear the words, " CAUTION, HIGH RADIATION AREA" or " DANGER, HIGH RADIATION AREA." To aid in maintaining exposure ALARA, sources within l
the area shall be individually marked with the exposure rate at one foot.
j Survey Reauirements l
High radiation areas rarely exist. Special survey requirements will be specified by Health Physics or Radiological Safety as needed.
Dosimetry l
Personnel dosimetry is required by all personnel in high radiation area.
Trainino Radiation worker training, or escorted by a person who has received radiation
-)
worker training.
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Entrance Reauiremer)13 A specific RWP shall be necessary for each high radiation area.
Each entrance or access point to a high radiation area shall be:
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EMF-30, Chapter 2 Revision 15 Page 27 1.
Equipped with a control device which shall cause the level of radiation to be reduced below that at which an individual might receive a dose of 100 mrem in one hour upon entry into the area; or Equipped with a control device which shall energize a conspicuous visible 2.
or audible alarm signal in such a manner that the individual entering the high radiation area and Radiological safety or a supervisor of the activity are made aware of the entry; or 3.
Maintained locked, except during periods when access to the area is required, with positive control over each individual entry.
a.
The controls shall be established in such a way that no individual will be prevented from leaving a high radiet;on area.
b.
HST shall log each personnel entry and exit.
4.8 Airborne Radioactivity Area (10 CFR 20.1003(d))
Definition An Airborne Radioactivity Area is any area, room, or enclosure in which airborne radioactive material, composed wholly or partly of licensed material, exists in concentrations:
1.
In excess of the derived air concentrations (DAC) specified in Appendix B
't'o CFR 2010012401, or 2.
To such a degree that an individual present in the area without respiratory protection could exceed over a 40-hour work week, an intake of 0.6 percent of the annual limit on intake (All) or 12 DAC-hours.
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4 EMF-30, Chapter 2 Revision 15 Page 28 Work which involves operations that have been known to have caused high airborne radioactivity are listed below:
Grinding Welding Flame-cutting Steam Cleaning Enrichment Clean Out of Equipment Postino (10CFR 20.1902)
=
The same requirements as a Radioactive Materials Area. In addition, a sign shall O
bear the words " CAUTION, AIRBORNE RADIOACTIVITY AREA" or " DANGER, AIRBORNE RADIOACTMTY AREA."
The area shall be posted wt en the requirements of the definition are met. An HST shall be contacted whenevar an area is posted. HST authorization is required to remove the posting.
Survey Reauirements
=
Continuous campling for airborne particulate radioactivity shall be provided that is representative or adjusted to be representative of the air in the breathing zone of the personnel. This may require the use of personnel air samplers. Records of air sampling data shall be retained per Section 5,4.
The Supervisor, Radiological Safety, shall determine the need for continuous air monitors. The continuous air monitors shall have both a visual and audible alarrra The alarm set point shall be as low as possible to give the earliest possible L,
EMF-30, Chapter 2 Revision 15 Page 29 warning of airborne radioactivity, but shall be high enough above background to preclude frequent " false" alarms. Continuous air monitors shall be inspected at least weekly for proper operation, and for indications of abnormal air contamination that have not been alarmed.
The airflow rates through air samplers as measured by in-line rotameters shall be checked by HST at the start and at the end of each respective sampling period.
All rotameters used for measurement of airflows through sampler or monitors shall be calibrated at least yearly, or at the request of Radiological Safety. Calibration shall be the responsibility of Plant Engineering. Calibration record retention shall be the responsibility of Plant Engineering.
Radiological Safety shall provide lapel air sampling (LAS), as necessary, during the year. LAS will be used to verify the level of air contamination as measured by area air samplers and document the adequacy of the respiratory protection worn.
Respiratory Protection All appropriate personnel entering the area shall have been trained and fitted to use a respirator (see Chapter 1, industrial Safety). If facial changes have occurred due to factors such as weight gain / loss, an up-to-date respirator fit shall be obtained prior to being issued or wearing a respirator. If there is any question on the adequacy of the respirator fit or training, the use of the respirator shall not be authorized until all questions are adequately resolved. Radiological Safety shall be responsible for issuing a respirator to authorized personnel.
l Respiratory protection equipment is to be selected to provide a protection factor greater than the multiple by which peak concentrations of radioactive materials are expected to exceed the air concentration limits. Protection factors specified by 10 CFR 20, Appendix A, are listed below.
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EMF-30, Chapter 2 Revision 15 i
Page 30 i
Half-Mask Respirator 10 Full-Face Respirator 50 Airline Full-Face Respirator (continuous flow and pressure demand) 2,000 l
SCBA Full-Face Respirator (pressure demand) 1d,000 t
Procedures for the use and maintenance of respiratory equipment are outlined in the Industrial Safety Standards (Chapter 1), and those procedures shall be in accordance with the requirements listed in Regulatory Guide 8.15,10 CFR 20.1701-1704 and WAC 296-62-071.
Trainino Radiation worker training. Visitors are not allowed in areas requiring masks unless given permission by Health Physics. Medical approval and successful respirator fitting is required before respiratory protection can be worn.
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EMF-30, Chapter 2 Revision 15 Page 31 5.0 EXPOSURE 5.1 Nonoccuostional Evmure (Off Site) (10 CFR 20.105) and (40 CFR 190.10(a))
SPC shall control the radioactive materials in its possession such that the annual dose equivalent to any member of the public does not exceed 25 mrem to the whole body,75 mrem to the thyroid, and 25 mrom to any other organ as the result of exposures to planned discharges of radioactive materials.
5.2 Occupational Exposure (10 CFR 20.1201)
The occupational exposure limits given in Table 5.1 apply to persons over 18 years of age, and shall be applied to all such persons for whom SPC has control responsibilities, including visitors. The limits in Section 5.1 apply to members of the public when given access to SPC facilities. The total occupational dose shall comprise the dose contributed by external V
and internal sources during working hours. It shall not include medical exposure or exposure to natural radiation background.
The exposure of any individual under age 18 shall be limited to one-tenth of the occupational exposure limits given in Table 5.1 (10 CFR 20.1207). Individuals under age 18 shall not receive a routine work assignment where they would be expected to receive radiation exposure, especially internal exposure from airborne radioactivity.
5.2.1 Exposure to an Unborn Child (10CFR 20.1208)
All employees shall be advised of the National Council on Radiatio'n Protection and Measurements recommendation to keep radiation exposure to an embryo or fetus to the very
)
lowest practicable level during the entire gestation period. The dose limit to the unborn child is I
a maximum of 0.5 rem. Therefore, exposure to a fetus of a declared expectant mother shall not exceed 0.5 rem during the gestation period.
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EMF-30, Chapter 2 Revision 15 1
Page 32 TABLE 5.1 OCCUPATIONAL EXPOSURE LIMITS Most Umiting of Company Guide NRC & Annual Umit Total Effective Dose Equivalent (TEDE) 5 Rem 1 Rem /QTR Deep-Dose Equivalent to any individual 50 Rem 10 Rem /QTR organ (other than lens of eye)
Lens of Eye 15 Rem 3 Rem /QTR Shallow-close equivalent to skin or to any 50 Rem 10 Rem /QTR extremity Note: Total Effective Dose Equivalent (TEDE) is the sum of the deep-dose equivalect (for external exposure) and the committed effective dose equivalent (for internal exposure).
Committed dose equivalent is the dose equivalent to organs or tissues.
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i EMF-30, Chapter 2 -
Revision 15 Page 33 l
F 5.2.2 Emergency Exposures f
in an emergency situation, it may be necessary for emergency personnel to exceed the l
occupational exposure limits in order to save lives or valuable property. In such situations, the i
probable effect of high exposure to the rescuer must be weighed against the expected benefits.
The exposure allowed to workers responding to an emergency situation shall be determined by j
the Emergency Director using the following guidance:.1) emergency work <25 rem whole body dose, and 2) lifesaving activities <75 rem whole body dose.
i Emergency exposure, or rescue action that may involve substantial personal risk, shall l
be performed by volunteers who shall be advised of the known or estimated extent of such risk prior to participation. Personnel who have received exposures in an emergency situation will have their exposure evaluated and appropriate action taken to limit future occupational exposure, j
i 5.2.3 Control of External Occupational Exposure Umits (10 CFR 20.1201)
The occupational exposure received by SPC employees shall not exceed the NRC annual limit, shown in Table 5.1. To avoid accidental over-exposure, and to alert management to unusual exposures, Company Guides (CG) lower than the NRC limits have been set. - Current Company guidelines are shown in Table 5.1 along with the NRC limits.
Exposure that inadvertently exceeds the CG shall be investigated by Health Physics, and a report placed in the l
personnel folder of the individual (s). Discussion will be held with the individual as part of the investigation to determin,e the cause.
Prior to first entry into a radioactive material area where an individual will, or is likely to receive, a dose in excess of 10% of the NRC annual limit for internal or external exposure, the
- individual shall disclose in a signed statement any prior occupational exposure received,-and speedically identify the location and exposure which he/she received occupational exposure. The use of TLDs and/or other individual monitoring devices is required. Additionally, for individuals likely to receive, in one year, an intake in excess of 10% of the applicable All found in Appendix B to 10CFR20.1001-20.2401,'SPC shall monitor the occupational intake and assess the committed effective dose equivalent.
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i EMF-30, Chapter 2 Revision 15 Page 34 Normally, employees working with radioactive materials at non-SPC facilities within the U.S. shall not wear their SPC dosimeter. The non-SPC facility shall be requested to provide a summary of internal and external exposure, including whole body and/or lung counting data received by SPC employees at that facility. Employees working in facilities outside the U.S.
should wear their SPC dosimeter unless objections are raised by the host facility. Where SPC dosimeters are not worn, the host facility shall be requested by the visiting SPC personnel to supply dose information as mentioned above.
if the exposure status of an individual becomes uncertain, and/or it is believed that NRC limits may have been exceeded, the individual shall be removed from further exposure assignments, and S2fety, Security, and Ucensing shall be advised promptly. The Supervisor, Radiological Safety, shall determine the exposure status and advise supervision of any special controls or restrictions to be applied.
An increase above the CG limit in occupational radiation exposures may be authorized upon written approval of the employee, the employee's Department Manager, and the Manager, Safety, Security, and Ucensing. T'he work to be accomplished and the exposure expected shall be documented before the exposure is permitted. The documentation shall be retained for at least five years.
5.2.4 Measurement NVI.AP radiation exposure dosimeters shall be issued to personne! working in areas where they have the potential, in one year, to exceed 10% of the NRC occupational exposure limit (as judged by the Supervisor, Radiological Safety), and each dosimeter shall be analyzed quarterly. The NVLAP dosimeter shall have a range of 10 mrem to 1,000 rem p-y. Dosimeters i
shall be worn in an unshielded position, above the waist, on the front part of the body. Five-chip NVLAP dosimeters shall be assigned to personnel when their work assignment involves neutron l
exposure.
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EMF-30, Chapter 2 Revision 15 Page 35 Normally, employees will not be required to wear finger-ring dosimeters; however, selected indMduals from each group han' ling sintered UO2 Pellets shall be required to wear d
finger-ring dosimeters for selected periods each year to demonstrate that extremity exposures for such groups are within CG. Finger-ring dosimeters shall be adjusted to indicate the area of the finger receiving the dose, when determining whether finger dosimetry is necessary. Assigned finger-ring dosimeters shall be worn at all times by the individual whenever he or she handles radioactive materials. (Finger rings are not NVLAP approved.)
5.2.5 Exposure Estimates Estimates of personnel external radiation exposures for control purposes shall be provided for areas where radiation levels vary, and where personnel could receive exposures in excess of CG in a matter of days. Such an area is the X-Ray Facility in the UO Building.
2
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Self-reading dosimeters or personnel electronic dosimeters may be worn by persons working in the UO Building X-Ray Facility. These dosimeters shall be sensitive to gamma and 2
x-rays, and shall be calibrated and maintained per ANSI N-13.5.
5.2Property "ANSI code" (as page type) with input value "ANSI N-13.5.</br></br>5.2" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..6, Care of Personnel Dosimeters Dosimeter results may be erroneous if the dosimeter is mistreated, not worn, contaminated, exposed to extreme heat, or worn during medical or dental x-ray procedures.
When it is known or suspected that personnel dosimeters have been mistreated, Radiological Safety personnel shall be notified promptly. Prompt action shall be taken to preserve exposure data.
If a dosimeter is lost or damaged while at work, the person involved shall leave the radiation area, notify Radiological Safety, and obtain a new personnel dosimeter. This applies to the following cases:
m 1.
Actualloss of dosimeter;
s EMF-30, Chapter 2 Revision 15 Page 36 2.
Where badge or finger-ring dosimeters become wet, are subjected to temperatures greater than 125'F, or where the packet has been punctured or torn; and 3.
Where pocket dosimeters (pencils) have been dropped, subjected to excessive moisture, heat or severe vibration, or where the cap has been removed accidentally.
5.3 Internal Exposure Airborne radioactivity is the presence of radioactive particles or gases in the air. Control of airborne radioactivity is necessary to limit the internal radiation exposure that can result from the inhalation of radioactive materials. Managers of operating facilities and engineering groups are responsible for maintaining concentrations of airborne radioactivity below the SPC Design Guide (Table 5.2).
5.3.1 Internal Exposure Prevention Health Physics will provide technical assistance to Radiological Safety in the selection of the air samplers used to detect and evaluate the levels of airborne radioactivity, and in their placement in work areas.
The prevention of internal deposition of radionuclides shall be accomplished to the extent practicable by the use of engineered controls (containment, ventilation, etc.), and the proper use of protective equipment by employees. When establishing radiological controls for work involving potential airborne radioactivity, the first consideration shall be to use techniques which will prevent airborne radioact5vity and maintain surface contamination to as low as practicable levels.
When it is impractical to apply process or engineering controls to limit airborne concentrations, other precautionary procedures such as timely surveillance and cleanup, limitation of working times, or respiratory protection equipment, shall be used to maintain intake as far below the limits as is reasonably achievable.
It is initially assumed that an individual inhales radioactive material at the airborne concentration in which he or she is present, unless he/she uses respiratory protection equipment s
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l A{J EMF-30, Chapter 2 Revision 15 Page 37 for which he/she has been fitted and trained. When respiratory protection equipment is used to limit inhalation, allowances may be made for such use using the protection factors specified by Section 4.6 in estimating exposure to the individual. Evaluations based on bioassay may be substituted for initial calculations based on airbome measurements.
Personnel are not allowed into areas without adequate respiratory protection when the concentration of uranium air samples is known to exceed 75% DAC. If air samples unexpectedly indicate the airborne concentration has exceeded (the DAC the values) in Table 5.3, an 1
investigation or special sampling shall be performed to evaluate the cause.
TABLE 5.2 AIRBORNE RADIOACTIVITY EXPOSURES NRC Annual Company Design Limit Guide Uranium 2000 DAC-brs 400 DAC hrs /qtr Mixed Fission Products Thorium
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EMF-30, Chapter 2 Revision 15 Page 38 TABLE 5.3 RESTRICTED AREA AIRBORNE RADIOACTIVITY CONCENTRATION ACTION LEVELS AND ACTIONS Action Level Multiple of Derived Air Required Action Concentration 1.0 For a single shift sample Document investigation 1.0 For a weekly average Document investigation Special air sampling study 0.5 For a quarter average Document investigation Special air sampling study Engineering evaluation 10 For a single shift sample Operation shut down Timely corrective action s
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EMF-30, Chapter 2 Revision 15 Page 39 j
h 5.3.2 Excessive intake Investiastion Personnel whose normal work assignment exposes them to airborne radioactivity for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> a week will be included in a bioassay program to monitor for possible internal deposition. Should the bioassay results or other indicators suggest a significant internal deposition which would cause an individual to exceed the annual limit of intake, an investigation shall be performed. The investigation may include analysis of special urine specimens and/or in-vivo counts.
Indicators of potential internal deposition include:
i 1.
Elevated air samples.
2.
Skin or clothing contamination.
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3.
Contamination on interior surfaces of respirator face pieces.
4.
Nasal smears in excess of 150 dpm.
5.
Open injuries occurring in a contaminated, radioactive materials area.
6.
Exposure to a radioactivity concentration which exceeds the guidelines for the respiratory equipment worn.
7.
A significantly elevated urine specimen.
i' 8.
A significantly positive lung or whole body count.
The investigation (as to the possible source and cause) shall be conducted by Health Physics, and a report shall be issued. Any resulting diagnostic evaluations shall be performed utilizing established models.
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EMF-30, Chapter 2 Revision 15 Page 40 5.3.2.1 Urinalysis Employees shall be scheduled for routine urine sampling when their routine work schedule normally requires them to spend greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of their time in a contaminated radioactive materials area a week. The urine sample should be submitted when returning to work following two days off and prior to entering a contaminated area. The urine sample may be collected prior to arrival on the job or in a clean restroom when returning to SPC.
In addition to the routine sampling program, special samples may be required as a part of an incident investigation or as a followup of an elevated result from the routine sample program.
The urinalysis program is designed to investigate situations in which the kidneys could suffer adverse health effects and to take corrective action when appropriate. Action and action levels are established by Health Physics and are contained in EMF-1507,2.3.
5.3.2.2 In Vivo (Luna Count for Fuel Fabrication Personnel or Whole Body Count for Personnel Workino with Fission or Activation Products)
All new employees when hired, who have previously handled radioactive materials, shall receive an in-vivo examination. All personnel who had work assignments in a contaminated area shall be scheduled for in-vivo examination at termination (contractor employees at job completion).
Employees shall be scheduled for lung or whole body counts annually when their normal work assignments during the preceding 12 months were in contaminated radioactive materials areas >4 hours per week.
In addition to the routine counting program, special counts may be scheduled as a part of an incident investigation or a followup to an elevated result from the routine sampling program.
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Revision 15 Page 41 l
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Actions and action levels are established by Health Physics and are contained in EMF.
l 1507, 3.3.
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5.4 Records and Reports i
Data records required shall be retained indefinitely, or until release is authorized by f
t Regulatory Compliance.
In addition to, and/or in-line with the documentation requirements specified in other
'f sections of the Chapter and 10 CFR 20.2102 and 10 CFR 20.2103, the following records are
{
retained 1.
HSTs Radiation and Contamination Surveys, including room and exhaust air monitoring.
2.
Environmental Surveillance Data and Waste Discharge Reports.
i 3.
Incident Investigation Reports.
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4.
Facility and Process Acceptance Tests.
l 5.
Radiological Safety and Health Physics Component inspection Reports.
6.
ALARA Committee Reports, j
7.
Criticality Dosimeter inspection Reports, f
8.
Reports of Test Results for the Criticality Accident Alarm System.
9.
Reports of Test Results for the Emergency Electrical Power Supply System.
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10.
Radiation Detection Instrument Maintenance and Calibration, also for the Neutron Detectors of the Criticality Accident Alarm System.
11.
Results of Sealed Source-Leak Checks.
12.
HVAC System Monitoring and Test Results.
13.
Engineering Change Notices (ECN).
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EMF-30, Chapter 2 Revision 15 Page 42 5.4.1 Employee Records Exposure records pertaining to each SPC employee who receives occupational exposure shall be maintained by Radiological Safety. Each individual's folder for whom records are maintained should include:
1.
The date(s) of bioassay and external radiation measurement.
2.
The identity of the individual to whom it applies.
3.
The method by which the result was obtained so that the result can be recalculated.
4.
Prior employment exposure history obtained in accordance with 10 CFR 20.2104.
5.
Exposure' received occupationally, including that received at other installations during current employment (Form NRC-4). These records must include where applicable:
a.
The deep-dose equivalent to the whole body, eye dose equivalent, shallow-dose equivalent to the skin, and shallow-dose equivalent to the extremities; and b.
The estimated intake or body burden of radionuclides (see 10 CFR 20.1202); and c.
The committed effective dose equivalent assigned to the intake or body burden of radionuclides; and d.
The specific information used to calculate the committed effective dose equivalent pursuant to 10 CFR 20.1204(c); and e.
The total effective dose equivalent when required by 10 CFR 20.1202; and f.
The total of the deep-dose equivalent and the committed dose to the organ receiving the highest total dose.
6.
Special dose evaluations.
7.
Reports of unusual exposure or incidents.
8.
Other data having a bearing on the individual's exposure status.
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EMF-30, Chapter 2 Revision 15 Page 43 9.
Records of radiation protection training received.
The results of the exposure measurement program which identify an individual shall be considered privileged information, and shall be available only to personnel having need of them in the performance of their duties and to the individual involved. The release of this information to others will be permitted only upon specific prior approval of the individual, his authorized agent (when required by law), by the NRC, or by the State.
5.4.2 Proaram Records Records which describe or support the scope, depth, and quality of the radiation protection program shall be accumulated and maintained for a minimum of three years by the Health Physics Component. These records shallinclude:
1.
Radiation protection policies and procedures.
q 2.
Procedures and methods for control, interpretation, and evaluation of individual exposure.
5.4.3 Reports in addition, and/or in-line with the record requirements specified above, the following reporting schedule shall be adhered to.
1.
Employee, former employee, or terminating employee radiation exposure information shall be reported to individuals in accordance with 10 CFR 19.13.
2.
Employee exposures and monitoring information shall be reported to the NRC in accordance with 10 CFR 20.2206(b)(c).
3.
Overexposures and excessive levels and concentrations shall be reported to the NRC in accordance with 10 CFR 20.2203.
4.
The NRC sh'all be notified of incidents in accordcnce with 10 CFR 20.2202 and 10 CFR 70.50.
EMF-30, Chapter 2 Revision 15 Page 44 5.
Theft or loss of licensed material shall be reported in accordance with 10 CFR 20.2201.
6.
Effluent monitoring information shall be reported to the NRC in accordance with 10 CFR 70.59.
7.
In the event that the radioactivity in plant gaseous effluents exceeds 50 pCi per calendar quarter, a report shall be submitted within 30 days to the NRC (Director, Office of Nuclear Material Safety and Safeguards), with a copy to NRC-Region V identifying the cause for exceeding this value, and the corrective actions to be taken to reduce release rates.
8.
If parameters important to dose assessment of the public relative to gaseous effluents from the plant change, a report shall be submitted to the NRC (Director, Office of Nuclear Material Safety and Safeguards), with a copy to NRC-Region V within 30 days identifying the changes in parameters, and providing an estimate of the resultant change in dose commitment.
9.
Reports of excessive radioactive contamination on packages of radioactivo material and excessive radiation levels external to the packages on receipt shall be reported to the NRC immediately in accordance with 10 CFR 20.
10.
Accident reports on transportation of licensed material shall be reported in accordance with 49 CFR 171.15, and 49 CFR 171.16.
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EMF-30, Chapter 2 Revision 15 Page 45 6.0 TRAINING Radiological Safety shall provide radiological safety training to all employees.
6.1 New Employee Orientation l
All persons who are allowed unescorted access to plant areas shall receive new employee
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orientation for radiation safety (at the same time orientation is given for criticality and industrial I
safety).
New employee indoctrination should include the topics listed below as appropriate for their positions. Emphasis for the new employee shall be on the meaning of the required radiation safety postings.
1.
The basic meaning of the radiation safety postings that may be encountered.
(
2.
The limitations of the scope of work that may be performed until additional training
[
is required.
3.
How to identify operations and areas of plants that require additional training.
4.
Regulatory limits concerning dose.
6.2 Radiation Worker Trainina Upon completion of the classroom training, an examination shall be given for the purpose of enhancing the retention of the material presented, and to determine the effectiveness of the
)
training. All incorrect answers shall be resolved between the trainee and instructor prior to completion of training. At the completion of training, each trainee shall sign a statement that j
he/she has received the instruction.
6.2.1 Freauency j
All persons listed to receive radiation worker training per Section 6.2 shall receive such training prior to entering a contaminated, radioactive material area without an escort, and shall receive refresher or radiation worker training annually.
I EMF-30, Chapter 2 Revision 15 Page 46 6.2.2 Content Radiation worker training may cover the following subjects:
1.
Radiation hazards (working with radioactive materials as outlined in Regulatory Guide 8.29).
2.
The meaning / definition of areas and their radiation postings.
3.
Each person shall be trained in, and shall demonstrate to the instructor, the ability to perform a personal survey for contamination.
4.
General and special RWPs and their location in the workplace for reference.
Special requirements for handling, moving radioactive material and contamination 5.
control.
6.
. Instructions on use and testing of respiratory protection equipment.
7.
Response to alarm signals.
8.
Change room procedures.
9.
Urinalysis / bioassay requirements.
10.
Emergency plan and response.
11.
The need to consult an HST when confronted with a problem regarding radiation / contamination control or personal dosimetry.
12.
Notification that personal radiation exposure reports may be requested from Radiation Safety.
13.
Instruction on their responsibility to report promptly to their supervisor and Radiological Safety, any condition which may lead to, or cause a violation of NRC regulations, or the license, or unnecessary exposure to radiation or radioactive
~
material (10 CFR 19.12).
14.
Notification that the worker, or his/her representative, may request an inspection by the NRC if he believes an NRC regulation or license condition violation exists or has occurred (10 CFR 19.16).
O l
4 I
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~ EMF-30, Chapter 2 j
Revision 15 Page 47 i
t
'i Refresher training shall cover problem areas and general subjects at the discretion of the j
instructor.
l The format of the radiation worker training, refresher training class, and the test, shall be reviewed and approved by the Health Physics Component.
l i
6.3 Prenatal Exposure Training All female employees requiring radiation worker training shall receive instruction in the possible health risks to the unborn child of pregnant women who are exposed to radiation during pregnancy. Persons who receive this instruction shall acknowledge, in writing, that the instruction has been received. These acknowledgements shall be maintained indefinitely by i
Employee Relations. Normally, the instruction and acknowledgement shall be completed at the time of new employee orientation or radiation worker training.
8.4 Radiation-Producing Devices l
No employee shall operate radiation-producing devices unless he/she has been qualified and registered with the State as an Operator for the specific machine to be operated. Annual f
re-qualification on each machine used is required. Authorized operators are listed on the specific l
RWP.
l t
The training standards for an employee whose assignment requires operation of a radiation-producing machine are:
I 1.
The employee must have received radiation worker training.
i 2.
The employee must be instructed in, and demonstrate a knowledge of the f
applicable RWPs, and meet the requirements of WAC-402-36-100 and/or WAC-l 402-40.
l 3.
Minimum subjects to be covered in training radioaraphers are listed in WAC 402.
l 36-160. The training course outline shall be approved by the Health Physics Component.
l t
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EMF-30, Chapter 2 Revision 15 Page 48 4.
This training must be documented annually by passing a written test approved by the Health Physics Component.
6.5 Health and Safety Technician Trainino HSTs are given special training related to their radiation protection assignment. Previous training is accepted if considered equivalent to the SPC training program. Despite previous acceptable training, the HSTs are required to become proficient in SPC radiation protection and criticality safety programs, criteria, specifications, procedures, and routines as demonstrated by successfully passing an SPC certification examination within six months after attaining the Radiation Monitor 111 level. The certification examination shall be approved by the Supervisor, Radiological Safety, and the Health Physics Component. In addition, refresher training will be provided to HSTs at least annually. Details of the HST training are contained in EMF-1507,1.3.
B
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EMF-30, Chapter 2 Revision 15 Page 49 7.0 SHIPPING AND RECEIVING RADIOACTIVE MATERIALS t
Shipments of radioactive material shall conform to applicable regulations of the NRC, the U.S. Department of Transportation, the U.S. Post Office, the Washington Utilities and
(
Transportation Commission, and the International Atomic Energy Agency.
j The radiological safety aspects of shipping and receiving radioactive materials are -
addressed in EMF-30, Chapter 5, " Radioactive Material Shipping Standard."
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EMF-30, Chapter 2 Revision 16 Page 50 8.0 REPORTING OF INCIDENTS t
8.1 Responsibility i
it is the responsibility of each employee to report immediately to his supervisor (or designee) any incidents related to radiation safety. Such incidents include a fire, explosion, contamination, failure of safety equipment or release or theft of radioactive material.
The Manager, Regulatory Compliance has the responsibility to report such incidents occurring at SPC's Engineering and Manufacturing Facility to regulatory agencies in accordance with the criteria detailed herein. The Richland Plant Manager should be notified of the intent to make such reports.
8.2 Evaluation and Documentation s
The supervisor or on-shift Health & Safety Technician (HST) shall document the information reported to him on the " Radiation incident Corrective Action Report" (RICAR) form (see Appendix 1) by filling out the information through the " Description of incident or Condition" block and signing the " Originator's Signature" block. The descriptive information supplied by the supervisor or employee shall include:
1.
A description of the incident including the time and date; 2.
The exact location of the incident; 3.
The quantity and description of the radioactive materialinvolved; 4.
Any personnel exposure data available, if applicable; and 5.
Any other readily apparent consequences of the incident, e.g., facility / equipment contamination, environmental release, etc.
He shall then submit the form to Radiological Safety. The Supervisor, Radiological Safety (or his designee) shall immediately conduct an evaluation to determine if the incident is s
EMF-30, Chapter 2 Revision 16 Page 51 reportable to the U.S. Nuclear Regulatory Commission (NRC) or the State of Washington using the criteria given in Sections 8.4 and 8.5. If the Supervisor, Radiological Safety determines that the incident is reportable to either of these agencies or is unsure, he shall immediately report the incident to Safety, Security and Ucensing as noted in 8.3.
[ Note: The originator of the RICAR may have incident or abnormal event reporting requirements within his line organization. In any event, either the supervisor to whom the incident was reported or the Supervisor, Radiological Safety must immediately notify one of the persons listed in 8.3 if the incident is reportable to an outside agency or if there is uncertainty as to its reportability.]
Once the Supervisor, Radiological Safety has orally reported the incident to Safety, Security and Ucensing or it is clear that the incident is not reportable to outside agencies, he shall complete the RICAR which shall include:
1.
Determination of reportability; 2.
Confirmation of report (if reportable);
3.
Emergency Plan implications; 4.
Immediate and long-term corrective actions (if applicable); and 5.
Root cause (if applicable)
Copies of the RICAR shall be submitted to the Supervisor, Safety; the Manager, Regulatory Compliance; the Manager, Safety, Security and Ucensing; the Health Physicist, and within the originating supervisor's line organization as appropriate.
8.3 Notification of Safety. Security and Licensina One of the following individuals shall be contacted immediately for a reportable event.
If the first on the list is not available, go to the next person on the list and so on.
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EMF-30, Chapter 2 j
Revision 16 i
Page 52 i
1.
Health Physicist j
2.
Supervisor, Safety j
3.
Manager, Safety, Security and Ucensing 4.
Manager, Regulatory Compliance 5.
Staff Engineer, Licensing 6.
Environmental Engineer 7.
Criticality Safety Specialist
'i if none of the above individuals is available on plant, use the " Quick Reference Section" of the emergency plan, EMF-32, Part 11, to find home phone and/or pager numbers. If a member j
of the above list cannot be reached, immediately contact the Plant Emergency Director (also j
found in the " Quick Reference Section of EMF-32) and report the event.
l The person who is notified regarding a reportable incident pursuant to this section shall
. immediately conduct a further evaluation using the criteria in Sections 8.4 and 8.5 to confirm the reportability of the incident. If the incident is confirmed as reportable, the Manager, Regulatory
-l Compliance or his delegate shall be notified immediately.
8.4 Reportina to NRC i
i i
S.4.1 Telephone Report to NRC j
When informed of a confirmed reportable incident, the Manager, Regulatory Compliance or his delegate shall notify the NRC of the incident by telephoning the NRC Operations Center on (301) 816-5100 [ backup no. is (301)951-0550] and inform them that he is reporting a radiological incident as required by 10CFR20.2201,10CFR20.2202 or 10CFR70.50. He should be prepared to provide SPC's NRC license and docket numbers (SNM-1227 and 70-1257,-
respectively) and should request the report number assigned by the NRC. The following incident information shall be provided:
s EMF-30, Chapter 2 Revision 16 Page 53 1.
The caller's name and call back number; 2.
A description of the incident including the time and date; 3.
The exact location of the incident; 4.
The isotopes, quantities, and chemical and physical forms of the licensed material involved; 5.
Any personnel radiation exposure data available; and 6.
Assuming such is the case, it is important to inform the NRC that the situation is currently under control.
Incidents such as fires, explosions, or releases of toxic gases, any of which prevent immediate (within 15 minutes) protective actions necessary for radiation safety, must be reported as soon as possible but not later than four hours after discovery of the incident incidents of less serious consequences such as a contamination event, a failure of safety equipment, an event damaging to licensed material or an unplanned medical treatment of an individual with spreadable contamination must be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery. See Section 8.4.3 for further discussion of reporting criteria.
8.4.2 Written Report to NRC A written followup report of the incident shall be prepared and submitted to NRC by the Manager, Regulatory Compliance within 30 days of the initial report. That report shallinclude the following information:
1.
A description of the incident including the probable cause and manufacturer and model number of any equipment that failed or malfunctioned; 2.
The exact location of the incident; 3.
The time and date of the incident; 4.
The isotopes, quantities and chemical and physical form of the licensed material involved; O
l i
EMF-30, Chapter 2 Revision 16 Page 54 l
l 5.
Corrective actions taken or planned and the results of any evaluations or assessments; and
{
6.
The extent of exposure of individuals to radiation or radioactive materials.
i This information can be derived from the Radiation Incident Corrective Action Report.
Reports filed with the NRC pursuant to this subsection shall include (for each individual i
L exposed) the name, social securfy number, date of birth, and an estimate of the individual's i
exposure. Such information shall.3 stated in a separate part of the report.
{
The written report shall be submitted to:
l U.S Nuclear Regulatory Commission.
I Document Control Center Washington DC 20555
[
-l with copies to:
U.S Nuclear Regulatory Commission, Region IV l
Attn: Regional Administrator i
611 Ryan Plaza Drive, Suite 400 l
Arlington TX 76011-8064 l
t and f
U.S Nuclear Regulatory Commission
[
Walnut Creek Field Office 1450 Maria Lane, Suite 210 l
Walnut Creek, CA 94596 Copies of such reports shall be distributed internally to:
(
1.
Each affected employee f
2.
Supervisor, Radiological Safety f
3.
Health Physicist 4.
Supervisor, Safety f
5.
Manager, Safety, Security, and Licensing
EMF-30, Chapter 2 Revision 16 Page 55 6.
Affected Department Manager 7.
Richland Plant Manager 8.4.3 Criteria for incidents Reportable to NRC (per 10 CFR 70.50 and 20.2201 and 20.2202) 8.4.3.1 incidents Reauirina immediate (<4 hours) Notification 1.
Incidents that prevent immediate (within 15 minutes) protective actions necessary^
to avoid either exposure to radiation or radioactive materials or releases of licensed material that could exceed regulatory limits must be reported to NRC as soon as possible, but not later than four hours after discovery. Such incidents include but are not limited to fires, explosions, and releases of toxic gases.
2.
Immediately report any event involving by-product, source, or special nuclear material possessed by the licensee that may have caused or threatens to cause any of the following conditions -
a.
An individual to receive -
(1)
A total effective dose equivalent of 25 rems (0.25 Sv) or more; or (2)
An eye dose equivalent of 75 rems (0.75 Sv) or more; or (3)
A shallow-dose equivalent to the skin or extremities of 250 rads (2.5 Gy) or more; or b.
The release of radioactive material,inside or outside of a restricted area, so that, had an individual been present for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the individual could have received an intake five times the annual limit of intake (the provisions of this paragraph do not apply to locations where personnel are not normally stationed during routino operations, such as hot-cells or process enclosures).
1 9;
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EMF-30, Chapter 2 (k'
Revision 16 Page 56 3.
Immediately after its occurrence becomes known, any lost, stolen or missing licensed material in an aggregate quantity equal to or greater than 1,000 times the f
quantity specified in appendix C to 10CFR 20.1001-20.2401 under such circumstances that it appears that an exposure could result to persons in unrestricted areas.
4.
Release of radioactive material whose 24-hour averaged concentration exceeds 42 8.3X10 pCi U/mi for environmental air, to a member of the general population. '
Appendix 2 to this chapter provides examples of incidents requiring immediate notification to the l
NRC.
8.4.3.2 Incidents Reauirino 24 Hour Notification LJ 1.
An unplanned contamination incident which results in restricted access to the contaminated area by imposing additional radiological controls or prohibiting entry to an area for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and involves a quantity of material greater than five times the lowest annual limit of intake specified for the material.
2.
A failure or malfunction of equipment required by regulation or license condition to prevent releases exceeding regulatory limits, to prevent exposures to radiation and radioactive materials exceeding regulatory limits or to mitigate the consequences of an accident. To qualify as reportable the equipment must fail or malfunction at the time it is needed and there must be no redundant equipment available.
3.
An unplanned medical treatment at a medical facility of an individual with 2
spreadable contamination (in excess of 200 dpm/100cm alpha or beta-gamma).
l 4.
An unplanned fire or explosion causing damage which affects the integrity of any
(
)
licensed material or container of licensed material, and.the quantity of material 1
EMF-30, Chapter 2 Revision 16 Page 57 involved is greater than five times the lowest annual limit of intake specified for the material.
l 5.
Any event involving loss of control of licensed material that may have caused, or threatens to cause, any of the following conditions:
a.
An individual to receive, in a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> -
i (1)
A total effective dose equivalent exceeding 5 rems (0.05 Sv): or j
(2)
An eye dose equivalent exceeding 15 rems (0.15 Sv); or I
(3)
A shallow-dose equivalent to the skin or extremities exceeding 50 rems (0.5 Sv); or b.
Tne release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the individual could have received an intake in excess of one occupational annual limit on intake (the provisions of this paragraph do not apply to locations where personnel are not normally stationed.
[ Note: The "de minimis" (non reportable) amount of material involved in 1 and 4 above allowed by the regulation; i.e.,5 times the lowest annual limit of Appendix B of Part 20, is a very small quantity. For 3.0 wt% enriched uranium the de minimis amounts of material involved are shown below)
Non-Reportable Quantities for CFR 70.50 3.0 wt% Enriched Uranium Compounds De Minimis Amount, grams U UO, U 0 0.1 2
3 s UO, UF,, UCL 2.5 3
4 UF, UO F, UO (NO )2 3.2 6
p2 p
3
~_
4 EMF-30, Chapter 2 Revision 16 Page 58 Appendix 2 to this chapter provides examples of incidents requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the i
NRC.
L 8.5 Reportina to the State of Washinaton I
8.5.1 Telephone Report to the State of Washinaton When informed of a confirmed reportable incident, the Manager, Regulatory Compliance or his delegate shall notify the State of the event by telephoning the Department of Health's Division of Radiation Protection at (206) 682-5327. The following information should be provided:
1.
The caller name and call back number; 2.
A description of the event including the time and date; 3.
The exact location of the event; 4.
The isotopes, quantities, and chemical and physical form of the licensed material involved; and 5.
Any personnel radiation exposure data available.
]
6.
Assuming such is the case, it is important to inform the State that the situation is j
currently under control.
]
8.5.2 Written Report to the State of Washinaton The Manager, Regulatory Compliance, when required to make a telephone report, shall submit a report in writing (within 30 days of the occurrence of the incident) to the State of Washington. The report shallinclude:
1.
Description of the extent of exposures of persons to radiation or to radioactive material, including estimates of each individual's exposure.
2.
Levels of radiation and concentrations of radioactive material involved.
3.
The cause of the exposure, levels, or concentrations.
EMF-30, Chapter 2 Revision 16 Page 59 4.
Corrective steps taken or planned to assure against a recurrence.
Reports filed with the State pursuant to this sub-section shall include, for each individual exposed, the name, social security number, date of birth, and an estimate of the individual's exposure. Such information shall be stated in a separate part of the report.
The written report shall be submitted to:
Washington State Dept. of Health Division of Radiation Protection Mail Stop LE-13 Olympia, WA 98504 i
Copies of such reports shall be distributed internally to:
1.
Each affected employee 2.
Supervisor, Radiological Safety 3.
Health Physicist 4.
Supervisor, Safety 5.
Manager, Safety, Security, and Ucensing 6.
Affected Department Manager
- 7..
Richland Plant Manager l
i 4
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EMF-30, Chapter 2 k
Revision 16 Page 60 8.5.3 Criteria for Reportable incidents to Washinaton State foer WAC-246-221-240 and 250) 8.5.3.1 incidents Raouirina Im.TM'_; (<4 hours)" Notification i
Washington State shall be notified within four hours by telephone at (206) 682-5327 of any incident involving radioactive material possessed by the Company, and which may have caused l
t or threatens to cause:
1.
External radiation exposure to any individual or dosimeter assigned to an l
individual equal to, or in excess of the following values:
i a.
25 rems to the whole body; b.
150 roms to the skin of the whole body; or c.
375 rems to the feet, ankles, hands, or forearms.
2.
Release of radioactive material whose 24-hour averaged concentration exceeds 4
1.5X10 pCi U/mi for environmental air, or 1.5X10'1 pCi U/mi for environmental water at the SPC site boundary.
i 3.
A loss or theft of such quantities under such circumstances that a substantial hazard to persons in unrestricted areas may result.
i Appendix 2 to this chapter provides examples of incidents requiring immediate notification to the i
i State of Washington, j
i i
The NRC defines immediate notification es "as soon as possible, but not later than fo ur hours." The assumption here is that the State agrees with this definition, a
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w.-
-,-..----..n-._
EMF-30, Chapter 2 Revision 16 Page 61 8.5.3.2 Incidents Reauirina 24-Hour Notification Washington State shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone (206) 682-5327 of any incident involving radioactive material possessed by the Company, and which may have caused or threatens to cause:
1.
External radiation exposure to any individual or dosimeter assigned to an individual equal to, or in excess of the following values:
a.
5 rems to the whole body; b.
30 rems to the skin of the whole body; or c.
75 rems to the feet, ankles, hands, or forearms.
2.
Release of radioactive material whose 24-hour averaged concentration exceeds 4
1.5X10~8 pCi U/mi for environmental air, or 1.5X10 pCi U/mi for environmental water, at the SPC site boundary.
Appendix 2 to this chapter provides examples of incidents requiring 24-hour notification to the State of Washington.
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EMF-30, Chapter 2 Revision 15 Page 62 i
4 Appendix 1 RADIATION INCIDENT
"%,BUTION:
DISTRI r S.S. a t Siemens Power Corporation CORRECTIVE ACTION REPORT M'"*L"T.wr, =hano.
C Nuclear D...nnsion oeDt An NO.
Saw sVDermor Actoness assemeATm s sinnes DATE or nasant DATuvasE m:aDEw on cONDrTICDs usAs DSCOVERED E NNDrfoe DEacsePfo.OF PCOENT OR CONDrf or weseig benee and Domesuneen of hedenew m m ?
W Dean W asamme ene siseer aspescat C a
(See Crnena n EMF.30 ChaDier 2 Secten 8)
POTENTtALLY REPORTABLE TO NRC OR STATE 7 YES CNO lF YES, NOTIFY SS&L IMMEDIATELY s a ab sf AFf MEMBER CONI ACTED DATE TIME SS&L DETEAM.NED EVENT l$
REPORTAeJ TO NR:: oR $T ATE?
YES NO STATE RE* ORT NO.
DATE & TIME NA0AfPDATNo sIEDOATED (See Cinens n EMF-30 Chapter 2 Secten 8)
PLANT EMERGENCY DIRECTOR CALLEDt C YES NO EMERGENCY PLAN IMPLEMENTED?
YES NO ACTION IMMEDIATE ACTIONS TAKEN TAKEN BY 1
9 OseGie:ATOR s SouATL5tE APPROVED 9Y MEA.Toi Pwy scs?
$ 18 COWnN1KD QPERATION P8u0R TO ADDITICreAL CORREDTivt A0 TION JU$TIFIED'IF YES. EXPLAIN WW v
$ COefrielutD DPERATch AP8440VED SV DEPARTMENT anANAGER
$ CONTINUED OPERATiose A*PaovtD ev asAseAGER $$&L
- samamEDsom Au rms:TeenT Amt PorternAuv st*onTED Totog esRc om sf ATE sec.No massa pvD:yez
3 EMF-30, Chapter 2 Revision 15 Page 63 Apoendix 1 (Cont.)
RADIATION INCIDENT CORRECTIVE ACTION REPORT (cont.)
PROBABLE ROOT CAUSE:
I j DATE TO BE ACTIONE E I COMPLETED BY LONG TEAM CORAECTh/E ACTIONS TAKEN TO PAEVENT AEOCCUARENCE s
0 st' SPCJc; 3330.seeA IMCK Pv0393
I EMF-30, Chapter 2 i
Revision 15 l
Page 64 Appendig 3
' i' Below are examples of incidents requiring immediate (<4 hours) and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification.
immediate (<4 Hour) Nei;TE="-:n l
A fire in a control room which prevents access for more than 15 minutes to needed safety equipment.
A release of UF through a cylinder valve which prevents personnel from s
immediately (within 15 minutes) closing the valve.
An explosion which prevents access to needed safety equipment.
l These examples must involve radioactive material and the possibility of exceeding regulatory I
limits.
24 Hour Notification A spill of uranium which cannot be adequately cleaned up in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or one that requires the use of additional respiratory protection or additional protective clothing for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
~
Contamination from a leaking container which requires a normally unrestricted -
l area to be isolated or classed as a restricted area for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Damage to a HEPA filter bank that results in stack concentrations exceeding j
license limit.
A UF vaporization room scrubber that fails when required to control a UF
)
s s
i release and there is no backup system.
i A person is burned and contaminated by a hot acidic uranyl nitrate solution I
resulting in removable contamination and is taken directly to the hospital.
j A low level waste barrel containing cleaning paper saturated with nitric acid that
~
undergoes spontaneous combustion resulting in an explosion which damages the
)
waste container.
)
4ll-3My'y""nn SIEMENS
i EMF-91-198 1990 ALARA COMMITTEE REPORT OCTOBER 1991 Siemens Nuclear Power Corporation 0