ML20236J490

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Notification of Licensee Meeting 87-095 on 870722 W/Util in King of Prussia,Pa to Discuss Licensee Program to Control Contaminated Matl Outside Radiation Controlled Area
ML20236J490
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 07/15/1987
From: Elsasser T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
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NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
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-_ _ _ _ _

lJ E

i 1

ENCLOSURE l'

+

f.

t No.87-095 l

U.S. NUCLEAR REGULATORY COMMISSION REGION I NOTICE OF LICENSEE MEETING.

JUL 15 1987

'Name of Licensee:

Vermont Yankee Nuclear Power Corporation Name of Facility:

Vermont' Yankee Nuclear Power Station

-Docket No.:

50-271 Time and Date of Meeting:

1:00 p.m.

July 22, 1987 i

Location of Meeting:

NRC Region I Office, King of Prussia, PA (8th Avenue Conference Room)

Purpose'of Meeting:

Management meeting to discuss licensee program to control contaminated material outside RCA.

NRC Attendees:

S. Collins, Deputy Director, DRP E. Wenzinger, Chief, Projects Branch No. 3, DRP R. Bellamy, Chief, Emergency Preparedness.and Radiological Protection Branch, DRSS T. Elsasser, Chief, Reactor Projects Section 3C,.ORP M. Shanbaky, Chief, Facilities Radiation Protection Section, DRSS

0. Haverkamp, Project Engineer, DRP J. Cioffi, Radiation Specialist, DRSS Licensee Attendees:

J. Pelletier, Plant Manager R. Wanczyk, Operations Superintendent R. Leach, Radiation Protection Supervisor R. Morrissette, Plant Health Physicist Note:

Attendance by NRC personnel at this meeting should be made known by 4:00 p.m., July 20, 1987 via telephone call to T.C. Elsasser, Region I, at FTS,8-488-1378 or 215-337-5378.

//

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T.C. Elsasser,) Chi [f, RPS 3C UD d

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t ENCLOSURE 2 1

U.S. NUCLEAR REGULATORY COMMISSION REGION I MEETING

SUMMARY

' Docket. No. :

iG-Al '

License No.:

DPR-28

. Licensee:

Vermont. Yankee Nuclear Power Corporation RD.5,LBox-169-

. Ferry Road Brattleboro. Vermont 05301 Facility Name: Vermont Yankee Nuclear Power Stat' ion-

. Purpose of Meeting:' Management Meeting to Discuss Licensee Program to Control Contaminated Material Outside RCA Introduction-A. meeting was held at the NRC Region I Office on July 22, 1987 at 1:00 p.m.

The meeting was1 requested by Vermont Yankee Nuclear Power Corporation, as discussed in NRC Inspection Report 50-271/87-09.

NRC Attendees E..Wenzinger, Chief, Projects Branch No. 3, Division of. Reactor Projects (DRP)

T. Elsasser, Chief, Reactor Projects Section'3C, DRP M. Shanbaky, Chief, Facilities Radiation Protection Section, Division'of Radiation Safety and Safeguards (DRSS)

D. Haverkamp, Project Engineer, DRP J. Cioffi, Radiation Specialist, CRSS

- C. Carpenter, Reactor Engineer, DRP Vermont Yankee Nuclear Power Corporation l-.

J. Pelletier, Plant Manager R.- Wanczyk, Operations Superintendera l

R. Leach, Radiation Protection Supsr/isor l-R. Morrissette, Plant Health Physicist' Summary

);

1.

The licensee discussed recent incidents in which contaminated material was

~

found outside the Radiation Controlled Area, the actions'they took to identify the source of'the problems, and corrective actions to prevent their recurrence.

I i

2 2.

The licensee discussed the requirements for surveying potentially radioactive solid waste materials prior to disposal from nuclear reactor facilities and the administrative release limits established by Vermont Yanke,e Nuclear Power Corporation.

3.

The licensee also discussed recent findings of " hot particles" at Vermont Yankee and the precautions that will be taken at Vermont Yankee to avoid hot particle contamination.

4. summarizes the presentation given by Vermont. Yankee Nuclear Power Corporation.

Commitments 1.

The licensee will evaluate the appropriateness of revising the frisking policy of people leaving the RCA.

The change under consideration is to identify use of the PCM-1B as the required (vice preferred) method.

2.

The licensee will evaluate revising the radiation worker initial and periodic training programs to include increased emphasis on contaminated material con-trol policies and procedures.

3.

The licensee will evaluate revising (or initiating) radiation protection pro-cedures for control of work in accessible tanks located in the RCA.

4.

The licensee will evaluate the " hot particle" program at another boiling water reactor facility to assess the need for program enhancement at Vermont Yankee.

5 l

\\

ENCLOSURE 3 VY/NRC MEETING TO DISCUSS DISCOVERY OF CONTAMINATED MATERIAL OUTSIDE THE RCA JULY 22, 1987 NRC REGION 1 OFFICES KING OF PRUSSIA, PA.

I.

INTRODUCTION OF VY ATTENDEES II.

PURPOSE OF MEETING III.

OV5RVIEW OF VY POLICIES A.

.? RISKING B.

PCA EXITS IV.

DISCUSSION OF FINDINGS A.

DISCOVERIES B.

CORRECTIVE ACTIONS V.

SIgNIFICANCEOFDISCOVERIES VI.

DISCUSSION OF REGULATORY ISSUES / REQUIREMENTS VII.

SUMMARY

/ IDENTIFICATION OF OPEN ITEMS 1

VIII.

DISCUSSION OF OTHER ITEMS l

A.

ALARA PROGRAM STATUS B.

" HOT PARTICLES" C.

INTERNAL DOSIMETRY PROGRAM STATUS D.

REFUEL OUTAGE PLANS E.

DEPARTMENT REORGANIZATION I

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l ADMINISTRATIVE POLICIES INDOCTRINATION / TRAINING FRISKING WITHIN THE RCA FRISKING OUTSIDE THE RCA PRE-EXIT MONITORING I

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Sorted' Dumpsters checked a

BACKGROUND Less than 300 cpm'frelease from RCA)

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LEAVING THE RCA Q-

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People-frisk From contaminated area WB RM-14/HP-210 probe PCM-1B.(prefered)

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T From clean area H&F RM-14/HP-210 probe

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Leaving FICA from contaminated area

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p DEFENSE IN DEPTH-L JGENERALL 7

Administrative' policies on waste reduction Indoctrination Training

' : PRACTICE.

People who have not been in a contaminated area Hand and foot frisk RM-14/HP-210 probe-PCM-1B (prefered)

People.who have been in a contaminated area-Whole body frisk RM-14/HP-210 probe PCM-1B (prefered)

. MaterialL RM-14/HP-210. probe Bkg less'than 300 cpm Trash Sorted and' surveyed RM-11/HP-210 probe Bkg less than 300 cpm EXITING THE RCA Prop'erty pass needed o

Only. authorized Health Physics Technicians will. survey with RM-14/HP-210 probe.

All dumpster are' surveyed before release.

Property' pass issued AUTHORIZATION TO LEAVE SITE People Exit the site through a sensitive portal

' Material i

o security will insure a property pass is properly filled out, o

Exit from the site is through the personnel or truck portal.

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LEAVING THE' PROTECTED AREA Pre-Contamination Incidents c...

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1 I I l J 1 i l RESIN INCIDENT CORRECTIVE ACTIONS l I l i 1. All of the other dumpsters were surveyed. j 2. A Department Instruction was implemented on DP-4531. 3 The incident was reviewed with the entire RP Dept. at our weekly meeting. . _, - - - - - - ~ _s,.-4_ .._--a----

f HAMMER' INCIDENT CORRECTIVE ACTIONS

1. A complete survey of the construction warehouse, and tool storage

. trailer was initiated.

2. The contractor's offsite fabrication shop was surveyed.
3. The frisking policy was changed requiring an additional frisk in a background of less than 100 cpm for all items leaving site, or stored outside the RCA.
4. The incident was reviewed at the RP Dept. weekly meeting.

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l j .~ INSULATION INCIDENT CORRECTIVE ACTIONS 1

1. The number of exits from the RCA were reduced.
2. The remaining exits are manned by Prisker Watchera.
3. All the exits are sealed during the off normal hears, except for the exit located at the RP control point.
4. The Plant Manager held a meeting with all plant personnel.
5. The incident was reviewed at the weekly meeting of the RP Dept.
6. A tagging program was established on all trash leaving the RCA.

i i l l

L. DEFENSE IN DEPTH GENERAL Administrative policies on waste reduction Indoctrination Training PRACTICE People who have not been in a contaminated area j Hand and foot frisk RM-14/HP-210 probe PCM 1B.(prefered) People who have been in a contaminated area Whole body frisk RM 14/HP-210 probe PCM-1B (prefered) Material RM-14/HP-210 probe Bkg less than 300 cpm Trash Sorted and surveyed RM-14/HP-210 probe Skg less than 300 cpm Resurveyed after rebagged RM-14/HP-210 probe Bkg less than 100 cpm EXITING THE RCA Property pass needed o' only authorized Health Physics Technicians will survey with RM-14/HP-210 probe. o Bkg less than 100 cpm All dumpsters are surveyed before release. Property pass issued AUTHORIZATION TO LEAVE SITE People Exit the site through a sensitive portal Material o security will insure a property pass is properly filled out. 1 o Exit from the site is through the personnel or truck portal. LEAVING THE PROTECTED AREA i

REQUIREMENTS REG GUIDES (in effect) 1.86 Termination of Operating Licenses for Nuclear Reactors June 1974 8.21 Health Physics Surveys for Byproduct Material at NRC Processing and Manufacturing Plants. May 1978 Allows multiplying numbers by 5 for fixed contamination NUREGS (draft) 0613 Residual Radioactivity Limits for Decommissioning October 1979 Does not distinguish between fixed and loose. 49CFR 173.443 Contamination Control October 1986 Multiply numbers by 10 i TECH SPEC ] Ammendment 83 1983 Drief history NRC CIRCULAR _____==_ IEC 81-07 May 1981 I&E INFORMATION NOTICE IN 85-92 Dec 1985 j j INDUSTRY STANDARDS { Guidelines for Radiological Protection at Nuclear ,s.- 3tations Febuary 1985 )

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~=*;' d d u; c: j 1 TEC 81-07' May 14, 1981 Page 2 of 4

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~ ~. -Discussion: During routine operations, items (e.g., tools and equipment) and materials ~4 (e.g., scrap material, paper products, and trash) have the potential of becoming'slightly contaminated. Analytical capabilities are available to ' distinguish very' low levels of radioactive contamination from the natural background levels of radioactivity. However, these capabilities are often very elaborate, costly, and time consuming making their use impractical (and unnec'essary)'for routine operations. Therefore, guidance is needed to-establish operational. detection levels below which the probability of any remaining, undetected contamination is negligible and can be disregarded when considering the practicality of detecting and controlling such potential contamination and the associated negligible radiation doses to the public. In other words, guidance is needed which will provide reasonable assurance that contaminated materials are properly controlled and disposed of while at the 4 3 same time prov.iding a practical method for the uncontrolled release of materials e d' 'from the restricted area. These levels and detection capabilities must be set considering these factors:

1) the practicality of conducting a contamination survey, 2) the potential 'of leaving minute level's of contamination undetected;

) and, 3) the potential radiation doses to individuals of the public resulting from potential. release of any. undetected, uncontrolled contamination. 1 Studies performed by Sommers have concluded that for discrete particle low-level contamination, about 5000 dpm of. beta activity is the minimum level of activity that can be routinely detected under a surface contamination control program j using direct survey methods. The indirect method of contamination monitoring (smear survey) provides a method for evaluating removable (loose, surface) I contamination at levels below which it can be detected by the direct survey 2 method. For smears of a 100cm area (a de facto industry standard), the corresponding detection capability with a thin window detector and a fixed 2 ' sample geometry is on the order of 1000 dpm (i.e., 1000.dpm/100 cm ). Therefore, taking into consideration the practicality of conducting surface contamination J 2 surveys; contamination control limits should not be set below 5000 dpm/100 cm 2 total and 1000 dpm/100 cm resvable. Ti ability to detect minute, discrete SSIN No.: 6835 IN 85-92 I* UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 December 2, 1985 1 IE INFORMATION NOTICE N0. 85-92: SURVEYS OF WASTES BEFORE DISPOSAL FROM l NUCLEAR REACTOR FACILITIES I I Addressees: ~ All production and utilization facilities, including ~ nuclear power reactors and research and test reactors, holding an operating license (0L) or construc-tion permit (CP).

Purpose:

The purpose of this information notice is to' supplement the guidance of IE Circular 81-07 as it applies to surveys of solid waste materials before disposal from nuclear reactor facilities. It is expected that recipients will review the information for applicability to their facilities.

However, this information notice does not constitute NRC requirements; therefore, no

( specific action or licensee response is required. Description of Circumstance: Some questions have arisen concerning appropriate methods of surveying solid waste materials for surface contamination before releasing them as nonradio-active (i.e., as wastes that do not contain NRC-licensed material). Discussion: The need to minimize the volume of radioactive waste generated and shipped to commercial waste burial sites is recognized.by the NRC and industry. Some auclear power plan'ts have initiated programs to segregate waste generated in radiologically controlled areas. Such programs can contribute to the reduction in volume of radioactive waste; however, care should be taken to ensure that no licensed radioactive material is released contrary to the provisions of n 10 CF ion 20.301. In practice, no radioactive (licensed) material means ( no d tectab radioactive material, In 1981, IE Circular 81-07 was issued by the NRC. That circular provided guidance on the control of radioactively contaminated material and identified the extent to which licensees should survey for contamination. It did not establish release limits. The criteria in the circular that addressed surface contamination levels were based on the best information available at the time and were related to the detection capability of portable survey instruments i \\ 8511270325

1. Radioactive Contamination Limits Radioactive contamination is described in two ways. Fixed contamina-tion adheres tightly to a surface or can be embedded within the mate-i rial such as by neutron activation. Removable contamination adheres loosely to a surface and is easily transferred to other surfaces bi touching or by air currents. Fixed contamination can be tra,tsformed into removable contamination by activities such as welding, burning, or grinding on the material. Total contamination is the sum of the fixed and removable contamination measured on the surface of material. I Section 2 below describes techniques for measuring contamination in f areas or on material and for monitoring personnel for contamination. Areas should be posted and controlled as contaminated (see Section 2)- when removable contamination levels exceed 1,000 disintegrations per 2 minute (dpm)/100cm.of beta / gamma emitting radionuclides or 20 dpm/ 100cm2 of alpha emitting radionuclides. Equipment, materials, and tools should be labeled and controlled as radioactive (see Section 3) when removable plus fixed (i.e'.,' tot'al)^ 2 contamination exceeds 5000 dpm/100cm or removable contamination exceeds 1000 dpm/100cm'. 'These limits are for beta / gamma-emitting 2 total i radionuclides..For alpha-emitting radionuclides, 300 dpm/100cm 2 I and 20 dpm/100cm removable should be used. Internal surfaces that have been exposed to radioactive contamination should also meet these

  • limits.

{ Personnel should be considered contaminated and subject to the actions of Section 5 when total contamination on any portion of their body or , personal clothing exceeds 100 counts per minute (cpm) above background ~using a pancake GM detector and a count rate meter or an equivalently sensitive technique. Protective clothino with significant fixed contamination.(e.g., 50,000 dpm beta and ga6ma) should be laundered or disposed of as radioactive waste. This clothing should not be used against the body as it might j contribute to skin or clothing contamination. Respiratory protection equipment should be cleaned to less than 1000 dpm/100cm of removable contamination prior to reuse. Significant j 2 fixed contamination (e.g. 50,000 dpm beta and gamma) should be

-_=_-. 4 ALARA PROGRAM UPDATE Brief-History RAT Team audit after TMI no formal program no individual assigned primarily to ALARA Made an open item in 1982 several alternatives purposed Identified as concern in last two SALP reports position authorized in 1986 position filled Dec 1986 formal program established and procedures issued spring 1987 Goals Established Plant 450 man-rem Department individual Reports to support projected j status Man-Rem Projections for Each Job l Man-Rem Projections for each design change i ALARA Committee Membership Function o pre-job reviews for jobs projected.at greater than 10 l man-rem ) o review exposure reports o post job reviews Reporting lines l l 1 1 1 1 l l C.

llll L - 0 0 2 3 0 5 0 4 3 3 4 1 6 1 6 7 2 N 1 1 4 1 E 7 7 8 4 5 2 4 5 5 2 2 6 3 A - R 7 T - 1R O - 0 1 7 4 8 6 9 5 5 2 0 1 5 6 2 7 1 / T - 6 3 1 1 2 2 3 8 5 N e0 A V1 - = = = = = = = = = e = = = = = = = N E/ 2 R2 - 0 2 7 1 5 3 7 5 0 9 1 3 1 7 7 7 3 _ 8 6 2 5 8 4 6 7 0 0 0 8 0 6 0 1 1 1 _ 1 6 C - U 8 E _ D - 2 0 0 0 0 1 0 1 0 0 0 0 0 1 0 0 0 _ 1 3 _ 1 = L - 0 2 7 1 5 3 7 5 0 9 1 3 1 7 7 7 3 _ 8 A V - 6 2 5 8 4 6 7 0 0 0 8 0 6 0 1 1 1 _ 1 T O _ O N - 2 0 0 0 0 1 0 1 0 0 0 0 0 1 0 0 0 _ 1 T _ 1 - 0 2 7 1 5 3 7 5 0 9 1 3 1 7 7 7 3 _ 8 6 2 5 8 4 6 7 0 0 0 8 0 6 0 1 1 1 _ 1 T - C _ O - 2 0 0 0 0 1 0 1 0 0 0 0 0 1 0 0 0 _ 1 _ 1 - 0 0 0 6 0 0 3 4 0 4 1 5 3 0 3 0 3 _ 2 0 8 5 5 9 2 9 3 7 5 2 9 5 6 1 1 _ 1 P - 1 E -. S - 7 9 3 5 6 5 3 8 2 0 0 0 2 2 0 5 0 _ 5 - 1 1 1 4 2 _ 5 _ 1 _ 0 0 2 7 5 0 5 0 3 9 9 6 3 1 3 0 9 _ 2 9 5 3, 4 2 0 8 2 5 4 5 3 6 3 3 3 4 1 G _ U _ A _ 9 0 2 3 3 3 8 5 1 0 o 0 1 5 0 5 0 _ 2 1 2 1 _ 9 _ 0 2 7 5 0 7 5 0 9 1 3 1 7 7 7 3 _ 5 8 2 5 8 6 3 3 0 0, 0 8 0 8 0, 0 1 1 1 L _ U _ J _ J 0 0 0 0 2 1 2 0 0 0 0 0 1 0 1 0 _ 6 1 _ 0 2 7 1 5 0 7 5 0 9 1 3 1 7 7 7 3 - 5 8 2 5 8 6 3 3 0 0 0 8 0 8 0 0 1 1 1 N _ U _ J _ 3 0 0 0 0 2 0 2 0 0 0 0 0 1 0 1 0 - 5 - 1 S - _ 0 2 7 1 5 0 7 5 0 9 1 3 1 7 7 7 3 - 5 8 2 5 8 6 3 3 0 0 0 8 0 8 0 0 N - Y _ 1 1 1 O - A _ I - M _ 3 0 0 0 0 2 0 2 0 0 0 0 0 1 0 1 0 - 5 T - - 1 C - E - J - O - _ 0 2 7 1 5 0 7 5 0 9 1 3 1 7 7 7 3 - 5 1 1 1 8 2 5 8 6 3 3 0 0 0 8 0 8 0 0 R - R _ P - P _ A _ 3 0 0 0 0 2 0 2 0 0 0 0 0 1 0 1 0 - 5 M - - 1 E - R - N - _ 0 2 7 1 5 0 9 5 0 9 1 3 1 7 7 4 3 - 4 1 1 1 A - R _ 5 2 5 8 2 3 3 0 0 0 8 0 0 0 5 M - A _ H _ 5 0 0 0 0 2 1 2 0 0 0 0 0 1 0 6 0 - 1 T - - 2 N - E - M - T - _ 0 2 7 1 5 3 7 5 0 9 1 3 1 7 7 7 3 - 8 1 1 1 6 - 1 R - B _ 6 2 5 8 4 6 7 0 0 0 8 0 0 A - E - P - F - 2 0 0 0 0 1 0 1 0 0 0 0 0 1 0 0 0 - 1 E - - 1 D - 7 - 8 - - 0 2 7 1 5 3 7 5 0 9 1 3 1 7 7 7 3 - 8 1 1 1 - 1 6 2 5 8 4 6 7 0 0 0 8 0 6 0 9 - N - 1 - A - J - 2 0 0 0 0 1 0 1 0 0 0 0 O 1 0 0 0 - 1 _ 1 I l l 1 I i I I I I I iI l I i I I I 1 I i1 1 l I l i 1 iI i1 T - E T T N - C R C S E - N O N A L M - A P Y O R A T - N S P R I T T R - E N U O T N O A - T O S S Y C O T P - N O I I T Y U C P E - I O C C T G G V I R R M Y I' - A C E P N A N N R N R U T E L - M S D I H A R E E E I U C S C T H P S S N E P H C R N S T I Y N - Y E N P Y Y U P X Y U l' E E O - V N Y N V V N D R V S A S M C H V O H lll1llll l

9 L198'f DEFUSLING AND MAINTENANCE OUTAGE ESTinAIED MAN REN E.) h ' ! P E: DRYWELL d ' SNUBBERS -4.2 . SRV/MS IV - 6.3 'L P RM - 1.2 1Rn/SRM INSP. 2.0

1. R T 0.3 CRD 15.0 MOVATS 5.0

. IS I 32.8 'l DRYLELL MISC. 11.2 . SHIELDING / STAGING 9.1 ) INSULATION 11.1 REACTOR WATER UPGRADE 19.2 't DRYWELL RT UPGRADE 6.2 VALVE REPLACEMENT (V2-19149) 9.8 RADIATION PROTECTION 10.5 l 143.9 MAN REM i REACTOR BLDG., TURBINE BLDG., RAD WASTE DISASSEMBLE / ASSEMBLE REACTOR VESSEL 16.0 - FUEL MOVES 3.5 FUEL POOL WORK 3.0 345-FT. MISC. 9.0 CAVITY DECON 2.0 INSTRUMENTATION MISC. 3.4 PUMPS / VALVES MISC. 10.0 REACTOR BLDG, MISC. 15.0 ACTUATORS MISC 0.2 VALVE REPLACEMENT (V10-26A&31A) 4.7 STEAM DRYER LIFT LUG REPAIR 0.6 RAD' WASTE MISC. 6.0 TURBINE 1.0 BLADES 1.0 RADIATION PROTECTION 3.0 OPERATIONS MISC. 8.7 APP. R MODIFICATION 0.6 ISI-8.3 RCU PUMP 'A' 2.S i55:3 MnN REM ~~ 344.2 TOTAL MAN REM EXPOSURE FOR OUTAGE l

l 1997 *UNTHL'r D E F A P ? rt : ;I n A a

c. E n P ROJ ECT IONS ss SELF :EADING DOS D' ETEPs ( SP D i

] APR MAY JIJ N l l DEPARThENT PROJECTED l SRD ! PROJECTED l SRD l PROJECTED l SRD l i l MAINTENANCE l 4.66 4.01l 4.66 4.37l 3.80 1.77l lNEPSCO l 0.53 0.86l 0.53 0.62l 0.53 0.88l j l l l l l j lYNSD l 0.17 0.04l 0.17 0.011 0.17 0.06l j lNPS l 0.20 0.49l 0.20 1.16l 0.20 0.61l 1 1 I I l lVY ISC l 0.85 0.44l 0.85 0.571 0.85 0.71l lVY HP l 2.41 1.73l 2.41 2.97) 2.10 0.531 1 I I I i l POWER SERVICE. l 0.40 0.321 0.40 0.42l 0.40 0.90l l0PERATIONS -l 2.35 1.27l 2.35 1.22l 2.35 1.131 I I I I i l REACTOR ENG. l 0.30 0.04l 0.30 0.03l 0.30 0.08l lENG. SUPPORT l 0.09 0.07] 0.09 0.05l 0.09 0.06l l 1 1 I I l SUPERVISORY l 0.01 0.01l 0.01 0.01l 0.01 0.01l l ADMIN. l 0.03 0.04l 0.03 0.02l 0.03 0.05l l I 1 1 I l SECURITY l 0.11 0.01l 0.11 0.06l 0.11 0.10l l MERCURY l 1.87 0.66l 1.87 0.36l 1.87 1.27l 1 I I I I l CONSTRUCTION l 0.07 0.02l 0.07 0.02l 0.07 o0.04l [HISC. CONTRAC. l 3.96 1.08l 3.96 1.67l 1.87 2.17l l l I I I lVY TEMP l 0.03 0.01l 0.03 0.01l 0.03 0.01l JCURP./PR l 0.01 0.05l 0.01 0.04l 0.01 0.05l l 1 I I l STORES /TRNG. l 0.01 0.01l 0.01 0.01l 0.01 0.01l lempty l 0.00 0.00l 0.00 0.00l 0.00 0.00j l I I I l lempty l 0.00 0.,00l 0.00 0.00l 0.00 0.00l lempty l 0.00 0.00l 0.00 0.00l 0.00 0.00l l__________ __________________________________________________________l MONTHLY TOTALS 18.06 11.16 18.06 13.62 14.80 10.44 4 TLD/SRS AVERAGE CONVERSION RATIO TRfsd 3RD AND 4TH QTR. 1986 cc: J.P. Pelletier R.J. Wanc=yk Superintendents Dept. Supervisors Bulletin Boards R.R. Morrissette ALARA COMMITTEE MEMBERG t-i

c_ t - ~,, l \\ 1 n

j. _

2 .+- b J b i MAN-REM 1 REPORT FOR ALL PERSONNEL =Guarter Projected Exposure Actual Exposure (TLD) 1 33,330 '20,627 2 50.920 31,s74 TOTAL: .e4.250 52.501 I, 1 i I L i 3

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i HOT PARTICLES S Historical data at Vermont Yankee indicates the following: s

1. Particles identified so far have been mostly Co 60.
2. The activity has ranged from.005 to.247 uCi.

uu e f ,. / _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - _ - ~

RP-0520 1 4 SKIN DOSE CALCULATION

1. A skin dose calculation is required for any skin contamination greater than 5000 ccpm on the skin for one hour.
2. The calculation is based on Louvinger's equations.
3. A daily skin dose calculation is performed if decontamination does not reduce the level of activity to below 500 cepm.

q i i

ss-s .;.) d: i a v y; ' n,...._ ;, ,mm .. !). I l SPECI AL PRECAUTIONS FOR CONTROL

1. PCM-1B whole body friskers.

1

2. A,juidelina was issued for the technicians on skin contaminations.
3. A survey of all of our protective clothing was done.
4. A laundry monitor will be evaluated during the 1987 refueling outage.

i l l 1 l-. b ~'

ADDITION AL PRECAUTIONS IF HOT PARTICLES ARE PRESENT 1

1. All personnel will be required to frisk every hour.
2. Equipment will be wiped down af ter each use.
3. The work area will be set up into separate zones.
4. The work area and all the egipment will be thoroughly monitored once the~ job is complete.
5. The laundry will be segregated.
6. Outer glove will be changed frequently.

l

^ g. 1 i ,' i I-DOSE CALCULATION FOR HOT PARTICLES Ifi hot p?rticle is found on a person's skin. The skin dose . calculation will be averaged over a 1 cm2 area to a depth of 7mg. We will use the Varskin computer code to do the calcu-lation. Results of greater than 100 mrem will be recorded on exposure record i

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PROPOSED PADIATION PHOTECTION DEPARTMENT C I 1* RAD PROT SUPVR i 1* PLANT HEALTH PHYSICIST 1* RADWASTE ASST 4* RAD PROT ASSTS 1* ALARA ENGR h '2* RADWASTE TECHS 2* DOSIMETRY ASSTS 2 - TECHS 10* RAD PROT TECHS 7 - ROTATING SHIFT 3 - 1 CK PT 0 - 2 TRNU 2* DOSIMETRY CLERKS 3* LAUNDRY TECHS l'- LAUNDRY 1 - CK PT 1 - TRNG FUNCTIONAL RESPONSIBILITIES:

  • TOTAL PERSONNEL = 27

- Radiatior monitoring, surveying, posting - RWPs and health physics coverage - ALARA program - Dosimetry, W.B.C., respiratory protection program - Radioactive material receipt, packaging, shipping - Laundry operations / provision for protective clothing - Closed space entry monitoring (Oxygen, hazardous atmosphere, etc.) and asbestos monitoring - Maintain the surveillance program as presently delineated in the E Plan operating procedures d 4 \\ C +' c\\ at h ce"sec's tv u est. N o r f_.- krrennEI 4xrif *e #3

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PROPOSED CHEMISTRY DEPARTMl:NT i 1 i 1* CHEMISTRY SUPVR 2* CHEM ASSTS 1* CHEM ENGR 1* ENV5RON ASSTS 4* CHEM TECHS 4 (1) FUNCTIONAL RESPONSIBILITIES:

  • TOTAL PERSONNEL = 9

- Primary System chemistry - BOP System chemistry - Environmental monitoritig (radiological, chemical, NPDES permit) - Hazardous waste / chemical control programs and hazardous chemical communication program - Demineralized performance - Radioactive discharges bJ oTE ; De r r ow n e. \\ 4ri me"D 08\\ n 1 J}}

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