ML20055G743
| ML20055G743 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 07/14/1990 |
| From: | Nimitz R, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20055G739 | List: |
| References | |
| 50-309-90-11-EC, NUDOCS 9007240127 | |
| Download: ML20055G743 (42) | |
See also: IR 05000309/1990011
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50 309/90-11
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Docket No.
50 309
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Category
C
License No.
Priority
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Licensee:
Maine Yankee Atomic Power Company
53 Edison Drive
Augusta, Maine 04336
Facility Name:
Maine Yankee Atomic Power Station
Meeting At:
King of Prussia, Pennsylvania
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Meeting Conducted:
June 27, 1990
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Prepared By:
l2 L.hlim[
7 lH 'ld
R. L. Nimitz, CHP, Sen10rJ Radiation Specialist
date.
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Approved by:
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W. J; Pa
tak, Chief, Fac1 Titles Radiation
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Protecti
Section
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Meeting Summary:
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Enforcement Conference Conducted on June 27, 1990 (Inspection Report No.
507U9/90-11)
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The Enforcement Conference was held to discuss the circumstances surrounding the
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unplanned, unmonitored occu)ational radiation exposures of three workers working
on valve. PCC A 216 during tio period May'7-17,luation of the information and-1990, the license
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and corrective actions, and the licensee s eva
-apparent violations discussed in NRC Inspection Report No. 50-309/90-11.
Senior
licensee and NRC management attended the meeting which lasted about three hours,
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DETAILS
1.0 Individuals Atten@ng
1.1 Maine Yankee Atomic Power Company
E. T. Boulette Vice President Operations
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R. Blackmore, klant Manager
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R. Nelson Manager, Technical Support
G. Pillsbu,ry,icensing Section Head
Radiation Protection Manager
S. Nichols, L
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NRC
D. Cooper
Division of Radiation Safety and Safeguards
W.Pasciak,De)utyDirectorC11ef,facilitiesRadiationProtectionSection
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E. McCabe, Chief Reactor Projects Section 2a, Division of Reactor Projects
K. Christopher, Enforcement Specialist, Office of Enforcement
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K. Smith, Regional Counsel, Office of the Regional Administrator
R. Nimitz, Senior Radiat hn Specialist, facilities Radiation Protection
Section.
2.0 Purpose of Meeting
The NRC held an Enforcement Conference with the licensee to discuss the
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circumstances surrounding the unplanned,lve PCC-216 during the period Mayun
exposures of three workers working on va
7-17 1990, the licensee's corrective actions, and the licensee s
evalu,ation of the information and apparent violations discussed in NRC
Inspection Report No. 50-309/90-11.
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3.0 Licensee Presentation
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The attachment-to this meeting report provides the information discussed by
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the licensee at the Enforcement conference. During the conference
licensee discussed the method of identification of the unplanned, , the
unmonitored radiation exposures of the three workers, the circumstances
surrounding the unplanned, unmonitored occupational radiation exposures of
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the workers, the appropriateness of several of the a
50 309/90 11,pparent violationsthe immedia
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discussed in NRC Inspection Report No.
term corrective actions taken,during the outage.and the performance of the license
radiological controls program
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4.0 NRC Discussions
NRC senior management acknowledged the licensee's comments and indicated
that the information provided at the Enforcement Conference would be
evaluated.
The NRC's Region I senior management informed the licensee's
senior management that they would be informed of the need for and nature of
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appropriate enforcement action in the near future.
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RADIOLOGICAL CONTROLS ENFORCERENT CONFERENCE
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MEETING AGENDA: JUNE 27,1990
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INTRODUCTION
E. T. BOULETTE
PCC VALVE WORK
G. D. PILLSBURY
RAD INCIDENT REPORT
G. D. PILLSBURY
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REVIEW OF APPARENT VIOLATIONS
S. E. NICHOLS
OUTAGE SCOPE /HP SUPPORT
R. W. BLACKMORE
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OUTAGE RAD CON PERFORMANCE
R. H. NELSON
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SUMMARY / CONCLUSIONS
E. T. BOULETTE
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OBJECTIVES
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DESCRIPTION OF EVENT
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ADDRESS EACH APPARENT VIOLATION.
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- UCENSEE IDENTIFIED
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-CORRECTIVE ACTIONS TAKEN
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-NRC DISCRETION 15 APPUCABUE
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Pt. ACE INCIDENTIN Pli3ISPEC1WE
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- OVERALL OUTAGE PERFORMANCE
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- HP PERFORMANCE IN PARTICULAR
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IMMEDIATE CORRECTIVE ACTIONS
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1.
Work Stopped on PCC-A 216
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Worker's Dosimetry Processed
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Work Area including Trench Resurveyed
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All involved Personnel Were Interviewed
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Dose Assessment Conducted
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Event Report Reviewed For Completeness And Technical Adequacy
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LONG TERM CORRECTIVE ACTIONS TO PREVENT RECURRENCE
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Event Discussed At Shift Turnover And in " Night Orders" 5/23/90
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Report To Be included in Training For Rad Con Techs And GPK
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Survey Procedure To Be Revised To Require Surveys Of Floor
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Trenches in Work Areas
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Qualify Valve Workers As Self Monitors For Next Outage
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Evaluate Use Of Dedicated Tech (s) For Valve Work For Next
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Outage
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Briefed Workers Concerning Good Communication With Rad Con
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When Work Scope Changes
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Briefed Management On The Event-
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Develop Standard RWP Preparation Checklist To Ensure Accurate
Information On How Work Will Be Done
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Requiro Work Party Leader Be Listed For Every RWP
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10.
Develop Generic Guidelines For Draining Systems
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EVALUATION OF THE POTENTIAL FOR OTHER WORKERS
TO HAVE RECElVED UNMONITORED EXPOSURE
1.
All Workers Listed On Access Log For PCC A 216 Were Interviewed
- No Other Workers Were Under The Valve.
2.
RWPs For Other Air-Operated Valves Were Checked
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13 Air-Operated Valves Were Worked
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7 Not Near Floor Trench
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5 Near Floor Trench But Only Air Filters Changed
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1 Valve Repacked From Top In Less Than 30 Minutes
3.
RWPs For Other Valve Work Were Checked
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76 RWPs For Valve Work Were Reviewed
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56 Not Near Any Floor Trench
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9 Near Floor Trenches But Limited To Top Of Valves (Air
Filters, l&C cals, etc.)
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8 Near Floor Trenches With Dose Rates Similar To General
Area Dose Rates Or Work Was Of Short (Less Than 1 hr)
Duration -
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3 Potential Valves Were Looked At in Detail. All Three Were
Swing Check Valves With Top Flanges Located Very Near
The Floor.
4.
RWPr, For Potential Unmonitored Extremity Dose
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76 RWPs Evaluated
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Total Man Hours Logged Which Would Give Worker 10% Of
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Applicable Dose Were Evaluated
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individual Worker Times Checked
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No Single Worker Had Work Time Sufficient To Exceed 10%
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Of Extremity Limit Even If He Stood Directly On The Trench
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The Entire Time.
CONCLUSION: No Other Workers Had Unmonitored Exposure
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NOV RESPONSE
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90-11-01 Failure To Survey
The trench was not surveyed. it was not an obvious part of the
work area based on the original work scope.
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90-11-02 Failure To Perform Periodic Surveillance
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Techs checked on workers by performing dosimeter checks. This
was reasonable for the dose rates as known.
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90-11-03 Failure To Instruct Workers About Trench
- Workers were instructed to the extent that the job hazards were
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known via the projob briefing form. Some crews were specifically.
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90-11-04 Examples Of Failure To Follow Procedure
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All items deal with RWP procedure. May need to look at adequacy
=or clarity of procedure:
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Items 1,2,5 all hinge on knowing the trench was part of the work
area and a high rad area.
Item 3 specifies where stay times are to be recorded, not that they
must be recorded all the time.
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item 4 - A respirator was required "If in the area of venting or
draining". AO present only long enough to open valve and then
shut valve.
Air sample from the other end of the line showed 3.9E-10 ucl/cc.
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NRC APPARENT VIOLATIONS
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A.
AV 50-309/90-11-01
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"THE INSPECTOR CONCLUDED THAT IT WAS NECESSARY AND
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REASONABLE FOR THE LICENSEE TO MAKE OR CAUSE TO. BE
MADE SURVEYS TO ENSURE COMPLIANCE WITH THE
REQUIREMENTS OF 10 CFR 20.101 AND 10 CFR 20.202.
THESE SURVEYS INCLUDED THE PHYSICAL MEASUREMENTS
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OF RADIATION FIELDS IN THE AREA AND EVALUATION OF
THE WORKERS' TOTAL QUARTERLY EXPOSURE PRIOR
ALLOWING THE WORKERS TO RETURN TO WORK IN A
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FAILURE TO MAKE OR CAUSE TO BE MADE SUCH SURVEYS
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AS ARE NECESSARY AND REASONABLE TO COMPLY WITH 10.
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CFR 20.101 AND 10 CFR 20.202 WAS AN APPARENT
VK)LATION OF 10 CFR 20,201."
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AV 50-300/90-11-02
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"THE INSPECTOR IND6CATED THAT FAILURE TO PERFOslB8
RADIATION SURVElLLANCE AT A FREQUENCY SPECWED ON
THE RWP IS AN APPARENT VIOLATION OF TECHNICAL
- SPECIFICATION 5.12.1."
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AV 50-309/90-11-03
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THE INSPECTOR INDICATED THAT FAlLURE TO INSTRUCT THE
WORKERS IN PRECAUTIONS TO MINENZE THEIR EXPOSURE,
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WAS AN APPARENT VIOLATION OF 10 CFR 19.12."
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AV 50-309/90-11-04
" FAILURE TO ADHERE TO RADIATION PROTECTION
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PROCEDURES CONSTITUTE AN APPARENT YpOLATION OF
TECHNICAL SPECIFICATION 5.11."
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APPARENT VIOLATION 01
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FAILURE TO MAKE OR CAUSE TO BE MADE AN ADEQUATE SURVEY. .
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MYAPCO POSITION ON EXISTENCE OF A VIOLATION
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WHILE MAINE YANKEE AGREES THAT THE SURVEY CONDUCTED
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DID NOT IDENTIFY A CONTACT SOURCE OF APPROXIMATELY 150
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mR/HR, WE DO NOT BELIEVE THAT A CITATION IS APPROPRIATE.
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DISCUSSION OF MYAPCO POSITION
QUALIFIED INDIVIDUAL WAS PRESENT MONITORING
EXPOSURE AN HOURLY BASIS IN ACColtDANCE WITH RWP.
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SURVEY RESULTS INDICATED A 30-50 rnR/HR FIELD IN
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WORK AREA.
SURVEY INDICATED IMMEDIATE WORK AREA NOT TO BE
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METHOD OF MONITORING EXPOSURE WAS BY MEANS
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OF POCKET DOSIMETRY.
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THIS MEANS OF MONITORING lS CONSIDERED
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APPROPRIATE FOR NON-HIGH RADIATION AREA.
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DOSE RATES WERE APPROPRIATE TO THE AREA LEVELS
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RECORDED DURING PRE JOB AND ROUTINE SURVEYS.
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THE RC TECHNICIAN EXERCISED GOOD ALARA
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PRACTICES
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IF SURVEY INDICATED IMMEDIATE WORK AREA TO BE A HK1H
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. RADIATION AREA, DIFFERENT SURVEILLANCE TECHNIQUES
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DIRECT RADIATION SURVEYS ARE APPROPRIATE FOR
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FOR EXAMPLE, STEAM GENERATOR PLATFORM WORK
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HAD CONSTANT RC COVERAGE BECAUSE RELDS ARE
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MUCH HIGHER.
JOB COVERAGE WAS IN ACCORDANCE WITH MAO CONTROLS
PROCEDURE
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PERSONNEL SAFETY SIGNIFICANCE
THIS APPARENT VIOLATION DOES NOT REPRESENT A
SIGNIFICANT SAFETY CONCERN.
THIS FINDING RELATES TO:
THE INDIVIDUALS INVOLVED D00 NOT RECEIVE DOSES IN
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EXCESS OF NRC REGULATORY UMITS.
THE ADMINISTRATIVE LIMITS ESTABLISHED ARE
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CONSERVATIVE WITH RESPECT TO REGULATORY LIMITS
, AND FOR PERSONNEL NEALTH CONCERNS.
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A LIMITED NUMBER OF JOB ACTIVITIES AND
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INEIVIDUALS WERE INVOLVED.
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OTHER CONSIDERATIONS
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MYAPCO lDENTIFIED THE ISSUE.
A PROMPT AND THOROUGH RADIOLOGICAL N
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REPORT WAS PREPARED.
NRC HAS REVIEWED THE RIR AND IS SATISFIED WITH
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THE CORRECTIVE ACTIONS.
ISSUE DOES NOT APPEAR TO BE OF A RECURRlNG -
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NATURE.
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NRC DISCRETION SEEMS APPROPRIATE
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APPARENT VIOLATION 02
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FAILURE TO PERFORM RADIATION SURVEILLANCE AT A FRiEQUENCY
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SPECIFIED ON THE RWP.
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MYAPCO POSITION ON EXISTENCE OF VIOLATION:
MAINE YANKEE ADMITS THAT IF THE INITIAL SURVEY HAD
IDENTIFIED THE 150 mR/HR SOURCE, THEN DIRECT
SURVElLLANCE OF THE AREA ON AN HOURLY BASIS WOULD BE
- APPROPRIATE. THE ROOT'OF THIS APPARENT VIOLATION,
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HOWEVER, IS IDENTICAL TO AV 01. WE DO NOT BELIEVE A
SEPARATE FINDING IS APPROPRIATE.
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DISCUSSION OF MYAPCO POSITION:
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INITIAL JOB SURVEY WAS PROPERLY CONDUCTED.
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AT START OF WORK,-WORKERS /RC TECHS ESTABLISHED
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METHODS OF CONDUCTING WORK.
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WORK FROM CATWALK.
- WORK FROM ABOVE THE VALVE.
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MAY STRADDLE VALVE.
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DURING. CONDUCT OF WORK, METHODS OF CONDUCTING -
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WORK CHANGED.
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CHANGE IN WORK SCOPE WAS NOT cot 0000N0CATED TO RC
TECHNICIANS.
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SUBSEQUENT SURVEYS WERE NOT APPROPRIATE.
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PERSONNEL SAFETY SIGNIFICANCE:
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THb8 APPARENT VIOLATION DOES NOT REPRESENT A
S4GNIFICANT SAFETY CONCERN.
THIS FINDING REl.ATES TO:
THE RC TECHNICIAN EXERCISED GOOD ALARA
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PRACTICES IN VIEW OF SURVEY AREA DOSE RATES.
(ACCESS ROUTE AND WORK AREA.)
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D. LOTHER CONSIDERATIONS:l
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- IF INITIAL AREA SURVEYS HAD IDENTIFtED CONTAMINATED
AREA, THEN RADIOLOGICAL CONTROLS WOULD HAVE BEEN
DIFFERENT.
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THE ROOT CAUSE OF THIS AV IS IDENTICAL TO ThlAT OF AV
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MYAPCO DOES NOT BELIEVE THIS APPARENT VIOLATION IS
SEPARATE OR DIFFERENT FROM AV1. AN ADDITIONAL
VIOt.ATION, THEREFORE, IS NOT APPROPRIATE.
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APPARENT VIOLATK)N 03
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FAILURE TO INSTRUCT WORKERS IN PRECAUDOWS TO halagems
EXPOSURE FROM RADIATION FIELDS EMANATING FROM A TRENCH IN
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WORK AREA.
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MYAPCO POSITION ON EXISTENCE OF VIOLATION:
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. MAINE YANKEE ADMITS THAT IT HAD NOT NOTIFIED WORKERS OF.
THE EXISTENCE OF THE 150 mR/HR AREA. IF THIS FIELD WERE
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KNOWN, HOWEVER, PROPER POSTING AND-INSTRUCTIONS
- WOULD HAVE BEEN CARRIED OUT. THE ROOT CAUSE OF THIS
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AV 1S IDENDCAL TO THAT OF AV 01. A SEPARATE FINDING
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.SEEMS INAPPROPRIATE.
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DISCUSSION OF MYAPCO POSITION:
RC TECHNICIANS STATE THEY INSTRUCTED WORKERS TO
REMAIN IN VICINITY OF WORK AREA AND POSITED OUT Te4E
- PRESENCE OF LOCAL HOT SPOTS.
WORKERS WERE PROVIDED TRAINING APPROPRIATE TO
THEIR EXPERIENCE AND JOB SCOPE PRIOR TO ANY WORK
BEING PERFORMED.
. WORKERS RECEIVED TRAINING IN THE AREA OF
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RADIOLOGICAL CONTROL PRACTICES AT MYAPCO AND
AT OTHER NUCLEAR LICENSEES.
DISCUSSION OF WORK METHODS WAS NOT CORRECTLY
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COMMUNICATED TO RC TECHNICIANS.
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INITIAL PRE JOB BRIEFINGS INCLUDED DISCUSS 80NS OF
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WORKING ON TOP OF CATWALK AND STRADDLING 1NE
VALVE.
SURVEY AND WORK PERMIT WERE PREPARED PROPERLY
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BASED ON THIS WORK SCOPE.
-WORKING PARTY DID NOT REPORT PLANS OF LAYING
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BENEATH VALVE TO CONDUCT WORK.
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~ BASED ON RC TECHNICIAN'S UNDERSTANDING OF WORK
SCOPE, PRECAUTIONS AND INSTRUCTIONS WERE PROPER.
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NOT BELIEVE THE IDENTIFICATION OF THIS AV REPRESENTS ANY
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RADIATION PROTECTION PROCEDURE 9.1.te, SECTION S.3:
FAILURE TO ADEQUATELY VERIFY WORK AltEA DOSE RATES.
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PROCEDURE 9.1.10, SECTION 6.1.8: FAILURE TO SPECIFY
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SPECIAL ALARA COMMITTEE MEETINGS
PRE-OUTAGE
01/11/90
Thermal Shield Repair
01/17/90
Nozzle Plug Installation / Removal
01 31 90
. In Service inspection (ISI)
/ /
02/22/90
Inspection / Repair RC-M-11
03/07/90
Pressurizer Heater Sleeve inspection
,
AFTER OUTAGE START
-
.
05/12/90
.S/G increased Inspection / Repair
(Scope not determined until after start of Outage)
L
- 05/16/90
Thermal Shield Repair
,
(Meeting required due to reaching pre-set Dose
'
Limit)
A total of 20 projects (including above) had in depth reviews
L
conducted prior to start of outage.
1
'
Departmental ALARA reviews conducted of other RWPs of less
1
dose potential.
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RAD
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APR
MAY
JUN
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)AILY HOTSIDE JOB LOADING (JOB / DAY)' -
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1990
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200
AVERAGE # JOBS / DAY
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- MAJOR PROJECT DOSE TRACKING
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TASK NUMBER
OUTAGE' TOTAL 4/7-6/7 480 MAN-REM
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EXPOSURE TRACKING
TASK
LIST
'1,
SGR-STEAM GENERATOR REPAIR ONCL OUT OF SCOPE ECT)
2.
MOV.-MOV - MAINTENANCE / TESTING
3,:
'VLV.-NON MOV VALVE MAINTENANCE
4.
RX.-REACTOR . DlSASSEMBLY/ REASSEMBLY.
5.
ISI.-
INSERVICE INSPECTION
6.
CSB.-THERMAL SHIELD INSPECTION / REPAIR
7.
OPS,-ROUTINE VALVING / TAGGING
8.
ECT.-S/G EDDY CURRENT TESTING < *2 mes spec iNSPECTICN )
9.
PZR.- HEATER SLEEVE INSPECTION / REPAIR
10. MLO.-MID L'OOP OPS INSTRUhENTATION
11. SHLD-INSTALL / REMOVE LEAD- SHIELDING
-
'
m
13. FHE.-REPAIR / TESTING FUEL HANDLING EQUIP.
14. FMV.-FUEL MOVEMENT /RELATED ACTIVITIES
15. PLUG 8-INSTALL REMOVE NOZZLE PLUG 8
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.
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RECENT MAINE YANKEE
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OUTAGE EXPOSURE
HISTORY
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YEAR
MAN REM
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1984
755
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1985
573
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1987
600
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1988
635
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1990
479
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