IR 05000317/1990014

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Radiation Safety Insp Repts 50-317/90-14 & 50-318/90-12 on 900625-29.No Violations Noted.Major Areas Inspected:Status of Previously Identified Items,Worker Allegations,Control of Outage Work,Alara & Site Access for NRC Personnel
ML20058P170
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 08/08/1990
From: Dragoun T, Pasciak W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20058P137 List:
References
50-317-90-14, 50-318-90-12, NUDOCS 9008160106
Download: ML20058P170 (8)


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O.S.-NUCLEAR' REGULATORY C030tISSION

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REGION I'

,50-317/90-14

Report Nos. 50-318/90-12

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50-317 i

Docket Nos. 50-318

- DPR-53-License'Nos. DPR-69

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I Licensee: Baltimore Gas and Flectric'Comoany

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P.

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Box 1475 Baltimore. Maryland ~21203-

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s Facility Name:

Calvert Cliffs Nuclear Power' Plant. Units 1 and 2 i

s Inspection At:

Lusbv. Maryland'

i Inspection Conducted:. June =25129."1990

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Inspector:

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art x T. Diggpn, Senior: Radiation: Specialist.

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Approved by:

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W.. Pasciak, Chief,\\) Facilities Date:

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Radiation Protection Section; l

L Insoection Summary:

Insoection conducted'on June 25-29, 1990

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(Combined Insoection Report Nos. 50-317/90-14 and-50-318/90-12i Areas Insoected:

Routine: inspection of the:radiatilon safety:

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program including status'of previouslyLidentified' items,' worker y

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allegations, control of outage' work, ALARA,.and.' site access'for

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NRC personnel.

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Results:. No violations were identified.- Lor.g term ~ corrective action for improper High Radiation Areas.(>100 mrem /hr) entries =

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9008160106 900808

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i-l DETAILS 1.0 Persons Contacted

1.1 ; Licensee Personnel l

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  • J.:T. Carlson, Supervisor - Technical'. Training

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  • G.

L.. Detter,- Director - Nuclear Regulatory Affairs

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  • M.LD.-Milbradt, Compliance Engineer-
  • L. S. Larragoite, Compliance-Engineer.

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  • N.

L. Millis,-' General Supervisor - Radiation Saft y.

  • G. P..Phair, Assistant General = Supervisor - Radia. ion

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Control 1and Support,

  • T.- N. Pritchett, General Supervisor - Quality Assurance

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H. Roach, Quality. Assurance

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S. G. Hutson, Supervisor - Radiation Control & ALARA

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D. R. - Adams,c Supervisor -LDosimetry 1.

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R.~ Leonard, Supervisor - Security Screening

1.2 NRC Personnel

  • L.

E. Nicholson, Senior Resident Inspector

  • Attended the Exit-Interview on June 29,-1990.

2.0 Puroogg The purpose-of this routine-radiation safety inspection was to review the following program elements:i

Status of'Previously IdentifiedLItems

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Worker Allegations

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Control'of Outage Work

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ALARA

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Site Access for NRC Personnel

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3.0 Status of Previously Identified Items l

3.1 (Closed). ' Unresolved Item, (50-317/88-16-02)'., Two workers received an-unanticipated radiation exposureTin June 1988.while working in theLUnit'1 valve = alley'due-

'to an' inadequate radiation survey.. This matter was reviewed'during Inspection, Number-50-317/88-20 and'

reculted in violation'J88-20-01.

This matter is

resolved.

(See Section 3.2 of.this report.)

3.2 (Closed) Violation '(50-317/88-20-01)'.1 - A Ilealth Phys.d es

(HP) Technician:did unot perform an adequate. pre-fobt

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survey prior to work.intthe Unitil:27-foottelevation'

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valve alley.

This' constitutes aLviolationiof 10 OFR

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20.201-requirements.

Although'most' conditions

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q specified in 10 CPR 2 Appendix C for mitigation-were

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met, the'insp00 tor noted that measures to prevent a

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recurrence were n?t: completed in a= reasonable period' of

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time.

Additional ~ corrective action described.in l

licensec-letter dated october 719, 1988, is complete and This matter is closed._

satisfactory..

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3.3L-(Closed)s Follow. Item'(50-317 and 50-318/89-02-01).-

l Licensee to upgrade Radiological Concern Report-(RCR):

procedure.

Procedure RSP1-109, " Issuance'and

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Administration of Radiological Control Reports",+was revised in February /1989 to: include a requirement'to-

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identify-any RCR that may! involve a violation of j

regulations or Technical Specifications and to provida;

~j timellimica for completion of1 corrective-action. ~This-

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' item is closed.

-3.4 (Closed) Follow Item (50-317 and 50-318/89-02-02).

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Proceduralize the use of Job Coverage Record.

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i Procedure RSP1-101;." Radiological Surveys", was revised,

j in February 1989 to incorporate.the. requirement.to:

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L document all-pre-job: surveys:on'a. form called'" Job

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Coverage Record".

In addition,to recording the-as-

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found conditions-, the form also required a formal closeout'of the job < including items such--'as (~

housekeeping.

Several formal $ reviews of the form are l

completed prior to filing'the information. 'This item is clossd.

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3.5.(Closed) Unresolved Item'(50-317sandL50-318/89-02-03).

Review upgrades to training for survey ~ instrument t

l calibration' technicians. LIn-April.1989_the licensee

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promulgated-training and qualification! Program IR-6,_

" Instrument Repairer Training l Program".'LIncludedLare requirements for special work 1 force and contractor

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personnel.

The newly' hired instrumant repair L

technician used the new' training = program..'Thisimatter-

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isLresolved, s

3.6 (Closed)-Violation ~(50-317 and150-318/89-10-01).

Failure to follow-Radiation Protection-(RP); procedures..

LicenseeLaction,' as described in the' reply dated =

July 7, 1989, is complete and-satisfactory.

This.

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matter is closed.

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J 3.7 (Closed) Unresolved Item-(bO-317'and-50-318/90-02-01).-

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This' item.was unresolved-pending'a: review of the.

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licensee's corrective action for'three events:

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1.

In January 1990, two contractors entered a High-Radiation Area without a. survey meter.-

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In February-1990, a similar: event occurred;.

l inve,1ving a plantLoperator.

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In February 1990, a11arge arem of the Auxiliary 1

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Building:became contaminated during; work lon the t

Chemical'and Volume Control Filter..

p As a result of event #11and #2, theilicensee changed the posting / barricading policy and retrained health i

Physics l technicians.

All other. plant personnel 1weral

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informed of the incident;via sta tionwide. meno.

These corrective actions were~not fully stfectiveninL l

preventing improper high radiation' area er.triest as

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discussed in Section 5.0:of this report.

Additional

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licensee action relative to.this matter is consolidated e

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into unresolved; item 50-317/90-14-01-andJ l

50-318/90-12-01.

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. the licenseeLauspendedfworklon-

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Relative to event #3, l

the system, revised'the applicable maintenance

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procedures, revised;the HP; job' coverage procedure, andi i

retrained HP technicians and thafworkforce"onLtheLnew-

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job criteria.-

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As a result of these considerations,;this unresolved item-is closed.

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4.0 Worker Concerns

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- 4.1 ~ Termination of'Emnlovment (RI-89-A-0050)

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An HP technician indicated'that histemploymentihad been

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'tnat workers were required to violate procedures:and~

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don respiratorslln a contaminated area.

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The technician was' advised!that' labor disputes are_not

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within the purview offthe~NRC and toibring those;

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concerns to the Department of Labor..

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100 arem/hr) by two contracted workers performing Motor Operated Valve testing. " Initial.

corrective action. appeared. appropriate. 1However, since this event is similar to other recent occurrencas as described in;

'Section 3.7, the long term corrective' action"is still1under management review.

The Human' Performance Evaluation Survey-was still-in-progress.

The inspector-concluded that this was reasonable considering the need'to consider the other, j

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similar events.

This matter remains unresolved pending; j

licensee long1 term corrective. action to' prevent a recurrence.' (50-317/90-14-01 and 50-31b/90-12-01).

The licensee also briefed 1theLinspector regarding'a self--

identified event wherein personnel dosimetry was not-correctly.placed:to measure the.highestJwhole body exposure.

Personnel acting as safety / rescue watchTfor a confined-space entry inside the pressurizer =were involved in the incident.

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The watch personnel' sat at the-pressurizer vessel manway._

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wearing-their dosimetry on the cheh'.: Ahresurvey' indicated'

a hot spot in a valve; caused a higher reading:to the worker's backs.

The licensee assigned' calculated exposures:

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7-after extensive measurements and mockup in.the area.

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The-inspector's review indicated,that the. differences.in'

l exposure: values.(front to:back) was about,20r percent'and was s-well within regulatory limits.

The licensee's/ program _for-

'I the> placement of dosimetry will1be reviewed in a future; l

inspection.

A significant effort.was. underway;to reduceLthe number ofL

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personnel contamination events.:

Contaminated areas.in the:

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reactor building were being= decontaminated and-painted'.

An:

z impervious epoxy coating was to'be placed on the' floors.

g Yhe GOT training was enhanced by.using, one : instructor peut

t.tudent during the'PC: donning and1 removal ~ practice.

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i success.of thace efforts.will be reviewed in a future f

inspection.

Coverage by HP technicians-of' work in toe. Reactor Auxiliary l=

Building was excellent.

There was a "LoveliTech" assigned

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j responsibility-for all work on an elevation.in.theLbuilding.

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In addition, there were " Job coverage Techs" assigned to each' job in progress and a " Rover-Tech" who conducted spot-audits throughout the-building and assisted as'necessary.-

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6.O ALARA

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i The licensee's efforts'to maintain: exposures'as lowcas,

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L reasonably achievable (ALARA)iwas determined:from. interviews

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l with personnel,-review of status reports, and a tour'of the

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steam generator mockup.. Strengtta E.1. weaknesses were'notud:

l-as follows:

As a result of findings during; the recent N' L Maihtenance:

Team! Inspection both the ALARAEand HP-Te7h'

aian staff.were

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doubled.

This'has allowed-better.long.rr e.: planning and-liaison with work-groups on' site.

During this extended outage there is re.iologically challenging work unterway.- on Unit:1'the pressurizer

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l heaters were inspected.and repaired.. on Unit 2 all heater l.

assemblies were removed-and replaced by working from inside.

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the prassurizer.

Total exposure 1to,date for this jobtis 113 l

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. man-rea = with an estimated savings of 240 ~ man-rem-due.txt

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h ALARA efforts.

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Upcoming work includes the replacement:ofLthe feedfrino h

thermal sleeve inside4 a' steam generator,in UnitL1.

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ALARA. group directed the construction of a special mockup;on-

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Special ALARA precautions'

L such as depth of water above'the tube bundle is incorporated h

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into - the work procedures. i During.- the. weekly '-job planning

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ALARA.

The inspector concluded that the present ALARA

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efforts are excellent.-

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7.0 EEit Meetina (

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The inspector met with the licenseoeperspnnel denoted'in ~

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Section'1.1.at the conclusion!of this inspection on June 29,:n 1990..

The scope _and findings of2the inspection-were-presented at that; time.

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