IR 05000293/1990012
| ML20043A230 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/04/1990 |
| From: | Dragoun T, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20043A229 | List: |
| References | |
| 50-293-90-12, NUDOCS 9005210043 | |
| Download: ML20043A230 (5) | |
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i U. S NUCLEAR. REGULATORY COMMISSIONf
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REGION:I Report No~.
90-12^
Docket No.
50-293 License;No.
. Priority Category C
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Licensee:
Boston Edison Company M/C Nuclear 800 Boylston Street-
. Boston, Massachusetts 02199
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-Facility Name: Pilgrim Nuclear Power Station
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Inspection At:- Plymouth, Massachusetts-
'iq Inspection Conducted: April-16-20,-1990-
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- f Inspectors:
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T.~ Drag g Senior Radiation Specialist
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Approved by:
As o~ -:7 a.
u W. Pisciak, ChieT, Facilities Radiation da
.j Protection Section
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-g-f Inspection Summary:
Inspection on April 16-20, 1990 (Report'No; 90-12)
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Areas Inspected:
Routine, unannounced-inspection of radiological _ controls
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during an outage by one region-based inspector. Areas ' reviewed included:
status of previously identified items;. organization and-staffing; control of
outage work; and ALARA.
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Results: No violations were observed.
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DETAILS-
1.0 Persons Contacted l
1.11 Boston Edison Company-
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. *K. Highfill,'V. P. Nuclear Operations and. Station Director
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- F Famulari, QA Dept. Manager.
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- D Long, Plant Support Dept ~. Manager
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- Rl-Fairbank, Nuclear Engineering' Dept. Manager-(Acting)
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- D. Eng',-Planning:and Outage Dept. Manager
- N. Dimascio, RadiationiProtection. Manager.
- B. Eldredgen Radiological As'sessor-
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- B. Lunn, Senior Compliance Engineer:
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.B; Mcdonald, Radiological Ops, Support' Division Manager
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J. Posselt. Senior ALARA Engineer
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R. Deacy. Safeguards and Security. Division Manager
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1.2 NRC'
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- J. Mcdonald, Senior Resident Inspector C. Carpenter, Resident' Inspector
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W. Olsen,; Resident Inspector.
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- Attended the Exit Interview onLApril"20, 1990.
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2.0 Purpose
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The purpose of this' routine radiation safety inspection was to. review the following-program elements:
-Status of Previously. Identified Items'
-Organization and Staffing-Control of Outage Work-ALARA
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3.0. Previously Identified' Items 3.1 (0 pen) Viol"ation (89-10-01) A condenser bay door, controlled as a
. Locked High Radiation Area (LHRA) was found unlocked and unattended. ' Licensee ' corrective action as' described in a letter dated.
December 26,1989 (Boston Edison Company Letter.89-181) is complete.
and satisfactory. However, the inspector advised the licensee that additional' action wastrequired to ensure that door hardware and mechanisms were functioning properly. The' licensee stated that a preventative maintenance plan for controlled doors included LHRA
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doors will-be implemented in June. 1990.
This matter remains open and will be reviewed-in a future inspection.
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- 3.2 (C16 sed) Unresolved Item (89-13-01)-the licensee to evaluate
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effectiveness of worker training in preventing unauthorized entry
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into high radiation areas. The inspector determined that the current
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training is adequate.
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-'4.0 Organization and Staffing j
't The organization and staffing in the Radiological Controis Department was_-
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reviewed relative to the criteria in-Technical Specifications 6.2:
't Organization, 6.3 Facility.. Staff. Qualifications, and ANSI N18.1-1971:
" Selection and Training of Personnel for Nuclear Power Plants."
Performance was determined through interviews with selected managers'and.
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review of selected records.
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W1 thin.the scope of this review,:no_ violations were-ob' served. 'The current-
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organization is fully staffed with_ qualified: personnel. A11Lopenings'were
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filled by promotions of permanent-personnel. The staff _ size-'is adequate-
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to support normal plant operations and outages.
However, thereais'no-corporate HP staff in'the current' organization.- Since corporate' staffs'
normally assist with program improvements, sitt management decided.to.
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place program changes on-hold for the last ew months and devote full-attention.to theLspring-outage. -This contributed to good performance-during the' outage. 'As the result of effective use,ofcthe 35 permanent.
radiation: protection < technicians combined with good' work planning, only 9 i
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contractor technicians were hired for outage support.
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i; 5.0 Control of Outage-Work l
The radiological'controis-implemented by the licensee!for outage work were
reviewed with respect to criteria contained in'10 CFR 19 " Notices,
Instructions, and' Reports to Workers"fand 10.CFR 20 " Standards-for i
L Protection Against Radiation".
Performance was determined from:
-Observation of work planning meetings.
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-Review of selected radiation work permits in use in-the field.
l-Observation of worker briefings.
-i-Interviews with selected personnel.
Within the scope of this review, no violations were. observed.
Several strengths and improvements were-noted during this. outage including the following:
i; The licensee implemented a centralized Outage Control Center in the.
I administration building conference room.
The Center was manned around the clock and was the' focal point for all decisions affecting work.
Shift turnover meetings (every'12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) were. held in-this room and included an overall status of scheduled and actual work. Corporate staff
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and others were tied into each meeting via'a conferenceJtelephone-
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network. The inspector noted that the radiological outage controls appeared to be strict..Only work ~ authorized by the Center as shown on the l
Maintenance Work Plan was performed. LSimilarly,- the. status of work in.
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progress was accurately reported.
This represents.a significant
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improvement in preplanning, scheduling and controllof work.
Several state of the art items of equipment:were introduced during the _
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- i outage. Two'new computer controlled."portacount"Ldevices were used to fit-
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test workers for respirator u:,e.c A digital alarming dosimeter. (ALNOR)
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.was issued to alliworkers entering the drywell. ~ These devices-provide'
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audible alarms at preset. doses:and dose rates.
Sensitive new portal
monitors (Eberline PM-7) were installed.at' the main and contractor '
i personnel exit gates. Thesi provide:a final l check for' contamination as-personnel leave the site.
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A'new Pilgrim Nuclear Power Station Personnel.' Radiation Exposure _ Policy
(Nuclear Policy: C.3.11) was ~1ntroduced'that set administrative exposure i
limits for workers at 750. mrem per quarter 'and 1500 mrem per year. The
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Radiation Protection Manager stated that'only;twoLinstances-occurred
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during the outage that required approval to exceed.the. quarterly limit.
These limits are well below the regulatory criteria set by the ~NRC..
A daily exposure report was issued 'during the. outage. 1Th%.information allowed management to_ quickly detect adverse trends : eMnough this'
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initiative was somewhat impacted by the unreliability-of the computer t
system used to produce the report. Management stated that; efforts to debug the computer _ hardware and software'are continuing.
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The inspector noted inconsistencies in radiation._ protection procedures-such as the radiation work permit L and Locked High Radiation-Area procedures. The licensee's QA organization had also-identified procedure weaknesses in Audit 89-51 and issued Defic.iency Report-(DR).#1884.
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licensee stated that management is aware of these' weaknesses.and-has
draf ted revisions for several' radiation protection procedures.
In addition, all radiation protection procedures will be reviewed and--
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upgraded by September 1990.
Completion of.this project _wil_1 be reviewed
.in a future inspection.
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6.0 ALARA
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Licensee efforts to maintain personnel exposures As Low As Reasonably Achievable (ALARA) during the outage were determined from:
-A review of the October Mini-Outage ALARA Report.
-March-April Outage interim status reports provided by the ALARA'
group.
-Interviews with selected personnel and a review of selected records.
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Within the scope of-this review, the. inspector determined that the
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licensee's ALARA performance continuesito show excellent improvement.,
The;1989 cumulativc e posure of 211 man-rem ranked Pilgrim as the fifth-x
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lowest-among the A vnestic BWR plants. The 1990- gJa1 is 185. man-rem,';of
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which 73 man-rem is tlocated to the o~utage.
This compares favorably:
M with the:BWR industry; average of'about 400 man-rem.
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a Continued improvement and refinement of the ALARA program was' demonstrated
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during work ~on the Reactor Water; Clean-up:(RWCU) heat exchangers (Hx).
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May 1989 the "A'!-RWCV-Hx was repaired,; resulting in a' 6.42 man-rem.
exposure.
In the; current' outage, both the "B".and "C" had similar repairs
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completed at a total-of 4.5' man-rem, a' reduction of a factor of 3 in the
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exposure. -The inspector'also noted.that closed circuit TV monitors'were
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being installed in theiRWCU-Hx room.
This eliminates-the:need for.
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operator-entries to inspect the equipment, thereby reducing; routine j
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operations exposu.res.
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' Efforts underway to'further reduce exposures include:
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-training of personnel and use of hydrolazing equipmentito clean contaminated. floor drains and tanks. to reduce' general area: radiation
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levels.
-Implementation of a central control pointJtoLcontrol all: personnel l l
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-access to the radiologically controlled areas. :This will, become J
L operational'in June' 1990 for-a 6 month trial period...
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-Replacement of:the spent resin storage tank in the'radwaste building.
i with.a closed v'essel. 'This one million dollar project will enhance-i the safety-of' spent resin transfers and reduce-.radwaste operator-
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-Completion of the design' and fabrication of a portable, co111 mated
detector to identify and characterize " hot-spots" in plant systems.
These hot spots will then be eliminated.
The inspector had no further questions.
7.0 Exit Interview
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. The inspector met with the personnel denoted in Section"l'.0 at the completion of this inspection on April 20,' 1990
.The scope and findings li were presented at'that time.