IR 05000289/1978006
| ML19276H262 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/10/1978 |
| From: | Clemons P, Knapp P, Plumlee K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19276H253 | List: |
| References | |
| 50-289-78-06, 50-289-78-6, NUDOCS 7910150884 | |
| Download: ML19276H262 (5) | |
Text
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NUCLEAR REGULATORY COMMISSIL..
OFFICE OF INSPECTION AND ENFORCEMENT
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Region I port No. E 9g/79_r
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Docket No.
50-2ec License No.
OpR-50 Priority Category C
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Licensee:
v trocolitan Edison Comcany
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e D. O. Box Sa2 Readinc. Pennsvivania 19603
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Facility Name:
Three Mile Island Nuclear Generating Station, Unit 1 Inspection at:
Mi*ddletown, Pennsylvania Inspection conducted:
an-1 2-4, 1978 c
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Inspectors: MI J c t.u [; It
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/ /,. E. Plumlee, T<ac1ation Specialist cate signed fh Ybb !
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P. E. Clemens, Raciation Specialist cat'e signec
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Approved by:
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e P. J. fnapp, Chief, Raa1ation Support cate signed Section, Fuel Facility and Materials Safety Branch Insoection Summary:
Inscection on Acril 2-4. 1978 (Recort No. 50-289/78-06)
Areas Inscectec:
Routine, unannounced inspection of tne radiation protection program curing a refueling outage, including:
procedures; advanced planning and preparations; radiation protection training and qualifications; exposure control; posting and control of radiation areas and high radiation areas; labeling and control of radioactive materials and contaminated equipment; surveys; and re-sairatory protection program. The initial inspection and area examination was conducted during non-regular hcurs (April 2,197S, 8 p.m.-Midnight).
This inspection involved 40 insoector-heurs onsite by two NRC ins:ectors.
Resul s:
Of the eight areas inscected nc items of ncncomoliance or ceviations were icer.ti'#ec in seven areas.
One item Of ncncomoliance was identi'ied in
- ne area,': #-ac-ion inacecuate survey
- aracraon 2),
1411 075
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DETAILS 1.
Persons Contacted a.
Metrocolitan Edison Comoany Personnel M. Beers, Station Shift Suoervisor
- R. Dubiel, Supervisor of Radiation Protection and Chemistry E. Fuhrer, Engineer II - Nuclear L. Landry, Engineer II - Nuclear
- T. Mulleavy, Radiation Protection Supervisor
- J. O'Hanlon, Unit 1 Superintendent J. Taylor, Site Protection Supervisor
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R. Zeckman, Group Supervisor, Nuclear and Technical Training J. Wealand, Administrator of Safety
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b.
Nuclear Succort Services (NSS) Personnel D. Ferguson, Supervisor
- L. St. Laurent, Supervisor
- Denotes those present during the exit interview, a:30 p.m.
April 4, 1978.
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2.
Survevs 10 CFR 20.201, " Surveys," requires that each licensee make or cause to be made such surveys as may be necessary for him to comply with the regulations of 10 CFR 20. As defined in 10 CFR 20.201 section (a) " survey" means an evaluation of the radiation hazards incident to the production, use, release, disposal, or presence of radio.
active materials or other sources of radiation under a specific set of conditions.
10 CFR 20.202 " Personnel monitoring" requires that (a) Each licensee shall supply appropriate cersonnel monitoring eouipment to and shall require the use of such ecuipment by:
(1) Each, individual wno enters a restricted area under such circumstances that he receives, or is likely to receive a dose in any calendar cuarter in excess of 25 percent of the applicable value scecified in paragraon (a) of : 20.101....(b) As used in this cart, (1) "?ersonnel mont-t: ring ecuictent" means devices designed o be worn cr carried by ar 'ncividual for :ne curcose of measurinc :ne cose received (e.c.,
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- acges, :ccke: : nam:ers, ;ccke; dosimeters, #':r rings, etc.):
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The values specified in paragraph (a) of f 20.101 are listed below along with 25 percent of each value.
Rems per calendar quarter (25", values)
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1.
Whole body; head and trunk; active blood-forming organs; lens of eyes ; or gonads.................
I 1/4 (0.32)
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Hands and forearms; feet and
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ankles.............................
18 3/4 (4.69)
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3.
Skin of whole body.................
71/2 (1.88)
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During a review of survey records on Acril 4, 1978 the inspector noticed that the gamma radiation intensities in steam genera. tors A and B were recorded as 8 and 9 R/hr maximum at contact.
The ganza radiation surveys were taken with a Teletector.
Based on these surveys, the licensee permitted personnel entries into the steam generators, provided.that each person wear a TLD monitoring device on the upper trunk of the body.
No extremity
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monitoring was required by the licensee.
Entries were made between March 23 and April 1, 1978, and according to the TLD devices, exposures ranged between 0.1 and 0.965 rem, penetrating whole body
radiation.
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On April 4, 1978, the licensee used TLD badges to re-evaluate the steam generator radiation levels.
On May 3,1978, the licensee's representative stated in a telephone conversation with the inspector that this survey indicated 45 R/hr gamma and 43 rads /hr beta dose rate at contact;and 7.6 R/hr and 21 rads /hr at a distance of cne foot from the tubesheet.
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The inspector noted that this evaluation made with TLD badges indicated that the dose rate due to penetrating radiation was six times greater at contact than at a distance of one foot from the steam generator tubesheet.
Since entries into the steam generators rade it necessary for personnel to stand on the tube sheet temolate, their extremities (feet) were in a significantly higher intensity field as compared with the TLD badge (worn above the waist). The inspector indicated that in such a situation personnel could be expected to exceed 25% of the apolicable extremity.value specified in 10 CFR 20.101(a), and would consecuently recuire extremity monitoring in accord with 10 CFR 20.202.
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a The inspector noted that failure to adequately perform surveys in the steam generators sufficient to determine the need for extremity monitoring in accordance with 10 CFR 20.202 constituted noncompliance with 10 CFR 20.201.
(78-06-01)
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3.
Cther Insoection Items The inspector reviewed the following items and no examples of non-compliance were identified in these areas of the inspection:
a.
Radiation Protection Procedures: The inspector reviewed pro-cecures and rac1ation work permits that were used during the outage and found that adequate provision for radiation pro-tection appeared to be incorporated into these procedures and permits.
b.
Advanced Planninc and Precaration for the Outace:
The in-spector reviewed tne licensee's preparations for the outage which included advance preparation and review of procedures
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for major jobs, familiarization of the maintenance crews with
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appropriate mockups and equipment, and arrangements for the increased work force and longer shifts during the outage.
The licensee preparations placed particular smphasis on the high exposure jobs (inservice inspection tests of the steam generators, the plugging of steam generator tubes, the re-placement of a letdown cooling system heat exchanger, and the removal of the in-core detectors).
c.
Conduct of Work Durino the Outaae:
The inspector toured the facility curing a backsnift and cayshifts to observe the workers use of specified protective clothing and equipments and the workers adherence to prescribed stay times and work restrictions.
No neglect of these requirements was identified.
d.
Trainino: The inspector observed that the training required by 10 CFR 19.12 and by the licensee's precedures was provided to individuals prior to their being admitted to.the facility; and that additional training was required to qualify personnel who were scheduled to perform work requiring Radiation Work Permits and respirators.
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- Before their records were stamped to allow the use of respira-tors, personnel were giver, physical examinations with a medical doctor's evaluation.
Each individual was fitted and the respirator protection factor was measured in a test booth.
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e.
Control of Contaminated Ecuioment: The inscector observed the control of contaminatec equipment and tools, the management of discarded protective clothing and respirators, and the disposi-tion of waste.
The inspector also observed the labels containers of radioactive ~ materials.
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Postina of Radiation Areas, Hich Radiation Areas and Contaminated Areas: The inspector made confirmatory measure-ments of radiation levels and observed the posting and control of access to Radiation Areas, High Radiation Areas, Contaminated Areas, and Airborne Radioactivity Areas.
No items of non-compliance or deviations were identified.
4.
Exit Interview
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The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the on site inspection.
The inspector stated that the following items would be reviewed in the regional office and the licensee would be informed of the outcome by telephone.
a.
Adequacy of surveys *.
b.
Adequacy of personnel dosimetry *.
The licensee representative was infomed by telephone on May 3,-
1978 that the review of the above items had identified one item of apparent noncompliance; inadequate surveys.
- The licensee representatives provided additional information by telephone on April 5, 7, 10, 17, and May 3,1978.
The review of this information is included in Paragraph 2.
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