IR 05000101/1974002

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Insp Repts 70-0903/74-01,50-101/74-02,50-290/74-02 on 740909-11 & 15-16.Major Areas Inspected:Selective Exam of Procedures & Representative Records,Interviews W/Personnel & Measurements/Observations Made by Inspectors
ML20092A231
Person / Time
Site: 05000290, 05000101, 07000903
Issue date: 04/24/1974
From: Jerman P, Knapp P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20091R728 List:
References
FOIA-90-406 50-101-94-02, 50-101-94-2, 50-290-84-02, 50-290-84-2, 70-0903-74-01, 70-903-74-1, NUDOCS 9202100019
Download: ML20092A231 (32)
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. U. S. A'J0'11C E!;ERGY C0:2115510:; DIRECT 0nATI: OT REGULATORY OPTIATIONS REC 10:1 1 70-903/74-01 70-903 50-101/74-02 50-101 to Inspection Report lion 50-290/74-02 Docket 1o 50-290 ' 6:01STl Gulf Nuclear fuelr; Corporation License 1;o R-4 9 Licensect CX-25 Crnnsinno Pond Priority J Elmsford, New York 10523 Caterory: (A 1) G Locatfon Pawlinr,, New York , _ Fuel Fabrication and Roscarch and Test Reactor Operation Type of Licensect Type of Inspection: Ann unced Close Out Inspection ' April 9-11 and 15-16, 1974 Dates of Inspection November 26-28, 1973 Dates of Previous Inspection .&; - ~ ~.bb ' n -$ . J. asf. 7 *! " Reporting Inspector.: "" Ph,1111p C. Jerman, Radiation Specialist 'T~*- 'l d'/- 7'l Accorpanying Inspectors: N - - Date April '.5 & 16, 1974 P. J. Knapp, Senior, Pacilities Radiological Protection Branch . Date Date

Date , , Other Accompanying Personnel: Nonc _ Unte (.. - -- , ' ' \\ ~ f./.,' u. 7 t ! ~ 1) ' L Reviewed By: m , U"I* ' P.J. Knapp, Senior ' Tacilities Radiological Protection Section 9202100019 910621 PDR FOIA NORfIS,90-406 PDR '11 O " J- _ _ - -. - - _. _ - _ _ _ _ _ - - _ - - - _ _ _ _ _ - _ _ _ ______ _ _

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I SUttiARY OF TINDINGS I ..iforcement Action ' A.

Violations

' None' t

. B.

Safety items.

i None , License Action on Previously Identified Enforcement items ! Not applicable , ' , .

Unusual Occurrences ~

! None.

, ( .. t Other Sinnificant Findings- . J-

A.. Current Findinge j

Atcor, 1pcorporated, Peckskill, N.Y. under contract with the licensee, > surveyed.the licensee's entire Pawling. H.Y. plant and carried out all , work necessary to' reduce contamination levels to below those'specified ' in the, " Guidelines for-Decontamination of Facilities and Equipment Prior To-Release For Unrestricted Use or Termination of License for y Byproduct Source or Special-Nuclear Material," issued by the Directorate

' of Licensing. Atcor, Inc. holds AEC Byproduct Material License No.

, 31-11640-01 under which the. work was.done.- The inspection consisted i of a radiation survey to verify contamination levels at the plant fa-r cilities as reported by the' licensee to the AEC in-letters dated !! arch l .11 and 13, 1974.- The_ existing contamination levels appeared to meet the Directorate of , Licensing guidelines for tennination of License Nos. SN>t-871,-R-49 and ! CX-25.

.

~ B.

Status of Previously Reported Unresolved Items ' None , Hanngement Intervlew . The'following' individuals attended the management it.terview at the conclusion ' of the inspection on April 16,'1974.

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, . , -2- . Gulf J. E. Anderson, Plant Manager ,Attor J. Ssiger, President R. Lovesque, Radiation Protection Officer

At3 P. J. - Kn a p p P. C. Jerman The inspectors informed the Gulf and Atcor representatives that all in-strument surveys and resurveys f ollowing neccesary decontamination indicated

that contamination leve19 inet the Directorate of Licensing guidelines for release of the facilities and that vipes taken would have to be counted at R0:1. On April 17, 1974, P. C. Jerman informed J. E. Anderson that two wipes taken inside small diameter pipes which penetrated the wall between two rooms, a showed excessive alpha contamination.

Later that day, J. E. Anderson in-formed RO I that the contaminated items had been removed for disposal.

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I 'o ) ~ ' ' . , - \\ j a =. , l i REPORT DETAILS ! 1.

Persons contacted l

- J. E. Anderson, Culf, Plant !!aanger P. Loysen, Culf, !!anager, Regulatory Administration E. C. Iloiman, Atcor, Vice Preside.nti Operations - 0. Sullivan, Atcor, Project Manager

- R. Levesque, Atcor, Radiation Protection Officer

2.

Material Possessed and Processed _under the Licensen a.

The-Pawling Plutonium Facility operated from 1961 to 1965 under AEC contract.

Since 1965, under AEC license the facility had used Pu and U for fuel development work.

Early iri the period, the facil-ity included a Gamma Laboratory for studying ' irradiated fuel material.

  • In December, 1972, an explosion occurred in a Pu glove box which caused signi'icant contamination within the facility.

The facility

did not resu o the manufacture of fuel following the explosion.

t b.

The Critical. Facility had housed the Pawling Lattice Test Rig;since 1960 and the Proof Test Facility since 1967. At the time of thia inspection the reactors' had been completely dismantled and removed ' from the facility.

' 3.- Instrumentation l ,

a.

JSurvey meters .,

1)_ _For the alpha surveys, an Eberline PACISA, (Scrial No_. 720) was _ used.

It was calibrated by Brookhaven National Laboratory on - March 23 1974. An Eberline-Pu source (Serial No. 6786) which i is certified to be 1285 cpm, 2Pi, was used to check the instru- -ment.

2) For beta-gamma surveys two Eberline Model E-120lGM Heters, with . 2 of absorber, ' end nindow probes containing about 2 milligrams /cm were used.' The serial numbers were-1269 and 3174. The two me-s ' ters' were calibrated against Co-60 gamma radiation by Brookhaven . National Laboratory on January 22, 1974. This calibration would-be accurate for most beta-gamma measurements, but would not be accurate for measuring beta radiation from uranium. An instru-ment of-the same model was calibrated with beta radiation from - natural uranium.

In this case it was found that the mR/hr read-l ing had to be multiplied by a factor of'six or slightly more to ' obtain true mrad /hr readings from uranium.

+ " Surveys made with the E-120 s during this inspection showed no more than 0.05 mR/hr.

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Countinn Instruments surface area were counted for alpha in an Wipes taken over 100cm2 Eberline Model SAC-4.

Calibration war. accomplished through the use ' of a certified Pu-239 source. The wipes were also counted in an Eberline Model LCS-1 with an RD-14 Beta Detector. The instrument was calibrated through the use of a certified Sr-90 source.

' 4.

Faeflitles Surveyed Figure I shows the location of the buildings at the pawling site.

De-tailed surveys vere conducted in the Critical Tacility which housed the test reactors, the Plutonium racility where uranium and plutoniun fuels were manufactured and the waste pit which reportedly was never used.

' The two facilities had, contained AEC Ifcensed material.

Cursory surveys were conducted in the Remote Assembly. Building, Storage Building, Lodge - Engineering Building, ilock-up Building and Multiple railure Building.

A license representative stated that these buildings normally did not contain AEC licensed material.

However, the Mock-up Building was uscd for storige of drums containing contaminated waste resulting from the - clean-up of the plutonium racility.

Also, the employee whose person was contaminated with plutonium during the December,197/ explosion was decontaminated in the Remote Assembly Building.

5.

Surveygesults a.

The Directorate of Licensing guidelines for release of licensed facilities specify that plutonium total contamination levels may not exceed an average of 50N ow or a maximum of 2500dpm alpha /100 cm2 They also specify that total beta-gamma contamination may not exceed 0.4 mrad /hr at lem and removable beta-gamma contamination may not exceed 1000dpm/100cm2 b.

All surveys conducted by the AEC inspectors showed no contamination IcVels exceeding the guidelines except as followst 1) One section of the upper level of the east wall in the Gas House of the Plutonium Facility showed an average of about 800dpm/100cm2 over 10 square meters.

The maximum was 2000dpm.

The wall was c1 caned by the licensee's contractor personnel to an average of less than 500dpm alpha and a maximum of about 1000dpm as measured by the AEC inspectors.

2) Wipes taken inside five sections of').5 inch conduit in the wall ' between the pilot Area and the Weld and Load Area in the plutonium Facility showed 200 to 235dpm alpha /100cm2 On' April 15,1974 the inspectors observed that three sections had been removed from the wall. A licensee representative infortned R0:1 by phone on April 17, 1974 that the other two sections had been removed for disposal.

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g % >J - State of New York STAFF COORDIN ATOR CH AIRM AN j ' NE AL L. MOYLAN Department of Commerce DEPUTY OM M ir. ONtR COMMISalONER OF COMMERCE 99 Weehin0 ton Avenue DIV. OF INDusTRI AL SCIENCt'S Albany. New York 12210 AND TECHNOLOQlES June 7, 1974 h f, H 0 R A N 2 y H 10 1 Peter Knapp - Region 1, l'. S. AEC f

PR014: Fred V. Strnisa 4y SUliJECT Gulf-United Nuclea : Tuels, Pawling New York Enclosed per our discussion is a copy of Section 7.0 of the report prepared by Atcor, Inc., entitled " Final Survey Results Af ter Decontamination, Gulf-United Nucicar Fuels Corporation riutonium Facility, pawling, New York.

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