IR 05000283/1988029

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Insp Rept 50-283/88-29 on 880818-20.No Violations or Deviations Noted.Major Areas Inspected:Use of NRC Mobile Radioanalytical Lab to Perform Independent Measurements of Soil to Determine Existence & Level of Contamination
ML20154J311
Person / Time
Site: Pilgrim, 05000283
Issue date: 09/07/1988
From: Ronald Bellamy, Kottan J, Pasciak W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20154J308 List:
References
50-293-88-29, NUDOCS 8809220322
Download: ML20154J311 (6)


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U.S. NUCLEAR REGULATORY COMMISSIGN

REGION I

Report No.

50-293/88-29

Docket No.

50-293

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License No.

DPR-35 Priority Category C Licensee:

Boston Edison Company M/C Nuclear I W Boyiston Street Boston Ha m h.sett,s 02199 Fscility Name: UljrimNu

/ower Station l

Inspection At: Plymouth, Massachusetts l

Inspection Conducted:

August 18-20, 1988

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IN N D 5 l' OO Inspectors:

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J. J. Kotta$ Laboratory Specialist date

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W. J. ; PasFiak, Chief, Ef fluents

/ dafe RadiaMon Protection Section, FRSSB Approved by:

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't h.R.BeTlamy,ChieCfackles ate Radiation Safety & Safeguards Branch

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l Inspection Summary: Inspection on August 18-20, 1953 (Report No. 50-293/89-21

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Areas Inspected:

Special announced inspection of contarainated soil stored onsite and of olfsite laydo n area. Areas reviewed included use of NRC mobile

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radicanalytical laboratory to perform independent measurements of soil to

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determine existence and level of contamination.

Results:

No violations or deviations were identified.

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8S09200322 80050s PDR ADOCK 05000293 O

FDC

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DETAILS 1.0 Person _s Contacted 1.1 Boston Edison Company K. Highfill, Station Director P. Hamilton, Compliance Division Manager E. S. Kraf t, Jr., Plant Support Dept. Manager

  • J. P. Jens, Radiation Section Manager W. P. Mullins, Radiological Operations Division Manager T. L. Sowdon, Chief, Radiological Scientist
  • R. Anderson, Plant Manager
  • R. Grazio, Regulatory Affairs Section Manager C. Bowman, Environmental Section Manager B. Dionne, Senior Environmental Scientist 1.2 Nuclear Regulatory Commission C. Warren, Senior Resident Inspector
  • denotes those individuals attending the exit meeting on August 20, 1988.

2.0 Purpose and Scope The purpose of this inspection was to sample and analyze dirt samples onsite and offsite.

The onsite samples analyzed were collected from piles in the new contaminated dirt storage area and from locations where this dirt was previously stored.

The offsite samples analyzed were from the offsite laydown area off the station access road. All samples were collected by use of a coring tool.

Core depths of samples varied from one to two feet.

Gammi spectrometry analyses of the samples were performed utilizing the NRC:I Mobile Radiological Measurements Laboratory.

Each sample of approximately 600 grams of soil was counted for 1000 seconds.

A background soil sample was taken and analyzed, with the background results subtracted from each soil sample results.

3.0 Analytical Results Samples were taken from two on-site locations.

They were taken from the existing dirt storage pile which was located in the east end of the lower contractor parking lot, and from the soil below the surface where the soil was previously stored in the upper contractor parking lot.

The soil was moved in early August, 1988, to locate it further away from wetland areas.

Thirty samples were collected from the dirt piles in the new storage location and four samples were collected from just below the surface in the old dirt storage area.

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The approximate amount of dirt stored in this area is 65,000 cubic feet.

This was determined when it was moved to the new location by multiplying the number of truck loads by the volume of each load.

Licensee representa-tives stated that six tamples were collected from each load fer future analysis but no analysis had been made at the time of the inspection.

The contaminated soil was accumulated over a few years (1985-1986) as a result of various construction projects.

Four projects contributed the majority of the soil and were (1) installation of the third diesel generator; (2)

Appendix R fire protection modifications; (3) excavation of the foundation for the hydrogen water chemistry injection building; and (4) security modifications.

The soil was placed in this pile during the time period of January 1985 through December 1986.

The soil stored in the pile does not represent all the excavated soil from a particular activity, but only that amount that was known or thought to be contaminated with radioactivity.

In its present location, the soil is on top of a layer of polyethylene film.

The area is enclosed by an eight foot high fence and attached to the fence is a double layer of polythylene film forming a wind barrier.

Polyethyene film was also placed on top of the pile of soil but was noted to be only about 50% effective as much of it had fallen off the piles. The licensee stated that they were considering getting a heavier material to cover it to more effect.ively prevent wind and rain erosion.

In its present state, it is likely that erosion of the pile could take place which could result in the spread of contamination. Protection of the pile

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from wind and rain erosion will be reviewed during a followup inspection (83-29-01).

Attachment 1 provides the results of NRC measurements. Attachment 2 provides the licensee's numbering scheme fer each truck load of dirt and is used in identifying sample locations in Attachment 1. Of the 30 samples analyzed, the average concentration of Co-60 was 350 pC1/kg and the maximum concentration was 3200 pCi/kg.

The four surface samples taken from the upper contractor parking lot had concentrations of Co-60 of 70, 70, 80 pC1/kg, and the last was less than MDA. Co-60 was the only nuclide found in the soil that was directly attributable to station operation.

Attachment 3 provides locations from which samples were collected in the offsite laydown area. All analysis results in this locations were below MDA.

4.0 Exit Interview

The inspector met with the licensee representatives noted in Paragraph 1 at the conclusion of the inspection on August 20, 1988.

The inspector summarized the purpose and scrpe of the inspection and the inspection finaings.

At no time was written material provided to the licensee.

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ATTACHMENT 1

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NRC ANALYTICAL RESULTS - Co-60 ONSITE SAMPLES; DIRT STORAGE PILE

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SAMPLE NO.

LICENSE PILE NO.

CONCENTRATION (pCi/kg)*

1 3200 400

3 430 90

3 11002200

3 300 60

4 80 20

5 110 30

6 340 90

7 200 50

27

<MDA*

32 120 40

35 180 40

38 270 70

49 1100 200

49 420 80

49 1100 200

55 120 40

64 300 70

68

<MDA

70 30113

76 20 7

79 200 50

83

<MDA

94 110 30

106 150 40

112 110 30

119

<MDA

120 270 70

124 130 40

128 120!40

B-24

<MOA UPPER CONTRACTOR PARKING AREA Sample No.

Location Near Entrance 70 20

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Midway Back Near South Fence 70 20

Way Back Near North Fence 80120

Wetland Sample (South)

(M0A

  • MDA = 138 pCi/kg, concentration values reported are af ter background (200 pC1/kg) was substracted out.

NOTE: The reported uncertainty is the counting uncertainty at one standard deviation (lo).

Estimated systematic uncertainty is 25*....

o ATTACHMENT 2

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PILGRIM NUCLEAR POWER STATION

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Radiation Survey Form Map No.

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Survey by:

Date:

Time:

RWP No.

Dose Rate Instr.:

Ser. No.

Beta Dose Rate: O yes O N/A Ccntamination Instr.:

Ser. No.

MDA Beta:

MDA Alpha:

AS Data:

MPC's (No PF)

Reactor Power:

Activity uCilce dpm/100 cm2 No.

Beta Alpha

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ATTACHMENT 3 NRC ANALYTICAL RESULTS - Co-60 0FFSITE LAYDOWN AREA SAMPLES pCi/kg SAMPLE NO.

CONCENTRATION

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