ML20073B504

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Annual Rept for 1982
ML20073B504
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 04/06/1983
From:
JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML20073B502 List:
References
NUDOCS 8304120439
Download: ML20073B504 (5)


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1 SAXTON NUCLEAR EXPERIMENTAL CORPORATION ANNUAL REPORT FOR THE PERIOD OF JANUARY 1,1982 - DECEMBER 31, 1982 t-l B304120439 830406 PDR ADOCK 05000144 R

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4 Annual Report in compliance with Paragraph B.5.b of the Technical Specifications a

l 1.

"Information relating to changes in those staff positions that are designa-i ted as being responsible for the deactivated facility."

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In September 1982, a new Manager for-the Radiological & Environmental Mon-itoring Program was a9 pointed, and the Vice President of SNEC was designa-ted as the responsible Corporate Officer, pursuant to NRC Regulation 10CFR.

21. 21(a).

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j 2.

"A summary of entries into the Containment Vessel or Radioactive Waste Disposal Facility, and the. reasons for entry."

Entries were made into the Containment Vessel and/or Radioactive Waste Disposal Facility, as follows:

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Date Purpose

1) 03-19-82 First Quarter Radiological Survey j
2) 04-02-82 Environmental Survey and First Quarter TLD Change J

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3) 05-13-82 Radiological Sampling 1

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4) 06-08-82 Site Inspection i
5) 06-09-82 Second Quarter Radiological Survey
6) 09-22-82 Third Quarter Radiological Survey

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7) 10-01-82 Third Quarter Environmental Survey and TLD Change j
8) 10-18-82 Installation of Security Bars on Windows-2
9) 12-16-82 Fourth Quarter Radiological and Environmental Surveys and TLD Change i

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10) 12-17-82 In addition to the above, TMI Nuclear Station j

Communication Department video documentation a

l 3.

"A summary of maintenance and design changes made to the deactivated facil-ity."

2 i

In. March, 1982, the drain pipe in the Containment Vessel was cut and capped in an attempt to prevent-the flow of water to the Containment Vessel sump.

In October, 1982, security bars were installed on selected windows and doors

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of the Control and Auxiliary '(C&A) Building, and the Radioactive Waste Dis-posal Facility (RWDF) Building.

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"Results of surveys of radioactivity levels and of water sample analyses."

Results of the 1982 Quarterly Inspections of the facility are as follows:

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1) Radiation levels at the exclusion area fence ranged from<0.01 mR/hr to

<0.06 mR/hr.

2) Radiation levels at the Containment Vessel's breather pipe filter ranged from<0.05 mR/hr to<0.02 mR/hr.
3) Radiation levels at the 20 permanently marked survey points in the Containment Vessel ranged from<0.02 mR/hr. to<0.12 mR/hr.

Smear surveys from the same 20 points yielded a range of<500 to 9,000 dpm.

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4) Radiation levels in the Containment Vessel above elevation 812' ranged from.05 to 0.1 mR/hr.

See attachments: Table 1 - SNEC Pipe Tunnel Water 1982 Table 2 - SNEC RWDF Building Water 1982 Inspection of the Containment Vessel lower levels indicates the vessel is i

dry and free of water.

The water in the Containment Vessel sump, reported by SNEC letter-to NRC Office of Inspection and Enforcement dated April 27, 1982, was removed j

from the sump, packaged with Vermiculite in two 55 gallon drums, and stored in the Containment Vessel.

l-5.

"A summary of the performance of security and surveillance measures."

There were no observed attempted break-ins, vandalism, or other security breaches at the facility during 1982.

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TABLE 1 SNEC PIPE TUNNEL WATER 1982 (uci/ml) i 1st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

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Isotope 3/19/82 6/9/82 9/22/82 12/17/83 t

I-131

~<3.0E-8

<1.5E-7

<l.2E-7

<1.1E-7 Ca-134

<3.4E-8

<2.6E-7

<l.5E-7

<l.5E-7 i

Os-137 2.2E-7 2.0E 2.7E-7 4.5E-7

._2.4E-8

+

+7 8E 8

_6.2E-8

+

+

_.1.lE-7 Co-58

- <3.1E-8

<2.4E-7

<l.4E-7

<l.4E-7.

Co-60

<4.4E-8

< 3. 6E-7

< 2. 0E-7

. <2.0E-7 G-Beta

<5.53E-6 1.4E-6 2.3E-7 i

2.2E-7 4.0E-8 i

  • Gross Beta analysis was inadvertently omitted i

from the request for analysis.

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TABLE 2 i

l SNEC RWDF BUILDING WATER 1982 fuci/ml) i 1st Qtr.

2nd Qtr.

3rd Qtr..

4th Qtr.*

Isotope 3/19/82-6/9/82 9/22/82 12/17/83 I-131

' 1.0E-7

<1.4E-7

<1.8E-7

<2.0E-8 i

Ca-134

<1.5E-7

<1.5E-7

<2.6E-7

<7.0E-9 Ca-137 2.6E-7 2.7E-7

<3.6E-7 3.2E-7

+7.0E-8

+5.5E-8

+3.3E-8 4

4 Co-58

<l.4E-7

<l.4E-7

<2.4E-7

<6.0E-9 i,.

Co-60

<2.0E-7

<2.0E-7

<3.6E-7.

<6.0E-9 G. Beta

<3.9E-6 1.8E-7 1.8E-7 3.8E-7 I

1.2E-7 i3.8E-8' l.0E-8 i

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  • The difference in LLD levels between Quaters

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1-3,and 4 are due to a change in analytical laboratories.

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