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

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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."

i I 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:

] 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

i 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

l 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- l 2

ity." '

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.

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

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

! posal Facility (RWDF) Building.

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4. "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.

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  ;

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._2.4E-8 +

_6.2E-8 +

_.1.lE-7 +7 8E 8 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  !

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  • Gross Beta analysis was inadvertently omitted i from the request for analysis. ,

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

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