ML20073B504
| 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."
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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
~<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.
<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,.
<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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