ML20214J287

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Corrected Tables 1,2,3,5 & 6 to Saxton Nuclear Experimental Corp,1985 Annual Rept
ML20214J287
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 12/31/1985
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20214J274 List:
References
NUDOCS 8608140571
Download: ML20214J287 (4)


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TABLE 1 SNEC Contaimnent Vessel (CV) Sump Water Analysis Results 1985 (uCi/ml)

Radio- 1st Qtr. 2nd Qtr. 3rd Qtr.* 4th Qtr.*

nuclides 03-19-85 05-09-85 07-16-85 10-29-85 Cs-137 2.6,+.0.1E-3 2.0+0.1E-3 ,

Cs-134 1.9+0.1E-5 1.4+0.1E-5 --- ---

Co-60 < 4.7 E-7 <2.0E-7 --- ---

Gr Alpha '

t.8E-7 <6.1E-7 --- ---

Gr Beta / Gamma 3.0+0.1E-3 2.6,+0.1E-3 --- ---

H-3 8.9,+0.1E-4 8.9,+0.3E-4 --- ---

Sr-90 2.2+2.2E-5 9.8+0.7E-6 --- ---

Equipnent Hatch Sump (Operating Deck) Analysis Results (uCi/ml)

Radio- 1st Qtr.* 2nd Qtr.* 3rd Qtr.* 4th Qtr.

nuclides 03-19-85 05-09-85 07-16-85 10-29-85 Cs-137 --- --- ---

2.1,+ 0. 2E-5 Cs-134 --- --- ---

1. 4,+0. 3E-7 Co-60 --- --- ---

<3.0E-8 l Gr Alpha --- --- ---

1. 6,+0.7 E-8 Gr Beta / Gamma --- --- ---
2. 3,+ 0.1E-5 1

H-3 --- --- ---

7.8,+0.1E-4 Sr-90 --- .

3.5,+0.4E-8

  • No water present in sump.

8608140571 860425 i

PDR ADOCK 05000146 R PDR

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TABLE 2 RWDF Analysis Results 1985 ,

(uCi/ml)

Radio- ist Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

nuclides 03-19-85 05-09-85 07-16-85 10-10-85 Cs-137 1.8+0.8E-7 2.8+ 0.7 E-7 2.0+0.5E-7 2.5+0.4E-7 Cs-134 <1. 4E-7 <7 . 5E-8 <4.3E-8 < 2. 5 E-8 Co-60 <1.8E-7 <1.0E-7 <5.4E-8 <3.1E-8 Gr Alpha <5.1E-9 <6.1E-9 <7 . 2E-9 <3.6E-9 Gr 8 eta / Gamma 3. 4,+ 0.7 E-7 3. 0,+ 0.7 E-7 3. 2+0.7 E-7 3. 5+0.8 E-7 H-3 <3.8E-6 <4.2E-6 <3.8E-6 <4.0E-6 Sr-90 <3.2E-8 <3.4E-8 <3.3E-8 <3.9E-8

/ TABLE 3 h3pe Tunnel Analysis Results 1985 (uCi/ml)

Radio- 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

nuclides 03-19-85 05-09-85 07-16-85 10-10-85 Cs-137 <2.3E-7 1. 6+ 0. 4E-7 2.7 + 0. 4E-7 5. 4+1. 6E-7 Cs-134 <1.4E-7 <4.3E-8 <2.5E-8 <7 .1E-8 Co-60 <1.8E-8 <5.4E-8 <3.1E-8 <9.2E-8 Gr Alpha <5.1E-9 <6.1E-9 <7 . 2E-9 <3.6E-9 Gr Beta / Gamma 2.9 + 0.7 E-7 2.3+0.6E-7 2.2+0.6E-7 6.7 +0.9 E-7, H-3 <3.6E-6 <4.0E-6 <4.0E-6 <4.0E-6 Sr-90 <3.4E-8 <3.3E-8 <3.5E-8 <4.2E-8 i

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TABLE 5 SNEC CV Snear Surveys 1985 20 Permanent Survey Points (dpm) ist Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

i Survey Point No. 03-19-85 05-09-85 07-16-85 10-29-85 1 <1,000 <1,000 <1,000 <1,000 2 <1,000 <1,000 <1,000 <1,000 3 <1,000 1,000 <1,000 <1,000 4 <1,000 1,000 <1,000 <1,000 5 <1,000 <1,000 <1,000 <1,000 l 6 <1,000 <1,000 <1,000 <1,000 7 <1,000 1,000 <1,000 <1,000 8 1,600 1,600 10,000 6,000 1

9 <1,000 1,000 <1,000 <1,000 10 <1,000 1,000 <1,000 <1,000 11 <1,000 <1,000 <1,000 <1,000 12 3,000 1,800 2,000 9,000 13 <1,000 <1,000 1,200 <1,000 14 <1,000 <1,000 <1,000 <1,000 15 <1,000 1,000 1,000 <1,000 16 <1,000 <1,000 1,000 <1,000 l 17 <1,000 <1,000 <1,000 <1,000 18 <1,000 <1,000 <1,000 <1,000 l 19 1,000 <1,000 <1,000 <1,000 1

20 <1,000 <1,000 <1,000 <1,000 i

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l TABLE 6 8

SNEC CV Dose Rate Surveys 1985 l (mR/hr?

Ist Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

03-19-85 05-09-85 07-16-85 10-29-85 Exclusion Area Fence <.1 <.1 < 01 <.1 l CV 812' <.1 <.1 .05 <.1 (operating deck)

HEPA Filter <.1 <.1 .04 <.1 NOTE: Third quarter values resulted from a different measurenent technique utilized by the radiological personnel; values for all quarters were comparable.

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Director RNuclear Reactor Regulation

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i Mail Stop No. 340 U.S. Nuclear Regulato Commission l Washington, DC 20545 l

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