ML20206G021
| ML20206G021 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 12/31/1986 |
| From: | Heward R SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2241G, 5201-87-2003, SNEC-87-0013, SNEC-87-13, NUDOCS 8704140427 | |
| Download: ML20206G021 (14) | |
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i SAXTON NUCLEAR EXPERIMENTAL CORPORATION 1986 ANNUAL REPORT January 1, 1986 - December 31, 1986
, h 8704140427 861231 y PDR ADOCK 05000146 R PDR 2241g \
EXECUTIVE
SUMMARY
During the report period January 1, 1986 to December 31, 1986, various
, activities were conducted at the SNEC facility to ensure the continued protection of the health and safety of the public.
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The existing composition of SNEC officers responsible for the facility j changed during the 1986 reporting period.
There were a total of twenty-nine (29) entries made into the Containment j Vessel (CV) and/or the Radioactive Waste Disposal Facility (RWDF). These
! entries were principally for surveys, sampling, and groundwater discharge
] from the RWDF and facility pipe tunnels.
1 Routine maintenance at the site included general cleanup to remove fallen debris from the buildings, decontamination to prevent the spread of contamination internally within the buildings and to individuals working in the buildings. Removal of groundwater f rom the basement of the RWDF and facility pipe tunnels began on December 8, 1986 and continued through the end of the year. From December 8, 1986 to December 31, 1986 approximately 177,000 gallons of water was discharged from the site. The water met all !
radiological and non-radiological discharge criteria established by the NRC and the Commonwealth of Pennsylvania.
. The required quarterly radiation surveys were conducted at the facility. In addition, the supplemental environmental monitoring program maintained by GPU Nuclear at the site continued during 1986. Results of these surveys j indicated that there has been no noticeable change in the radiological or 4
environmental conditions at the facility when compared to previous years.
i The facility currently poses no threat to the health and safety of the public.
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! i ANNUAL REPORT IN COMPLIANCE WITH PARAGRAPH B.S.b l 0F THE SNEC TECHNICAL SPECIFICATIONS '
January 1, 1986 - December 31, 1986 l 1
Introduction This report is prepared in compliance with Section B.5.b of the Saxton Nuclear
- Experimental Corporation (SNEC) Technical Specifications. The reporting l period covers January 1, 1986 to December 31, 1986. Each section presented corresponds to the appropriate reporting requirement of the Technical Specifications.
l A. Information Relating to Changes in those Staff Positions that are
! Designated as Being Responsible for the Deactivated Facility.
- (Section B.5.b(1))
The following changes occurred in staff positions responsible for the !
deactivated facility during 1986:
- 1. R. J. Leva was elected Chairman of the Board. ,
- 2. R. L. Wise was elected as a board member.
- 3. W. A. Verrochi retired.
4 4. M. B. Roche was appointed as Secretary.
- 5. W. F. Sayers was appointed Assistant Secretary.
i 4 B. Summary of Entries into the Containment Vessel (CV) or Radioactive Waste
] Disposal Facility (R.W.D.F. ) and Reasons for Each Entry.
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- (Section B.5.b(2))
Buildings Date Purpose Entered
- 1) 02/06/86 First quarter survey and building survey RWDF 1
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- 2) 02/07/86 First quarter survey and building survey RWDF, CV
- 3) 02/08/86 Building survey RWDF i
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! 4) 04/09/86 Communications activities RWDF, CV i
- 5) 04/10/86 Communications activities RWDF, CV ;
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- 6) 05/09/86 Communications activities RWDF, CV I
- 7) 05/29/86 Second quarter survey RWDF, CV
- 8) 05/30/86 Second quarter survey and RWDF, CV
- Board of Directors tour 4
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ANNUAL REPORT IN COMPLIANCE WITH PARAGRAPH B.5.b I 0F THE SNEC TECHNICAL SPECIFICATIONS January 1, 1986 - December 31, 1986 (Continued)
- 9) 06/23/86 Environmental survey RWDF
! 10) 06/24/86 Environmental survey RWDF 1
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{ 11) 06/30/86 Exclusion Area survey RWDF l 12) 07/01/86 Exclusion Area survey RWDF i 13) 08/18/86 Third quarter survey RWDF i ,
! 14) 08/19/86 Third quarter survey RWDF, CV
- 15) 08/20/86 Pa. Dept. of Environmental Resources tour RWDF, CV I
- 16) 10/09/86 Building inspection RWDF
- 17) 10/14/86 Tank inspection and maintenance RWDF l
- 18) 10/31/86 Equipment delivery RWDF
- 19) 11/06/86 Fourth quarter survey RWDF, CV l 20) 11/07/86 Fourth quarter survey RWDF, CV
- 21) 11/18/86 Water discharge RWDF I
- 22) 11/25/86 Water discharge RWDF i
- 23) 11/26/86 Water discharge RWDF
- 24) 12/04/86 Water discharge RWDF
- 25) 12/05/86 Water discharge RWDF
- 26) 12/08/86 Water discharge RWDF thru i 12/12/86
- 27) 12/15/86 Water discharge RWDF. l thru 12/19/86 l I 28) 12/22/86 Water discharge RWDF
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12/23/86 I
} 29) 12/29/86 Water Discharge RWDF thru j 12/31/86 l
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i C. Summary of Maintenance and Design Changes Made to the Deactivated Facility. - (Section B.5.b(3))
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- 1) In May of 1986, a maintenance crew applied herbicides to prevent the l
growth of weeds within the SNEC exclusion area yard.
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- 2) On December 8, 1986, removal of ground water from the RWDF and pipe tunnels began and continued through the end of the year.
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D. Results of Radioactivity Levels and of Water Sample Analyses.
- (Section B.5.b(4))
Analysis results of water samples from the CV, RWDF, and CV pipe tunnel are presented in Tables 1-5. The samples from the CV sump were the only samples to yield radioisotopic concentrations in excess of 10 CFR 20, Table II, Column 2 limits for the release of radiological effluents to unrestricted areas. This water is contained wholly within the CV and therefore pose no threat to the environment or public health and safety. The water originates from condensation within the CV. The water is periodically removed, packaged and shipped to a licensed radioactive waste landfill.
Dose rates at the 20 permanent survey points in the CV ranged from 0.01 mr/hr to less than 0.2 mr/hr. The results are presented in Table 6. Smear surveys from the same 20 points ranged from less than 1000 dpm to 12,000 dpm. These results are presented in Table 7. Survey points 8 and 12 are located along the walkway to the lower levels of the CV. As such, they are expected to reflect movement of contamination from the lower levels of the CV to the radiological control point.
The data from these surveys are generally consistent with past results. l E. Review of the Performance of Security and Surveillance Measures.
- (Section B.5.b(5))
Based on existing surveillance measures, there were no identified breaches in security during the reporting period and no abnormal conditions noted at the facility during the reporting period.
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! TABLE 1 i
SNEC Containment Vessel (CV) Sump Water Analysis Results 1986 f (uci/ml)
Radio- 1st Qtr. 2nd Qtr. 05-29-86 3rd Qtr. 4th Qtr.
nuclides 02-07-86 P-1(a) H-1(b) 08-19-86 11-07-86 Cs-137 1.9E-3+9.2E-6(c) 2.4E-3 t l.0E-5(c) 1.5E-3+8.1E-6(c) 2.4E-311.1E-5(c) 2.3E-311.1E-5(c)
I Cs-134 1.1E-5_+7.4E-7 1. 2E-5_+7.9E-7 7.4E-6t6.1E-7 1.2E-528.9E-7 1.0E-518.1E-7 T
Co-60 < 4.4E-7 3.4E-6+4.7E-7 < 2.9E-7 1.0E-5+8.6E-7 5.7E-6+7.0E-7 1
1 Gr Alpha < 3.8E-6 4.9E-833.8E-8 < 2.8E-8 <2.8E-6 < 2.9E-6 Cr Beta / Gamma- 2.0E-3 1 8.7E-5 2.4E-313.0E-5 1.5E-312.4E-5 2.3E-321.0E-4 2.5E-321.1E-4 H-3 5.8E-416.3E-5 1.9E-316.7E-5 8.1E-412.1E-5 8.0E-417.7E-5 8.7E-411.3E-5
- i j St-90 1.2E-5g6.1E-7(c) 1.5E-5 1 7.4E-7(e) 1.4E-312.5E-5(c) 9,9E-616.2E-7(c) 7.3E-6t l.6E-7(c) 1 (a) P-1 sample - water in R.B. sump underneath Herculite liner.
(b) H-1 sample - water in R.B. sump within Herculite liner.
(c) Exceed 10 CFR 20, Table 2, Column 2 limits.
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i Equipment Hatch Sump (Operating Deck) Analysis Results 1986
) (uC1/ml) i
! Radio- let Qtr.(a) 2nd Qtr. 3rd Qtr.(a) 4th Qtr.(a) i nuelldes 02-07-86 05-29-86 08-19-86 11-07 86 i
Co-137 ---
3.2E-6g5.0E-7 -- --
Cs-134 ---
<3.0E-7 --- --
l Co-60 ---
<4.1E-7 --- ---
1 (a) No water present in sump.
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A e-+- m_m..__ __.________m_ - . . _ m__ .____.__ ___--_-_____m.._._
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TABLE 2 l
Quarterly RWDF Sump Water Analysis Results for 1986 (uCi/ml)
Radio- 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
nuclides 02-07-86 05-29-86 08-19-86 11-07-86 Cs-137 < 2.8E-7 1.9E-7+7.7E-8 1.7E-7+5.0E-8 1.7E-7+3.9E-8 j Cs-134 < 2.0E-7 <1.6E-7 < 4. 5E-8 < 2.5E-8 Co-60 < 2.7E-7 < 2.0E-7 < 5. 6E-8 < 3.2E-8 Gr Alpha < 6. 0E-8 <1.4E-8 < 2.8E-9 < 3.0E-9 Gr Beta /Gama 1.5E-715.4E-8 2.2E-716.0E-8 9.9E-8+5.1E-8 1.9E-715.6E-8 H-3 < 4.4E-6 5.6E-6+2.2E-6 < 4.6E-6 < 4.4E-6 Sr-90 < 3.6E-8 < 4.0E-8 < 3.2E-8 < 4.0E-8 l
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1 TABLE 3 Radioloaical Analyses Results of Batch Water Released from the RWDF i
j (uci/ml) i Other Principal (a) i Fission / Activation Date Batch Cs-137 Co-60 Products Gr Alpha Gr Bets H-3 12/08/86 120886A 1.4E-73 0E-8 < 4. 0E-B LLD < 3.0E-9 2.8E-7 5.6E-712.8E-7 12/09/86 120986A 1.0E-713.0E-8 < 3.0E-8 LLD < 2.0E-9 1.7E-7 < 3.0E-7 12/10/86 121086A 1.2E-73 0E-8 < 3.0E-8 LLD < 3.0E-9 2.7E-7 5.0E.718.0E-8 12/11/86 121186A 1.6E-73 0E-8 < 4.0E-8 LLD < 3.0E-9 2.7E-7 3.9E-718.0E-8 12/11/86 1211868 1.5E-713.0E-8 <4.0E-8 LLD- < 3.0E-9 2.6E-7 3.0E-7+1.1E-7 ,
12/12/86 121286A -1.4E-713.0E-8 < 2.0E-8 LLD < 4.0E-9 3.K -7 3.1E-711.0E-7 12/15/86 121586A 1.2E-713.0E-8 . < 3.0E-8 LLD < 3.0E-9 2.8E-7 (c) 12/16/86 121686A 1.2E-723.0E-8 < 3.0E-8 LLD < 3.0E-9 2.8E-7 (c) 12/16/86 1216868 1.2E-713.0E-8 < 4.0E-8 LLD < 3.0E-9 2.7E-7 2.1E-719.0E-8 e
12/17/86 121786A 1.4E-73 0E-8 4 <4.0E-8 LLD < 3.0E-9 2.7E-7 2.7E-711.5E-7 12/17/86 1217868 1.3E-713.0E-8 < 4.0E-8 LLD < 3. 0E-9 2.7E-7 3.7E-719.0E-8 1
12/17/86 121786C 1.4E-713.0E-8 < 2.0E-8 LLD < 3.0E-9 2.6E-7 3.1E-717.0E-8 4
12/18/86 121886A 1.5E-713.0E-8 < 4. 0E-8 LLD < 3.0E-9 2.8E-7 2.7E-719.0E-8 12/18/86 1218868 1.6E-713.0E-8 < 2.0E-8 LLD < 3.0E-9 2.K-7 2.7E-717.0E-8 12/18/86 121886C 1.2E-713.0E-8 <5.0E-8 LLD < 3.0E-9 2.8E-7 (e) 12/18/86 121886D 1.3E-713.0E-8 < 3.0E-8 LLD < 3.0E-9 2.8E-7 (c) 12/19/86 121986A 1.3C-713.0E-8 < 3.0E-8 LLD < 3.0E-9 2.8E-7 (c) j 12/19/86 1219868 1.4E-713.0E-8 < 3.0E-8 LLD < 3.0E-9 2.8E-7 (c) i 12/22/86 122286A 1.6E-713.0E-8 < 4.0E-8 LLD < 3.0E-9 2.8E-7 (c) 12/22/86 1222868 1.3E-713.0E-8 < 4. 0E-8 LLD < 3.0E-9 2.6E-7 (c) 4 12/23/86 122386A 1.4E-713.0E-8 < 3. 0E-8 LLD < 3.0E-9 2.8E-7 (c) j 12/23/86 1223868 1.4E-7+3.0E-8
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< 4.0E-8 LLD < 3.0E-9 3.1E-7 (c) 12/23/86 122386C(b)2.6E-7g.0E-8 < 3.0E-8 LLD < 3. 0E-9 4.3C-7 (c) 12/29/86 122986A 2.0E-73 0E-8 < 4.0E-8 LLD 3.2E-9 3.0E-7 (c) 12/29/86 1229868 2.0E-73 0E-8 < 4. 0E-8 LLD 3.0E-9 3.3E-7 (c) i 12/30/86 123086A 2.1E-73 0E-8 <4.0E-8 LLD 5.3E-9 3.4E-7 (c) j 12/30/86 1230868 1.9E-73 0E-8 < 4.0E-8 LLD < 3.0E-9 3.0L-7 (c) l 12/30/86 123086C 2.0E-7p.0E-8 < 3.0E-8 LLD 4.7E-9 3.3E-7 (c) 1 12/31/86 123186A 1.6E-713.0E-8 < 3.0E-8 LLD < 2.0E-9 2.1E-7 (c) f 12/31/86 1231868 1.8E-73 0E-8 < 3.0E-8 LLD < 2.0E-9 1.6E-7 (c) i (a) Typical LLD's provided in Table 4.
(b) Not discharged.
(c) Analyses resulta not ave 11able at report time.
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TABLE 4 l
1 TYPICAL RADIONUCLIDES AND LLDa VALUES FOR (GP)UN
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ENVIRONMENTAL RADIOACTIVITY LABORATORY Radionuclide LLD Value (uCi/ml)
Ac-228 1.0E-7 Ag-110M - 3.0E-8 Ba-140 .6,0E-8 Be-7 2.0E-7 Bi-214 8.0E-8 Ce-141 3.0E-8 Ce-144 1.1 E-7 Co-56 3.0E-8 Co-60 3.0E-8 Cr-51 1.9E-7 Cs-134 3.0E-8 i Cs-136 3.0E-8 i
Cs-137 4.0E-8 Fe-59 4.0E-8 I-1 31 4.0E-8 K-40 3.0E-7 La-140 5.0E-8
, Mn-54 2.0E-8 Mo-99 5.0E-8 Nb-95 3.0E-8 Pb-214 7.0E-8 Ra-226 5.0E-7 Ru-103 2.0E-8
- Sb-125 6.0E-8 T1-208 8.0E-8 U-235 1.4E-7 Zn-65 6.0E-8 Zr-95 4.0E-8 (a) These LLD's are based upon a 4000 second count in the one liter Marinelli geometry with a five day decay between sampling and analysis, i
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1 TABLE 5 Pipe Tunnel Analysis Results 1986 (uCi/ml)
Radio- 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
nuclides 02-07-86 05-29-86 08-19-86 11-07-86 Cs-137 2. 8E-7+1. l E-7 < 1.5E-7 2. 4E-7+1.1 E-7 6.3E-7+8.1E-8 ]
Cs-134 < 2.0E-7 < 1.6E-7 < 1. 5E-7 < 4.4E-8 l Co-60 < 2.7E-7 < 2.0E-7 < 1.9E-7 < 5.6E-8 l
! l Gr Alpha < 6.0E-8 < 1.4E-8 < 2.8E-9 < 3.0E-9 l Gr Beta / Gamma 1.8E-7+5.5E-8 2.2E-7+6.0E-8 2.2E-7+5.5E-8 4.8E-7+6.4E-8
, H-3 < 4.2E-6 < 4.6E-6 < 4.4E-6 < 4.3E-6 Sr-90 < 3.7E-8 < 4.2E-8 < 3.1 E-8 < 4.3E-8 i ,
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i TABLE 6
! SNEC CV Dose Rates 1986 20 Permanent Survey Points l
(mR/hr) 1st Qtr. 2nd Qtr. 3rd Qtr.(a) 4th Qtr.
Survey Point No. 02-07-86 05-29-86 08-19-86 11-07-86 1 .01 . 01 <.2 .01 2 .02 .05 <2. .03 3 .03 .06 <2. .05 4 .02 .07 <2. .04 5 .03 .03 <2. .03 6 .04 .05 <.2 .02 7 .03 .05 <.2 .08 8 .05 .07 <.2 .03 9 .04 .06 <2. .02 10 .02 .04 <.? .02 11 .03 .05 <.2 .03 12 .02 .05 <.2 .05 13 .03 .04 <.2 .02 14 .05 .08 <.2 .06 15 .04 .04 <.2 .03 16 .02 .05 <2
. .03 17 .02 .04 <2
. .03 18 .03 .05 <2
. .04 19 .04 .05 4.2 .05 i
20 .01 .02 <.2 .02 (a) A different survey instrument (RO-2) used than in other quarters yielding a slightly higher LLD.
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SNEC CV Smear Surveys 1986 20 Permanent Survey Points (dpm) 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
Survey Point No. 02-07-86 05-29-86 08-19-86 11-07-86 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 6 <1,000 < 1,000 <1,000 < 1,000 7 < 1,000 < 1,000 <1,000 < 1,000 8 8,000 4,000 3,400 12,000 9 < 1,000 <1,000 <1,000 < 1,000 10 < 1,000 41,000 < 1,000 < 1,000 11 < 1,000 < 1,000 < 1,000 < 1,000 12 2,000 8,000 10,000 10,000 13 1,200 < 1,000 < 1,000 < 1,000 14 < 1,000 41,000 <1,000 < 1,000 15 < 1,000 < 1,000 <1,000 < 1,000 16 < 1,000 < 1,000 <1,000 < 1,000 17 < 1,000 (1,000 <1,000 <1,000 18 < 1,000 < 1,000 < 1,000 < 1,000 19 < 1,000 < 1,000 <1,000 < 1,000 20 < 1,000 <1,000 <1,000 < 1,000 1
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TABLE 8 SNEC CV Dose Rate Surveys 1986 (mR/hr) 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.
02-07-86 05-29-86 08-19-86 11-07-86 Perimeter Fence .03 < 05 . .06 .05 l
Vessel General Area <.2 .5 < .1 <.2 .06 ;
High Efficiency Filter .03 .02 <.2 < . 01 l
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ue SAXTON NUCLEAR EXPERIMENTAL CORPORATION GENERAL P U B LIC UTILITIES SYSTEM P SNEC Jed Central Power & Ught Company
= Pennsylvania Electnc Company l Metrogoistan Edison Company PE JC TELEPHONE:
MAluNG ADoRESS: I l 1 Upper Pond Rd. (201) 316-7000 1 Parsippany, NJ 07054 1
l April 10,1987 SNEC-87-0013 5201-87-2003 l
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Dear Sirs:
Saxton Nuclear Facility Operating License No. DPR-4 Docket No. 50-146 1986 Annual Report l The Saxton Technical Specifications require that the Saxton Nuclear Experimental Corporation (SNEC) submit to the Nuclear Regulatory Commission, on an annual basis, a written report covering the status of the i
Saxton Nuclear Facility. In compliance with Paragraph B.5 b of the SNEC Technical Specifications, SNEC herewith submits a report for the period l January 1, 1986 through December 31, 1986.
l Sincerely, 1
/
R. W. Heward, Jr.
President RWH/GGB/cb:0244S Enclosures
( cc: H. Berkow, NRC l R. Carter, NRC l T. Murley, NRC E. Wenzinger, NRC W. Baunack, NRC 1
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