ML20070A350

SNEC 1993 Annual Rept Jan-Dec 1993

ML20070A350
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	12/31/1993
From:	Good B SAXTON NUCLEAR EXPERIMENTAL CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C301-94-2003, SNEC-94-0018, SNEC-94-18, NUDOCS 9406280314
Download: ML20070A350 (11)

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, SAXTON NUCLEAR EXPERIMENTAL CORPORATION GENERAL P U B LIC UTILITIES SYSTEM

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SNEC Jersey Central Power & Ught Company Pennsylvania Electric Company PE JC Metropolitan Edison Company June 20, 1994 MAILING ADDRESS: C301-94-2003 ,

1 Upper Pond Road SNEC-94-0018 Parsippany, NJ 07054 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen,

Subject:

Saxton Nuclear Experimental Corporation Operating License No. DPR-4 Docket No. 50-146 1993 Annual Report Section B.5.b. of the Saxton Nuclear Experimental Corporation (SNEC) Technical Specifications requires submittal, on an annual basis, of a written report covering the status of the SNEC facility.

Enclosed, in accordance with the Technical Specification section, is the SNEC Annual Report for the period beginning January 1, 1993 through December 31, ,

1993.

Sincerely, h

B. A. Good Vice President WGH Attachment cc: Administrator, Region I .

NRC Project Engineer NRR NRC Project Engineer, Region I NRC Project Scientist, Region I I

9406200314 931231 PDR N $224 (1188)

R ADCCK 05000146 PCR

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SAXTON NUCLEAR EXPERIMENTAL CORPORATION l

l 1993 Annual Report l

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January 1.1993 - December 31.1993 1

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EXECUTIVE

SUMMARY

During the report period January 1,1993 to December 31, 1993, various activities were conducted at the SNEC facility to funher the decontamination and decommissioning efforts at the site while assuring continued protection of the health and safety of the public and SNEC staff.

A total of 41 individuals made 92 entries into the Containment Vessel (CV) on 15 separate occasions. These entries were made for Technical Specification quarterly surveys, routine housekeeping and related work, decommissioning planning, and NRC and GPUN management tours.

All of the required Technical Specification quanerly radiation surveys were successfully conducted. In addition, the supplemental environmental monitoring program maintained by GPU Nuclear at the site continued during 1993. Results of these monitoring programs and surveys indicate that there has been no appreciable change in the radiological or environmental conditions at the facility when compamd to previous years. The facility currently poses no increased risk to the health and safety of the public.

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ANNUAL REPORT IN COMPLIANCE WITH PARAGRAPII B.5.b OF THE SNEC TECIINICAL SPECIFICATIONS JANUARY 1,1993 - DECEMBER 31,1993 IntIfMhtflion This repon is prepared in compliance with Section B.5.b of the Saxton Nuclear Experimental Corpomtion (SNEC) Technical Specifications. The mporting period covers January 1,1993 to December 31, 1993. Each section presented corresponds to the appmpriate mponing requirement of the Technical Specifications.

A. In[gnpation Relating to Changes in those_ Staff Positions that are Designated as being Resoonsible for the Deactivated Facility. - (Section B.5.b(1))

Them were no changes in staff positions responsible for the deactivated facility during 1993.

B. Summary of Entries into the Containment Vessel (CV) and Reason for Each Entry. -

(Section B.5.b(2))

A list of 1993 entries into the SNEC Containment Vessel and mason for each is presented below.

1. 03/04/93 First Quarterly Inspection

2. 03/23/93 Radiological Survey for 3/24/93 Entry

3. 03/24/93 NRC Inspection / Assessment

4. 06/11/93 Second Quanerly Inspection

5. 08/27/93 Third Quanerly Inspection

6. 09/13/93 Management Tour / Inspection

7. 09/14/93 NRC Tour / Inspection

8. 10/27/93 Radiological Survey for 10/28/93 Entry

9. 10/28/93 GPUN Engineering Inspection ,

10. 11/03/93 GPUN Engineering Inspection

11. 12/01/93 Fourth Quanerly Inspection

12. 12/02/93 Housekeeping

13. 12/10/93 Remote Crane Inspection

14. 12/15/93 Hands-on Crane Inspection

15. 12/16/93 Hands-on Crane Inspection The RWDF and other outbuilding stmetums wem demolished in 1992.

i C. Summary of Maintenance and Design Chances Made to the Deactivated Facility. -

(Section B.5.b(3))

There were no maintenance and design changes instituted during 1993.

D. Results of Radioactivity Ixvels and of Water Samole Analyses. - (Section B.5.b(4)).

Analysis results of water samples from the CV sump and CV pipe tunnel are presented in Tables I and II. Sample results from the CV sump contain the highest activity. This is consistent with previous data. The water in the CV sump is completely contained and not in contact with the environment, therefore, there is no threat to the public health and safety. CV sump water originates from condensation that forms on the inside of the CV walls which drains downward into the sump. CV sump capacity is approximately 325 gallons. Water levels are measured quarterly and have shown slight increases. The sump contained approximately 120 gallons of water on 12/31/93.

Table III presents the highest contact dose rates on the CV Operating Deck and the highest waist level dose rates taken around the CV and Penelec perimeter fences during the quarterly surveys. Count rate information obtained from surveys of the CV High Efficiency Filter is pmsented in Table IV.

Dose rates at the 20 permanent survey points in the CV were less than 0.2 to 0.4 mr/hr.

The data are presented in Table V. Smear surveys from the same 20 permanently marked points ranged from less than minimum detectable activity to 2900 dpm/100cm2 (Table VI). The data from these surveys are generally consistent with past results and do not display any adverse trends.

1 In 1992, after demolition of the outbuilding structures was completed, 8 piezometers  !

were installed around the Site to provide groundwater movement information. Several l additional monitoring wells will be installed near the CV in early 1994 based on the piezometric data obtained. Four of these piezometers were sampled and analyzed by gamma spectroscopy. These results are reported in Table VII.

l E. Review of the Performance of Security and Surveillance Measures. - Section B.5.b(5))

During 1993 there were no break-ins or no known attempted break-ins at the SNEC facility. No changes were made to in-place security features since demolition of the ,

outbuilding structures was completed in 1992. l l

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TABLE I SNEC Containment Vessel (CV) Sumo Water Analysis Results 1993*

(pCi/ml) l Radio-nuclides 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

03/04/93 06/11/93 08/27/93 12/01/93 Gross Alpha < 5.0E-8 < 6.0E-8 <l.0E-7 < 6.0E-8 Gross Beta 2.5E-3 2.5E-3 i 2.5E-3 3.2E-3 i 0.1 E-3 0.1E-3 0.1E-3 0.1E-3 H-3 4.2E-4 i 4.lE-4 4.4E-4 4.3E-4 0.1E-4 0. lE-4 0.1E-4 0.1E-4 Sr-90 6.1E-6 i 7.2E-6 8.2E-6 6.60E-6 0.1E-6 0.1E-6 0.1E-6 0.1E-6 Co-60 < 4.0E-7 < 8.0E-7 < 7.0E-7 <1.0E-6 Cs-134 8.74E-7 i < 2.0E-6 <1.0E-6 < 2.0E-6 3.51E-7 Cs-137 2.52E-3 2.38E-3 2.45E-3 2.68E-3 0.25E-3 0.24E-3 0.25E-3 0.27E-3

• Analysis results from Teledyne Isotopes Lab i

TABLE II  ;

CV Pine Tunnel Analysis Results 1993 (pCi/ml) {

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Radio-nuclities 1st Qtr. 2nd Qtr. < 3rd Qtr. 4th Qtr. l 03/04/93 06/11/93 08/27/93 12/01/93  !

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Gross Beta 3.2E-8 3.9E-8 i 4.6E-8 2.7E-8 i f 0.3E-8 0.4E-8 0.5E-8 0.3E-8 H-3 < l.4E-7 < l .4E-7 < l .6E-7 < l .6E-7 .

Co-60 < 5.0E-9 < 3.0E-9 < 3.0E-9 < l .5E-9 Cs-134 < 3.0E-9 < 3.0E-9 < 3.0E-9 < l .4E-9 t

Cs-137 1.8E-8 1.8E-8 i 3.0E-8 1.8E-8 [

0.3E-8 0.4E-8 0.4E-8 0.2E-8 l h

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l TABLE III ,

SNEC Site Perimeter Fence Highest Dose Rates

1. 03/04/93 32 R/hr

2. 06/11/93 30 R/hr  !

3. 08/27/93 34 R/hr

4. 12/01/93 30 R/hr CV Perimeter Fence Highest Dose Rates

1. 03/04/93 15 R/hr

2. 06/11/93 19 R/hr

3. 08/27/93 21 R/hr

4. 12/01/93 18 R/hr Penelec Perimeter Fence Highest Dose Rates ,

1. 03/04/93 14 R/hr

2. 06/11/93 15 R/hr

3. 08/27/93 17 pR/hr

4. 12/01/93 15 R/hr TABLE IV Count Rate Surveys CV High Efficiency Filter 1993 i

1. 03/04/93 < 100 nepm

2. 06/11/93 < 100 nepm i

3. 08/27/93 < 100 nepm

4. 12/01/93 < 100 nepm l

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TABLE V SNEC CV Dose Rates 1993 20 Permanent Survey Points (Gross Beta - mr/hr) j Survey 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Point No. 03/04/93 06/11/93 08/27/93 12/01193 1 < 0.2 0.2 < 0.2 < C.2 2 < 0.2 0.2 < 0.2 < 0.2 -

I 3 < 0.2 0.2 < 0.2 < 0.2 4 < 0.2 0.2 < 0.2 < 0.2 5 < 0.2 0.3 < 0.2 < 0.2 6 < 0.2 0.2 < 0.2 < 0.2 7 < 0.2 0.2 < 0.2 < 0.2 8 < 0.2 < 0.2 < 0.2 < 0.2 l

9 < 0.2 0.2 < 0.2 < 0.2 10 < 0.2 0.4 < 0.2 < 0.2 11 < 0.2 0.4 < 0.2 < 0.2 12 < 0.2 0.3 < 0.2 < 0.2 13 < 0.2 0.2 < 0.2 < 0.2 14 < 0.2 0.2 < 0.2 < 0.2 15 < 0.2 0.2 < 0.2 < 0.2 16 < 0.2 0.2 < 0.2 < 0.2 17 < 0.2 0.2 < 0.2 < 0.2 18 < 0.2 0.2 < 0.2 < 0.2 19 < 0.2 0.2 < 0.2 < 0.2 20 < 0.2 0.2 < 0.2 < 0.2 I

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i TABLE VI SNEC CV Smear Surveys 1993 20 Permanent Survey Points (dpm/100cm2)

Survey 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Point No. 03/04/93 06/11/93 08/27/93 12/01/93 1 < 1000 < 186 < 279 < 244 ,

2 < 1000 < 186 < 279 < 244 3 < 1000 < 186 < 279 < 244 4 < 1000 < 186 < 279 < 244 5 < 1000 < 186 < 279 < 244 6 < 1000 <186 < 279 < 244 7 < 1000 < 186 < 279 < 244 8 < 1000 202 < 279 < 244 ,

9 < 1000 < 186 < 279 < 244 10 < 1000 < 186 < 279 300 11 < 1000 < 186 < 279 < 244 12 1000 552 319 880 13 < 1000 192 <279 2900 14 < 1000 < 186 < 279 660 15 < 1000 < 186 339 420 16 < 1000 < 186 < 279 480 17 < 1000 < 186 < 279 260 18 < 1000 < 186 < 279 < 244 19 < 1000 < 186 < 279 1320 20 < 1000 < 186 < 279 < 244 m

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Sample Results of Groundwater taken from the Piezometers Around the CV Pipe Tunnel in 1993 i

(pCi/L)

Location Co-60 Cs-134 Cs-137 SAMPLE DATE - 7/15/93 GEO-3 <6 <4 <4  !

GEO-4 <7 <6 <6 GEO-6 <2 <2 <2 '

GEO-7 <5 <4 <5 SAMPLE DATE - 10/7/93 GEO-3 <6 <5 <6 .

GEO-4 <3 <3 <3 GEO-6 <6 <4 <4 ,

GEO-7 <7 <6 <6 t

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