ML20141C666

1996 Annual Rept for Saxton Nuclear Experimental Corp Facility

ML20141C666
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	12/31/1996
From:	Kuehn G SAXTON NUCLEAR EXPERIMENTAL CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C301-97-2019, NUDOCS 9706250378
Download: ML20141C666 (14)

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l GPU Nuclear,Inc.

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Route 441 South NUCLEAR Post Office Box 430 Middletown, PA 17057 0480 Tel 717-944 7621 j C301-97-2019 June 16,1997 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 1996 Annual Report The purpose of this letter is to submit, in accordance with Section B.6.b. of the Saxton Nuclear Experimental Corporation (SNEC) Technical Specifications, a written report covering the status of the Saxton Nuclear Experimental Corporation (SNEC) Facility.

The report is for the period beginning January 1,1996 through December 31,1996.

i S.' cerely, f  ;

,, II G. A. 'uehn Vice President SNEC t II WGH Attachment cc: Document Control Desk NRC Project Manager NRR- Alexander Adams NRC Project Scientist, Region I- Thomas Dragoun File 97508

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i SAXTON NUCLEAR EXPERIMENTAL CORPORATION 1

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1996 ANNUAL REPORT l

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SAXTON NUCLEAR EXPERIMENTAL CORPORATION FACILITY I l  ;

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January 1,1996 - December 31,1996 l

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i EXECUTIVE

SUMMARY

During the report period January 1,1996 through December 31,1996, various activities were conducted at the SNEC facility to prepare for future decontamination and decommissioning efforts. SNEC Facility staff continued to monitor radiological conditions at the site to assure l protection of the health and safety of the general public and site personnel.

A total of 147 entry days into the Containment Vessel (CV) were recorded. These entries were j made for Technical Specification quarterly surveys, routine maintenance and housekeeping, installation of decommissioning support systems such as compressed (breathing) air / electrical power, radiological / characterization surveys, asbestos removal, loose material removal, decommissioning planning, and management oversight inspections. Entries were also made in support of NRC and public (open house) tours of the facility. All required Technical Specification quarterly facility inspections and radiation monitoring surveys were successfully conducted.

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' Also performed were installation of decommissioning support trailers, site road improvements, fence line alterations, new gate installations, and installation of the Decommissioning Support Building (DSB), Personnel Access Facility (PAF) & Material Handling Building (MHB) adjacent to the south side of the CV. Soil excavated during construction of the DSB/PAF/MHB and during site road improvements was kept onsite and used to construct a shield wall for radioactive materials in sea-land vans awaiting offsite shipment. ,

L In addition, the GPU Nuclear supplemental environmental monitoring program was maintained during 1996. Results of these monitoring programs and surveys indicate that there has been no appreciable change in the radiological or environmental conditions at the facility compared to i

previous years. The facility currently poses no ncreased risk to the health and safety of the l

public.

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. ANNUAL REPORT IN COMPLIANCE WITH PARAGRAPH B.6.b OF THE SNEC TECHNICAL SPECIFICATIONS JANUARY 1,1996 - DECEMBER 31,1996

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I Introductip.n This report is prepared in compliance with Section B.6.b of the Saxton Nuclear Experimental Corporation (SNEC) Technical Specifications. The reporting period covers Januanf1 ,1996  ;

through December 31,1996. Each section presented corresponds to the appropriate requirements  ;

of the Technical Specifications.

A. Information Relating to Changes to those Staff Positions that are Designated as being E_esconsible for the Deactivated Facility. (Section B.6.b(1)) l Effective November 1,1996, the GPU Nuclear division responsible for the SNEC Facility i was renamed from Nuclear Services Division to Nuclear Safety and Technical Services

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Division. At that time, Arthur H. Rone was named Vice-President and Director of the i Nuclear Safety and Technical Services Division.  !

No.other changes were made to SNEC management / supervisory staff positions  !

responsible for the facility during 1996. 1

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B. Summary orEntries in the Containment Vessel (CV) From January 1.1996 to December 31.1996. (Section B.6.b(2)) i 1

1 A summary of the 1996 entries into the Saxton Nuclear Experimental Corporation Facility )

(SNEC) Containment Vessel is presented below. q l

1. Twenty-four (24) First Quarter Entry Days were performed for: l A. Quarterly inspections i B. Radiological surveys C. Characterization surveys / inspections l D. SNEC management tour (s)/ inspection (s) l E. Routine maintenance and inspections F. Decommissioning planning / engineering inspections L

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2. . Twenty-one (21) Second Quarter Entry Days were performed for:

A. Quarterly inspections B. Radiological surveys C. Characterization surveys / inspections D. SNEC management tour (s)/ inspection (s)

E Routine maintenance and inspections F. Decommissioning planning / engineering inspections G. NRC tour / inspection H. . An>rican Nuclear Insurers (ANI) tour / inspection I. Citizens Task Force Tour J. Communications Dept. Public (Open House) Tour

3. Fifty-two (52) Third Quarter Entry days were performed for:

- A. Quarterly inspections B. Radiological surveys C. Characterization surveys / inspections D. SNEC management tour (s) & inspection (s)

E. Routine maintenance and inspections F. Decommissioning planning / engineering inspections G. NRC oversight tours / inspections H. Nuclear Safety Assurance (NSA) inspections I. Radiation Safety Committee (RSC) tour / inspections J. Loose material removal / preps.

K. Insulation (fiberglass and asbestos) removal / preps. i l

L. Kelly Enclosure erection for high contamination work M. Radio testing for worker communications N. Breathing air compressor installation

4. Fifty (50) Fourth Quarter Entry Days were performed for:

A. Quarterly inspections B. Radiological surveys C. Characterization surveys / inspections D. SNEC management tour (s) & inspection (s)

E. Routine maintenance and inspections F. Decommissioning planning / engineering inspections G. Insulation (fiberglass and asbestos) removal / preps.

H. Saxton Fire Dept. Training

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l C. Summary of Maintenance and Design Changes Made to the Deactivated Facility. -

(Section B.6.b(3))

1 Maintenance and design changes instituted during 1996 were as follows:

The Reactor Coolant Drain Tank was barricaded'off to prevent unauthorized 1.

access and posted per 10CFR20. This allowed the High Radiation Area access control, formerly the grating at the 812' stairwell, to be moved to the door of the

' Primary Compartment (CV 781' el.). This eliminates unnecessary high radiation area radiological controls requirements for Auxiliary Compartment access. The Rod Room door lock was removed and the area under the reactor vessel was opened for general access. These changes were permitted in accordance with Amendment 14 to the Technical Specifications.

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2. A Decommissioning Support Building (DSB), Personnel Access Facility (PAF), _^

and Material Handling Building (MHB) were constructed adjacent to the south side of the CV. The CV (Exclusion Area) fence was modified to accommodate these buildings.

3. Site road improvements and fence modi" cations were performed to accommodate truck traffic and new support trailers ure provided to support the decommissioning project. New vehicle gates were installed south and east of the i DSB, new (gravel) roads were constructed in these areas, and existing site roads were improved to accommodate this traffic.

4. Dedicated electrical power was supplied to the CV for the decommissioning project. This power was routed via three (3) power buggies constmeted specifically for this project.

l S. A breathing air compressor was installed adjacent to the CV. This compressor will be used to supply tool air when not in use for breathing air.

6. Accessible asbestos was removed from plant piping and components. Asbestos removal was approximately 95% complete by the end of 1996.

, 7. Support facilities installed included a restroom trailer, craft break trailer, shower l trailer (for asbestos removal), an engineering support trailer and all associated utilities hookups to each.

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. D. Results of Radioactivity Surveys and Water Sample Analyses - (Section B.6.b(4))

Analysis results of water samples from the CV sump and CV pipe tunnel are presented in Tables I and II respectively. Sample results from the CV sump contain the highest activity.

This is consistent with previous data. Water in the CV sump is completely contained and is not in contact with the environment, therefore, there is no threat to the public health and safety. CV sump water originates from condensation on surfaces inside the CV which drains downward into the sump. Also, water generated during minor decontamination and maintenance activities is occasionally routed to the sump. This accounts for fluctuations in ,

CV sump activity as seen in quarterly sample results. CV sump capacity is approximately 325 gallons. Water levels are measured at least quarterly and have shown slight increases due to the above activities. The sump contained approximately 140 gallons on 12/16/96.

Table III presents the highest waist level dose rates taken around the CV and GPU Energy (formerly Penelec) perimeter fences during the quarterly surveys. During the tirst three quarters of 1996, the highest SNEC Perimeter Fence and CV Perimeter Fence dose rates f were in a location where the boundaries share the same fence line. These dose rates show  !

a decrease during the fourth quarter after a radioactive material storage van was relocated to the east SNEC Yard area. Ecse rates around the GPU Energy perimeter fence are consistent with previous data but show a slight increase during the fourth quarter due to i temporary storage of radioactive asbestos in the east SNEC. Yard area, pending off site shipment.

The CV " Breather" High Efliciency Filter was replaced during performance of each quarterly survey. Count rate information obtained from surveys of the filter is presented in r Table IV.

Dose rates at the 20 permanent survey points in the CV ranged from less than 0.2 to 2.6 mr/hr with normal variations due to work evolutions in the surveyed area (s). This data is -

presented in Table V. Smear surveys from the same 20 permanently marked points ranged 2

from less than detectable activity to 3000 dpm/100 cm and is presented in Table VI. Data from these surveys, taking into account variations due to ongoing work activities in the surveyed areas, are generally consistent with past results and do not display any adverse trends.

Groundwater was sampled and analyzed on at least a quarterly basis. The monitoring results from wells GEO 3,4,6, & 7 are reported in Table VII.

E. Review of the performance of Access Control and Surveillance measures. -(Section B.6.b.(5)) -

I l: All required access control and surveillance measures were satisfactorily completed. There were no break-ins or known attempted break-ins at the SNEC Facility during 1996.

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TABLEI

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SNEC Containment Vessel (CV) Sump Water Analysis Results 1996 (uCi/ml) j ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Radio-Nuclides 03/07/96 05/14/96 07/23/96 10/08/96 12/16/96 Gross Alpha < l.7 E-6 4.2 E-6 0.5 E-6 4.4 E-6 0.5 E-6 2.7 E-6 0.5 E-6 2.7 E-6 0.2 E-6 i

Gross Beta 3.5 E-3 0.3 E-3 3.5 E-3 0.4 E-3 3.5 E-3 0.4 E-3 2.3 E-3 0.2 E-3 2.5 E-3 0.3 E-3 l'

H-3 4.9 E-4 0.5 E-4 4.2 E-4 i 0.4 E-4 3.9 E-4 0.4 E-4 3.5 E-4 0.3 E-4 3.2 E-4 i 0.3 E-4 Sr-90 1.2 E-4 0.1 E-4 1.0 E-4 0.1 E-4 1.0 E-4 0.1 E-4 6.0 E-5 0.6 E-5 7.3 E-5 0.7 E-5 Co-60 < 2.0 E-6 < l.7 E-6 < l.3 E-6 < 3.0 E-6 2.7 E-610.9 E-6 Cs-134 < 6.0 E-6 < 6.0 E-6 < 6.0 E-6 < 4.0 E-6 < 3.0 E-6 Cs-137 4.3 E-3 0.4 E-3 3.4 E-3 0.3 E-3 3.5 E-3 i 0.4 E-3 2.2 E-3 0.2 E-3 2.5 E-3 0.3 E-3 i

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, TABLE 11 SNEC (CV) Pipe Tunnel Water Analysis Results 1996 (uCi/ml)

Ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Radio-Nuclides 03/07/96 05/14/96 07/23/96 10/08/96 12/16/96 Gross Beta 7.2 E-8 0.3 E-8 2.6 E-8 0.3 E-8 1.3 E-8 0.2 E-8 3.0 E-8 0.3 E-8 3.2 E-8 0.3 E-8 i )

H-3 < l.6 E-7 < l .5 E-7 < l .4 E-7 < l .5 E-7 < l .4 E-7 Co-60 < 3 E-9 < l.3 E-9 < l .9 E-9 < l .4 E-9 < l .3 E-9 Cs-134 < 2.0 E-9 < l .2 E-9 < l.5 E-9 < l.5 E-9 < l .3 E-9  :

I Cs-137 4.8 E-9 2.5 E-9 5.0 E-9 1.5 E-9 < 2.0 E-9 3.9 E-9 1.3 E-9 2.6 E-9 1.6 E-9 I

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, TABLE III

, SNEC/GPU ENERGY (Formerly Penelec) Perimeter Fence Highest Dose Rates 1996 l

i l SNEC Site Perimeter Fence Highest Dose Rates (micro-R/hr) * "'

I 03/07/96 300 05/14/96 400 07/23/96 440 10/08/96 280 12/16/96 90 l SNEC CV Perimeter Fence Highest Dose Rates (micro-R/hr) * "'

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l 10/08/96 280 12/16/96 75 GPU Energy Perimeter Fence Highest Dose Rates (micro-R/hr) * "'

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05/14/96 15 07/23/96 20 10/08/96 17 12/16/96 34 NOTE l- See explanation in "Section D" of this report I

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TABLE IV CV " Breather" High Efficiency Filter Count Rate Surveys -

1996 03/07/96 < 100 ncpm 05/14/96 < 100 nepm 07/23/96- < 100 nepm 10/08/96 < 100 ncpm 12/16/96 < 100 nepm i i

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, TABLEV i SNEC CV Dose Rates 1996 - 20 Permanent Survey Points (Gamma - mr/hr) l l

l 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Survey Peint # 03/07/96 05/14/96 07/23/96 10/08/96 12/16/96 1 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 2 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 3 < 0.2 < 0.2 0.2 < 0.2 < 0.2 4 < 0.2 < 0.2 < 0.2 0.2 0.4

l. 5 < 0.2 0.4 0.4 0.5 0.8 6 < 0.2 < 0.2 0.2 < 0.2 < 0.2 7 < 0.2 < 0.2 < 0.2 '< 0.2 0.2 l 8 < 0.2 0.2 0.8 < 0.2 0.4 l

l 9 0.2 0.2 0.2 < 0.2 0.4 10 < 0.2 < 0.2 < 0.2 < 0.2 0.2 11 < 0.2 0.2 0.2 < 0.2 0.2 l 12 0.2 0.2 < 0.2 < 0.2 0.2 13 < 0.2 < 0.2 < 0.2 0.5 1.0 14 < 0.2 0.5 0.5 1.6 0.8 l 15 < 0.2 0.2 0.2 0.2 0.6 16 < 0.2 < 0.2 < 0.2 0.5 0.8 ,

17 < 0.2 < 0.2 0.2 0.5 1.2 18 NOTE 1 0.8 2.6 1.5 0.8 1

. 19 < 0.2 0.5 0.2 0.4 0.4 l l l 20 < 0.2 0.2 0.2 < 0.2 0.4 J l

I NOTE 1 - Survey point not accessible with an ion chamber. No dose rate obtained.

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TABLE VI 2

SNEC CV Contamination Levels 1996 - 20 Permanent Survey Points (dpm/100cm )

ist Qtr 2nd Qtr 3rd Qtr 4th Qtr l

Survey Point # 03/07/96 05/14/96 07/23/96 10/08/96 12/16/96 1 < 227 < 1000 < 231 320 < 245 2 < 227 < 1000 < 231 < 227 < 245 3 < 227 < 1000 < 231 < 227 < 245 4 < 227 < 1000 < 231 290 < 245 5 < 227 < 1000 < 231 330 < 245 6 < 227 < 1000 < 231 250 < 245 7 < 227 < 1000 < 231 < 227 < 245 8 < 227 < 1000 < 231 630 < 245 9 < 227 < 1000 < 231 1090 330 10 1110 1000 940 1250 < 245 i

11 < 227 < " 00 -

< 231 < 227 < 245 l 12 630 0 720 1650 < 245 13 2250 3000 900 2310 790 14 1590 2000 900 1650 330 15 1090 < 1000 660 1270 < 245 16 < 227 < 1000 560 2770 970 17 < 227 < 1000 < 231 < 227 < 245 l 18 < 227 < 1000 700 < 227 290 19 1010 < 1000 460 2610 510 20 < 227 < 1000 < 231 < 227 < 245 l

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TABLE VII

- Groundwater Resulta from Piezometers Around the CV Pipe Tunnel (pCi/l)

Location Co-60 Cs-134 Cs-137

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Sample Date 01/25/96 GEO-3 <3 <3 <3 GEO-4 Well under ice and snow - sample not obtained GEO-6 <6 <5 <5 GEO-7 <7 <6 <6 Sample Date 04/03/96 GEO-3 <2 <2 <2 GEO-4 Well under water and mud - sample not obtained GEO-6 <5 <4 <5 GEO-7 < l.3 < l.1 < l.3 Sample Date 07/1096 GEO-3 <5 <4 <5 GEO-4 <8 <6 <7 GEO-6 <3 <3 <3 GEO-7 <2 <2 <2 Sample Date 10/03/96 GEO-3 <4 <3 <3 GE04 <7 <6 <6 GEO-6 <7 <5 <6 GEO-7 <7 <5 <6 a

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