ML20112C845

1995 Annual Rept for Saxton Nuclear Experimental Corp Facility

ML20112C845
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	12/31/1995
From:	Kuehn G, Kuehn G GENERAL PUBLIC UTILITIES CORP., SAXTON NUCLEAR EXPERIMENTAL CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
6710-96-2029, NUDOCS 9606030077
Download: ML20112C845 (13)

Text

..

GPU Nuclear Corporation gg g Route 441 South P.O. Box 480 Middletown, Pennsylvania 17057-0480 (717)944 7621 Writer's Direct Dial Number:

May 24, 1996 6710-96-2029 U. S. Nuclear Regulatory Commission Attn: Document Contml Desk

' Washington, D.C. 20555 l Gentlemen:

Subject:

Saxton Nuclear Experimental Corpo:ation Operating License No. DPR-4 Docket No. 50-146 1995 AnnualReport I

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 mport covering the status of the SNEC Facility.

The mport is for the period beginning January 1,1995 thmugh December 31,1995.

i 4

Sincerely,

)

/

. A. Kuehn, II rr i j

Pmgram Director, SNEC Facility WGH Attachment i

cc: Document Control Desk NRC Pmject Manager NRR NRC Project Scientist, Region I i

9606030077 951231 i PDR ADOCK 05000146 R PDR

l SAXTON NUCLEAR EXPERIMENTAL CORPOPATION I

'I 1995 ANNUAL REPORT FOR THE SAXTON NUCLEAR EXPERIMENTAL CORPORATION FACILITY January 1,1995 - December 31,1995 9

3 i

d I

EXECUTIVE

SUMMARY

During the report period January 1,1995 through December 31,1995, 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 protection of the health and safety of the general public and site personnel.

A total of 155 entry days into the Containment Vessel (CV) were recorded. These entries were made for Technical Specification quarterly surveys, routine housekeeping, routine maintenance, polar crane inspections / maintenance, telephone line installation, characterization surveys / sampling, decommissioning planning, and management inspections. Entries were also  !

made in support of NRC and public (open house) tours of the facility. All required Technical Specification quarterly mdiation surveys were successfully conducted.

In addition, the supplemental environmental monitoring program maintained by GPU Nuclear at the site continued during 1995. 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 previous years. The facility currently poses no increased risk to the health and safety of the public.

1 ANNUAL REPORT IN COMPLIANCE WITH PARAGRAPH B.6.b OF THE SNEC l TECHNICAL SPECIFICATIONS  ;

JANUARY 1,1995 - DECEMBER 31,1995 l l

Introduction 1

l This report is prepared in compliance with Section B.6.b of the Saxton Nuclear Experimental '

Corporation (SNEC) Technical Specifications. The reporting period covers January 1,1995 I through December 31,1995. Each section presented corresponds to the appropriate requirements of the Technical Specifications.

A. Information Relatine to Changes in those Management and Supervisory Positions i Designated in Section B.I.a as being Resoonsible for the Deactivated Facility. (Section B.6.b(1))

There were no changes to the management and supervisory structure for the deactivated facility during 1995. However, action by the SNEC Board of Directors led to the naming Fred D. Hafer as successor to J. E. Hildebrand as SNEC President and the naming of George A. Kuehn Jr. to the position of SNEC Vice President and General Manager succeeding Beverly A. Good.

B. Summary of Entries in the Containment Vessel (CV) and Reasons for Entry. (Section B.6.b(2))

1 A summary of the 1995 entries into the Saxton Nuclear Experimental Corporation i Facility (SNEC) Containment Vessel is presented below. l

1. Five (5) First Quarter Entry Days were performed for:

A. Quarterly inspection B. Radiological surveys C. Communications - open house / tour and inspection

2. Thirty-three (33) Second Quarter Entry Days were performed for:

A. Quarterly inspection  !

B. Radiological surveys l

C. Characterization surveys and sampling (core bore / pipe cutting / system opening)

D. GPUN engineering inspections l

1 E. Communications open house / tour and inspection F. Routine maintenance and inspection G. NRC/SNEC management tours i H. Safety equipment installation  !

I. CV liner hole repair and inspection

3. Fifty-seven (57) Third Quarter Entry days were performed for:

A. Quarterly inspection B. Radiological surveys C. Characterization surveys and sampling (core bore / pipe cutting / system opening)

D. GPUN engineering inspections /Decomm. planning E. NRC tour I F. QA inspection G. Fire Dept./ safety inspection H. Video inspections I. CV polar crane maintenance l J. Routine maintenance - move gate K. GPUN management inspection 1

4. Thirty-eight (38) Fourth Quarter Entry Days were performed for:

)

l A. Quarterly inspections B. Radiological surveys C. Characterization surveys and sampling (core bore / pipe cutting / system opening)

D. GPUN Engineering inspections /Decomm. planning E. Communications Dept. - tour / inspection F. CV hole repair / testing / inspections C. Summary of Maintenance and Design Channes Made to the Deactivated Facility.

(Section B.6.b(3))

Maintenance and design changes instituted during 1995 were as follows:

1. A new locking mechanism was installed in the existing Hi Rad access (grating, 812' el.). This modification allows unlocking the hi-rad gate / door from below without a key (for personnel egress) while (still) requiring a High Radiation Area key for entry.

i 1 ,

2. A vehicle gate was installed in the CV Fence just outside the personnel hatch to increase accessibility for equipment installation and removal.

3. Two Reactor Cavity Shield Blocks were removed to provide access to the Storage Well for characterization work. Four steel plates, each weighing approximately 700 lbs., were fabricated to replace the two removed concrete blocks. The steel plates are placed over the canal opening to prevent unauthorized access when no work is in progress in the stcrage well.

D. Results of Sutveys of Radioactivity Levels and Water Sample Analyses - (Section e

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. The 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 i surfaces inside the CV which drains downward into the sump. CV sump capacity is approximately 325 gallons. Water levels are measured at least quarterly and have '

shown slight incmases due to condensation. The sump contained approximately 118 l gallons on 12/5/94, i

! Table III presents the highest waist level dose rates taken around the CV and Penelec

. perimeter fences during the quarterly surveys. Dose rates around the Penelec perimeter fence is consistent with previous data. Dose rates around the CV (yard) fence is slightly higher than previous data. This is due to installation of a " Sea-van" storage

container and staging within of several drums of CV waste awaiting shipment.

. The CV High Efficiency Filter was replaced during performance of each quarterly survey. Count rate information obtained from surveys of the filter is presented in Table IV. 1 I

Dose rates at the 20 permanent survey points in the CV ranged from less than 0.2 to

! 3.0 mr/hr. This data is presented in Table V. Smear surveys from the same 20 l permanently marked points ranged from less than detectable activity to 8000 dpm/100 )

cm' and is presented in Table VI. The data from these surveys are generally consistent l

! the past results and do not display any adverse trends.

i  ;

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. I i i j

4 P

{  !

J J

i 1

i .

j .

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

I s

i All required access control and surveillance measures were satisfactorily completed.

During 1995 there were no break-ins or known attempted break-ins at the SNEC

Facility.

I I

+ i t l 4

)

4 b

I t

i i

J r

i 1

3 1

1 1

i e

a 1

1 I

i 1

{

4 .

\

, l 2

l 4

TABLEI SNEC Containment Vessel (CV) Sump Water Analysis Results 1995 (u Cihni) 4 ist Qtr 2nd Qtr 3rdQtt 4th Qtt

Radio-Nuclides 03/24/95 06/06/95 08/11/95 10/03/95 l 12/05/95 4

Gross Alpha < 7.0 E-8 < 7.0 E-8 < 7.0 E-8 < l.7 E-6 < l.2 E-6 i -

Gross Beta 3.2 E-3 2 0.1 E-3 1.6 E-310,1 E-3 4.3 E-3 2 0.1 E-3 4.1 E-3 ! 0.4 E-3 3.4 E-3 0.3 E-3 4

H-3 3.0 E-4 i 0.1 E-4 1.2 E-410.1 E-4 7.0 E-4 0.1 E-4 7.1 E-410.7E-4 4.5 E-4 0.4 E-4 4

Sr-90 7.4 E-6 ! 0.1 E-6 7.6 E-6 0.1 E-6 2.2 E-4 i 0.1 E-4 7 0 E-4 0.2 E-4 1.4 E-4 0. I E-4 Co-60 < 7.0 E-8 4.5 E-710.7 E -7 1.5 E-6 0.2 E-6 < 2.0 E-6 < l.7 E-6

. Cs-134 < 3.0 E-7 < l.0 E-7 < 3.0 r ' < 6.0 E-6 < 5.0 E-6 Cs-13" 3.0 E-3 ! 0.3 E-3 1.5 E-310.2 E-3 4.0 E-3 0.4 E-3 4.0 E-3 0.4 E-3 3.3 E-3 i o.1 E-3 r

j 6

4 i

l 1

6 TABLEII SNEC (CV) Pipe Tunnel Water Analysis Results 1995 (u Ci/ml) ist Qtr 2nd Qtr 3rdQtr 4thQtt ,

Radio-Nucl69 03/24/95 06/06/95 08/11/95 10/03/95 l 12/06/95 Gross Beta 2.2 E-8 0.3 E-8 2.9 E-810.3 E -8 2.7 E-8 0.3 E-8 3.0 E-810.3 E-8 2.0 E-8 t 0.3 E-8 H3 < l.8 E-7 < l.9 E-7 < l.8 E-7 < l.2E-7 < l.9 E-7 Co-60 < 1.8 E-9 < 3.0 E-9 < l 9 E-9 < 4.0 E-9 < l.3 E-9 Cs-134 < l.5 E-9 < 2.0 E-9 < l.5 E-9 < 3.0 E-9 < l.3 E-9 Cs-137 5.1 E-9 1.6 E-9 8.1 E-9 0.3 E-8 1.0 E-8 0.2 E-8 1.1 E-8 0.3 E-8 7.3 E-9 ! 1.4 E-9 ;

I 1

l 1

1 1

- _ . ,= - . - - . .. . .. _ - _ _ _ _ _ _ - _ _ _

TABLE III SNEC/Penelec Perimeter Fence IIighest Dose Rates 1995 SNEC Site Perime:cr Fence Highest Dose Rates (micro-R/hr)

, 03/24/95 13 06/06/95 22 08/11/95 40 10/03/95 120 12/05/95 100 SNEC CV Perimeter Fence liighest Dose Rates (micro-R/hr) 03/24/95 15 Note i 06/06/95 70

, Note I j 08/1I/95 160 Note I ,

10/03/95 320 l l Note 1 12/05/95 340 Penelec Perimeter Fence Highest Dose Rates (rnicro-R/hr) ,

l 03/24/95 15 I

06/06/95 17 08/11/95 16 l l

10/03/95 20 12/05/95 22 Note 1 - see explanation in "Section D" of this report.

l TABLE IV l i l

! I l CV High Efuciency Filter Count Rate Surveys 1995 i

! l 3/28/95 < 100 nepm

. 06/06/95 < 100 ncpm 8/l1/95 NOTE 1 < 100 ncpm 10/3/95 < 100 ncpm 12/6/95 < 100 nepm j NOTE 1 - equivalent reading by gamma spectroscopy analysis. Reference gamma scan

(GPU ID) # 083333, performed at TMI Environmental Radioactivity Laboratory (ERL).

l 1

l i,

4 J

4 1

I l

1. .

1 i j '

l 1

1

.- l TABLE V SNEC CV Dose Rates 1995 - 20 Permanent Survey Points (Gamma - mr/hr) ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Survey Point # 03/24/95 06/06/95 08/11/95 10/03/95 l 12/05/95 l 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 i

4 < 0.2 < 0.2 0.2 < 0.2 0.2 )

1 5 < 0.2 < 0.2 0.8 0.6 0.5 1 1

6 < 0.2 < 0.2 0.2 < 0.2 < 0.2 i i

7 < 0.2 < 0.2 0.2 < 0.2 < 0.2 '

8 0.2 < 0.2 < 0.2 < 0.2 < 0.2 )

9 < 0.2 0.2 0.2 < 0.2 < 0.2 10 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 11 < 0.2 0.2 0.2 < 0.2 < 0.2 12 0.4 < 0.2 0.2 < 0.2 < 0.2 l l

13 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 J

14 < 0.2 < 0.2 0.5 0.4 0.8 15 < 0.2 < 0.2 0.2 < 0.2 0.2 l

16 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 17 < 0.2 < 0.2 < 0.2 < 0.2 < 0.2 4

18 < 0.2 < 0.2 2.5 3.0 0.6 19 < 0.2 < 0.2 0.2 0.2 0.2 20 < 0.2 < 0.2 0.2 < 0.2 0.2 1

i' I

TABLE VI )

2 SNEC CV Dose Rates 1995 - 20 Permanent Survey Points (dpm/100 cm )

ist Qtr 2nd Qtr 3rd Qtr 4th Qtr Suney Point # 03/24/95 06/06/95 08/11/95 10/03/95 l 12/05/95 1 < 247 < 248 < 1000 < 1000 < 1000 2 < 247 < 248 < 1000 < 1000 < 1000 I 3 < 247 < 248 < 1000 < 1000 < 1000 l 4 < 247 < 248 < 1000 < 1000 < 1000 l 5 < 247 < 248 < 1000 < 1000 < 1000 6 < 247 < 248 < 1000 < 1000 < 1000 7 < 247 < 248 < 1000 < 1000 < 1000 8 492 < 248 < 1000 < 1000 < 1000 9 < 247 < 248 < 1000 < 1000 < 1000 I 10 1552 270 1000 1000 1000 l 11 < 247 < 248 < 1000 < 1000 < 1000 12 3992 490 2000 1000 1000 13 372 290 1000 < 1000 5000 14 632 1030 < 1000 < 1000 1000 15 492 710 1000 < 1000 < 1000 16 512 < 248 3000 1000 8000 17 < 247 < 248 < 1000 < 1000 < 1006 18 1020 < 248 1000 < 1000 < 1000 19 372 < 248 2000 1000 1000 20 < 247 < 248 < 1000 < 1000 < 1000