ML20045D716

1992 Annual Rept for Saxton Nuclear Experimental Corp. W/ 930622 Ltr

ML20045D716
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	12/31/1992
From:	Good B GENERAL PUBLIC UTILITIES CORP., SAXTON NUCLEAR EXPERIMENTAL CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C300-93-2006, SNEC-93-0014, SNEC-93-14, NUDOCS 9306290344
Download: ML20045D716 (13)

Text

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I SAXTON NUCLEAR-EXPERIMENTAL CORPORATION B ME GENERAL P U B LI C- U TI LITI E S' S Y ST E M i

P SNEC Jersey Central Power & Light Company Pennsylvania Electric Company PE JC Metropolitan Edison Company j MAILING ADDRESS:

1 Upper Pond Road June 22, 1993- '!'

C301-93-2006 SNEC-93-0014 -

I - U. S. Nuclear . Regulatory Commission .[

Attn: Document Control Desk' Washington, D.C. 20555 Gentlemen, i

Subject:

Saxton Nuclear Experimental Corporation Operating License _No. DPR

• Docket No. 50-146 '!

! 1992 Annual ~ Report Section B.5.b. of the Saxton Nuclear Experimental Corporation (SNEC)' Technical Specifications requires submittal,- on' an annual' basis, of a- written 1 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 1,1992, through December. 31, 1992. .;

l l Sincerely,

. I B. A. Good Vice President- <

WGH L Attachment

.l cc:- Administrator, Regi_on I 'l NRC Project Engineer NRR-NRC Project Engineer,' Region I' )

i NRC Project; Scientist,. Region.I )

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9306290344 921231 l PDR N S224 (11-88)

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ADOCK 05000146

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SAXTON NUCLEAR EXPERIMENTAL CORPORATION 1992 ,

Annual Report '

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Ianuary 1,1992 - December 31,1992 i

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. EXECUTIVE

SUMMARY

During the report period January 1,1992 to December 31,1992, various activities were conducted at the SNEC facility to further the-decontamination and decommissioning efforts at the site while assuring continued protection of the health and safety of the .

! public and SNEC staff. Amendment No.11 to_ the facility license No.'DPR-4 was ,

issued. The vnendment removed the Control and Auxiliary Building, the Radioactive Waste Disposal Facility, the Refueling Water Storage Tank, the Filled Drum Storage l Area, and the Pipe Tunnel (outbuildings) from the facility. description. Demolition of i these facilities was completed June through August 1992. The removal of 'these facilities from the site increased'the protection of the health and safety ef the public and the SNEC staff.

i A total of 16 entries were made into the Containment Vessel (CV). These entries were {

, made for Technical Specification quarterly surveys, routine housekeeping'and related i .

l work, radiological assessment tour, QA audit tour and GPUN management tours.

All of the required Technical Specification quarterly radiation surveys were successfully conducted at the facility. In addition, the supplemental environmental monitoring - ,

program maintained by GPU Nuclear at the site _ continued during 1992. L 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 compared 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 PARAGRAPH B.5.b OF THE SNEC TECHNICAL SPECIFICATIONS j JANUARY'1,.1992 - DECEMBER 31,1992  ;

I Introduction  ;

This report is prepared in complianceiwith Section:B.S.b of the Saxton Nuclear Experimental Corporation (SNEC) Technical Specificationsi The reporting period covers January 1,1992 to December 31,1992.- Each section' presented corresponds to 1 the appropriate reporting requirement of the Technical Specifications.

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l L A. Information Relating to Changes in those St'aff Positions that are Desienated as :

j j being Responsible for the Deactivated Facility. - (Section B.5.b(1)) - .

i There were no changes in staff positions responsible for the deactivated facility?

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B. Summarv of Entries into the Containment Vessel (CV) or' Radioactive Waste  !

Disposal Facility (R.W.D.F.) and Reason for Each Entry. -.(Section~B.5.b(2)); y During the time frame of January 1,' 1992 to December 31,1992, there were 228'-  :

l entries into the RWDF. Daily sign-in and sign-out logs are on file and available :

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L A' list of entries into the- SNEC Containment' Vessel and' reason for ~eachlis '

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i presented below. l ;

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2.

03/27/92 06/16/92 First Quarterly Inspection 1 Second _ Quarterly Inspectioni

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i 3. 06/25/92 - NRC Inspection Tour

4. 07/02/92' GPUN Management Tourl- _.

5. 07/20/92 ~. Routine Housekeeping & Related Work;

6. 07/27/92 Routine Housekeeping & Related WorkT  !

7. 08/06/92 Routine Housek~eeping & Related Work

8. -08/17/92 Routine Housekeeping & Related. Work '

9. 08/18/92 Third Quarterly Inspection L 10. 08/20/92 - - Routine Housekeeping & Related Work 1

11. 08/25/92 Routine Housekeeping & Related Work

12. 08/28/92: Routine Housekeeping &s Related Work

13. 09/01/92 . GPUN Management To'ur? 4

14. 09/25/92_ Routine Houseke(ping & Related Work.

15. 10/02/92 Fourth Quarterly Inspection i

16; 11/17/92 GPUN Manageme'n t Tour L

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

(Section B.5.b(3))

During 1992, NRC approval was received to remove the Control and Auxiliary Building, the Radioactive Waste Disposal facility, the Filled Drum Storage facility, and the Pipe Tunnel from the Technical Specifications. Demontion of these facilities was completed June through August 1992.

D. Results of Radioactivity I.evels and of Water Sample Analyses. -(Section B.5.b(4)).

Analysis results of water samples from the CV sump, RWDF sump and CV pipe tunnel are presented in Tables I, II, III, respectively. Sample results from the CV sump contain the highest activity. This is consistent with previous years 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 small amounts of condensation that form on the inside of the j CV walls and drain dowrw rd into the sump. CV sump capacity is approximately - 1 325 gallons. Water levels are measured quarterly and have shown slight increases. l To ensure an adequate freeboard in the sump for the next five years, approximately 75 gallons of water was pumped from the sump into 15 gallon poly containers.

Therefore, a significant decrease in sump level was observed between the third and -

fourth quarter surveillances. The sump contains approximately 100 gallons of water.

Table IV 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 presented in Table V.

All the dose rates at the 20 permanent survey points in the CV, were less than 0.2 mr/hr. The data are presented in Table VI. Smear surveys from~ the same 20 permanently marked points ranged from less than minimum detectable activity to 850 2

dpm/100cm (Table VII). The data from these surveys are generally consistent with past results and do not display any adverse trends. During the second and third quarters of 1992 housekeeping efforts were performed. Radioactive material, waste generat_ed from the quarterly .surveillances and waste picked up from the housekeeping, was packaged for shipment. This mdioactive material was shipped for disposal with the radioactive' waste from the hold' points of the demolition _of the outbuildings.

Table VIII contains the results of composite water samples collected on the discharge of sump pumps that dewater groundwater inleakage from the RWDF and yard pipe tunnel.

Ir.1992, _8 piezometers were installed around the- Site to provide groundwater -

movement information. Four of the piezometers around the CV Pipe Tunnel v ere

sampled and analyzed by gamma spectroscopy. The results are reported in Table IX.

Groundwater' monitoring wells will be installed around the CV and the CV Pipe Tunnel based on the piezometric data obtained.

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

l During 1992 there were no break-ins or no known attempted break-ins at the SNEC j facility. Changes were made to in-place security features. Two new security fences I were installed. One fence was installed around the parking lot area to facilitate l demolition activities. The other fence was installed to replace Control and Auxiliary l Building wa'l which was providing the south barrier of the Containment Vessel yard I

(Exclusion Area).

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I TABLE I l- SNEC Contaijiment Vessel (CV) Sumo Water Analysis Results 1992*

(pCilml) l- Radio- 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

nuclides 03/27/92 06/16/92 08/18/92 .10/02/92 Gr-Alpha < 6.0E-7 <1.0E-7. <1.0E-6 <1.0E-6  ;

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Gr-Beta 3.0E-3 i 3.0E-3 i~ 3.0E-3 3.0E-3 't  !

0.1E-3 0.1E 0.1E 0.1E-3 H-3 '4.7E-4 i , ~4.7E-4"i 4.5E-4 i . _4.4E-4 i 0.1E-4 0.1E-4 0.1E-4 0.1E-4 i Sr-90 6.4E-6 6.3E-6 i 8.3E 6 -'t <1.0E-8; ,

i 0.1E-6 '. 0.1E-6 0.1E-6 ,

l l Co-60 < 6.0E-7 < 7.0E-7 < 1.0E-6 : < 5.0E i t 4

l Cs-134 < 1.0E-6 <1.0E-6 < 2.0E-6 < 2.0E-6  !

L Cs-137 2.88E-3 i 2.71E-3 . i' 5.40E-3 'i 5.07E-3 ~ l 0.29E-3 .. 0.27E 0.54E 0.51E-3 i 1

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• Analysis results from Teledyne Isotopes:

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RWDF Sump Analysis Results 1992 l (pCilml)

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

nuclides 03/27/92 06/16/92 08/18/92- 10/02/92 Gr-Alpha < 7.0E-9 < 6.0E-9 < 1.3E-8 Gr-Beta ' 1.3E-8 i 1.2E-8 i . 6.6E-8 i 0.2E-8 0.1E-8 1.0E-8 H-3 <1.5E-7 <1.8E-7 < 1.8E-7 -

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Sr-90* **

< 2.0E-10 ,

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l Co-60 < 4.0E-9 **

< 4.0E-9 < 6.0E-9 Cs-134 < 5.0E-9 < 5.0E-9 _<7.0E-9 Cs-137 < 4.0E-9 **

< 3.0E-9 < 5.0E

• Sr-90 analysis'has been changed to "as needed".

** RWDF demolished.

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. TABLE III CV Pipe Tunnel Analysis Results 1992 (pCi/ml)

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

nuclides 03/27/92 06/16/92 08/18/92 10/02/92 Gr-Alpha < 4.0E-9 < 5.0E-9 <5.0E-9 < 4.0E-9 Gr-Beta 2.9E-8 3.3E-8 i 3.6E-8 i 6.0E-8 i 0.3E-8 0.3E 0.4E-8 0.6E-8 H-3 <1.5E < 1.8E-7 < 1.8E-7 < 1.6E-7 Sr-90* --- -- -- --

Co-60 < 3.0E-9 < 2.0E-9 < 1.9E-9 < 1.8E-9 Cs-134 < 4.0E-9 < 2.0E-9 < 3.0E-9 < 2.0E-9 Cs-137 1.5E-8 2.1E-8 i 2.5E-8 i 5.7E-8 i 0.2E-8 0.2E-8 0.3E-8 0.6E-8 1

• Sr-90 analysis has been changed to "as needed".

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. TABLE IV General Area Dose Rate Survey CV Operating Deck 1992

1. 03/27/92 <0.2 mR/hr .

2. 06/16/92 <0.2 mR/hr

3. 08/18/92 <0.2 mR/hr -

4. 10/02/92 . <0.2 mR/hr CV Perimeter Fence Dose Rate Survey 1992

1. 03/27/92 20 R/hr-

2. 06/16/92 25 R/hr

3. 08/18/92 20 R/hr

4. 10/02/92 22 pRlhr Penelec Perimeter Fence Dose Rate Survey 1992i

1. 03/27/91- 15 Rlhr

2. 06/16/92 '15 pR/hr

3. 08/18/92 18 R/hr

4. 10/02/92 16 pR/hr .

TABLE V Count Rate Surveys CV High Efficiency Filter 1992

1. 03/27/92 . <100 nepm

2. 06/16/92 <100 nepm

3. 08/18/92- <100 nepm

4. 10/02/92 <100 ncpm-

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SNEC CV Dose Rates 1992 20 Pe_rmanent Survey Points (Gross Beta - mrlhr) i 1-Stuvey 1st Qtr. 2nd Qtr. 3rd Qtr. ' 4th Qtr'.

Point No. 03/27/92 06/16/92 08/18/92 10/02/92 ,

! 1 < 0.2 < 0.2 l ' < 0.2 '< 0.2 l

2 < 0.2 < 0.2 < 0.2 -- - < 0.2 -

[ 3 < 0.2 < 0.2 < 0.2 - < 0.2 -  :

l 4 < 0.2~ < 0.2 <0.2' < 0.2 .

5 < 0.2 < 0.2. < 0.2 - < 0.2 ,

l 6 -<0.2 < 0.2 - < 0.2

< < 0.2

< 0.2

! 7 < 0.2 < 0.2 - .~<0.2- l 8 < 0.2 < 0.2 '< 0.2 < 0.2 9 < 0.2 < 0.2 < 0.2 < 0. 2  !

10 < 0.2 - < 0.2 - < 0.2 ~ < 0.2 -

11 < 0.2 ' < 0.2 - < 0.2 < 0.2 12 .<0.2 - < 0.2 < 0.2 < 0.2 ~

13 < 0.2 .< 0.2 - < 0.2  : < 0.2.

14 < 0.2 < 0.2 :- <0.2: ~<0.2 I 15 < 0.2 < 0.2 ' < 0.2 - < 0.2 1 16 <0.2 < 0.2 - < 0.2 . <0.2:

17 . < 0.2 < 0.2 . < 0.2 ' < 0.2 l 18 < 0.2 < 0.2 < 0.2 " < 0.2 :.'

i 19 '<0.21 < 0.2 ' < 0.2. ' <

"<0.2' 20' < 0.2 < 0.2 - < 0.2 < 0.2 -

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. TABLE VII j SNEC CV Smear Surveys 1992 20 Permanent Survey Points (dpm/100cm2) ,

Survey 1st Qtr. _2nd Qtr. 3rd Qtr. -4th Qtr. '

Point No. 03/27/92 06/16/92 08/18/92 10/02/92.L

.1 < 294 < 266 < 287 - < 258 -

2 < 294 - . < 266 - < 287. ' < 258 .

3 < 294 < 266 <287 < 258 4 < 294 < 266 ' < 287 < 258 l 5 < 294 < 266 < 287 -  : < 258 -i l

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6 < 294 < 266 < 287- < 258 7 ~ < 294 -  : < 266 - < 287 < 258 -

8 < 294 - < 266 - - < 287 < 258 9 < 294 < 266 < 287 .<258 .

10 < 294 ~ < 266 - < 287 ' < 258 11 < 294 < 266 - . < 287 330 ,

12 360 850 360 470 13 < 294 530 320 390 I 14 < 294 510 < 287- -830 15 < 294 ' '410 < 287 ' 310 16 < 294 310 < 287 410 17 < 294 < 266 - ~ < 287 -: < 258 ,

18 < 294 < 266 ' ' < 287- < 258 - j i

19- < 294 ' '< 266 < 287 -290 20' < 294 - < 266 . < 287 - < 258 i

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. TABLE VIII l

l Analysis of Groundwater Dewatered from RWDF and i Other Subsurface Building Areas - 1992  !

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Date Sr-90 Cs-137 Co-60 Gr-Alpha - Gr-Beta H-3 01/10/92 - 01/29/92 < 1.4E-9 < 1.4E-9 < 8.0E-9 8.3E-9 i - < 1.7E-7 2.5E-9. -

01/29/92 - 03/13/92 <1.1E-8 <1.0E-8 <5.0E-9 5.2E-9i < 1.7E-7 -

2.9E-9 ~

03/13/92 - 04/01/92 < 2.0E-10 < 4.0E-9 <5.0E '<7.0E-9 8.2E-9 < 1.5E <

1.6E

• 04/01/92 - 05/05/92 - < 2.0E-9 . < 2.0E-9 <5.0E 5.2E-9 i < 1.2E-7

! 2.9E-9 l 05/05/92 - 06/02/92 < 3.0E-9 < 4.0E-9 . .< 6.0E-9 7.8E-9 i < 1.4E-7 '- -

1.3E-9 L 06/02/92 - 06/25/92 - < 4.0E-10 < 3.0E-9 ' < 5.0E-9 < 8.0E-9 6.9E-9 i < 1.8E-7.

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. . . . +k Sample Resultsfof Groundwater taken from i the Piezometers 'Around the CV Pipe Tunnel on 11/06/92

'(pCi/L) L L Location Co-60 Cs-134 Cs-137 -

GEO-3 <7 -<8 <6' i GEO-4 <4' P< 5 -  :<3 .

GEO-6 <8' < 11. J< 6 '

GEO < 4 .:. <5 <4.-

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