ML20101L334

Experimental Corp 1991 Annual Rept. W/

ML20101L334
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	12/31/1991
From:	Good B SAXTON NUCLEAR EXPERIMENTAL CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SNEC-92-0021, SNEC-92-21, NUDOCS 9207070081
Download: ML20101L334 (15)

Text

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M. SAXTON NUCLEAR EXPERIMENTAL CORPORATION GENERAL P U B LIC UTILITIES SYSTEM

, d. Jersey Central Powe, & Light Company Pennsytvania Eiectne Company JC Meropohtan Esson Company PE MMLING ADDRESS: TELEPHONE.

1-Uppw Pond Rd. (201) 316-7000 Parsippany, NJ 07054 June 30, 1992 SNEC-92-0021 C-301-92-0010 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Dear Sir:

Saxton Nuclear Facility Operating License No. DPR-4 Docket No. 50-146 1991 Annual Report The Saxton Nuclear Experimental Corporation (SNEC) Technical Specification (TS), Section D.5.b, requires submittal, on an annual basis, of a written report covering the status of the SNEC facility.

Enclosed, in compliance with the TS section, is the SNEC Annual Report covering the period January 1, 1991 through December II, 1991.

Sincerely,

$. if. <%Yf4c B. A. Good Vice President BAG /cb Enclosures cci A. Adams - NRC (w/ encl)

R._ Bores - NRC (w/ encl)

J. Roth - NRC (w/ encl)

-S. Weiss - NRC (w/ encl)

T. Martin - Administrator Region I

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SAXTON NUCLEAR EXPERIMENTAL CORPORNflON l

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1991 Annual Repmt P

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l-l JARuary 1,1991 - Desember 31, 391 1

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t EXECUTIVH

SUMMARY

During the report period January 1,1991 to December 31,1991, 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.

A total of 47 entries were made into the Containment Vessel (CV). These entries were made for Technical Specification quarterly surveys, routine housekeeping and related work, radiological assessment tour, QA audit tour and radiological characterization Surveys.

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 1991. 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 threat to the health and safety of the public.

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i ANNUAL REPORT IN COMPLIANCE WITil PARAGRAPII B,5,b OF TIIE SNEC TECIINICAL SPECIFICATIONS JANUARY 1,1991 DECEMBER 31,1991 intt011uc'!on This report is prepared in compli:mce with Section 11.5.b of the Saxton huclear Experimental Corporation (SNEC) Technical Specifications. 'lhe reporting period covers January 1,1991 to December 31,1991. Each section presented corresponds to the appropriate reporting requirement of the Technical Specifications.

A. Information Relating to Chances in those Staff Positions that are Designated as beine Re.sponsible for tile Deactivated.FacilitL - (Section ll.5.b(1))

^1here were no changes in staff positions responsible for the deactivated facility during 1991.

D. Summarv.of Entries into the Containment Vesfel (CV) or Radhactive Waste Disposal Facility (R.W.D.F.) and Reason for Each Entry 2 - (Section U.S.b(2))

During the time frame of January 1,1991 to December 31,1991, there were 274 entries into the RWDF. Daily sign-in and sign-out logs are on file and available ,

for inspection.

A list of entries into the SNEC Containment Vessel and reason for each is

presented below, i

1. 03/21/91 First Quarterly Inspection & Radiological Assessment

2. 06/20/91 Second Quarterly Inspection

3. 07/16/91 Radiological Characterization 4, 07/17/91 Radiological Characterization

5. 07/18/91 Radiological Characterization

6. 07/19/91 Radiological Characterization

7. 07/22/91 Radiological Characterization /GPUN QA Audit Tour

8. 07/23/91 Radiological Characterization /GPUN QA Audit Tour

, 9. 08/08/91 Radiological Characterization l

10. 08/12/91 Radiological Characterization & Inspection

11. 08/13/91 Radiological Characterization

12. 08/14/91 Radiological Characterization

13. 08/15/91 Radiological Characterization l 14. 08/16/91 Radiological Characterization l 15. 08/20/91 Radiological Characterization j 16. 08/21/91 Radiological Characterization

17. 08/22/91 Radiological Characterization

18. 08/23/91 Radiological Characterization

19. 08/26/91 Radiological Characterization

i I

20. 08/27!91 Radiological Characterization

21. 08/28/91 Radiological Characterization

22. 08/29/91 Radiological Characterization

23. 09/03/91 Radiological Characterization

24. 09/05/91 Radiological Characterization

25. 09/06/91 Radiological Characterization

26. 09/09/91 Radiological Characterization

27. 09/10/91 Radiological Characterization

28. 09/11/91 Third Quarterly Insp2ction & Radiological Assessment

29. 09/12/91 Radiological Characterization

30. 09/16/91 Radiological Characterization

31. 11/25/91 Radiological Characterization

32. 11/26/91 Radiological Characterization

33. 11/27/91 Radiological Characterization

34. 12/04/91 Radiological Characterization

35. 12/05/91 Fourth Quarterly inspection & Radiological Characterization

36. 12/06/91 Radiological Characterization 37, 12/07/91 Radiological Characterization

38. 12/08/91 Radiological Characterization 39, 12/09/91 Radiological Characteri. .ation

40. 12/10/91 Radiological Characterization

41. 12/11/91 Radiological Characterization

42. 12/12/91 Radiological Characterization

- 43. 12/13/91 Radiological Characterization 44, 12/17/91 Radiological Characterization

45. 12/18/91 Radiological Characterization

46. 12/19/91 Radiological Characterization 47, 12/20/91 Radiological Characterization C Summmy ofMaintenano.and Design Changes Made to the Deactivated Facility,

- (Section B.5.b(3))

During 1991, there were no major maintenance or design changes made at SNEC. Some minor changes related to radiological characterization surveys in the CV were made (i.e., flange removals for sampling).

D. Results of Radioactivity _I 'vels and of Water Sample Analyses. - (Section B.5 b(4)).

Analysis results of water samples trom the CV sump, RWDF sump and CV pipe tunnel are presented in Tables I,11, 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 amounu, of condensation that

1 form on the inside of the CV walls and drain dowmvard into the sump. CV sump capacity is approximately 325 gallons. It contains approximately 170 gallons of water. Water levels are measured quarterly and have shown slight increases.

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 Penelee perimeter >

fences during the quarterly surveys. Count rate information obtained from  !

surveys of the CV High Efficiency Filter is presented in Table V.

Dose rates at the 20 permanent survey points in the CV, ranged from less than 0.2 mrlhr to 0.2 mrlhr. The data are presented in Table VI. Smear surveys from the same 20 permanently marked points ranged from less than minimum detectable activity to 6260 dpm/100cm2 (Table VII). Between the second and third quarter of 1991 some housekeeping efforts resulted in a reduction of contamination on most of the marked survey point areas. The first twelve survey points are in e accessible from clean areas. The data from these surveys are generally consistem :vith past results and do not display any adverse trends.

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.

E. Review of the Performance of Security and Surveillance Measures. - Section 11.5.b(5))

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During 1991 there were no break-ins or no known attempted break ins at the SNEC facility. No major changes were made to in-place security features.

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TABLE 1 SNEC Containment Vessel (CV) Sump Water Analysis Ilnults 1991.*

(pCilml)

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

nuclides 03/21/91 06/20/91 09/11/91 12/05/91 Gr-Alpha < 3.0E-10 < 4.0E-8 1.2E-7 i < 5.0E-7 0.6E-7 Gr Beta 2.0E-3 i 2.4E-3 i 2.8E-3 i 3.0E-3 i 0.1E-3 0.1E-3 0.1E-3 0.1E-3 H3 5.4E-4 6.4E-4 i 5.4E 4 i 4.9E-4 i 0.1E-4 0.1E-4 0.1E-4 0.1E-4 Sr-90 4.9E 5 i 6.5E-6 i 6.5E-6 t 6.8E-6 i 0.1E-5 0.1E-6 0.1E 6 0.1E-6 i Co-60 < 7.0E-7 1.48E-6 i < 6.0E-7 < 8.0E '/

0.15E-6

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Cs-134 2.47E-6 i 2.57E-6 i 1.71E-6 i 2.60E-6 i l 0.95E-6 1.08E-6 0.56E-6 0.68E-6 Cs-137 2.04E-3 i 2.13E-3 1 2.55E-3 i 3.01E-3 i 0.20E-3 0.21E-3 0.26E-3 0.30E-3 l

• Analysis results from Teledyne Isotopes

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TABLE 11 RWDF SufnpAtalygls Restdts 1991

( Cllml)

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

nuclides 03/21/91 06/20/91 09/11/91 12/05/91 Gr-Alpha < 7.0E-9 < 7.0E-9 < 6.0E 9 < 7.0E 9 Gr Beta 5.9E-9 1.2E-8 i 2,0E-8 i 1.0E-8 i 1.3E 9 0.3E-8 0.2E-8 0.1E-8 i

H3 <1.7E-7 < 1.7E 7 < 1.6E-7 < 1.3E-7 Sr-90* - --- --- --- ---

Co 60 < 9.0E-9 <5.0E-9 <5.0E-9 < 3.0E 9 Cs-134 <1.4F-8 < 9.0E-9 <5.0E-9 <5.0E-9 e

Cs.-137 < 7.0E-9 < 5.0E-9 < 3.0E-9 < 3.0E-9

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

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l TAllLE 111 CV PiptTunnel Analysis Results 1991

( Cilml)

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

nuclides 03/21/91 06/20/91 09/11/91 12/05/91 Gr-Alpha < 6.0E 9 < 4.0E-9 < 4.0E-9 < 3.0E-9 Gr Beta 1.8E-8 i 2.2E-8 i 3.7E-8 i 2.1E-8 i 0.2E-8 0.5E-8 0.4E-8 0.2E-8 I-1-3 < 1.7E-7 1.8E-7 i < 1.6E-7 < 1.3E-7 1.1E-7 St-90 * --- --- --- ---

Co 60 < 4.0E-9 < 5.0E-9 < 5.0E-9 <1.7E-9 Cs-134 < 8.0E-9 < 4.0E-9 < 4.0E-9 < 2.0E-9 ,

Cs-137 1.1E-8 i 1.5E-8 + 1.9E-8 i 1.2E-8 i 0.4E-8 0.3E-8 0.3E-8 0.2E-8

" Ur 90 analysis has been changed to "as needed".

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TABI.E IV F

• 6eneral Area Dose Rate Survey CV Operating Deck 1991

]

t 1((~ 1, 03/21/91 <0.2 mRlhr _

2. 06/20/91 <0.2 mRIhr 5 3. 09/11/91 < 0.2 mRlbr g 4. 12/05/91 ,

< 0.2 mRd CV Perimeter Fence Dose Rate Survey 1991

1. 03/21/91 22 pRlhr

2. 06/20/91 22 pRIhr 3

3. 09/11/91 23 pRlhr

4. 12/05/91 21 pRlhr

,..a.-

Penelec Perimeter Fence Dose Rate Survey 1991

1. 03/21/91 18 Rlhr

2. 06/20/91 14 pRlhr h

3. 09/11/91 17 gRlhr

4. n u ?) 19 pRlbr

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TABLE V -

Count Rate Surveys CV High Efficiency Filter 1991

1. 03/21/91 ( '90 ncpm i

2. 06/20/91 <100 ncpm

3. 09/11/91 < 100 nc u

4. 12/05/91 <100 ncpm s

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- - _ - - - - - _ _ _ - - _ _ - _ _ _ _ _ _ _ . _ - _ _ _ - - _ . - - - - - - - - - - - - - - - - - - - _ - . - _ _ _ _ - - - - - - - _ - . - - - - _ _ _ _ - - - - - _ _ - - --.._----_____-__._---____O

TABLE VI

. SNEC CV Dose Rates 1991 20ffrmanent Survey Poitdh LGross He_t3 - mn!'

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

Point No. 03/21/91 06/20/91 09/11/91 12/05/91 1 < 0.2 < 0.2 < 0.2 < 0.2 2

< 0.2 < 0.2 < 0.2 < 0.2 3 < 0.2 0.2 < 0.2 < 0.2 4- < 0.2 < 0.2 < 0.2 < 0.2 5 < 0.2 < 0.2 < 0.2 3

< 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 9 < 0.2 <0.2 < 0.2

< 0.2 10 < 0.2 < 0.2 < 0.2 < 0.2 11

<0.2 < n.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 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. I < 0.2 < 0.2 < 0.2

4 TABLE VII SNEC CV Smear Surveys 1991 20 Perma 1.ent Survey Points (dpm/100an 2)

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

Point No. 03/21/91 06/20/91 09/11/91 12/05/91 1 < 101 < MDC <MDC <MDC 2 < 101 <MDC <MDC <MDC 3 < 101 <MDC <MDC <MDC 4 1210 840 <MDC <MDC 5 < 101 <MDC <MDC <MDC 6 < 101 <MDC <MDC <MDC 7 230 100 <MDC <MDC S 1490 2380 <MDC <MDC 9 1370 1340 <MDC <MDC

. 10 840 340 <MDC <MDC 11 130 <MDC 1110 <MDC 12- 5310 6260 530 1570 l

13; 530 420 <MDC < MDC 14 580 <MDC <MDC <MDC l

15 -310 200 <MDC 340 16 210 480 <MDC <MDC 17 140 <MDC <MDC <MDC 18 280 160 <MDC <MDC 19 176 240 <MDC 42) 20 < 101 <MDC <MDC <MDC

[

TABLE Vill Analysis of Groundwater Dewatered from RWDF and Other Subsurface Building Areas - 1991

( Cilml)

Date Sr-90 Cs-137 Co-60 Gr-Alpha Gr-Beta H-3 01/02/91 - 02/08/91 *

< 3.0E-9 <*.0E-9 < 7.0E-9 8.4E-9 i <1.8E-7 2.1E-9 02/08/91 - 02/26!91 < 4.0E-9 < 4.0E-9 <8.0E-9 8.4E-91 1.5E-7 1 1.4 E-9 0.8E-7 -

02/26/91 - 03/21/91 < 3.0E-9 <5.0E-9 < 6.0E-9 < 7.0E-9 8.0E-9 i < 1.7E-7 1.4 E-9 03/21/91 - 04/30/91 < 3.0E-9 < 5.0F-9 < 9.0E-9 5.6E-9 i < 1.4 E-7 1.8E-9 04/30!91 - 06/06/91 <5.0E-9 < 5.0E-9 < 6.0E-9 1.1E-8 1 1.6E-7 i 0.4E-S 1,0E-7 06/06/91 - 07/01/91 < 7.0E-10 < 1.3E-9 < 1.4E-9 1.2E-8 1 1.1E-8 i < 1.7E-7 0.5E-8 0.3E-8 07/01/91 - 0~/30/91 <4.0E 9 < 4.0E-9 7.2E-9 i 7.9E-9 i 1.8E-7 i 4.5E-9 1.3E-9 1.0E-7 07/30!91 - 09/06/91 < 1 4 E-9 <1.5E-9 < 6.0E-9 1.2E-8 i < 1.6E-7 0.2E-8 09/06/91 - 09/30/91 < 3.0E-10 < 3.0E-9 < 4.0E-9 < 7.0E-9 8.2E-9 i < 1.5E-7 ,_

1.5E-9 h 09/30/91 - 11/15/91 < 3.0E-9 < 4.0E-9 < 9.0E-9 8.7E-9 i < 1.2E-7 1.5E ^

11/15/91 - 12/05/92 < 1.7E-9 < 1.6E-9 < 9.0E-9 7.7E-9 i 2.1E-7 i 1.4 E-9 0.9E-7 12/05/91 - 01/08/92 < 6.0E-10 < 3.0E-9 < 3.0E-9 <8.0E-9 6.8E-9 i < 1.7E-7

• 1.5E-9

• - Composited for quartedy analysis.

• • - RWDF sampler mdrunctioned in December 1991. A grab sample taken 1/8/92 6 900. New sampling unit was installed on Januaq 10,1992.

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