ML20066L448

Responds to Request for Addl Info in Insp Rept 50-146/90-02. Results of Paint Chip Samples,Plan of Action to Disposition Filled Drum Storage Bunker & Administrative Forms Encl

ML20066L448
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	01/31/1991
From:	Hildebrand J SAXTON NUCLEAR EXPERIMENTAL CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
C301-91-0001, C301-91-1, SNEC-91-0001, SNEC-91-1, NUDOCS 9102070061
Download: ML20066L448 (18)

Text

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ME SAXTON NUr EAR EXPERIMENTAL CORPORATION GENERAL P U B LIC UTILii r. '_ 7YSTEM h $NEC Jamey Central Power & Light Company p t PennsyNania Electne Company JC Monopeitan Eciaon Company PE MAILING ADDRESS TELEPHONE:

1 Upper Pond Rd. (201) 316-7000 Parsippany, NJ 07054 Jrauary 31, 1991 C301-91-0001 SNEC-91-0001 U. S. Nuclear Regulatory Commission Attention Document Control Desk Washington, DC 20555 Gentlemen:

Saxton Nuclear Facility Operating Licence No. DPR-4 Docket No. 50-146 Final Release Survey of the Reactor Support Duildingo, Reviolon No. 2 On October 15-26, 1990, the NRC conducted a safety inspection at the baxton Nuclear Experimental Corporation (SNEC) facility in Saxton, Pennoyivania.

During the inspection the NRC observed the verification survey conducted by the NRC contractor, Oak Ridge Associated Universities (ORAU). This inspection resulted in inspection report no. 50-146/90-02.

This submittal responds to additional information requested in the inspection repcrt. Also included are analytical results of paint chip samples that were reqvneted by the NRC during the July 10-12, 1990 eafety inspectirn 50-146/90-01.

Attachments 1, 2, and 3 comprise Revision 2 of the Final Release Survey Report. Attachments 1 and 2 provide results of the paint chip samples and a plan of action to disposition the Filled Drum Storage Bunker (FDSD),

respectively. Attachment 3 provides administrative forms to replace existing forms in Revision 1 of the report. In addition to the losues raised during the verification survey and addreeced by Attachment 2, there were twc other items which are addressed below

1. An area along the north edge of the yard pipe tunnel (referred to as area "d" in NRC Inspection Report 50-146/90-02) was identified by the USNRC and ORAU as having radiation readings above background levels.

The area was excavated and a drywell and a concrete storm drain were fP:C30100M j 9102070061 910131 'j PDR 0

ADOCK 0D000146 PDR _ _ _ _ _ _ _ _ _ _ _ _ _

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Final kelease survey of the Reactor Support Buildings, Revision No. 2 uncovered and removed. Soil surrounding the area was excavated until radiation readings of the soil were near background levels. The excavated soil is being stored onsite until it can be properly dispositioned. Following excavation, a coil sample was taken at the base of the hole with the resultant Cs-137 of 23 1 2 pCi/gm. To improve industrial safety conditions, the hole was then backfilled with soil from within the SNEC area fence that had radiation readingo near background levole.

This area has been established as a " hold point," thus providing the USNRC the option to review the results and/or conduct verification surveye before final disposition.

2. Drawings of the site were obtained f rom the architect / engineering firm and are available on aperture cards. These documents will be reviewed as part of the plan for final site closure and release of the yard area. Some work hae,already been performed to evaluate underground pipes and equipment. A ground penetrating radar study was performed but was unsuccessful due to the high iron concentrations in the soil.

Also core samplen to bedrock were taken in areas where underground storage tanke were previot.cly located and confirmed that the tanks were removed.

Please contact un if you require additional information.

Sincerely, d h13 A%-k -

J. E. Hildebrard president EJP/BA0/plp cet A. Adams - NRC R. Sores - NRC M. Mendonca - NRC M. Riley - Commonwealth of PA J. Roth - NRC S. Weise - NRC File 2412.5.4

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1 ATTACHMENT 1 RESULTS OF COMPOSITE PAINT CHIP SAMPLES 1

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R_ESULTS OF COMPOSITE PAINT CHIP SAMPLES Composite paint samples from the Control and Auxiliary (C&A) building and the Radioactive Waste Disposal Facility (RWDF) were collected to ensure residual radioactivity was not being masked by the painted surfaces. Paint samples were collected from most rooms / cubicles that had painted surfaces remaining. Areas were selected that had a higher probability of contamination based on their functions during operations. In the C&A building, samples 1

were collected from the Auxiliary Equipment Room, Sampling Room, Decon Room, Locker Room, 1st Floor Corridor, HP Room, and Switchgear Room. The RWDF did not have as many painted surfaces remaining. Samples from this building were collected from the Control Room, Scale and Storage Roc v., and the Drum Shipping Room.

A sanding machine was used to remove paint from a known amount of surface area. The radiological results were equated to units of activity (dpm) per 100 cm' for comparison to the USNRC guidelines for unrestricted release as stated in Regulatory. Guide 1.86. Table 1 contains the results of those radionuclides that were above the lower limit of detection (LLD) of the sensitive laboratory analytical equipment.

The sample results show that the residual radioactivity is less than tho'USNRC guidelines for unrestricted ' release as stated in Regulatory Guide 1.86. The results confirm that residual radioactivity was not masked by the paint and that survey

measurements made on these surfaces using portable field instrumentation is valid.

TABLE 1 RESULTS OF COMPOSITE PAINT CillP SAMPLES Building Radionuclide Activity (dpm/100cm 2)

Control & Cs-137 219 Auxiliary Co-60 5 U-234 1 U-235 3 U-230 0.5 Radioactive Waste Cs-137 116 Disposal Facility Co-60 1.5 Pu-238 1 U-234 3 l U-235 0.4 i

U-238 3

NOTE: Tile FOLLOWING IS Tile SAMPLE DATA THAT WAS USED TO L

GENERATE TABLE 1 1

C&A Building Total Surface Area Sanded: 11,342 cm 2 Tota) Weight of Sample: 195 grams Radionuclide Results of Samples l Co-60 1.39 1 0.27 pC1/gm Cs-137 57.5 1 5.8 pC1/gm U-234- 0.34 1 0.14 pC1/gm U-235 0.88 1 0.71 pC1/gm U-238 0.14-1 0.09 pC1/gm RWDF Total Surface Area Sanded: 7,535 cm 8 Total Weight of-Sample: 120 grama Radionuclide Results of Sample:

Co-60 0.42 1 0.09 pC1/gm Cs-137 32.9 i 3.3 pC1/gm Pu-238 0.27 1 0.15 pC1/gm U-234 0.93 1 0.28 pC1/gm U-235 0.12 i 0.10 pC1/gm U-238 0.83 1 0.26 pC1/gm l

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I ATTACitMENT 2 PLAN OF ACTION TO DISPOSITION TIIE FILLED DRUM STORAGE BUNKER

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PLAN OF ACTION TO DISPOSITION THE FILLED DRUM STORAGE BUNKER The FDSB is a timber and carthen structure that was used as temporary storage for low level radwaste during plant operations.

The structuro consists of four walls and a floor. The internal

walls are composed of timbers arranged in matricos intortwined with soil. The top 6 to 12 inches of surficial materials were removed from t.he outsido walls leaving 2 to 4 feet of clay soil.

T: o drums of soil and pile of soil that wore being stored inside the bunker were removed to gain access to the bunker and the macadam. floor. The soll was relocated to the north side of the SNEC area fence and was stabilized to prevent erosion and sediment.ation problems. The macadam floor of the bunker was survoyed using a gamma scintillation detector with a ratomoter.

Measurements greater than 2 times background lovels woro excavated and will bo dispositioned appropriately.

The outside walls were gridded (3 motors x 3 meters) and soil samplos woro collected and analyzed f rom each grid. Soll core samples (2 to 4' feet) were taken f rom the inside and outside walls.

Samplos were also taken of - the soil that became exposed after-excavation of contaminated sections of the macadam floor. Figure 1 shows the sample locations and Tables 1, 2, and 3 contain the radiological results of the grida, soll cores, and soil floor, respectively.

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l Following approval of Tech. Spec. Change Roquest No. 53, the FDSB will be dismantled by a demolition contractor. The timbers will be dismantled and separated from the soll. They will be surveyed in accordance with procedures for survey and release of equipment and l materials for unrestricted use. The release criteria will be Regulatory Guide 1.86. Any timbors found to be greater than the release criteria will olther be decontaminated and resurveyed or disposed of as low level radwaste. The timbers will be staged onsito and the USNRC will be notified of their status. The USNRC has the option to review the results and/or conduct verification surveys before final disposition. After final approved releaso, the timbers may be rocycled or disposed of offeite in an approved landfill.

The soll component of the bunker will remain onsite id stabilized to provent erosion and sedimentation problems. The acadam floor will also remain onsite. Final release of the soll and macadam floor will be addressed at the time of final site closure, t

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FIGURE 1 FILLED DRUM STORAGE BUNKER (FDSB)

(Layout of Grids and Sample Locations)

NORTH (C2) l l 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 (C1)  !'

(H) (G) (D) (C) (B) (A) 19 (E) 20 21 22 23 24 25 28 29 WEST EAST (C6) 26 27 (CS) 32 33 (C7) l (M) 30 31 (I) (F) (C3) 34 35 l l

36 3's 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 f (C4)

SOUTH

TABLE 1 SOIL RESULTS FROM FDSB OUTSIDE WALL GRIDS Cs-137 pCi/gm Grid No. Cs-137 oci/qm Grid No. Cs-137 pC1/qm Grid No. Cs-137 pCi/qm 20 0.73 1 0.07 39 2.5 1 0.2 1 1.7 ! 0.2 2.6 1 0.3 71.0 1 7 21 0.92 i O.09 40 2 41 5.6 1 0.6 3 5.3 i 0.5 22 8.0 i 0.8 23 2.4 0.2 42 13.0 1 1 4 1.2 ! 0.1 0.55 1 0.07 24 3.0 1 0.3 43 2.3 1 0.2 5 44 0.79 1 0.08 6 0.98 1 0.1 25 0.50 1 0.06 26 1.3 1 0.1 45 0.34 1 0.06 7 0.49 0.06 5.5 1 0.5 27 17.0 12 46 0.31 1 0.05 8

28 1.4 1 0.1 47 3.1 1 0.3 9 5.6 1 0.6 0.09 1 0.029 29 1.1 1 0.1 48 2.6 i 0.3 10 1.5 1 0.2 1.4 ! 0.1 30 7.5 0.8 49 11 0.82 1 0.08 0.91 1 0.09 31 5.8 1 0.6 50 12 1.2 i 0.1 0.56 1 0.06 32 0.78 i 0.08 51 13 52 2.7 i 0.3 14 0.26 i 0.04 33 3.1 1 0.3 0.29 0.05 34 2.4 1 0.2 53 1.5 1 0.1 15 2.1 1 0.2 0.44 1 0.05 35 1.8 1 0.2 54 16 2.1 i 0.2 0.97 1 0.01 36 7.0 ! 0.7 55 17 0.76 1 0.08 37 18.0 1 2 56 5.1 t 0.5 18 2.7 1 0.3 l

6.8 1 0.7 38 9.9 1 1 57 j

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TABLE 1 (Cont'd)

SOIL RESULTS PROM FDSB OUTSIDE WALL GRIDS Co-60 pCi/gm Grid No. Co-60 rC1/gn 2 0.5110.08 35 0.18 1 0.04 38 1.2 1 0.05 42 0.1610.05 l

43 0.1210.05 1

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4 TABLE 2 RESULTS OF SOIL CORES PROM INSIDE AND OUTSIDE WALLS OF THE FDSD CORE I.D. Cs-137 pCi/cm 1 -

4 C1 (inside wall) 0.26 1 0.05 C2 (outside wall) <0.04 s

C3 (Inside wall) 2.6 1 0.3 C4 (outside wall) <0.07 C5 (Inside wall) 2.9 1 0.3 C6 (outside wall) 0.33 1 0.06 C7 (outside wall) <0.05 4

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TABLE 3 REStlLTS OF SOIL SAMPLES PROM EXCAVATED llOLES IN Tile FDSB FLOOR SOIL No. Cs-137 pC1/cm i

A 0.92 + ~

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B 0.22 1 0.06 C 4.8 1 0.5 0 0.49 1 0.05 1

E 0.043 1 0.029 F 1.8 1 0.2 G 2.8 1 0.3 4

11 7.9 1 0.8

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ATTACHMENT 3 INSERTS FOR REV. 2, JANUARY 1991, TO THE FINAL RELEASE SURVEY OF THE REACTOR SUPPORT BUILDINGS

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Saxton Nuclear Experimental Facility ME C *"3 PE JC Final Release Survey of the Reactor Support Buildings Rev. 2 , January 1991 l

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l FINAL RELEASE SURVEY REPORT OF THE CONTROL AND AUXILIARY BUILDING, RADIOACTIVE WASTE DISPOSAL FACILITY REFUELING WATER STORAGE TANK, YARD PIPE TUNNEL, AND FILLED DRUM STORAGE BUNKER FOR THE SAXTON NUCLEAR EXPERIMENTAL FACILITY NRC LICENSE NO. DPR-4 Prepared by GPU Nuclear Corporation for the Saxton Nuclear Experimental Corporation (SNEC)

Revision 2, January, 1991

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TABLE OF CONTENTS Page TABLE OF CONTENTS 1 LIST OF TABLES 11 LIST OF FIGURES 111 j EXECUTIVE

SUMMARY

1 INTRODUCTION 6 DESCRIPTION OF SITE 14

[ FACILITY OPERATING llISTORY 16 RADIOLOGICAL CilARACTERIZATION PRIOR 18 TO Tl!E FINAL RELEASE SURVEY 1987/1988 DECONTAMINATION ACTIVITIES 27 FINAL SURVEY DESCRIPTION 30 FINAL SURVEY RESULTS 45 i

REFERENCES 58 i LIST OF ABBREVIATIONS 60 i APPENDIX At DESCRIPTION OF FUNCT20N OF Tile 61 l AUXILIARY BUILDING AND Tile RADIOACTIVE WASTE DISPOSAL FACILITY APPENDIX B: SURVEY DOCUMENTATION 75 APPENDIX C: MEASUREMENT AND ANALYTICAL PROCEDURES 163 APPENDIX D

SUMMARY

OF SURVEY RESULTS FOR 177 EACil AREA / CUBICLE l APPENDIX Et

SUMMARY

OF OFFSITE BASELINE / BACKGROUND 668 l MEASUREMENTS -

APPENDIX F: ENVIRONMENTAL PATilWAYS ANALYSIS 674 APPENDIX G DISMANTLEMENT AND DEMOLITION PROCESS 701 APPENDIX 11:

SUMMARY

OF SOIL RESULTS 707 l

APPENDIX I: PilOTOGRAPilS 713 ATTACilMENT 1: RESULTS OF COMPOSITE PAINT CilIF SAMPLES PLAN OF ACTION TO DISPOSITION TIIE ATTACllMENT 2:

FILLED DRUM STORAGE BUNKER 1

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