ML052860218

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Document Review - Final Status Survey Reports, Saxton Nuclear Experimental Corporation, Saxton, Pennsylvania (Docket No. 50-146; Task 1), August 2005
ML052860218
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 08/17/2005
From: Bauer T
Oak Ridge Institute for Science & Education
To: Dragoun T
Division of Regulatory Improvement Programs
References
Download: ML052860218 (5)


Text

A D R I S HE OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION August 17, 2005 Mr. Thomas Dragoun NRR/DRIP U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

SUBJECT:

DOCUMENT REVIEW-FINAL STATUS SURVEY REPORTS, SAXTON NUCLEAR EXPERIMENTAL CORPORATION, SAXTON, PENNSYLVANIA (DOCKET NO. 50-146; TASK 1)

Dear Mr. Dragoun:

The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) has reviewed Saxton Nuclear Experimental Corporation (SNEC) final status survey reports submitted to the U.S. Nuclear Regulatory Commission (NRC) on July 22, 25, and 26, 2005. These documents describe the final status survey results for the following SNEC-designated areas: SSGS Structural Surfaces for the Intake Tunnel, Discharge Tunnel, Discharge Tunnel Transition Area, and CV Steam Tunnel.

Comments identified are enclosed for your consideration. If you have any questions, please contact me at (865) 576-3356 or Alex J. Boerner at (865) 574-0951.

Sincerely, Timothy J. Bauer Health Physicist Environmental Survey and Site Assessment Program TJB:ar Enclosure cc: A. Adams, NRC/NRR/OWFN 12G13 A. Boerner, ORISE/ESSAP S. Adams, NRC/NRR/OWFN 012E5 File/0968 AO (

E. Abelquist, ORISE/ESSAP l Distributon approval and concurrence: I InitaL S4 l I Technical Management Team Member I )W I

P.0. BOX 117, OAK RIDGE, TENNESSEE 37831-0117 Operated by Oak Ridge Associated Universities for the U.S. Department of Energy 4

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Comments on Final Status Survey Reports Saxton Nuclear Experimental Corporation Saxton, Pennsylvania August 2005 Saxton Nuclear Experimental Corporation (SNEC) submitted final status survey reports (FSSR) to the U.S. Nuclear Regulatory Commission (NRC) on July 22, 25, and 26, 2005. These documents described the final status survey (FSS) results for the following SNEC-designated areas: SSGS [Saxton Steam Generating Station] Structural Surfaces for the Intake Tunnel, Discharge Tunnel, Discharge Tunnel Transition Area, and CV [Containment Vessel] Steam Tunnel. The FSSRs were reviewed for completeness and conformance to the SNEC License Termination Plan (LTP, GPU 2004a) and the MARSSIM (NRC 2000). Comments noted during the reviews are identified below.

SSGS StructuralSurfaces - Intake Tunnel (GPU2005a)

1. General-Was the Surface Contamination Monitor (SCM) data corrected for background contributions? If so, where were the background measurements using the SCM performed?
2. General-ESSAP recommends that the SCM technical summary presented in the Penelec Line Shack FSSR (GPU 2004b) be included in the Intake Tunnel FSSR. This comment also applies to all other FSSRs where the SCM was used.
3. General-Section 6.1.1 states that "all SCM surveys indicated activity less than the 75%

administrative limit for a minimum 1 square meter grid averaging. One square meter averages are applied to the SCM data since this is the minimum size of an area for emc testing per the SNEC LTP." This approach is inappropriate and is not consistent with the approach presented in the Penelec Line Shack FSSR (GPU 2004b) nor consistent with standard hand-held surveys. The SCM data should be filtered to identify all elevated activity greater than the administrative limit (AL) occurring in areas greater than or equal to 100 cm2. For areas less than or equal to 1 in in area, the 1 m2 area factor (AF) should apply.

4. General-Section 6.1.1 states that 69% of the area was scanned using the SCM. The FSSR discusses that this is adequate scan coverage for a Class 2 area. Section 6.1.2 notes that the "survey unit did not receive fixed point direct static measurements. As discussed in section 5.0, the SCM is equivalent to continuous static measurements of the entire surface scanned." It is ESSAP's opinion that the FSSR has not adequately discussed the differences between a statistically determined number of direct measurements, performed using a random-start systematic pattern, and limited area scan using the SCM which collects a great number of statistically poorer direct measurements. SNEC should provide a technical basis that answers the following question: Is an SCM survey of 69%, or in general less than 100%, of a Class 2 or 3 survey unit equivalent or superior to N number SNEC FSSR Document Review projects\O968\Letters\2005-8-17 FSSR Review.doc

of direct measurements to determine the average for comparison to the AL? This comment also applies to the review of the FSSR for the Small Penelec Garage submitted in a previous letter (ORISE 2005).

5. Section 7.4.1, Page 15 of 16-This section states that the "QC rescans did not identify any activity above alarm points and so are in agreement with the primary scans." It is ESSAP's opinion, based on preceding sections in the FSSR, that this statement does not apply to SCM surveys.
6. Section 7.4.1, Page 15 of 16-Since the SCM data collected was used to quantitatively assess the residual surface activity, it is ESSAP's opinion that the QC comparison should have been performed per Section 4.6.2.4 of SNEC Procedure E900-IMP-4520.04, Survey Methodology to Support SNEC License Termination (GPU 2005b) titled Static Measurements and documented in Section 7.4.2, Fixedpoint measurements, of the FSSR.
7. Section 8.0, Page 15 of 16-The first item in this section states that the "average residual radioactivity on the surfaces is less than the derived surrogate DCGLw in all the survey units." The average should be compared to the AL rather than the DCGLW. This comment also applies to the second item in this section.

SSGS StructuralSurfaces - Discharge Tunnel (GPU 2005c)

1. General-See Intake Tunnel Comments #3, #4, #5, and #7 for application to this FSSR.
2. Section 6.4.3, Page 13 of 24-Appendix E, which provides the details of the elevated area dose assessment, should be referenced in this section.
3. Section 7.4.2, Page 23 of 24-This section describes the fixed point QC measurement results. SNEC noted that the results provided in Table 7.4-1 had good agreement and supported the same conclusion. However, according to SNEC Procedure E900-lMP-4520.04, Survey Methodology to Support SNEC License Termination (GPU 2005b),

Section 4.6.2.4 indicates that for static measurements, QC measurements must have the same conclusion and must be within 20% of the original result. The following QC measurements shown in Table 7.4-1 do not meet the 20% requirement: SS1 07 and SS6-2 06. ESSAP recommends SNEC re-evaluate the QC measurements using the two times background provision discussed in Procedure E900-DMP4520.04.

4. Appendix E-Please discuss, providing appropriate references (e.g. LTP), why a dose assessment was performed to evaluate the identified elevated areas rather than the methodology provided in Appendix 5-1 of the LTP.
5. Appendix E, Table 1,Page 2 of 7-The explanation for NA values listed in the MDC column is not provided.

SNEC FSSR Document Review 2 projccts\D968'ettns\2005-08-17 FSSR Review.doc

SSGS StructuralSurfaces - DischargeTunnel TransitionArea (GPU2005d)

1. Section 6.4-Please discuss, providing appropriate references (e.g. LTP), the applicability of using Nal scans and direct measurements of steel surfaces.
2. Section 7.4.2, Page 19 of 22-This section describes the fixed point QC measurement results. SNEC noted that the results provided in Table 7.4-1 had good agreement and supported the same conclusion. However, according to SNEC Procedure E900-IMP-4520.04, Survey Methodology to Support SNEC License Termination (GPU 2005b),

Section 4.6.2.4 indicates that for static measurements, QC measurements must have the same conclusion and must be within 20% of the original result. The following QC measurements shown in Table 7.4-1 do not meet the 20% requirement: GFPC SS25-1 Ceiling 7, GFPC SS25-1 N Wall 6, GFPC SS25-1 S Wall 4, and Nal SS25-2 (62 and 86 cpm results). ESSAP recommends SNEC re-evaluate the QC measurements using the two times background provision discussed in Procedure E900-DM1P4520.04.

3. Section 8.0, Page 20 of 22-The first item in this section states that the "average residual radioactivity on the surfaces is less than the derived surrogate DCGLw in all the survey units." The average should be compared to the AL rather than the DCGLw.
4. Appendix A, Attachment 2-1-Were the three instrument/probe combinations noted as having an instrument conversion factor/efficiency less than 208,302 cpm/mR/hr used during the FSS? Refer to Appendix A, Section 2.2.2, Page 3 of 9 for this requirement.
5. Appendix B, Attachment 2-1-Were the three instrumentlprobe combinations noted as having an instrument conversion factor/efficiency less than 208,302 cpm/mR/hr used during the FSS? Refer to Appendix B, Section 2.2.2, Page 3 of 10 for this requirement.

SSGS StructuralSurfaces - CV Steam Tunnel (GPU2005e)

1. Section 8.0, Page 17 of 18-The first item in this section states that the "average residual radioactivity on the surfaces is less than the derived surrogate DCGLw in all the survey units." The average should be compared to the AL rather than the DCGLw. This comment also applies to the second item in this section.
2. Appendix A, Attachment 5-1-Were the two instrument/probe combinations noted as having an instrument conversion factor/efficiency less than 208 cpm/pR/hr used during the FSS? Refer to Appendix A, Table 4, Page 3 of 10 for this requirement.

SNEC FOSR Docment Review S Seees\0968\LztUs\2005-8-17 FSSR Review.doc 3

REFERENCES GPU Nuclear, Inc. (GPU). Saxton Nuclear Experimental Corporation Facility License Termination Plan. Saxton, Pennsylvania; Revision 3, February 2004a.

GPU Nuclear, Inc. Final Status Survey Report, Saxton Nuclear Experimental Corporation, Penelec Line Shack. Saxton, Pennsylvania; June 2004b.

GPU Nuclear, Inc. FSS Report - SSGS Structural Surfaces - Intake Tunnel. Saxton, Pennsylvania; July 26, 2005a.

GPU Nuclear, Inc. SNEC Procedure E900-.MP-4520.04, Survey Methodology to Support SNEC License Termination, Revision 11. Saxton, Pennsylvania; May 24, 2005b.

GPU Nuclear, Inc. FSS Report - SSGS Structural Surfaces - Discharge Tunnel. Saxton, Pennsylvania; July 26, 2005c.

GPU Nuclear, Inc. FSS Report - SSGS Structural Surfaces - Discharge Tunnel Transition Area.

Saxton, Pennsylvania; July 22, 2005d.

GPU Nuclear, Inc. FSS Report - SSGS Structural Surfaces - CV Steam Tunnel. Saxton, Pennsylvania; July 25, 2005e.

Oak Ridge Institute for Science and Education (ORISE).

Subject:

Document Review-Final Status Survey Reports, Saxton Nuclear Experimental Corporation, Saxton, Pennsylvania (Docket No. 50-146; Task 1). Oak Ridge, TN; August 11, 2005.

U.S. Nuclear Regulatory Commission (NRC). Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). Washington, DC; NUREG-1575; Revision 1, August 2000.

SNEC FSSR Document Review 4 projectsO968\Lztters\2m5M-8-17 FSSR Review.doc