ML12100A125

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Plum Brook Reactor Facility - Final Status Survey Report Hot Laboratory (Building 1112) Revision No. 0 Appendix B Survey Unit Maps Showing Measurement Locations: Survey Unit HL-2-3
ML12100A125
Person / Time
Site: Plum Brook
Issue date: 04/05/2012
From: Mann B
US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
To:
NRC/FSME
References
Download: ML12100A125 (71)
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Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 101 of 147 Survey Unit HL-2-3 Hot Laboratory, Mezzanine - South Wall

,ME~ VO HL-2-3 AREA: Hot Laboratory, Mezzanine South Wall Measurement Locations and results Location I X Co-ord (m) YCo-ord (m) dpmll 00-cm 2 Type Notes 1.2 2.1 SM-1 725 Systematic N/A 4.2 2.1 SM-2 919 Systematic N/A 7.2 2.1 SM-3 691 Systematic N/A 10.3 2.1 SM-4 879 Systematic N/A 2.7 4.8 SM-5 47 Systematic N/A 5.7 4.8 SM-6 161 Systematic N/A 8.8 4.8 SM-7 -40 Systematic N/A 1.2 7.4 SM-8 -121 Systematic N/A 4.2 7.4 SM-9 81 Systematic N/A 7.2 7.4 SM-10 -188 Systematic N/A 10.3 7.4 SM-11 -27 Systematic N/A

  • Sample measurements are from the lower left corner of the wall surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 102 of 147 Survey Unit HL-2-4 Hot Laboratory, Mezzanine Walls HL-2-4 AREA: Hot Laboratory, Mezzanine Walls Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (im) dpmll 00-cm2 Type Notes 1.5 2.0 SM-1 747 Systematic N/A 4.6 2.0 SM-2 932 Systematic N/A 1.7 2.0 SM-3 637 Systematic N/A 1.0 2.0 SM-4 514 Systematic N/A 4.1 2.0 SM-5 1120 Systematic N/A 0.8 2.0 SM-6 226 Systematic N/A 0.2 4.7 SM-7 96 Systematic N/A 3.3 4.7 SM-8 -130 Systematic N/A 6.4 4.7 SM-9 -7 Systematic N/A 1.7 7.3 SM-10 -130 Systematic N/A 4.8 7.3 SM-11 123 Systematic N/A

  • Sample measurements are from the lower left corner of the wall surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 103 of 147 Survey Unit HL-3-1 Hot Pipe Tunnel-Floor Section #1 and Sump SM-i SM SM SM SMI SM- OM-HL-3-1 AREA: Hot Pipe Tunnel-Floor Section #1 and Sump Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpm/100-cm2 Type Notes 1.8 0.5 SM-i 943 Systematic N/A 3.8 0.5 SM-2 496 Systematic N/A 5.7 0.5 SM-3 1220 Systematic N/A 7.7 0.5 SM-4 569 Systematic N/A 0.8 2.2 SM-5 984 Systematic N/A 2.8 2.2 SM-6 911 Systematic N/A 4.7 2.2 SM-7 626 Systematic N/A 6.7 2.2 SM-8 1220 Systematic N/A 8.7 2.2 SM-9 4980 Systematic N/A 1.8 3.9 SM-10 1250 Systematic N/A 3.8 3.9 SM- 1 528 Systematic N/A 5.7 3.9 SM-12 1190 Systematic N/A 7.7 3.9 SM-1 3 1150 Systematic N/A 0.4 1.0 SM-14 1098 Systematic N/A 2.3 1.0 SM- 5 707 Systematic N/A

  • SM-1 through SM-1 3 are taken from the southwest comer of the survey unit, SM-14 and SM-15 are measured from the North line of the sump.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 104 of 147 Survey Unit HL-3-2 Hot Pipe Tunnel-Floor Section #2 HL-3-2 AREA: Hot Pipe Tunnel-Floor Section #2 Measurement Locations and results Location / dpm/100-X Co-ord (m) Y Co-ord (m) cm2 Type Notes 0.2 1.5 SM-1 957 Systematic N/A 2.6 1.5 SM-2 652 Systematic N/A 4.9 1.5 SM-3 787 Systematic N/A 7.3 1.5 SM-4 1050 Systematic N/A 9.6 1.5 SM-5 1450 Systematic N/A 11.9 1.5 SM-6 1080 Systematic N/A 14.3 1.5 SM-7 1280 Systematic N/A 1.4 3.5 SM-8 1070 Systematic N/A 3.7 3.5 SM-9 463 Systematic N/A 6.1 3.5 SM-10 299 Systematic N/A 8.4 3.5 SM-11 646 Systematic N/A 10.8 3.5 SM-12 988 Systematic N/A 13.1 3.5 SM-13 994 Systematic N/A 11.9 5.6 SM-14 1180 Systematic N/A 14.3 5.6 SM-15 1,270 Systematic N/A

  • All measurements are taken from the southwest corner of the survey unit.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 105 of 147 Survey Unit HL-3-3 Hot Pipe Tunnel-Floor Section #3

  • M OM *M HL-3-3 AREA: Hot Pipe Tunnel-Floor Section #3 Measurement Locations and results Location / dpm/100-X Co-ord (m) Y Co-ord (m) cm 2 Type Notes 0.5 1.5 SM-1 1080 Systematic N/A 2.9 1.5 SM-2 1080 Systematic N/A 5.3 1.5 SM-3 963 Systematic N/A 7.7 1.5 SM-4 689 Systematic N/A 10.1 1.5 SM-5 896 Systematic N/A 12.5 1.5 SM-6 915 Systematic N/A 1.7 3.6 SM-7 823 Systematic N/A 4.1 3.6 SM-8 640 Systematic N/A 6.5 3.6 SM-9 1180 Systematic N/A 8.9 3.6 SM-10 518 Systematic N/A 11.3 3.6 SM-11 982 Systematic N/A 0.5 5.7 SM-12 1350 Systematic N/A 2.9 5.7 SM-13 872 Systematic N/A 1.7 7.7 SM-14 1170 Systematic N/A 4.1 7.7 SM-15 866 Systematic N/A All of the sample measurements are taken from the lower left comer of the survey unit.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 106 of 147 Survey Unit HL-3-4 Hot Pipe Tunnel-Floor Section #4 HL-3-4 AREA: Hot Pipe Tunnel-Floor Section #4 Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (mi) dpm/1 00-cm2 Type Notes 0.3 2.0 SM-I 817 Systematic N/A 2.6 2.0 SM-2 1140 Systematic N/A 1.5 4.0 SM-3 848 Systematic N/A 3.8 4.0 SM-4 591 Systematic N/A 0.3 6.1 SM-5 774 Systematic N/A 2.6 6.1 SM-6 768 Systematic N/A 1.5 8.1 SM-7 695 Systematic N/A 3.8 8.1 SM-8 530 Systematic N/A 0.3 10.1 SM-9 476 Systematic N/A 2.6 10.1 SM-10 1430 Systematic N/A 1.5 12.2 SM-11 287 Systematic N/A 3.8 12.2 SM-12 720 Systematic N/A 0.3 14.2 SM-13 707 Systematic N/A 2.6 14.2 SM-14 585 Systematic N/A 5.0 14.2 SM-I5 628 Systematic N/A All of the sample measurements are taken from the southwest comer of the survey unit.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 107 of 147 Survey Unit HL-3-5 Hot Pipe Tunnel-Floor Section #5 HL-3-5 AREA: Hot Pipe Tunnel-Floor Section #5 Measurement Locations and results Location I dpmll00-X Co-ord (m) Y Co-ord (m) cm2 Type Notes 0.3 1.5 SM-1 482 Systematic N/A 2.7 1.5 SM-2 628 Systematic N/A 5.0 1.5 SM-3 793 Systematic N/A 1.5 3.5 SM-4 506 Systematic N/A 3.8 3.5 SM-5 677 Systematic N/A 0.2 1.6 SM-6 4360 Systematic N/A 2.5 1.6 SM-7 1130 Systematic N/A 4.9 1.6 SM-8 1290 Systematic N/A 7.2 1.6 SM-9 713 Systematic N/A 9.5 1.6 SM-1 0 744 Systematic N/A 0.3 5.5 SM-1 1 482 Systematic N/A 2.7 5.5 SM-12 884 Systematic N/A 5.0 5.5 SM-13 951 Systematic N/A 1.5 7.5 SM-14 293 Systematic N/A 3.8 7.5 SM-15 5150 Systematic N/A All measurements are taken from the location on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 108 of 147 Survey Unit HL-3-6 Hot Pipe Tunnel- Corrugated Pipe Tunnel Section 1 in ---------- Line B Line A is the south side of the tunnel, at its longest point. The sample map is formed by unrolling the tunnel SM-B 13SJ SMo-I downward, with Line B being the opposite side of the tunnel on its north side. On the sample map, the bottom of the tunnel is the area to the left of the dashed line (Line B), while

"* S1"7 the top of the tunnel is the area to the right of the dashed line (line B).

The Tunnel circumference is 5.75m.

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Measure SM-1 and SM-2 from this Measure SM-3 through SM-12 from this point. Mn s Mnt i HL-3-6 AREA: HPT-Corrugated Pipe Tunnel Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpmll00-cm2 Type Notes 2.3 0.3 SM-1 3650 Systematic N/A 4.8 0.3 SM-2 -75 Systematic N/A 0.1 1.5 SM-3 -247 Systematic N/A 2.6 1.5 SM-4 75 Systematic N/A 5.1 1.5 SM-5 233 Systematic N/A 1.3 3.6 SM-6 1090 Systematic N/A 3.8 3.6 SM-7 -27 Systematic N/A 0.1 5.8 SM-8 199 Systematic N/A 2.6 5.8 SM-9 281 Systematic N/A 5.1 5.8 SM-10 110 Systematic N/A 1.3 7.9 SM-11 1690 Systematic N/A 3.8 7.9 SM-12 -14 Systematic N/A

  • All measurements are taken from the locations shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 109 of 147 Survey Unit HL-3-7 Hot Pipe Tunnel- Corrugated Pipe Tunnel Section 2 SM-Il I I4i Iie7B I SM4 I0 Line A is the south side of the tunnel,

  • __ I at its longest point. The sample map SM4 *W is formed by unrolling the tunnel downward, with Line B being the opposite side of the tunnel on its north side. On the sample map, the 4

SM bottom of the tunnel is the area to the left of the dashed line (Line B), while the top of the tunnel is the area to the right of the dashed line (line B).

  • __ I SM-I SM2 A

The Tunnel circumference is 5.75m.

Measure SM-I through SM-12 from this point.

HL-3-7 AREA: HPT-Corrugated Pipe Tunnel Section 2 Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpm/lOO-cm 2 Type Notes 1.6 0.4 SM-1 1747 Systematic N/A 4.1 0.4 SM-2 158 Systematic N/A 0.4 2.6 SM-3 507 Systematic N/A 2.8 2.6 SM-4 418 Systematic N/A 5.3 2.6 SM-5 123 Systematic N/A 1.6 4.7 SM-6 2356 Systematic N/A 4.1 4.7 SM-7 -137 Systematic N/A 0.4 6.8 SM-8 185 Systematic N/A 2.8 6.8 SM-9 -34 Systematic N/A 5.3 6.8 SM-10 144 Systematic N/A 1.6 9.0 SM-11 1438 Systematic N/A 4.1 9.0 SM-12 671 Systematic N/A

  • All measurements are taken from the location shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 110 of 147 Survey Unit HL-3-8 Hot Pipe Tunnel- Corrugated Pipe Tunnel Section 3 Line A I -LJ9EI IM Ij4S Line A is the south side of the tunnel, at its longest point. The sample map is formed by unrolling the tunnel downward, with Line B being the opposite side of the tunnel on its north side. On the sample map, the bottom of the tunnel is the area to the left of the dashed line (Line B), while the top of the tunnel is the area to the right of the dashed line (line B).

The Tunnel circumference is 5.75m.

7 IMeasure SM-I through SM-10 from this point.

HL-3-8 AREA: HPT-Corrugated Pipe Tunnel Section 3 Measurement Locations and results Location /

X Co-ord (im) Y Co-ord (m) dpm/1 00-cm 2 Type Notes 2.3 0.5 SM-1 662 Systematic N/A 4.8 0.5 SM-2 79 Systematic N/A 1.0 2.7 SM-3 583 Systematic N/A 3.5 2.7 SM-4 -216 Systematic N/A 2.3 4.9 SM-5 619 Systematic N/A 4.8 4.9 SM-6 -14 Systematic N/A 1.0 7.2 SM-7 230 Systematic N/A 3.5 7.2 SM-8 -122 Systematic N/A 2.3 9.4 SM-9 547 Systematic N/A 4.8 9.4 SM-10 -237 Systematic N/A 1.0 -1.0 SM-1 1 482 Systematic N/A 3.5 -1.0 SM-12 86 Systematic N/A

  • All measurements are taken from the locations shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 111 of 147 Survey Unit HL-3-9 Hot Pipe Tunnel-Walls Section #1 HL-3-9 AREA: Hot Pipe Tunnel-Walls Section #1 Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpmll 00-cm 2 Type Notes 0.2 0.1 SM-1 699 Systematic N/A 2.9 0.1 SM-2 993 Systematic N/A 5.7 0.1 SM-3 1140 Systematic N/A 8.4 0.1 SM-4 767 Systematic N/A 0.4 0.1 SM-5 1020 Systematic N/A 3.1 0.1 SM-6 1000 Systematic N/A 5.9 0.1 SM-7 568 Systematic N/A 8.7 0.1 SM-8 1010 Systematic N/A 1.5 2.5 SM-9 623 Systematic N/A 4.3 2.5 SM-10 644 Systematic N/A 7.1 2.5 SM-11 836 Systematic N/A 1.8 2.5 SM-12 534 Systematic N/A 4.5 2.5 SM-13 301 Systematic N/A 7.2 2.5 SM-14 603 Systematic N/A

  • All measurements are taken from the locations shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 112 of 147 Survey Unit HL-3-10 Hot Pipe Tunnel-Walls Section #2 HL-3-10 AREA: Hot Pipe Tunnel-Walls Section #2 Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpmI100-cm 2 Type Notes 2.6 0.2 SM-1 712 Systematic N/A 5.3 0.2 SM-2 658 Systematic N/A 7.9 0.2 SM-3 849 Systematic N/A 10.6 0.2 SM-4 836 Systematic N/A 13.3 0.2 SM-5 630 Systematic N/A 15.9 0.2 SM-6 1340 Systematic N/A 18.6 0.2 SM-7 1322 Systematic N/A 21.3 0.2 SM-8 1100 Systematic N/A 23.9 0.2 SM-9 877 Systematic N/A 26.6 0.2 SM-1 0 637 Systematic N/A 25.3 2.5 SM-1 1 904 Systematic N/A 27.9 2.5 SM-12 445 Systematic N/A

  • All measurements are taken from the location shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 113 of 147 Survey Unit HL-3-11 Hot Pipe Tunnel-Walls Section #3 HL-3-11 AREA: Hot Pipe Tunnel-Walls Section #3 Measurement Locations and results Location I X Co-ord (im) Y Co-ord (im) dpml/00-cm 2 Type Notes 0.1 0.6 SM-1 7980 Systematic N/A 3.0 0.6 SM-2 795 Systematic N/A 5.9 0.6 SM-3 592 Systematic N/A 8.8 0.6 SM-4 719 Systematic N/A 11.7 0.6 SM-5 678 Systematic N/A 14.6 0.6 SM-6 733 Systematic N/A 17.6 0.6 SM-7 493 Systematic N/A 20.5 0.6 SM-8 993 Systematic N/A 23.4 0.6 SM-9 685 Systematic N/A 26.3 0.6 SM-10 274 Systematic N/A 29.2 0.6 SM-1 1 342 Systematic N/A 32.1 0.6 SM-12 664 Systematic N/A

  • All measurements are taken from the location shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 114 of 147 Survey Unit HL-3-12 Hot Pipe Tunnel-Walls Section #4

-1 HL-3-12 AREA: Hot Pipe Tunnel-Walls Section #4 Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpmn/1 00-cm 2 Type Notes 0.1 0.55 SM-1 96 Systematic N/A

-.06 0.55 SM-2 185 Systematic N/A 0.6 1.8 SM-3 603 Systematic N/A 1.0 1.8 SM-4 925 Systematic N/A 1.4 1.8 SM-5 788 Systematic N/A 1.8 1.8 SM-6 678 Systematic N/A 4.8 1.8 SM-7 342 Systematic N/A 7.8 1.8 SM-8 664 Systematic N/A 10.8 1.8 SM-9 705 Systematic N/A 0.3 1.8 SM-10 582 Systematic N/A 2.1 1.8 SM-11 870 Systematic N/A 5.1 1.8 SM-12 842 Systematic N/A

  • All measurements are taken from the locations shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 115 of 147 Survey Unit HL-3-13 Hot Pipe Tunnel-Walls Section #5 HL-3-13 AREA: Hot Pipe Tunnel-Walls Section #5 Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpml100-cm 2 Type Notes 1.8 0.8 SM-1 427 Systematic N/A 4.8 0.8 SM-2 341 Systematic N/A 0.8 0.8 SM-3 720 Systematic N/A 3.9 0.8 SM-4 402 Systematic N/A 6.9 0.8 SM-5 579 Systematic N/A 10.0 0.8 SM-6 1040 Systematic N/A 13.0 0.8 SM-7 921 Systematic N/A 16.1 0.8 SM-8 439 Systematic N/A 19.1 0.8 SM-9 817 Systematic N/A 1.5 0.8 SM-10 671 Systematic N/A 2.1 0.8 SM-11 1070 Systematic N/A 2.1 0.8 SM-12 860 Systematic N/A

  • All measurements are taken from the locations shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 116 of 147 Survey Unit HL-3-14 Hot Pipe Tunnel-Walls Section #6

' *M *M2 *ME *ffm IE6 7--7

ýýý ISM-4YS-M-4 SM I I I HL-3-14 AREA: Hot Pipe Tunnel-Walls Section #6 Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpm/I 00-cm 2 Type Notes 2.2 1.2 SM-1 616 Systematic N/A 5.1 1.2 SM-2 787 Systematic N/A 0.2 0.06 SM-3 683 Systematic N/A 0.6 2.1 SM-4 854 Systematic N/A 0.4 0.3 SM-5 835 Systematic N/A 3.3 0.3 SM-6 805 Systematic N/A 2.7 0.3 SM-7 689 Systematic N/A 0.7 2.8 SM-8 963 Systematic N/A 1.8 2.8 SM-9 976 Systematic N/A 0.1 2.8 SM-10 1310 Systematic N/A 1.2 2.8 SM-i1 768 Systematic N/A 4.2 2.8 SM-12 585 Systematic N/A

  • SM-3 and SM-4 measurements are taken from the southwest comer of the surface on which they lie. All other sample measurements are taken from the lower left corner of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 117 of 147 Survey Unit HL-3-15 Hot Pipe Tunnel-Ceiling Section #1 SimI SM-I SM-I 4 4 Measure SM-1 through SM-12 from this point.

HL-3-15 AREA: Hot Pipe Tunnel-Ceiling Section #1 Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (im) dpm/1 00-cm2 Type Notes 1.9 1.0 SM-1 950 Systematic N/A 4.9 1.0 SM-2 619 Systematic N/A 7.8 1.0 SM-3 734 Systematic N/A 10.7 1.0 SM-4 813 Systematic N/A 13.6 1.0 SM-5 806 Systematic N/A 16.6 1.0 SM-6 647 Systematic N/A 0.5 3.5 SM-7 683 Systematic N/A 3.4 3.5 SM-8 734 Systematic N/A 6.3 3.5 SM-9 619 Systematic N/A 12.2 3.5 SM-10 590 Systematic N/A 15.1 3.5 SM-11 424 Systematic N/A 18.0 3.5 SM-12 942 Systematic N/A

  • All measurements are taken from the location shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 118 of 147 Survey Unit HL-3-16 Hot Pipe Tunnel-Ceiling Section #2 SM-? *M *gig SM-I S-Ial SM 12 SM-I*-SM-M SM SM °SM Measure SM-I through SM-12 from this point.

HL-3-16 AREA: Hot Pipe Tunnel-Ceiling Section #2 Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpm/l 00-cm2 Type Notes 0.8 0.2 SM-1 655 Systematic N/A 3.4 0.2 SM-2 1130 Systematic N/A 6.0 0.2 SM-3 748 Systematic N/A 8.5 0.2 SM-4 1150 Systematic N/A 11.1 0.2 SM-5 899 Systematic N/A 13.7 0.2 SM-6 1190 Systematic N/A 2.1 2.4 SM-7 331 Systematic N/A 4.7 2.4 SM-8 957 Systematic N/A 7.3 2.4 SM-9 547 Systematic N/A 9.8 2.4 SM-10 842 Systematic N/A 12.4 2.4 SM- 11 813 Systematic N/A 15.0 2.4 SM-12 1050 Systematic N/A

  • All measurements are taken from the location shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 119 of 147 Survey Unit HL-3-17 Hot Pipe Tunnel-Ceiling Section #3 Measure SM-1 through SM-12 from this point. I HL-3-17 AREA: Hot Pipe Tunnel-Ceiling Section #3 Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpml1 00-cm 2 Type Notes 2.0 0.5 SM-I 482 Systematic N/A 0.5 3.0 SM-2 770 Systematic N/A 3.4 3.0 SM-3 669 Systematic N/A 2.0 5.5 SM-4 705 Systematic N/A 0.5 8.0 SM-5 849 Systematic N/A 3.4 8.0 SM-6 748 Systematic N/A 2.0 10.5 SM-7 806 Systematic N/A 0.5 13.1 SM-8 705 Systematic N/A 3.4 13.1 SM-9 899 Systematic N/A 2.0 15.6 SM-10 734 Systematic N/A 0.5 18.1 SM-11 777 Systematic N/A 3.4 18.1 SM-12 712 Systematic N/A

  • All measurements are taken from the location shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 120 of 147 Survey Unit HL-3-18 Hot Pipe Tunnel-Ceiling Section #4 rim

  • fiim
  • M OW HL-3-18 AREA: Hot Pipe Tunnel-Ceiling Section #4 Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpm/1 00-cm2 Type Notes 1.1 1.3 SM- 1 869 Systematic N/A 4.2 1.3 SM-2 438 Systematic N/A 2.6 1.3 SM-3 515 Systematic N/A 5.7 1.3 SM-4 462 Systematic N/A 1.5 0.5 SM-5 669 Systematic N/A 4.6 0.5 SM-6 715 Systematic N/A 3.1 3.2 SM-7 446 Systematic N/A 1.5 5.8 SM-8 1020 Systematic N/A 4.6 5.8 SM-9 708 Systematic N/A 3.1 8.5 SM-10 662 Systematic N/A 1.5 11.2 SM-11 685 Systematic N/A 4.6 11.2 SM-12 692 Systematic N/A
  • All measurements are taken from the locations shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 121 of 147 Survey Unit HL-3-19 Hot Pipe Tunnel-Ceiling Vents & Penetrations I mIzI D

0 13=]

n3-M-SM_

D 0

r-HL-3-19 AREA: HPT- Ceiling Vents & Penetrations Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (ml dpm/I1O-cm 2 Type Notes 0.5 0.2 SM-1 1550 Systematic N/A 1.7 0.1 SM-2 1350 Systematic N/A 1.0 0.1 SM-3 454 Systematic N/A 0.1 0.25 SM-4 615 Systematic N/A 0.5 0.3 SM-5 915 Systematic N/A 1.0 0.1 SM-6 677 Systematic N/A 1.8 0.3 SM-7 623 Systematic N/A 0.1 0.6 SM-8 562 Systematic N/A 0.3 0.1 SM-9 62 Systematic N/A 0.2 0.4 SM-10 577 Systematic N/A 0.2 0.4 SM-11 477 Systematic N/A 0.3 0.2 SM-12 654 Systematic N/A

  • All measurements are taken from the lower left corner of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 122 of 147 Survey Unit HL-3-20 Hot Pipe Tunnel, Excavation (Soils)

IM *011a IBM o0 I

Area: Hot Pipe Tunnel, Class 1, Survey Unit HL-3-20* (Soils) 0 Measurement Locations and Results Cs-137 Co-60 X Co-ord (m) Y Co-ord (m) Location DCGLw 1 5.87 DCGLw7 3.8 Type Notes pClIg pCilg 0.1 1.3 SP-1 0.1730 <0.0513 Systematic N/A 2.3 1.3 SP-2 0.1300 <0.0503 Systematic N/A 4.4 1.3 SP-3 1.7400 <0.0453 Systematic N/A 0.4 1.3 SP-4 0.2870 <0.0490 Systematic N/A 1.2 3.2 SP-5 <0.0754 <0.0476 Systematic N/A 3.4 3.2 SP-6 0.2010 <0.0453 Systematic N/A 5.5 3.2 SP-7 0.2580 <0.0473 Systematic N/A 0.1 5.1 SP-8 <0.0466 <0.0436 Systematic N/A 2.3 5.1 SP-9 <0.0739 <0.0580 Systematic N/A 1.2 7.0 SP-10 <0.0538 <0.0460 Systematic N/A 3.4 7.0 SP-1 1 <0.0460 <0.0498 Systematic N/A 2.3 8.9 SP-12 <0.0777 <0.0503 Systematic N/A 1.2 10.7 SP-13 0.1720 <0.0494 Systematic N/A 3.4 10.7 SP-14 <0.0503 <0.0517 Systematic N/A

  • All of the sample measurements are taken from the southwest corner of the survey unit, except SP-4 which is taken from the southwest corner of the floor opening in which it lies.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 123 of 147 Survey Unit HL-3-21 Hot Pipe Tunnel, Excavation (Concrete Edges)

E~ *~ - -

t HL-3-21 AREA: Hot Pipe Tunnel Concrete Edges of Floor Removal Areas Measurement Locations and results Location I dpm/100-X Co-ord (m) Y Co-ord (m) cm2 Type Notes 3.0 0.1 SM-1 389 Systematic N/A 6.0 0.1 SM-2 618 Systematic N/A 0.9 0.1 SM-3 199 Systematic N/A 0.3 0.15 SM-4 573 Systematic N/A 2.0 0.15 SM-5 701 Systematic N/A 3.8 0.15 SM-6 565 Systematic N/A 0.7 0.15 SM-7 641 Systematic N/A 3.3 0.2 SM-8 433 Systematic N/A 0.3 0.2 SM-9 291 Systematic N/A 0.3 0.3 SM-10 468 Systematic N/A 2.1 0.3 SM-11 206 Systematic N/A 3.8 0.3 SM-12 328 Systematic N/A 1.7 0.3 SM-1 3 624 Systematic N/A 0.6 0.1 SM-14 156 Systematic N/A 0.6 0.1 SM-15 355 Systematic N/A

  • All of the sample measurements are taken from the lower left or southwest comer of the surface on which they lie.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 124 of 147 Survey Unit HL-4-1 Off-Gas Pit Floor & +6'6" Walkway SM s. M HL-4-1 AREA: Off-Gas Pit - Floor Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpm/100-crn Type Notes 1.5 1.7 SM-1 563 Systematic N/A 3.5 1.7 SM-2 563 Systematic N/A 5.4 1.7 SM-3 968 Systematic N/A 7.4 1.7 SM-4 443 Systematic N/A 1.3 1.7 SM-5 57 Systematic N/A 0.3 3.4 SM-6 411 Systematic N/A 1.3 5.2 SM-7 253 Systematic N/A 0.3 6.9 SM-8 677 Systematic N/A 1.3 8.6 SM-9 563 Systematic N/A 0.3 10.3 SM-10 589 Systematic N/A 1.3 12.0 SM-11 304 Systematic N/A

[*Sample measurements are taken from the southwest comer of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 125 of 147 Survey Unit HL-4-2 Off-Gas Pit North and East Walls HL-4-2 AREA: Off-Gas Pit - North and East Walls Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpm/100-cm 2 Type Notes 2.6 0.3 SM- 1 234 Systematic N/A 5.6 0.3 SM-2 468 Systematic N/A 0.6 0.3 SM-3 449 Systematic N/A 1.1 2.9 SM-4 342 Systematic N/A 4.1 2.9 SM-5 462 Systematic N/A 7.2 2.9 SM-6 386 Systematic N/A 2.6 5.6 SM-7 500 Systematic N/A 5.6 5.6 SM-8 323 Systematic N/A 0.6 5.6 SM-9 563 Systematic N/A 1.1 8.2 SM-10 677 Systematic N/A 4.1 8.2 SM-11 899 Systematic N/A

  • Sample measurements are from the lower left comer of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 126 of 147 Survey Unit HL-4-3 Off-Gas Pit - South and West Walls HL-4-3 AREA: Off-Gas Pit South and West Walls Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpm/100-cm 2 Type Notes 2.4 1.1 SM-1 494 Systematic N/A 5.5 1.1 SM-2 842 Systematic N/A 0.5 1.1 SM-3 373 Systematic N/A 0.8 3.8 SM-4 348 Systematic N/A 3.9 3.8 SM-5 500 Systematic N/A 7.1 3.8 SM-6 519 Systematic N/A 2.4 6.5 SM-7 880 Systematic N/A 5.5 6.5 SM-8 468 Systematic N/A 0.5 6.5 SM-9 778 Systematic N/A 3.9 9.2 SM-10 797 Systematic N/A 7.1 9.2 SM-11 778 Systematic N/A

  • Sample measurements are from the lower left comer of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 127 of 147 Survey Unit HL-4-4 Hot Dry Storage Beam LI sm-aI 7m-.jIJ .. =1 I o 00i 00 0C 0 mm(3 SM 111 SM SM I=E W LS-M.

F--.---l 'E=`

I ýj HR-4-4 AREA: Hot Dry Storage Beam Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpm/Il00-cm 2 Type Notes 1.1 0.1 SM-1 130 Systematic N/A 0.6 0.1 SM-2 -185 Systematic N/A 0.2 0.3 SM-3 -151 Systematic N/A 0.4 0.2 SM-4 260 Systematic N/A 0.5 0.3 SM-5 -14 Systematic N/A 0.3 0.5 SM-6 89 Systematic N/A 1.7 0.3 SM-7 -171 Systematic N/A 4.6 0.3 SM-8 171 Systematic N/A 1.1 0.5 SM-9 48 Systematic N/A 3.9 0.5 SM-10 171 Systematic N/A 6.8 0.5 SM-I1 -27 Systematic N/A

  • Sample measurements are from the lower left comer of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 128 of 147 Survey Unit HL-4-5 Hot Dry Storage West Floor

= - M IsmjIC ISM41i Outside - Loft/Top Outside - Right/Bottom Inside Surfaces HL-4-5 AREA: Hot Dry Storage Floor Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpm/100-cm 2 Type Notes 1.8 0.0. SM-1 8650 Systematic N/A 0.5 2.2 SM-2 2230 Systematic N/A 3.1 2.2 SM-3 1110 Systematic N/A 1.8 4.4 SM-4 764 Systematic N/A 0.5 6.6 SM-5 992 Systematic N/A 3.1 6.6 SM-6 683 Systematic N/A 1.80 8.8 SM-7 984 Systematic N/A 0.05 0.1 SM-8 1040 Systematic N/A 0.05 0.1 SM-9 691 Systematic N/A 0.2 0.05 SM-10 992 Systematic N/A 0.4 0.05 SM-11 2460 Systematic N/A

  • Sample measurements SM-1 through SM-7 are taken from the southwest comer of the floor. SM-8 through SM- 11are measured from the lower left comer of the surface on which they rest

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 129 of 147 Survey Unit HL-4-6 Hot Dry Storage East Floor WlW End End HL-4-6 AREA: Hot Dry Storage Floor (east side)

Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpm/l 00-cm2 Type Notes 4.3 0.3 SM- 1 341 Systematic N/A 6.5 0.3 SM-2 886 Systematic N/A 5.4 2.2 SM-3 1350 Systematic N/A 7.5 2.2 SM-4 1040 Systematic N/A 4.3 4.1 SM-5 1700 Systematic N/A 6.5 4.1 SM-6 943 Systematic N/A 5.4 5.9 SM-7 919 Systematic N/A 7.5 5.9 SM-8 894 Systematic N/A 4.3 7.8 SM-9 1050 Systematic N/A 6.5 7.8 SM-10 724 Systematic N/A 5.4 9.7 SM-11 585 Systematic N/A 7.5 9.7 SM-12 1250 Systematic N/A

  • Sample measurements are taken from the southwest comer of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 130 of 147 Survey Unit HL-4-7 Hot Dry Storage North Wall and Observation Window HL-4-7 AREA: Hot Dry Storage - North Wall and Observation Window Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpm/l 00-cm 2 Type Notes 2.7 1.1 SM-i 425 Systematic N/A 5.8 1.1 SM-2 616 Systematic N/A 1.1 3.8 SM-3 473 Systematic N/A 4.3 3.8 SM-4 404 Systematic N/A 7.4 3.8 SM-5 596 Systematic N/A 2.7 6.6 SM-6 781 Systematic N/A 5.8 6.6 SM-7 877 Systematic N/A 1.27 0.52 SM-8 884 Systematic N/A

-1.68 1.31 SM-9 1010 Systematic N/A 0.22 1.31 SM-10 555 Systematic N/A 1.59 0.28 SM-I 1 671 Systematic N/A

  • Sample measurements SM-I through SM-7 are from the lower left comer of the surface on which they rest.

Measure remaining points from areas identified on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 131 of 147 Survey Unit HL-4-8 Hot Dry Storage West Wall I I

  • Eil HL-4-8 AREA: Hot Dry Storage West Wall Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpm/100-cm2 Type Notes 0.3 1.5 SM-I 342 Systematic N/A 3.5 1.5 SM-2 500 Systematic N/A 6.6 1.5 SM-3 0 Systematic N/A 9.7 1.5 SM-4 349 Systematic N/A 1.9 4.2 SM-5 747 Systematic N/A 5.0 4.2 SM-6 411 Systematic N/A 8.2 4.2 SM-7 719 Systematic N/A 0.3 6.9 SM-8 753 Systematic N/A 3.5 6.9 SM-9 329 Systematic N/A 6.6 6.9 SM-10 589 Systematic N/A 9.7 6.9 SM-i1 671 Systematic N/A

  • Sample measurements are from the lower left comer of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 132 of 147 Survey Unit HL-4-9 Hot Dry Storage East Wall (below beam)

SM-S SM*

tblg Measure SM-I I from this point. SM-I [ Measure SM- 10 from this point.

HL-4-9 AREA: Hot Dry Storage - East Wall (below beam)

Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpm/lOO-cm2 Type Notes 1.4 2.0 SM-1 719 Systematic N/A 4.6 2.0 SM-2 568 Systematic N/A 7.8 2.0 SM-3 151 Systematic N/A 3.0 4.7 SM-4 445 Systematic N/A 6.2 4.7 SM-5 651 Systematic N/A 9.4 4.7 SM-6 568 Systematic N/A 1.4 7.5 SM-7 692 Systematic N/A 4.6 7.5 SM-8 1050 Systematic N/A 7.8 7.5 SM-9 616 Systematic N/A 1.0 0.5 SM- 10 466 Systematic N/A 3.9 0.6 SM-11 336 Systematic N/A

  • Sample measurements SM-1 through SM-9 are from the lower left comer of the surface on which they rest. Measure remaining points, SM-10 and SM-11, from areas identified on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 133 of 147 Survey Unit HL-4-10 Hot Dry Storage - South Wall and East Wall above beam Measure SM-10 from this point Measure SM-i I from this point SMbSM-Il*

SMc- SM SM SM-HL-4-10 AREA: Hot Dry Storage - South Wall and East Wall above beam Measurement Locations and results Location /

X Co-ord (m) Y Co-ord (m) dpm/1 00-cm 2 Type Notes 1.6 2.0 SM-1 240 Systematic N/A 4.6 2.0 SM-2 651 Systematic N/A 7.6 2.0 SM-3 342 Systematic N/A 0.1 4.6 SM-4 432 Systematic N/A 3.1 4.6 SM-5 1660 Systematic N/A 6.1 4.6 SM-6 356 Systematic N/A 1.6 7.2 SM-7 534 Systematic N/A 4.6 7.2 SM-8 281 Systematic N/A 7.6 7.2 SM-9 281 Systematic N/A 1.8 0.1 SM-10 815 Systematic N/A 2.3 0.1 SM-11 856 Systematic N/A

  • Sample measurements SM-1 through SM-9are from the lower left comer of the surface on which they rest. Measure remaining points from the areas identified on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 134 of 147 Survey Unit HL-4-11 Interim Storage Floor and Valve Pit l

I 4 SM- S-2SM-3 SM4 SM-5 HL-4-11 AREA: Interim Storage Floor And Valve Pit Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpm1O00-cm 2 Type Notes 1.0 0.1 SM-1 1220 Systematic N/A 2.6 0.1 SM-2 918 Systematic N/A 0.1 0.1 SM-3 905 Systematic N/A 1.7 0.1 SM-4 1480 Systematic N/A 0.3 0.1 SM-5 1210 Systematic N/A 0.8 1.0 SM-6 7620 Systematic N/A 2.4 1.0 SM-7 2610 Systematic N/A 1.6 2.4 SM-8 2690 Systematic N/A 3.2 2.4 SM-9 1270 Systematic N/A 0.8 3.7 SM-10 1260 Systematic N/A 2.4 3.7 SM-11 2840 Systematic N/A

  • Sample measurements SM-6 through SM-Il are taken from the southwest comer of the floor. SM-I through SM-5 are measured from the lower left comer of the surface which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 135 of 147 Survey Unit HL-4-12 Interim Storage East and West Walls

  • M ,ii
  • M HL-4-12 AREA: Interim Storage - East and West Walls Measurement Locations and results Location /

2 X Co-ord (m) Y Co-ord (m) dpm/100-cm Type Notes 1.4 0.9 SM-1 633 Systematic N/A 3.8 0.9 SM-2 715 Systematic N/A 0.2 3.0 SM-3 861 Systematic N/A 2.6 3.0 SM-4 671 Systematic N/A 1.4 5.2 SM-5 430 Systematic N/A 3.8 5.2 SM-6 405 Systematic N/A 1.1 1.3 SM-7 608 Systematic N/A 3.4 1.3 SM-8 671 Systematic N/A 2.2 3.5 SM-9 1032 Systematic N/A 1.0 5.5 SM-10 684 Systematic N/A 3.5 5.5 SM-11 747 Systematic N/A

  • Sample measurements are from the lower left comer of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 136 of 147 Survey Unit HL-4-13 Interim Storage North and South Walls and Ceiling/Opening I SM Sf I I I I I "I

  • M4 SM-3

-IM_-1SMI , from this SM-Measure point11 SM4 SM-I Sfm-4 HL-4-13 AREA: Interim Storage - North and South Walls and CeilinglOpening Measurement Locations and results Location I X Co-ord (m) Y Co-ord (m) dpml 00-cm 2 Type Notes 0.6 2.3 SM-1 392 Systematic N/A 3.2 2.3 SM-2 386 Systematic N/A 1.9 4.6 SM-3 506 Systematic N/A 0.9 0.6 SM-4 709 Systematic N/A 2.3 3.0 SM-5 582 Systematic N/A 0.9 5.3 SM-6 468 Systematic N/A 2.3 0.2 SM-7 1420 Systematic N/A 1.9 0.2 SM-8 2110 Systematic N/A 1.5 0.2 SM-9 4850 Systematic N/A 1.2 0.2 SM-10 323 Systematic N/A 1.7 0.1 SM- 11 778 Systematic N/A

  • Sample measurements are from the lower left comer of the surface on which they rest, except SM-1I which is measured from the point shown on the map.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 137 of 147 Survey Unit HL-4-14 Canal K Floor

  • Mr *MI7 OM-S SM SM-I SM II SM- SM- SM- SM3 SM HL-4-14 AREA: Canal K Floor Measurement Locations and results X Co-ord Y Co-ord dpmllO0-(m) (M) Location cm2 Type Notes 1.7 0.6 SM-1 543 Systematic N/A 4.3 0.6 SM-2 630 Systematic N/A 6.8 0.6 SM-3 488 Systematic N/A 9.5 0.6 SM-4 543 Systematic N/A 12.0 0.6 SM-5 753 Systematic N/A 0.5 2.7 SM-6 401 Systematic N/A 3.0 2.7 SM-7 253 Systematic N/A 5.7 2.7 SM-8 389 Systematic N/A 8.1 2.7 SM-9 753 Systematic N/A 10.7 2.7 SM-10 642 Systematic N/A 13.3 2.7 SM-11 556 Systematic N/A Sample measurements are from the southwest corner of the survey unit.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 138 of 147 Survey Unit HL-4-15 Canal K North Wall and Ceiling K7I=

S

  • M. NOM SM.

HL-4-15 AREA: Canal K North Wall and Ceiling Measurement Locations and results X Co-ord Y Co-ord dpm/100-(m) (m) Location cm2 Type Notes 0.9 0.5 SM-1 1138 Systematic N/A 4.5 0.5 SM-2 1040 Systematic N/A 8.2 0.5 SM-3 1100 Systematic N/A 2.7 3.7 SM-4 710 Systematic N/A 6.3 3.7 SM-5 478 Systematic N/A 9.8 3.7 SM-6 841 Systematic N/A 4.5 6.8 SM-7 630 Systematic N/A 8.2 6.8 SM-8 471 Systematic N/A 2.8 1.7 SM-9 493 Systematic N/A 6.4 0.9 SM-10 551 Systematic N/A 10.0 0.9 SM-11 435 Systematic N/A Sample measurements are from the lower left comer of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 139 of 147 Survey Unit HL-4-16 Canal K East Wall and E Section of South Wall EJ Cf n

-f

  • Im 9*a SMi11 SM-5 4 1M-6 *SIsm HL-4-16 AREA: Canal K East Wall and E Section of South Wall Measurement Locations and results X Co-ord Y Co-ord dpm/100-(m) (m) Location cm2 Type Notes 0.7 0.5 SM-1 891 Systematic N/A 3.7 0.5 SM-2 761 Systematic N/A 2.2 0.5 SM-3 848 Systematic N/A 5.1 0.5 SM-4 899 Systematic N/A 2.3 3.0 SM-5 442 Systematic N/A 0.7 3.0 SM-6 514 Systematic N/A 3.7 3.0 SM-7 862 Systematic N/A 0.7 5.6 SM-8 486 Systematic N/A 3.7 5.6 SM-9 594 Systematic N/A 2.2 5.6 SM-10 630 Systematic N/A 5.1 5.6 SM-11 630 Systematic N/A Sample measurements are from the lower left comer of the surface on which they rest.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 140 of 147 Survey Unit HL-4-17 Canal KWest Wall and W Section of South Wall 4Mi 45 SM4 SM SM4 SM SM4

  • =04 SM- *M-
  • SM 4 HL-4-17 AREA: Canal K West Wall and W Section of South Wall Measurement Locations and results X Co-ord Y Co-ord dpm/l00-Lm) (m) Location cm2 Type Notes 3.1 1.5 SM-1 643 Systematic N/A 6.2 1.5 SM-2 752 Systematic N/A 1.3 1.5 SM-3 949 Systematic N/A 4.5 1.5 SM-4 554 Systematic N/A 1.4 4.3 SM-5 885 Systematic N/A 4.4 4.3 SM-6 484 Systematic N/A 7.8 4.3 SM-7 1025 Systematic N/A 2.9 4.3 SM-8 573 Systematic N/A 3.1 7 SM-9 669 Systematic N/A 6.2 7 SM-10 904 Systematic N/A 1.3 7 SM-11 611 Systematic N/A Sample measurements are taken from the lower left corner of the surface which they lay.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 141 of 147 Survey Unit HL-4-18 Canal J Floor

  • M- SFM-I 0

S*M SM rM Om SM SM*

HL-4-18 AREA: Hot Laboratory, Canal J Floor Measurement Locations and results X Co-ord Y Co-ord dpmll00-(m) (m) Location cm2 Type Notes 0.8 0.5 SM-1 1470 Systematic N/A 3.0 0.5 SM-2 1290 Systematic N/A 1.9 2.4 SM-3 694 Systematic N/A 0.8 4.3 SM-4 459 Systematic N/A 3.0 4.3 SM-5 834 Systematic N/A 1.9 6.2 SM-6 650 Systematic N/A 0.8 8.1 SM-7 662 Systematic N/A 3.0 8.1 SM-8 637 Systematic N/A 1.9 10.0 SM-9 522 Systematic N/A 0.8 12.0 SM-10 904 Systematic N/A 3.0 12.0 SM-11 815 Systematic N/A Sample measurements are taken from the southwest corner of the survey unit.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 142 of 147 Survey Unit HL-4-19 Canal J West Wall, North Section 190.

  • MR
  • M *w HL-4-19 AREA: Hot Laboratory, Canal J West Wall, North Section Measurement Locations and results X Co-ord Y Co-ord dpmll00-(m) (m) Location cm2 Type Notes 0.8 2.3 SM-1 527 Systematic N/A 3.6 2.3 SM-2 467 Systematic N/A 6.3 2.3 SM-3 773 Systematic N/A 9.1 2.3 SM-4 1050 Systematic N/A 2.2 4.7 SM-5 420 Systematic N/A 5.0 4.7 SM-6 647 Systematic N/A 7.7 4.7 SM-7 647 Systematic N/A 0.8 7.1 SM-8 560 Systematic N/A 3.6 7.1 _ SM-9 953 Systematic N/A 6.3 7.1 SM-10 620 Systematic N/A 9.1 7.1 SM-11 840 Systematic N/A Sample measurements are taken from the lower left corner of the survey unit.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 143 of 147 Survey Unit HL-4-20 Canal J East Wall, North Section 1 11 Lii

___ SM.1o

,ii~ I5M~

l~i~ SM SM-SM-I .1 L HL-4-20 AREA: Hot Laboratory, Canal J East Wall, North Section Measurement Locations and results X Co-ord Y Co-ord dpml100-Lm) (m) Location cm2 Type Notes 0.1 1.9 SM-1 573 Systematic N/A 2.9 1.9 SM-2 540 Systematic N/A 5.6 1.9 SM-3 487 Systematic N/A 8.4 1.9 SM-4 373 Systematic N/A 1.5 4.2 SM-5 980 Systematic N/A 4.3 4.2 SM-6 613 Systematic N/A 7.0 4.2 SM-7 940 Systematic N/A 0.1 6.6 SM-8 1050 Systematic N/A 2.9 6.6 SM-9 753 Systematic N/A 5.6 6.6 SM-1 0 387 Systematic N/A 8.4 6.6 SM-1 1 627 Systematic N/A Sample measurements are taken from the lower left comer of the survey unit.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 144 of 147 Survey Unit HL-4-21 Canal J E & W Walls - South Section

  • M 4 ~ i~

4ý0 SM SM SM-SM-I HL-4-21 AREA: Canal J - E & W Walls - South Section Measurement Locations and results X Co-ord Y Co-ord dpmll 00-(m) (m) Location cm2 Type Notes 0.1 0.4 SM-1 547 Systematic N/A 0.2 2.8 SM-2 80 Systematic N/A 0.1 5.2 SM-3 833 Systematic N/A 0.2 Edge SM-4 -27 Systematic N/A 0.3 2.0 SM-5 533 Systematic N/A 1.6 2.0 SM-6 633 Systematic N/A 1.7 4.4 SM-7 1260 Systematic N/A 0.2 4.4 SM-8 240 Systematic N/A 1.7 Edge SM-9 1110 Systematic N/A 0.3 2.4 SM-10 927 Systematic N/A 1.2 2.4 SM-11 347 Systematic N/A Sample measurements are taken from the lower left corner of the surface which they lie.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 145 of 147 Survey Unit HL-5-1 Hot Lab Exterior - High Roof HL-5-1 AREA: Hot Lab Exterior - High Roof Measurement Locations and results X Co-ord Y Co-ord dpm/100-Jm)(L Location cm 2 Type Notes Edge 6.8 SM-I 608 Systematic N/A 8.9 6.8 SM-2 554 Systematic N/A 4.5 14.5 SM-3 277 Systematic N/A Edge 22.2 SM-4 736 Systematic N/A 8.9 22.2 SM-5 784 Systematic N/A 4.5 29.8 SM-6 169 Systematic N/A 13.3 29.8 SM-7 176 Systematic N/A 22.2 29.8 SM-8 392 Systematic N/A Edge 37.5 SM-9 392 Systematic N/A 8.9 37.5 SM-10 784 Systematic N/A 17.8 37.5 SM-11 345 Systematic N/A Sample measurements are taken from the southwest comer of the surface which they lie.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 146 of 147 Survey Unit HL-5-2 Hot Lab Exterior - Low Roof HL-5-2 AREA: Hot Lab Exterior - Low Roof Measurement Locations and results X Co-ord Y Co-ord dpm/100-(m) (m) Location cm2 Type Notes 4.5 0.6 SM-1 730 Systematic N/A 12.5 0.6 SM-2 419 Systematic N/A 2.5 7.5 SM-3 507 Systematic N/A 0.5 7.5 SM-4 95 Systematic N/A 8.5 7.5 SM-5 81 Systematic N/A 4.5 14.4 SM-6 68 Systematic N/A 12.5 14.4 SM-7 534 Systematic N/A 2.5 21.3 SM-8 568 Systematic N/A 0.5 21.3 SM-9 419 Systematic N/A 8.5 21.3 SM-10 -115 Systematic N/A 2.5 35.1 SM-11 797 Systematic N/A Sample measurements are taken from the southwest comer of the surface which they lie.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix B, Rev.0, Page 147 of 147 Survey Unit HL-5-3 Hot Lab Exterior Walls HL-5-3 AREA: Hot Lab Exterior - Walls Measurement Locations and results X Co-ord Y Co-ord dpm/100-(m) (m) Location cm2 Type Notes 9.8 2.6 SM-1 1030 Systematic N/A 41.1 3.4 SM-2 780 Systematic N/A 25.7 2.1 SM-3 598 Systematic N/A 23.8 4.5 SM-4 917 Systematic N/A 19.0 1.0 SM-5 833 Systematic N/A 6.8 3.0 SM-6 333 Systematic N/A 29.6 4.5 SM-7 773 Systematic N/A 18.5 0.5 SM-8 644 Systematic N/A 10.7 9.4 SM-9 621 Systematic N/A 34.9 5.3 SM-10 833 Systematic N/A 2.7 0.6 SM-11 -98 Systematic N/A Sample measurements are taken from the southwest corner of the surface which they lie.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix C, Rev. 0, Page 1 of 4 Final Status Survey Report Attachment 8 Hot Laboratory (Building 1112)

Revision 0 Appendix C QC Measurements

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix C, Rev. 0, Page 2 of 4 Measurement Net Activity (1)(2) QC Replicate 2(2) RPD (%)

Survey Unit ID (dpm/1 00-cm 2) (dpm/1 00-cm ) (3)

HL-1-59 SM-6 -316 -36 159.1 HL-1-58 SM-4 -264 -22 169.2 HL-1-24 SM-5 -188 -183 2.7 HL-5-2 SM-10 -115 427 347.4 HL-1-24 SM-4 -70 -159 77.7 HL-1-83 SM-2 7 56 155.6 HL-1-55 SM-i 122 -1 203.3 HL-1-50 SM-5 197 22 159.8 HL-1-50 SM-2 248 144 53.1 HL-1-27 SM-8 262 213 20.6 HL-1-27 SM-10 274 260 5.2 HL-5-1 SM-3 277 -238 2641.0 HL-1-22 SM-1 406 174 80.0 HL-1-16 SM-1 407 188 73.6 HL-4-19 SM-2 467 825 55.4 HL-4-3 SM-1 494 579 15.8 HL-1-42 SM-3 497 591 17.3 HL-1-42 SM-4 531 832 44.2 HL-1-88 SM-6 547 636 15.0 HL-1-42 SM-I 580 781 29.5 HL-1-83 SM-11 595 671 12.0 HL-4-12 SM-7 608 1050 53.3 HL-1-59 SM-9 610 691 12.5 HL-5-3 SM-8 644 399 47.0 HL-4-18 SM-6 650 985 41.0 HL-1-63 SM-2 653 92 150.6 HL-4-18 SM-3 694 723 4.1 HL-1-35 SM-5 697 1010 36.7 HL-1-47 SM-4 730 570 24.6 HL-1-76 SM-1 783 526 39.3 HL-1-33 SM-7 789 103 153.8 HL-1-7 SM-5 797 738 7.7 HL-1-35 SM-4 845 711 17.2 HL-1-6 SM-3 854 826 3.3 HL-1-76 SM-3 860 701 20.4 HL-1-31 SM-1 871 611 35.1 HL-4-7 SM-7 877 772 12.7 HL-4-2 SM-11 899 951 5.6 HL-1-18 SM-2 929 1140 20.4 HL-1-21 SM-3 935 779 18.2

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix C, Rev. 0, Page 3 of 4 Measurement Net Activity 1)(2) 2 QC Replicate 2(2) RPD (%)

Survey Unit ID (dpm/100-cm ) (dpm!100-cm ) (3)

HL-3-16 SM-8 957 884 7.9 HL-4-1 SM-3 968 384 86.4 HL-1-11 SM-2 993 960 3.4 HL-1-3 SM- 1i 1000 497 67.2 HL-1-47 SM-3 1000 901 10.4 HL-1-47 SM-5 1010 880 13.8 HL-1-88 SM-11 1010 462 74.5 HL-1-6 SM-1 1020 1210 17.0 HL-4-9 SM-8 1050 798 27.3 HL-1-7 SM-9 1060 839 23.3 HL-I-12 SM-9 1060 1200 12.4 HL-1-21 SM-6 1130 785 36.0 HL-2-2 SM-1 1150 961 17.9 HL-3-16 SM-6 1190 890 28.8 HL-1-77 SM-4 1200 1180 1.7 HL-3-10 SM-7 1322 1830 32.2 HL-3-10 SM-6 1340 1320 1.5 HL-3-4 SM-10 1430 604 81.2 HL-1-16 SM-2 1580 1720 8.5 HL-4-6 SM-5 1700 1270 29.0 HL-1-88 SM-1 1730 2180 23.0 HL-1-64 SM-5 1740 1550 11.6 HL-1-88 SM-4 2100 1830 13.7 HL-I-15 SM-2 2360 1470 46.5 HL-1-68 IM-3 2440 4370 56.7 HL-1-54 IM-3 3400 4040 17.2 HL-1-59 IM-i 3865 4640 18.2 HL-2-4 IM-1 4280 3870 10.1 HL-1-43 IM-1 4340 6370 37.9 HL-3-5 SM-6 4360 4680 7.1 HL-1-34 IM-1 4490 4780 6.3 HL-4-4 IM-1 5400 5720 5.8 HL-1-42 IM-1 6080 6260 2.9 HL-3-19 IM-1 6150 6430 4.5 HL-1-62 IM-1 7230 8290 13.7 HL-3-6 IM-1 7922 7280 8.4 HL-3-11 SM-1 7980 6930 14.1 HL-1-54 IM-1 9440 10300 8.7 HL-4-8 IM-I 9890 8310 17.4 HL-1-68 IM-1 9900 10700 7.8 HL-3-6 IM-1 10300 10500 1.9

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix C, Rev. 0, Page 4 of 4 Measurement Net Activity (1)(2) QC Replicate (2) RPD (%)

Survey Unt ID (dpm/100-cm 2) (dpm/1 00-cm 2) (3)

HL-3-21 IM-3 10400 9490 9.2 HL-3-19 IM-3 10600 9360 12.4 HL-1-29 IM-I 10800 11500 6.3 HL- 1-68 IM-2 11200 11200 0.0 HL-3-13 IM-I 11300 11700 3.5 HL-3-19 IM-2 12200 11500 5.9 HL-1-70 IM-i 12600 11900 5.7 HL-1-70 IM-i 12900 10500 20.5 HL-1-68 IM-5 14300 14400 0.7 HL-1-61 IM-1 14400 13500 6.5 HL-4-14 IM-2 15239 18557 19.6 HL-1-51 IM-1 15300 15300 0.0 HL-4-10 IM- 1 15400 15800 2.6 HL-4-11 IM-1 15500 17000 9.2 HL-3-5 IM-i 16400 15000 8.9 HL-1-38 IM-1 18100 16700 8.0 HL-3-5 IM-1 19600 20200 3.0 HL-1-69 IM-1 20100 19000 5.6 HL-1-72 IM-2 23000 23200 0.9 HL-1-79 IM 23169 25600 10.0 HL-1-68 IM-4 24400 31300 24.8 HL-4-5 IM-3 24600 24500 0.4 HL-1-68 IM-4 24700 31400 23.9 HL-4-13 IM-i 25800 28500 9.9 HL-4-15 IM-I 26164 24565 6.3 HL-4-14 IM-i 26560 28730 7.8 HL-4-5 IM-1 28700 22200 25.5 HL-3-21 IM-5 28900 34300 17.1 HL-1-72 IM-1 30500 30400 0.3 HL-1-86 IM-i 31804 33036 3.8 HL-3-21 IM-5 42400 32200 27.3 HL-4-5 IM-5 42500 49900 16.0 HL-4-19 IM-7 48100 49000 1.9 HL-1-88 IM-1 53847 49507 8.4 Appendix C Notes:

1. The table entries are sorted by Net Activity in increasing order.
2. Repeat replicate QC measurements performed where RPD criterion not met are not included.
3. Relative Percent Difference (RPD) is calculated as:

RPD (Original- Replicate)

(Original+ Replicate)/ 2

Plum Brook Reactor Facility Final Status Survey Report Attachment 8 Hot Laboratory Building Revision 1 Appendix D Evaluation of Revised DCGLs

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D, Rev. 1, Page 2 of 11 TABLE of CONTENTS 1.0 Introduction ............................................................................................................................ 3 2.0 R evised DC GLs .............................................................................................................. 4 3.0 Survey Design Calculations with Revised DCGLs ........................................................... 5 4.0 Instrument Sensitivities and Investigation Levels ............................................................. 6 5.0 Comparison of Investigative Measurements with Revised DCGLs ................................... 9 6.0 Evaluation of FSS Results to Ensure the Dose Criterion is met .......................................... 11 Addendum 1 - VSP Design Screens Addendum 2 - Calculation of Revised Equivalent Screening Level DCGL for ALARA Evaluation LIST of TABLES Table 1, DCGLs for the HL Structures - Comparison of Revised and Original Values ................. 4 Table 2, HL Survey Design Recalculation Summary ....................................................................... 5 Table 3, Revised DCGLEMC Values for HL Class 1 Survey Units ................................................... 6 Table 4, LMI 44-116 Detector Scan Sensitivity and Investigation Levels for Original and Revised DCGLs - Class 1 Areas ........................................................................................... ..........8 Table 5, LMI 44-9 Detector Scan Sensitivity and Investigation Levels for Original and Revised D C G L s - C lass 1 A reas ............................................... ......................................................................... 8 Table 6, LMI 44-116 Action Levels and Scan Capabilities for Hot Lab Class 2 Survey Units ..... 9 Table 7, Additional HL Investigative Static Measurements That Exceed DCGLs ................ 10 Table 8, Revised EM C and EM C Calculations ............................................................................. 10 LIST of FIGURES Figure 1, VSP Screen for Design 24A, Survey Unit HL-3-1 .......................................................... Al-i Figure 2, VSP Screen for Design 24A, Survey Unit HL-3-1, Revised ..................................... A1-2 Figure 3, VSP Design Screen for Design 25 Survey Unit HL-1-1 ............................................ A1-3 Figure 4, VSP Design Screen for Design 25 Survey Unit HL-I-1, Revised .................................. AI-4 Figure 5, VSP Design Screen for Design 41B Survey Unit HL-1-64 ............................................ Al-5 Figure 6, VSP Design Screen for Design 41B Survey Unit HL-1-64, Revised .............................. Al-6 Figure 7, VSP Design Screen for Design 67, Survey Unit HL-5-2 ................................................ Al-7 Figure 8, VSP Design Screen for Design 67, Survey Unit HL-5-2, Revised ............................. A1-8

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D, Rev. 1, Page 3 of 11 1.0 Introduction As part of an NRC inspection at the PBRF Decommissioning Project in July 2011, radiological surveys and records review were performed by the NRC independent verification contractor, the Oak Ridge Institute for Science and Education (ORISE). The ORISE review included a review of gross beta activity DCGL values used by the PBRF to evaluate FSS measurements for compliance with the 25 mrem/y release criterion. The gross beta activity DCGL values and the radionuclide mixtures used to calculate them are published in a PBRF Technical Basis Document, PBRF-TBD-07-001 [PBRF 2007].

The ORISE report, issued in October 2011, identified an error in the gross activity DCGL used for the -15 ft. elevation (Area 20) of the Reactor Building, 35,296 dpm/100-cm 2 . The ORISE report determined that this value did not correctly account for the use of beta surface activity measurements as surrogates in areas such as the Reactor Building -15 ft. elevation where the radionuclide mixture reported in TBD-07-001 included alpha emitting U-234 [ORISE 2011].

In subsequent discussions with the NRC, it was agreed that NASA would re-evaluate the method used to calculate DCGLs, with particular attention given to areas where uranium was included in the radionuclide mixture. This evaluation would also include a review of the basis for determining that uranium was present in the radionuclide mixtures. The results of this re-evaluation, including revised radionuclide mixtures and revised gross activity DCGLs for the PBRF structures, are published in a new technical basis document, [PBRF 2012]. In what follows, effects of the revised gross activity DCGLs on the FSS of the Hot Laboratory Building (HL) are evaluated. The following topics are addressed:

" The effect of revised DCGLs on the survey design calculation of the number of measurements, "N".

" Instrument sensitivities and scan survey investigation-action levels relative to the revised DCGLs.

  • Evaluation of FSS systematic measurement results against the revised DCGLs to ensure that the Hot Lab survey units satisfy the 25 mrem/y criterion.
  • Investigative static measurements are reviewed to determine if Elevated Measurement Comparison (EMC) and Elevated Measurement Test (EMT) results are changed as a result of reduced DCGLs.

The next section, Section 2.0, contains a summary of the revised gross activity DCGLs. In Section 3.0, an evaluation to determine if the number of systematic measurements, N, is changed as a result of the revised DCGLs is described. Section 4.0 summarizes an evaluation of instrument sensitivities and scan survey investigation levels to ensure that FSS Plan requirements for investigation levels relative to DCGLs are satisfied. In Section 5.0, the FSS systematic total surface beta measurement results are evaluated to demonstrate that the HL survey units meet the 25 mrem/y criterion, considering the revised DCGLs. Static investigative measurement results are compared to the revised DCGLs and are evaluated to determine the effect of revised-reduced DCGLs on EMC and EMT tests in Section 6.0. Addendum 1 provides the Visual Sample Plan output screens for design

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D, Rev. 1, Page 4 of 11 calculations using the revised DCGLs and Addendum 2 presents the EXCEL template used in the revised ALARA evaluation.

2.0 Revised DCGLs The revised gross beta activity DCGLs for HL structural areas are compared to the original DCGLs in Table 1. It is seen that there are only four DCGL values used in the 18 designs for HL structures and the changes due to the revised DCGLs are small in three of the four DCGL values. Only in the case of the default DCGL used in the FSS of the HL exterior is the change significant, a reduction of 14.8%. In the discussions which follow, Designs 24A, 25, 41 B and 67 will be examined to determine if the revised DCGLs affect the design calculations.

Table 1, DCGLs for the HL Structures - Comparison of Revised and Original Values Survey TBD-07-001 Table 5-3 Revised RvsdCLB %cag Design and Survey Units lDCGLB %change HL Area ( DCGLGB (dpm/1 00-cm 2) 24A (2) HL-3-1 thru HL-3-19 35,781 35,747 -0.1%

24B (2) HL-3-21 35,781 35,747 -0.1%

25 (3) HL-I-1 thru HL-1-22 38,647 38,538 -0.3%

38A (3) HL-4-2 thru HL-4-4, HI-4-7 thru HL-4-10, 38,647 38,538 -0.3%

HL-4-12 & HL-4-13 38B (3) HL-4-1, HL-4-5, H1-4-6 & HL-4-11 38,647 38,538 -0.3%

40A (3) HL-1-23 thru HL-1-28 38,647 38,538 -0.3%

40B (3) HL-1-29 thru HL-1-34 HI-2-1 thru HL-2-4 38,647 38,538 -0.3%

40C (3) HL-1-35 thru HL-1-39 38,647 38,538 -0.3%

40D (3) HL-1-74 thru HL-1-83 38,647 38,538 -0.3%

40E (3) HL-1-40 thru HL-1-48 38,647 38,538 -0.3%

40F (3) HL-1-49 thru HL-1-63 38,647 38,538 -0.3%

40G (3) HL-1-58 resurvey 38,647 38,538 -0.3%

40H (3) HL-1-86 thru HL-1-90 38,647 38,538 -0.3%

41A (4) HL-1-70 thru HL-1-73 34,404 34,583 0.5%

41B (4) HL-1-64 thru HL-1-69 34,404 34,583 0.5%

42A (3) HL-4-14 thru HL-4-17 38,647 38,538 -0.3%

42B/C (3) HL-4-18 thru HL-4-21 38,647 38,538 -0.3%

67 (5) HL-5-1 thru HL-5-3 27,166 23,146 -14.8%

Table I Notes:

1. The Hot Lab was assigned three area-specific DCGLGB values in TBD-07-001.
2. Hot Pipe Tunnel assigned in TBD-07-001.
3. Designated in TBD-07-001 as "Hot Lab, all other areas".
4. The DCGLGB assigned in TBD-07-001 to the Hot Cells.
5. The default radionuclide mixture and DCGLGB was assigned to the Hot Lab exterior in the Design process.

6.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D, Rev. 1, Page 5 of 11 3.0 Survey Design Calculations with Revised DCGLs To determine if the revised DCGLs would result in additional FSS measurements, the number of measurements was recalculated for the four selected survey designs which are representative of the four distinct Hot Lab DCGL values. The revised DCGLs were input into VSP. The principal design parameters and the VSP input parameter values are shown in Table 2. The table lists the original design parameters for Designs 24A, 25, 41B, and 67. The table rows immediately below the original design parameters show the design parameters associated with the revised DCGLs. Comparing the original and revised design parameter values, it is seen that the LBGR/DCGL ratio is preserved as is the value of a, except where a was assumed to be a fixed percentage of the DCGLw (20%). The LBGR values did change somewhat, because of the change in DCGL values, but the FSS Plan guidance to maintain the relative shift (A/a) between one and three was accomplished in all the design calculations. Figures 1 through 8 in Addendum 1 are images of the VSP design output screens for the original and re-calculations of N for the four designs. They show the values of a, the Type I error probability, P3,the Type II error probability (these are unchanged), A, the DCGL and a, the estimated standard deviation. Table 2 shows that the calculated numbers of measurements, N, for all the designs are unchanged.

Table 2, HL Survey Design Recalculation Summary Design No. DCGLw LBGR LBGR ( A2)

(% change)

(i)

Area (2) (2) DCGLw A (2) (2) 34,350 32,976 0.96 1,374 763 1.80 12 24A(0.1%) Hot Pipe Tunnel Hot Pipe Tunnel, (3)

(0.1%) Revised (3) 34,317 32,944 0.96 1,373 763 1.80 12 HL, All other Areas (4) 34,782 32,502 0.93 2,280 760 3.0 11 25

(-0.3%) HL, All other Areas, 760 2.99 11 Revised (4) 34,684 32,411 0.93 2,274 41B Hot Cells (5) 30,964 27,864 0.90 3,100 1,297 2.39 11 (0.5%) Hot Cells, Revised (5) 31,125 28,012 0.90 3,112 1,297 2.40 11 HL exterior surfaces, 0.5 12,225 4,890 2.50 11 67 default value (6) 24,449 12,224

(- 14.8%) HL exterior surfaces, default value, Revised 20,831 10,415 0.5 10,416 4,166 (7) 2.50 11 (6)

Table 2 Notes:

1. The percent change between the revised and the original DCGLGB values.
2. Units are dpm/1 00-cm 2.
3. The DCGLw value for the HPT (Design 24A) was obtained by adjusting the DCGLGB published in TBD-07-001, 35,781 dpm/100-cm 2, by a factor of 24/25 to account for the dose contribution from embedded piping (1.0 mrem). In Design 24A, the DCGLGB was not adjusted to account for the dose contribution from insignificant radionuclides. The revised DCGLw was obtained from the revised DCGLGB inTBD-11-002 in a similar manner to maintain consistency.
4. The DCGLw value for Design 25 was obtained by adjusting the DCGLGB published in TBD-07-00 1, 38,647 dpm/100-cm 2, by a factor of 22.5/25 to account for the 2.5 mrem/y dose contribution from insignificant radionuclides. The revised DCGLGB in TBD- 11-002, 38,538 dpm/100-cm 2 , was adjusted in a similar manner to obtain the revised DCGLw. No adjustment was made for embedded piping.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D, Rev. 1, Page 6 of 11

5. The DCGLw value for the Hot Cells (Design 41 B) was obtained from the DCGLGB in TBD-07 -001, 34,404 dpm/100-cm 2, by adjusting by a factor of 22.5/25 to account for the 2.5 mrem/y dose contribution from insignificant radionuclides. The revised DCGLw was obtained from the revised DCGLGB in TBD-11-002, 34,583 dpm/100-cm 2, in similar fashion. No adjustment for EP was made in either the original or revised design calculations.
6. The DCGLw value for the HL exterior surfaces (Design 67) was obtained from the default DCGLGB in TBD-07-001, 27,166 dpm/100-cm 2, by adjusting by a factor of 22.5/25 to account for the 2.5 mrem/y dose contribution from insignificant radionuclides. The revised DCGLw was obtained from the revised default DCGLGB in TBD- 11-002, 23,146 dpm/100-cm 2, in similar fashion. No adjustment for EP was made in either the original or revised design calculations.
7. The standard deviation for the revised Design 67 calculation is changed to maintain the original assumption that a = 20% of the DCGL.

4.0 Instrument Sensitivities and Investigation Levels Sensitivities of instruments used in the FSS of the HL are reviewed to ensure that they were sufficient to meet FSS Plan requirements in view of the revised DCGLs. As described in Section 4.1 of the main body of this report, the FSS Plan requirement for Class 1 survey units is that when an observed scan count rate is greater than a value equivalent to the DCGLEMC, an investigation is required. For Class 2 and 3 survey units, an investigation is required whenever a scan count rate is observed that is greater than a value equivalent to the DCGLw. Alternatively, if the scan MDC is greater than the DCGLw, an observed scan count rate greater than the scan MDC requires an investigation.

In the original survey designs and instructions for Class 1 survey units, scan investigation levels were set below the DCGL. This provided a conservative margin below the requirement that the investigation level be set at the DCGLEMC. The investigation levels used in the FSS of the HL are compared to DCGLEMC values associated with the revised DCGLs to determine if the FSS Plan requirement is satisfied in retrospect. Table 3 lists the revised DCGLEMC values for the representative HL designs where the revised DCGLws are decreased from the original values.

Table 3, Revised DCGLEMC Values for HL Class 1 Survey Units Revised Area of Area Revised Design No. AEMC DCGLEMC

(% change) Hot Lab Area DCGLw 2 Largest Factor (dpm/100-cm ) SU (mi) (m 00-cm 2 )

(m) (2) (dpm/10(3) 24A

(-0.1%) Hot Pipe Tunnel 34,317 99.9 9.1 2.2 75,497 25 Hot Lab, All other 34,684 98.2 8.9 2.2 76,305

(-0.3%) Areas Table 3 Notes:

1. Calculated as AEMC = 100/N where 100 m 2 is a conservative-representative value of the Class 1 HL survey unit areas.
2. The Area Factor for AEMC = 9.1 is 2.2. It is obtained by interpolation from FSS Plan Table 3-5, Building Reuse Area Factors (Structures).
3. The revised DCGLEMC is obtained as revised DCGL x 2.2.

Next, the investigation levels established in survey designs for the instrument models used in the HL FSS of Class 1 survey units are compared to the Revised DCGLEMC values for those survey designs

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D, Rev. 1, Page 7 of 11 where the revised DCGLs are decreased from those obtained from TBD-07-001. Table 4 shows the LMI model 44-116 detector information. The LMI 44-9 detector information is shown in Table 5.

The tables show that in all cases instrument scan sensitivities are sufficient to meet the investigation level requirement for Class 1 areas; the detectors are capable of detecting contamination levels at or below the DCGLEMC for the revised DCGLs.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D, Rev. 1, Page 8 of 11 Table 4, LMI 44-116 Detector Scan Sensitivity and Investigation Levels for Original and Revised DCGLs - Class 1 Areas SR Scan Scan count Scan count Scan count rate Investigation Investigation Design Scan MDC Investigation = Revised Level < Level <

No. Reactor Building Area() Original(2) Revised(2)

No._LevelDCGLw DCGLw DCGLEMC (2) Revised Revised (dpm/100-cm 2) (gcpm) (ncpm) DCGLw DCGLEMc 24A Hot Pipe Tunnel 1997 (3) 3500 (4) 4015 (5) 4011i 8825 (5) Yes Yes 25 Hot Lab, All other Areas 2587 (6) 3000 (7) 4066 (5) 4054 (5) 8919 (5) Yes Yes Table 4 Notes:

1. The scan investigation level for the 44-116 is in units of gcpm.
2. Investigation levels corresponding to DCGLs are in ncpm. Typical 44-116 background count rates are 200 to 250 cpm.
3. From Design 24A, Table 2. These values are for a background count rate = 200 cpm, detector-to-surface distance < 1/2in. & scan speed of 15.2 cm/sec.
4. From the Hot Pipe Tunnel survey requests (SR-158 thru SR-161).
5. Calculated for typical 44-116 detector efficiency (total efficiency = 0.140), scan speed = 15.2 cm/sec and background = 200 cpm.
6. From Design 25, Table 5. These values are for detector-to-surface distance < 1/2 in. & scan speed of 15.2 cm/sec.
7. From SR-125, 126, 127 survey instructions.

Table 5, LMI 44-9 Detector Scan Sensitivity and Investigation Levels for Original and Revised DCGLs - Class 1 Areas SR Scan Scan count Scan count Scan count rate Investigation Investigation Design Scan MDC Investigation r = Revised Level < Level <

No. Reactor Building Area Level 1 Original Revised DCGLw (1) DCGLw ) DCGLEMc ( Revised Revised (dpm/100-cm') (ncpm) DCGLw DCGLEMc 24A Hot Pipe Tunnel 7,287 (2) 604 (3) 295(4) 294(4) 648(4) No Yes 25 Hot Lab, All other Areas 19,699 (5) 290 (6) 298 4) 298 (4) 655 (4) Yes Yes Table 5 Notes:

1. For the 44-9, scan investigation levels and detector count rates corresponding to DCGLs are in ncpm.
2. From Design 24A, Table 2. This value is calculated for detector-to-surface distance on contact & scan speed of 4.4 cm/sec.
3. From SR-159 instructions.
4. Calculated for typical 44-9 detector efficiency (total efficiency = 0.0715), scan speed = 4.4 cm/sec and background = 105 cpm and detector-to-surface distance on contact. Note that the 44-9 calculations of scan count rates equivalent to DCGLs are sensitive to value assumed for the detector efficiency.
5. From Design 25, Table 5. These values are for detector-to-surface distance on contact and scan speed of 4.4 cm/sec.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D, Rev. 1, Page 9 of 11 To evaluate the effect of revised-reduced DCGLs on the Class 2 survey units in the FSS of the HL, the scan survey data was reviewed to determine the measurement capabilities of the detectors actually used in the surveys (there are no Class 3 survey units in the HL). Table 6 summarizes the results. It shows that in the actual surveys of the Class 2 survey units, scan sensitivities were well below the DCGL (the revised DCGLw for these survey units is 20,831 dpm/100-cm2 (with adjustment for deselected radionuclides). In these surveys, conservative scan investigation-action levels were used which corresponded to observed scan conditions; rough and fractured surfaces with detector-to-surface effective distance greater than the distance assumed under optimal conditions.

Also, in calculating the total surface activity equivalent to the investigation-action level, the detector background count rate is subtracted; in contrast with normal practice in the FSS. Table 6 shows that the total surface beta activity equivalent to the scan investigation levels established in the survey instructions is well below the revised DCGLw, 20,831 dpm/100-cm2 .

Table 6, LMI 44-116 Action Levels and Scan Capabilities for Hot Lab Class 2 Survey Units Investig. -Action Detector Detector Efficiency Total Surface Activity Survey Level used in Background Efficiency Correction Equivalent to Investig.

Unit Survey Survey (bkg, cpm) (E1) (2) Factor (EJ)(3) Level (dpm/1 00-cm 2) (4)

(AL, gcpm) (1)

HL-5-1 FSS-2167 1200 218 0.1745 0.3966 14,189 HL-5-1 FSS-2168 1200 218 0.1745 0.3966 14,189 HL-5-1 FSS-2170 1200 203 0.1800 0.3966 13,966 HL-5-1 FSS-2177 1200 184 0.1820 0.3966 14,076 HL-5-1 FSS-2178 1200 184 0.1820 0.3966 14,076 HL-5-2 FSS-2162 1200 208 0.1745 0.3966 14,334 HL-5-2 FSS-2163 1200 208 0.1745 0.3966 14,334 HL-5-2 FSS-2164 1200 226 0.1855 0.3966 13,239 HL-5-3 FSS-2161 900 276 0.1610 0.5427 7,142 HL-5-3 FSS-2165 900 226 0.1855 0.5427 6,695 HL-5-3 FSS-2171 900 264 0.1610 0.5427 7,279 Table 6 Notes:

1. Scan action levels applied by technicians to the survey.
2. These are the actual total efficiencies reported for the detectors used in the survey (Et = E, + E,; ES =

0.5 is applied to each).

3. This is an additional efficiency correction factor used to account for the reduced efficiency due to the increased effective detector-to-surface distance (44-116 detector). An E, of 0.3966 corresponds to 2.0 in. distance and an E, of 0.5427 corresponds to 1.5 in distance.

= AL - bkg

4. The Total surface beta activity equivalent to the action level is calculated as: TSA E, *0.5*Ec 5.0 Comparison of Investigative Measurements with Revised DCGLs The investigative static measurements are summarized in Table 12 of the Hot Lab FSS Report. The data in that table was reviewed against the revised DCGLs. It was found that four additional investigative static measurements exceeded the DCGL. In Table 7 below, the measurements which did not exceed the original, but exceeded the revised DCGLs are listed.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D, Rev. 1, Page 10 of I1 Table 7, Additional HL Investigative Static Measurements That Exceed DCGLs Size of Static Meas. > Meas. >

Survey Measurement Elevated Measurement Original Revised Orig. Rev.

Unit ID Area (dpm/100- DCGLw DCGLw (cm2) cm2) DCGLw DCGLw HL-1-43 IM-2 100 32,000 34,782 31,216 No Yes HL-1-57 IM-4 67 32,200 34,782 31,216 No Yes HL-1-72 IM- 1 100 30,500 30,960 28,013 No Yes HL-1-86 IM-1 100 31,804 34,782 31,216 No Yes As a result of the four additional investigative static measurements which exceed the DCGLw, these measurements are added to those for which the EMC and EMT are required. The EMC and EMT are re-calculated against the revised DCGLs. This recalculation includes the nine investigative measurements in Table 14 of the HL FSS Report plus the four measurements shown in Table 7 above. The results of these calculations are summarized in Table 8. Table 8 shows that in all cases where the DCGLw is reduced, the investigative measurements are still well below the DCGLEMC values. The table shows that the calculated EMT unity values are increased, but only slightly. The highest unity value is only 0.096. This is compared to 0.092, the highest unity fraction in the original EMC/EMT calculations. The Table 8 results show that the impacts of the revised DCGLs on the EMC and EMT are very small and do not change any conclusions from the original tests; all are still satisfactory.

Table 8, Revised EMC and EMC Calculations Size of Measured Revised Calculated Average EMT Survey Measurement DCGLEMC Activity in Sunit Mn Elevated Activity DCGLw (1) SU Unity Unit ID

________(dpm/1 Area (cm 2) I 00-cm 2) Value HL-1-40 EMA-1(2) 100 46,900 31,216 1.255E+06 6.810E+02 0.096 (3)

HL-1-40 EMA-2 (2) 100 47,700 31,216 1.255E+06 6.810E+02 0.096 (3)

HL-1-71 IM-3 100 35,800 28,013 1.126E+06 9.690E+02 0.066 HL-1-88 IM-1 100 53,847 31,216 1.255E+06 9.050E+02 0.071 HL-3-21 IM-5 4 42,400 34,317 1.380E+06 4.360E+02 0.043 HL-4-5 IM-5, IM-6 462 38,050 (4) 33,143 1.332E+06 1.872E+03 0.084 HL-4-8 IM-2 100 40,390 33,143 1.332E+06 4.920E+02 0.045 HL-4-19 EMA-1 1100 44,450 33,143 1.332E+06 8.120E+02 0.093 (3)

HL-4-19 EMA-2 1000 48,100 33,143 1.332E+06 8.120E+02 0.093 (3)

HL-1-43 IM-2 100 32,000 31,216 1.255E+06 6.760E+02 0.047 HL-1-57 IM-4 67 32,200 31,216 1.255E+06 1.470E+03 0.072 HL-1-72 IM-1 100 30,500 28,013 1.126E+06 5.230E+02 0.045 HL-1-86 IM-1 100 31,804 31,216 1.255E+06 9.290E+02 0.054 Table 8 Notes:

1. Calculated as the product of the AF and the DCGLw. Per Table 3-5 of the FSS Plan, the AF for areas up to 0.25 m2 is 40.2 [NASA 2007].

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D, Rev. 1, Page 11 of 11

2. The EMA label is used to designate an area of elevated activity where more than one investigative measurement is recorded.
3. The Unity Value includes the sum of contributions from each of the individual elevated areas in survey units where measurements exceeded the DCGL in more than one localized area.
4. The average of investigative measurements taken within an individual elevated area.

6.0 Evaluation of FSS Results to Ensure the Dose Criterion is met Results of the systematic fixed survey measurements from each survey unit are reviewed to ensure that they satisfy the 25 mrem/y criterion, considering the revised DCGLs. To this end, the results of fixed measurements and tests, reported in Table 11 of the main body of this report are examined.

This shows that the maximum individual measurement, 8,650 dpm/100-cm 2 (in survey unit HL-4-5) is well below the applicable revised DCGLw, 33,143 dpm/100-cm 2 . The maximum of the survey unit averages, 2,184 dpm/100-cm 2 (in survey unit HL-4-1 1) is also well below the applicable revised DCGLw, 33,143 dpm/100-cm2 (the same revised DCGLw as for HL-4-5).

The ALARA evaluation in Section 5.6 of the main report is also reviewed to examine the effect of revised DCGLs. Table 18 in the main report shows the screening level DCGL values and the PBRF radionuclide activity fractions used in the ALARA evaluation (Hot Pipe Tunnel mixture). Replacing the Table 18 activity fractions with the revised activity fractions developed in the TBD- 11-002 for the HPT radionuclide mixture results in a change in the screening level equivalent gross activity DCGL from 8,132 to 15,297 dpm/100-cm 2. The details of this calculation are shown in Addendum

2. This change is primarily due to the removal of U-234 and U-235 from the mixture. The average of the HL systematic total surface beta activity measurements (586 -620, with an upper 9 5 th %

confidence limit of 617 dpm/100-cm 2) is well below the revised equivalent screening level DCGL.

The conclusion that the ALARA requirement is satisfied is unchanged by the revised DCGLs.

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D Addendum 1, Rev. 1, Page A l-I of 8 Addendum I - VSP Design Screens Figure 1, VSP Screen for Design 24A, Survey Unit HL-3-1

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D Addendum 1, Rev. 1, Page A 1-2 of 8 Figure 2, VSP Screen for Design 24A, Survey Unit HL-3-1, Revised

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D Addendum 1, Rev. 1, Page A 1-3 of 8 Figure 3, VSP Design Screen for Design 25 Survey Unit HL-I-1

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D Addendum 1, Rev. 1, Page A 1-4 of 8 Figure 4, VSP Design Screen for Design 25 Survey Unit HL-1-1, Revised

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D Addendum 1, Rev. 1, Page A1-5 of 8 Figure 5, VSP Design Screen for Design 41B Survey Unit HL-1-64

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D Addendum 1, Rev. 1, Page A 1-6 of 8 Figure 6, VSP Design Screen for Design 41B Survey Unit HL-1-64, Revised

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D Addendum 1, Rev. 1, Page A 1-7 of 8 Figure 7, VSP Design Screen for Design 67, Survey Unit HL-5-2

f Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D Addendum 1, Rev. 1, Page A 1-8 of 8 Figure 8, VSP Design Screen for Design 67, Survey Unit HL-5-2, Revised

Plum Brook Reactor Facility FSSR, Attachment 8 Appendix D Addendum 2, Rev. 1, Page A2-1 of 1 Addendum 2 - Calculation of Revised Equivalent Screening Level DCGL for ALARA Evaluation The EXCEL template used to calculate screening level equivalent gross activity DCGLs for the ALARA evaluation described in Section 5.6 of the main body of this report is shown below. The individual radionuclide screening level DCGLs shown in the range B4:14 are the NRC screening level DCGLs shown in Table 18 of the main body of this report. The template uses the surrogate and gross beta activity DCGL equations from Section 3.6 of the PBRF FSS Plan. These equations are implemented in the cell formulas in the range L8:M9. Example cell formulas are shown for cells L8 and M8. The template calculates screening level equivalent DCGLs for the original and revised radionuclide mixtures.

A I B I C j D j E _ _F I G H I-I_ _I J L K M_

2 Level DCGLs (dpm/d0____

3 H-3 Co-60 Sr-90 1-129 Cs-137 Eu-154 U-234 U-235

-4 1.20E0 7.100 8.700 35.000 28,000 12.000 91 19" 5

&Treed"gSremn Actiyk Fractiam Ddectab& Lem Lemd Dem& A&*vk DcGL.~ DCGLOm Fractkm 7

H1-3 I Co-60 I Sr-90 1-129 1 Cs-137 Eu-154 1 U-234 1 U-235 8 HotPipe Tunnel Hot Pipe 1 0.006 0.006 0.0203 0.3444 0 0.624 0.0012 0.004 j0.0000 1.00 0.9900 9377 9075 4 0.02 0.346 0 0.627 0 0 1.00 0.9940 28000 15297 9 Revised 10 R Example Cell Formulas 13 Cell Formula Cmm 14 1K8 =(COOF.6+G8)/SUM(BS:I8) Detectable Acty Fraction A 15 ILS =1I/(((BI*4 FS)IA/$ 4)4f((EB/FE)$(IF4)((H/Fg)4ISI4( (FS)/i4)) Surrogae 1)CGL Cakodatian 16 IM8 =K*((FSI-B"C4)(DS/$.$4 )4(G8$G$/4)) Gnoss .. v, IXXL Ciakldatim

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