ML19164A268
| ML19164A268 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/15/2019 |
| From: | Bill Gleaves NRC/NRR/VPOB |
| To: | Southern Nuclear Operating Co |
| GLEAVES B/415-5848 | |
| Shared Package | |
| ML19164A263 | List: |
| References | |
| EPID L-2019-LLA-0069, LAR 19-005 | |
| Download: ML19164A268 (16) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 167 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO.52-025 Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Facility Combined License No. NPF-91 REMOVE INSERT 7
7 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-412 C-412 C-412a C-412a C-413 C-413 C-414 C-414 C-415 C-415 C-416 C-416 C-417 C-417 C-418 C-418 C-419 C-419 C-423 C-423 C-424 C-424 C-425 C-425 C-427 C-427 C-428 C-428
(7) Reporting Requirements (a)
Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).
(b)
SNC shall report any violation of a requirement in Section 2.D.(3),
Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.
(8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 167, are hereby incorporated into this license.
(9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).
(10) Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:
(a)
Environmental Qualification Program implemented before initial fuel load; (b)
Reactor Vessel Material Surveillance Program implemented before initial criticality; (c)
Preservice Testing Program implemented before initial fuel load; (d)
Containment Leakage Rate Testing Program implemented before initial fuel load; (e)
- 1.
The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7
Amendment No. 167
C-412 Amendment No. 167 Table 3.3-1 Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Wall or Section Description Column Lines(7)
Floor Elevation or Elevation Range(7)(8)
Concrete Thickness(2)(3)(4)(5)(9)(18)
Applicable Radiation Shielding Wall (Yes/No)
Containment Building Internal Structure(15)
Shield Wall between Reactor Vessel Cavity and RCDT Room E-W wall parallel with column line 7 (Inside face is 3'-0" north of column line 7. Width of wall section with stated thickness is defined by inside wall of reactor vessel cavity.)
From 71'-6" to 83'-0" 3'-0"(10)
Yes West Reactor Vessel Cavity Wall N-S wall parallel with column line N (Width of wall section with stated thickness is defined by inside wall of reactor vessel cavity.)
From 83'-0" to 98'-0" 7'-6"(10)
Yes North Reactor Vessel Cavity Wall E-W wall parallel with column line 7 (Width of wall section with stated thickness is defined by inside wall of reactor vessel cavity.)
From 83'-0" to 98'-0" 9'-0"(10)
Yes East Reactor Vessel Cavity Wall N-S wall parallel with column line N (Width of wall section with stated thickness is defined by inside wall of reactor vessel cavity.)
From 83'-0" to 98'-0" 7'-6"(10)
Yes West Refueling Cavity Wall N-S wall parallel with column line N From 98'-0" to 135'-3" 4'-0" Yes North Refueling Cavity Wall E-W wall parallel with column line 7 From 98'-0" to 135'-3" 4'-0" Yes East Refueling Cavity Wall N-S wall parallel with column line N From 98'-0" to 135'-3" 4'-0" Yes South Refueling Cavity Wall E-W wall parallel with column line 7 From 98'-0" to 135'-3" 4'-0" Yes South wall of west steam generator compartment Not Applicable From 103'-0" to 153'-0" 2'-6" Yes West wall of west steam generator compartment N-S wall parallel with column line N From 103'-0" to 153'-0" 2'-6" Yes North wall of west steam generator compartment Not Applicable From 103'-0" to 153'-0" 2'-6" Yes
C-412a Amendment No. 167
- 1.
The column lines and floor elevations are identified and included on Figures 3.3-1 through 3.3-13.
- 2.
These wall (and floor) thicknesses have a construction tolerance of +/- 1 inch, except as noted and for exterior walls below grade where the tolerance is +12 inches, - 1 inch. These tolerances are not applicable to the nuclear island basemat.
- 3.
For walls that are part of structural modules, the concrete thickness also includes the steel face plates. Where faceplates with a nominal thickness of 0.5 inches are used in the construction of the wall modules, the wall thicknesses in this column apply. Where faceplates thicker than the nominal 0.5 inches are used in the construction of the structural wall modules, the wall thicknesses in the area of the thicker faceplates are greater than indicated in this column by the amount of faceplate thickness increase over the nominal 0.5 inches. Overlay plates are not considered part of the faceplates, and thus are not considered in the wall thicknesses identified in this column.
- 4.
For floors with steel surface plates, the concrete thickness also includes the plate thickness.
- 5.
Where a wall (or a floor) has openings, the concrete thickness does not apply at the opening.
- 6.
The elevation ranges for the shield building items are rounded to the nearest inch.
- 7.
The Wall or Section Description, Column Line information, and Floor Elevation or Elevation Ranges are provided as reference points to define the general location. The concrete thickness of an item intersecting other walls, roofs or floors at a designated location (e.g., column line) is not intended to be measured to the stated column line, but only to the point where the intersection occurs.
- 8.
Where applicable, the upper wall portions extend to their associated roofs, which may vary in elevation, e.g., sloped roofs.
- 9.
From one wall/floor section to another, the concrete thickness transitions from one thickness to another, consistent with the configurations in Figures 3.3-1 through 3.3-14.
- 10. This wall thickness has a tolerance of 1-5/8 inch.
- 11. This wall thickness has a tolerance of +4 inches, -1 inch above grade.
- 12. The concrete thickness is the total floor thickness, including the metal decking, where applicable.
- 13. The concrete in the kitchen and restroom areas is 2 inches thinner.
- 14. The 6-foot concrete thickness includes the thickness of the containment vessel bottom head in a local area at the center of containment.
- 15. Reconciliation of construction deviations in the nuclear island structures from the thickness and tolerances specified in this table is included in the reconciliation reports, and demonstrate that the as-built structures will withstand design basis loads without loss of structural integrity or safety functions and without impacting compliance with the radiation protection licensing basis, such as GDC 19, established radiological zoning and equipment qualification in accordance with ITAAC 3.3.00.02a.i.a, 3.3.00.02a.i.b, 3.3.00.02a.i.c, or 3.3.00.02a.i.d.
- 16. Construction deviations in the annex building from the thickness and tolerances specified in this table are evaluated in the thickness report to demonstrate that the as-built structures will withstand design basis loads without loss of structural integrity or safety functions and without impacting compliance with the radiation protection licensing basis, such as GDC 19, established radiological zoning and equipment qualification in accordance with ITAAC 3.3.00.02a.ii.e.
- 17. Construction deviations in the turbine building from the thickness and tolerances specified in this table are evaluated in the thickness report to demonstrate that the as-built structures will withstand design basis loads without loss of structural integrity or safety functions in accordance with ITAAC 3.3.00.02a.ii.f.
- 18. Nonconformances from the thicknesses and tolerances specified in Table 3.3-1 (i.e. out of tolerance conditions) are addressed under the 10 CFR Part 50, Appendix B process and subsequently are screened in accordance with the 10 CFR Part 52, Appendix D, Section VIII process, to ensure that the licensing basis is adequately maintained. Construction deviations will continue to be assessed against the licensing basis requirements and will be addressed in accordance with licensee procedures and regulatory requirements and, if applicable, a license amendment will be obtained prior to implementation of the change.
C-413 Amendment No. 167 Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Wall or Section Description Column Lines(7)
Floor Elevation or Elevation Range(7)(8)
Concrete Thickness(2)(3)(4)(5)(9)(18)
Applicable Radiation Shielding Wall (Yes/No)
South wall of pressurizer compartment Not Applicable From 103'-0" to 153'-6" 2'-6" Yes West wall of pressurizer compartment N-S wall parallel with column line N From 107'-2" to 160'-0" 2'-6" Yes North wall of pressurizer compartment E-W wall parallel with column line 7 From 107'-2" to 160'-0" 2'-6" Yes East wall of pressurizer compartment N-S wall parallel with column line N From 118'-6" to 160'-0" 2'-6" Yes North-east wall of in-containment refueling water storage tank Parallel to column line N From 103'-0" to 135'-3" 2'-6" No West wall of in-containment refueling water storage tank Not applicable From 103'-0" to 135'-3" 5/8" steel plate with stiffeners No South wall of east steam generator compartment Not Applicable From 87'-6" to 153'-0" 2'-6" Yes East wall of east steam generator compartment N-S wall parallel with column line N From 94'-0" to 153'-0" 2'-6" Yes North wall of east steam generator compartment Not Applicable From 87'-6" to 153'-0" with a 158'-0" portion 2'-6" Yes Shield Building(6)(15)
Shield Building Cylinder Not Applicable From 100'-0" to 248'-6" 3'-0" (including 3/4 inch thick min.
steel plate liner on each face on portion not protected by auxiliary building)
Yes Air Inlet Not Applicable From 248'-6" to 251'-6" From 251'-6" to 254'-6" From 254'-6" to 266'-4" 3-0" (including 3/4 inch thick min.
steel plate liner on each face) 3'-0" to 4'-6" (including 1 inch thick steel plate liner on each face) 4'-6" (including 1 inch thick min. steel plate liner on each face)
Yes Yes Yes Tension Ring Not Applicable From 266'-4" to 271'-6 (at top of plate) 4'-6" (including 1-1/2 inch thick steel plate liner on each face)
Yes
C-414 Amendment No. 167 Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Wall or Section Description Column Lines(7)
Floor Elevation or Elevation Range(7)(8)
Concrete Thickness(2)(3)(4)(5)(9)(18)
Applicable Radiation Shielding Wall (Yes/No)
Conical Roof Not Applicable From 271'-6" to 293'-9" 3'-0" (including 1/2 inch thick min.
steel plate liner on bottom face, outside of PCS tank exterior wall)
Yes PCS Tank External Cylindrical Wall Not Applicable From 293'-9" to 328'-9" 2'-0" Yes PCS Tank Internal Cylindrical Wall Not Applicable From 309'-4" to 329'-0" 1'-6" Yes PCS Tank Roof Not Applicable 328'-9" (Lowest) 329'-0" (Highest) 1'-3" No Nuclear Island Basemat Below shield building From 60'-6" to containment vessel or 82'-6" 6'-0" (14) to 22'-0" (varies)
No Auxiliary Building Walls/Floors Radiologically Controlled(15)
Column Line 1 wall From I to N From 66'-6" to 100'-0" 3'-0" No Column Line 1 wall From I to 5'-7" west of K-2 From 100'-0" to 109'-3" 2'-3" Yes Column Line 1 wall From 5'-7" west of K-2 to N From 100'-0" to 109'-3" 3'-0" Yes Column Line 1 wall From I to 5'-6" east of L-2 From 109'-3" to 180'-0" 2'-3" Yes Column Line 1 wall From 5'-6" east of L-2 to N From 109'-3" to 125'-0" 3'-0" Yes Column Line 1 wall From 5'-6" east of L-2 to N From 125'-0" to 180'-0" 2'-3" Yes Column Line 2 wall From I to K-2 From 66'-6" to 135'-3" 2'-6" Yes Column Line 2 wall From K-2 to L-2 From 66'-6" to 135'-3" 5'-0" Yes Column Line 2 wall From L-2 to N From 82'-6" to 135'-3" 2'-6" Yes Column Line 2 wall From I to J-1 From 135'-3" to 153'-0" 2'-0" Yes Column Line 3 wall From J-1 to J-2 From 66'-6" to 82'-6" 2'-6" Yes Column Line 3 wall From J-1 to J-2 From 100'-0" to 135'-3" 2'-6" Yes Column Line 3 wall From J-2 to K-2 From 66'-6" to 135'-3" 2'-6" Yes Column Line 3 wall From K-2 to L-2 From 66'-6" to 92'-8 1/2" 2'-6" Yes Column Line 4 wall From I to J-1 From 66'-6" to 135'-3" 2'-6" Yes Column Line 4 wall From J-1 to J-2 From 66'-6" to 92'-6" 2'-6" Yes Column Line 4 wall From J-1 to J-2 From 107'-2" to 135'-3" 2'-6" Yes Column Line 4 wall From J-2 to K-2 From 66'-6" to 135'-3" 2'-6" Yes Column Line 4 wall From I to intersection with shield building wall From 135'-3" to 180'-0" 2'-0" Yes
C-415 Amendment No. 167 Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Wall or Section Description Column Lines(7)
Floor Elevation or Elevation Range(7)(8)
Concrete Thickness(2)(3)(4)(5)(9)(18)
Applicable Radiation Shielding Wall (Yes/No)
Column Line 5 wall From I to shield building; with opening east of J-1 (below 107'-2" floor).
From 66'-6" to 160'-6" 2'-0" Yes Wall, 17'-3" north of Column Line 7 From I to 8' east of J-1 From 66'-6" to 82'-6" 2'-0" Yes Wall, 10'-6" south of Column Line 7.3 From I to 5'-6"east of J-1 From 66'-6" to 82'-6" 2'-0" Yes Wall, 10'-6" south of Column Line 7.3 From I to just east of J From 82'-6" to 100'-0" 2'-0" Yes Column Line I wall From 1 to 4 From 66'-6" to 100'-0" 3'-0" No Column Line I wall From 4 to 16'-0" south of 5 From 66'-6" to 107'-2" 3'-0" No Column Line I wall From 16'-0" south of 5 to 5 From 66'-6" to 105'-0" 3'-0" No Column Line I wall From 5 to 7.3 From 66'-6" to 100'-0" 3'-0" No Column Line I wall From 1 to 3 From 100'-0" to roof 2'-0" Yes Column Line I wall From 3 to 4 From 100'-0" to roof 2'-0" Yes Column Line I wall From 4 to 16'-0" south of 5 From 107'-2" to roof 2'-0" No Column Line I wall From 16'-0" south of 5 to 5 From 105'-0" to roof 2'-0" No Column Line J-1 wall From 1 to 2 From 82'-6" to 100'-0" 2'-0" Yes Column Line J-1 wall From 2 to 4 From 66'-6" to 135'-3" 2'-6" Yes Column Line J-1 wall From 2 to 4 From 135'-3" to 153'-0" 2'-0" Yes Column Line J-1 wall From 4 to shield building From 66'-6" to 107'-2" 2'-0" Yes Column Line J-2 wall From 2 to 4 From 66'-6" to 135'-3" 2'-6" Yes Column Line J-2 wall From 4 to intersection with shield building wall From 66'-6" to 135'-3" 2'-0" Yes Column Line K-2 wall From 2 to 4 From 66'-6" to 135'-3" 4'-9" Yes Column Line L-2 wall From 2 to 4 From 66'-6" to 135'-3" 4'-0" Yes Column Line N wall From 1 to 2 From 66'-6" to 100'-0" 3'-0" No Column Line N wall From 1 to 12'-9" north of 1 From 100'-0" to 125'-0" 3'-9" Yes Column Line N wall From 1 to 12'-9" north of 1 From 125'-0" to 135'-3" 2'-0" Yes Column Line N wall From 12'-9" north of 1 to 2 From 100'-0" to 118'-2 1/2" 3'-0" Yes Column Line N wall From 12'-9" north of 1 to 2 From 118'-2 1/2" to 135'-3" 2'-0" Yes Column Line N wall From 2 to 4 (or to shield building)
From 66'-6" to 98'-1" 5'-6" No Column Line N wall From 2 to 4 (or to shield building)
From 98'-1" to 135'-3" 5'-6" (11)
Yes
C-416 Amendment No. 167 Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Wall or Section Description Column Lines(7)
Floor Elevation or Elevation Range(7)(8)
Concrete Thickness(2)(3)(4)(5)(9)(18)
Applicable Radiation Shielding Wall (Yes/No)
Column Line N wall From 1 to 4 (or to shield building)
From 135'-3" to 180'-0" 2'-0" Yes Labyrinth Wall between Col. Line 3 and 4 and J-1 to 5'-2" from J-2 Not Applicable From 82'-6" to 92'-6" 2'-6" Yes N-S Shield Wall (low wall) 5'-7" west of column line K-2 extending 16'-0" from column line 1 north From 100'-0" to 110'-0" 2'-6" Yes N-S Shield Wall 2'-9" east of column line L-2 extending 12'-9" from column line 1 north From 100'-0" to 109'-3" 3'-0" Yes N-S Shield Wall 2'-9" east of column line L-2 extending 12'-9" from column line 1 north From 109'-3" to 125'-0" 2'-9" Yes E-W Shield Wall 10'-0" north of column line 1 extending 13'-3" from column line N east From 100'-0" to 125'-0" 2'-9" Yes Auxiliary Area Basemat From 1-7.3 and I-N, excluding shield building From 60'-6" to 66'-6" 6'-0" No Floor From 1 to 2 and I to N 82'-6" 2'-0" Yes Floor From 2 to 4 and J-1 to J-2 82'-6" 2'-0" Yes Floor From 4 north to the shield building ending 17'-4" south of column line 5 and J-1 to J-2 82'-6" 0'-9" Yes Pipe Chase Floor From 2 north to the shield building ending 17'-4" south of column line 5 and J-1 to J-2 92'-6" 2'-0" Yes Floor From 2 to 3 and J-2 to K-2 90'-3" 3'-0" Yes Floor From 3 to 4 and J-2 to K-2 92'-6" 2'-0" Yes Floor From 4 to 7.3 and I to J-1 82'-6" 2'-0" Yes Floor From 1 to 2 and I to N 100'-0" 3'-0" Yes Floor From 2 to 4 and K-2 to L-2 92'-8 1/2" 3'-2 1/2" Yes Floor From I to J-2 and 4 to shield building and vertical wall 17'-0" south of column line 5 107'-2" 2'-0" Yes Floor From I to shield building wall and from intersecting vertical wall before column line 5 to column line 5 105'-0" 0'-9" Yes Floor From column line 1 to 10'-0" north of column line 1 and from 2'-9" east of column line L-2 to N 125'-0" 3'-0" Yes
C-417 Amendment No. 167 Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Wall or Section Description Column Lines(7)
Floor Elevation or Elevation Range(7)(8)
Concrete Thickness(2)(3)(4)(5)(9)(18)
Applicable Radiation Shielding Wall (Yes/No)
Floor From 12'-9" north of column line 1 to 2 and from 2'-9" east of column line L-2 to N 118'-2 1/2" 2'-0" Yes Floor From 3 to 4 and J-2 to K-2 117'-6" 2'-0" Yes Floor From 2 to 4 and I to J-1 153'-0" 1'-3" Yes Roof From 1 to 4 and I to N 180'-0" to 180'-9" 1'-3" Yes Floor From 4 to 16'-0" south of column line 5 and from I to intersection with shield building wall 135'-3" 0'-9" Yes Floor From 16'-0" south of column line 5 to column line 5 and from I to intersection with shield building wall 133'-0" 0'-9" Yes Auxiliary Building Walls/Floors Non-Radiologically Controlled(15)
Column Line 11 wall From I to Q From 66'-6" to 100'-0" 3'-0" No Column Line 11 wall From I to Q From 100'-0" to 117'-6" 2'-0" Yes Column Line 11 wall From I to L From 117'-6" to roof 2'-0" Yes Column Line 11 wall From L to M From 117'-6" to 135'-3" 4'-0" Yes Column Line 11 wall From M to P From 117'-6" to 135'-3" 2'-0" Yes Column Line 11 wall From P to Q From 117'-6" to 135'-3" 4'-0" Yes Column Line 11 wall From L to Q From 135'-3" to roof 2'-0" Yes Column Line 7.3 wall From I to shield building From 66'-6" to 100'-0" 3'-0" Yes Column Line 7.3 wall From I to shield building From 100'-0" to roof 2'-0" No Column Line I wall From 7.3 to 11 From 66'-6" to 100'-0" 3'-0" No Column Line I wall From 5 to 11 From 100'-0" to roof 2'-0" No Column Line J wall From 7.3 to 11 From 66'-6" to 117'-6" 2'-0" No Column Line K wall From shield building wall to 11 From 66'-6" to 135'-3" 2'-0" Yes Column Line L wall From shield building wall to 11 From 66'-6" to roof 2'-0" Yes Column Line M wall From shield building wall to 11 From 66'-6" to roof 2'-0" Yes Column Line P wall From shield building wall to 11 From 66'-6" to roof 2'-0" Yes Column Line Q wall From shield building wall to 11 From 66'-6" to 100'-0" 3'-0" No Column Line Q wall From shield building wall to 11 From 100'-0" to roof 2'-0" Yes Column Line 9.2 wall From I to J and K to L From 117'-6" to 135'-3" 2'-0" Yes
C-418 Amendment No. 167 Table 3.3-1 Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Wall or Section Description Column Lines(7)
Floor Elevation or Elevation Range(7)(8)
Concrete Thickness(2)(3)(4)(5)(9)(18)
Applicable Radiation Shielding Wall (Yes/No)
Labyrinth Wall between Column Line 7.3 and 9.2 and J to K
J to K From 117'-6" to 135'-3" 2'-0" Yes Auxiliary Area Basemat From 7.3-11 and I-Q, excluding shield building From 60'-6" to 66'-6" 6'-0" No Floor From 5 to 10'-6" south of 7.3 and I to shield building wall 100'-0" 2'-0" Yes Floor From 10'-6" south of 7.3 to 7.3 and I to shield building wall 100'-0" 3'-0" Yes Floor From K to L and shield building wall to column line 10 100'-0" 0'-9" Yes Main Control Room Floor From 9.2 to 11 and I to L 117'-6" 2'-0" Yes Floor Bounded by shield bldg, 7.3, J, 9.2 and L 117'-6" 2'-0" Yes Floor From shield building to 11 and L to Q
117'-6" 2'-0" Yes Floor From 5 to 7.3 and from I to intersection with shield building wall 135'-3" 0'-9" Yes Annex Building(16)
Column line 2 wall From E to H From 107'-2" to 135'-3" 19 3/4" Yes Column line 4 wall From E to H From 107'-2" to 162'-6" & 166'-0" 2'-0" Yes N-S Shield Wall between E and F From 2 to 4 From 107'-2" to 135'-3" 1'-0" Yes Column line 4.1 wall From E to H From 107'-2" to 135'-3" 2'-0" Yes N-S Labyrinth Wall between column line 7.8 and 9 and G to H Not Applicable From 100'-0" to 112'-0" 2'-0" Yes E-W Labyrinth Wall between column line 7.1 and 7.8 and G to H Not Applicable From 100'-0" to 112'-0" 2'-0" Yes Column Line 9 wall From E to connecting wall between G and H From 107'-2" to 117'-6" 2'-0" Yes Column Line E wall From 9 to 13 From 100'-0" to 135'-3" 2'-0" Yes Column Line 13 wall From E to I.1 From 100'-0" to 135'-3" 2'-0" Yes Column Line I.1 wall From 11.09 to 13 From 100'-0" to 135'-3" 2'-0" Yes Corridor Wall between G and H From 9 to near 13 From 100'-0" to 117'-6" 1'-6" Yes
C-419 Amendment No. 167 Table 3.3-1 (cont.)
Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building(1)
Wall or Section Description Column Lines(7)
Floor Elevation or Elevation Range(7)(8)
Concrete Thickness(2)(3)(4)(5)(9)(18)
Applicable Radiation Shielding Wall (Yes/No)
Corridor Wall between G and H From 9 to 13 From 117'-6" to 135'-3" 1'-6" Yes Column Line 9 wall From E to H From 117'-6" to 158'-0" 2'-0" Yes Floor From 2 to 4 and E to H 135'-3" 0'-8" Yes Floor From 4 to 4.1 and E to H 135'-3" 1'-0" (12)
Yes Floor From 9 to 13 and E to I.1 117'-6" 0'-8" (12)(13)
Yes Floor From 9 to 13 and E to I.1 135'-3" 0'-8" (12)
Yes Containment Filtration Rms A and B (North Wall)
Between column line E to H From 135'-3" to 158'-0" 1'-0" Yes Containment Filtration Rms A and B (East wall)
Between column line E to F From 135'-3" to 158'-0" 1'-0" Yes Containment Filtration Rm A (Floor)
Between column line E to H 135'-3" 1'-0" (12)
Yes Containment Filtration Rm B (Floor)
Between column line E to H 150'-3" 0'-8" (12)
Yes Turbine Building(17)
Wall adjacent to Column Line I.2 From Col. Line 11.05 to 11.2 From 100'-0" to 169'-0" 3'-0" No Wall along Column Line 11.2 From near I.2 to near Col. Line R From 100'-0" to 169'-0" 2'-0" No Wall adjacent to Column Line R From Col. Line 11.2 to Col. Line 11.02 From 100'-0" to 169'-0" 3'-0" No Wall along Column Line 11.02 From near Col. Line R to near Col.
Line Q From 100'-0" to 169'-0" 2'-0" No Wall along Column Line 11.05 From Col. Line K.4 to near Col. Line I.2 From 100'-0" to 169'-0" 2'-0" No
C-423 Amendment No. 167 Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No.
ITAAC No.
Design Commitment Inspections, Tests, Analyses Acceptance Criteria 759 3.3.00.01
- 1. The physical arrangement of the nuclear island structures and the annex building is as described in the Design Description of this Section 3.3 and Figures 3.3-1 through 3.3-14. The physical arrangement of the radwaste building, the turbine building, and the diesel generator building is as described in the Design Description of this Section 3.3.
An inspection of the nuclear island structures, the annex building, the radwaste building, the turbine building, and the diesel generator building will be performed.
The as-built nuclear island structures, the annex building, the radwaste building, the turbine building, and the diesel generator building conform with the physical arrangement as described in the Design Description of this Section 3.3 and Figures 3.3-1 through 3.3-14.
760 3.3.00.02a.i.a 2.a) The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category I and are designed and constructed to withstand design basis loads as specified in the Design Description, without loss of structural integrity and the safety-related functions.
3.) Walls and floors of the nuclear island structures as defined on Table 3.3-1 except for designed openings or penetrations, provide shielding during normal operations i) An inspection of the nuclear island structures will be performed. Deviations from the design due to as-built conditions will be analyzed for the design basis loads, and for radiation shielding.
i.a) A report exists which reconciles deviations during construction, including Table 3.3-1 wall and floor thicknesses, and concludes that the as-built containment internal structures, including the critical sections, conform to the approved design and will withstand the design basis loads specified in the Design Description without loss of structural integrity or the safety-related functions, and without impacting compliance with the radiation protection licensing basis.
761 3.3.00.02a.i.b 2.a) The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category I and are designed and constructed to withstand design basis loads as specified in the Design Description, without loss of structural integrity and the safety-related functions.
3.) Walls and floors of the nuclear island structures as defined on Table 3.3-1 except for designed openings or penetrations, provide shielding during normal operations.
i) An inspection of the nuclear island structures will be performed. Deviations from the design due to as-built conditions will be analyzed for the design basis loads, and for radiation shielding.
i.b) A report exists which reconciles deviations during construction, including Table 3.3-1 wall and floor thicknesses, and concludes that the as-built shield building structures, including the critical sections, conform to the approved design and will withstand the design basis loads specified in the Design Description without loss of structural integrity or the safety-related functions, and without impacting compliance with the radiation protection licensing basis.
C-424 Amendment No. 167 Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No.
ITAAC No.
Design Commitment Inspections, Tests, Analyses Acceptance Criteria 762 3.3.00.02a.i.c 2.a) The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category I and are designed and constructed to withstand design basis loads as specified in the Design Description, without loss of structural integrity and the safety-related functions.
3.) Walls and floors of the nuclear island structures as defined on Table 3.3-1 except for designed openings or penetrations, provide shielding during normal operations.
i) An inspection of the nuclear island structures will be performed. Deviations from the design due to as-built conditions will be analyzed for the design basis loads, and for radiation shielding.
i.c) A report exists which reconciles deviations during construction, including Table 3.3-1 wall and floor thicknesses, and concludes that the as-built structures in the non-radiologically controlled area of the auxiliary building, including the critical sections, conform to the approved design and will withstand the design basis loads specified in the Design Description without loss of structural integrity or the safety-related functions, and without impacting compliance with the radiation protection licensing basis.
763 3.3.00.02a.i.d 2.a) The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category I and are designed and constructed to withstand design basis loads as specified in the Design Description, without loss of structural integrity and the safety-related functions.
3.) Walls and floors of the nuclear island structures as defined on Table 3.3-1 except for designed openings or penetrations, provide shielding during normal operations.
i) An inspection of the nuclear island structures will be performed. Deviations from the design due to as-built conditions will be analyzed for the design basis loads, and for radiation shielding.
i.d) A report exists which reconciles deviations during construction, including Table 3.3-1 wall and floor thicknesses, and concludes that the as-built structures in the radiologically controlled area of the auxiliary building, including the critical sections, conform to the approved design and will withstand the design basis loads specified in the Design Description without loss of structural integrity or the safety-related functions, and without impacting compliance with the radiation protection licensing basis.
764 3.3.00.02a.ii.a Not used per Amendment No. 167 765 3.3.00.02a.ii.b Not used per Amendment No. 167
C-425 Amendment No. 167 Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No.
ITAAC No.
Design Commitment Inspections, Tests, Analyses Acceptance Criteria 766 3.3.00.02a.ii.c Not used per Amendment No. 167 767 3.3.00.02a.ii.d Not used per Amendment No. 167 768 3.3.00.02a.ii.e 2.a) The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category I and are designed and constructed to withstand design basis loads as specified in the Design Description, without loss of structural integrity and the safety-related functions.
4.a) Walls and floors of the annex building as defined on Table 3.3-1 except for designed openings or penetrations provide shielding during normal operations.
ii) An inspection of the as-built concrete thickness will be performed.
ii.e) A report exists that concludes that the as-built concrete thicknesses of the annex building sections conform with the building sections defined in Table 3.3-1, except for designed openings or penetrations, or the report documents an evaluation of thickness deviations identified during construction and demonstrates that the as-built structures will withstand the design basis loads without loss of structural integrity and without impacting compliance with the radiation protection licensing basis.
769 3.3.00.02a.ii.f 2.a) The nuclear island structures, including the critical sections listed in Table 3.3-7, are seismic Category I and are designed and constructed to withstand design basis loads as specified in the Design Description, without loss of structural integrity and the safety-related functions.
ii) An inspection of the as-built concrete thickness will be performed.
ii.f) A report exists that concludes that the as-built concrete thicknesses of the turbine building sections conform to the building sections defined in Table 3.3-1, except for designed openings or penetrations, or the report documents an evaluation of thickness deviations identified during construction and demonstrates that the as-built structures will withstand the design basis loads without loss of structural integrity.
770 3.3.00.02b 2.b) Site grade level is located relative to floor elevation 100'-0" per Table 3.3-5.
Inspection of the as-built site grade will be conducted.
Site grade is consistent with design plant grade within the dimension defined on Table 3.3-5.
771 3.3.00.02c Not used per Amendment No. 85
C-427 Amendment No. 167 Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No.
ITAAC No.
Design Commitment Inspections, Tests, Analyses Acceptance Criteria 777 3.3.00.03a Not used per Amendment No. 167 778 3.3.00.03b Not used per Amendment No. 167 779 3.3.00.03c Not used per Amendment No. 167 780 3.3.00.03d Not used per Amendment No. 167
C-428 Amendment No. 167 Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No.
ITAAC No.
Design Commitment Inspections, Tests, Analyses Acceptance Criteria 781 3.3.00.04a Not used per Amendment No. 167 782 3.3.00.04b 4.b) Walls of the waste accumulation room in the radwaste building except for designed openings or penetrations provide shielding during normal operations.
Inspection of the as-built radwaste building wall thicknesses will be performed.
A report exists and concludes that the shield walls of the waste accumulation room in the radwaste building except for designed openings or penetrations are consistent with the concrete wall thicknesses of 1'-4", and a concrete wall thickness of 1'-8" near the radwaste bunkers, or the report documents an evaluation of thickness deviations identified during construction and demonstrates there is no impact to compliance with the radiation protection licensing basis.
783 Deleted.
784 3.3.00.05a 5.a) Exterior walls and the basemat of the nuclear island have a water barrier up to site grade.
An inspection of the as-built water barrier will be performed during construction.
A report exists that confirms that a water barrier exists on the nuclear island exterior walls up to site grade.
785 3.3.00.05b 5.b) The boundaries between rooms identified in Table 3.3-2 of the auxiliary building are designed to prevent flooding of rooms that contain safety-related equipment.
An inspection of the auxiliary building rooms will be performed.
A report exists that confirms floors and walls as identified on Table 3.3-2 have provisions to prevent flooding between rooms up to the maximum flood levels for each room defined in Table 3.3-2.