ML16336A406
| ML16336A406 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/24/2016 |
| From: | Indiana Michigan Power Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16336A263 | List:
|
| References | |
| AEP-NRC-2016-42 | |
| Download: ML16336A406 (5) | |
Text
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:
2.9-2 Page:
1 of 5 (PART A)
LOADING CONDITIONS AND STRESS LIMITS: PRESSURE VESSELS LOADING CONDITIONS STRESS INTENSITY LIMITS NOTE
- 1.
Normal Conditions (a) Pm < Sm (b) Pm (or PL) + PB < 1.5Sm 1
(c) Pm (or PL) + PB + Q < 3.0Sm 2
- 2.
Upset Condition (a) Pm < Sm (b) Pm (or PL) + PB < 1.5Sm 1
(c) Pm (or PL) + PB + Q < 3.0Sm 2
- 3.
Emergency Condition (a) Pm <1.2Sm or Sy whichever is larger (b) Pm (or PL) + PB < 1.5(1.2Sm) or 1.5Sy whichever is larger 3
- 4.
Faulted Condition See Note 4 KEY:
Pm =
primary general membrane stress intensity PL =
primary local membrane stress intensity PB =
primary bending stress intensity Q =
secondary stress intensity Sm =
stress intensity value from ASME B&PV Code,Section III, Nuclear Vessels - 1968 Edition, Table N-421 Sy =
minimum specified material yield (ASME B&PV Code,Section III, Nuclear Vessels - 1968 Edition, Table N-424
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:
2.9-2 Page:
2 of 5 (PART B)
LOADING CONDITIONS AND STRESS LIMITS: PRESSURE PIPING LOADING CONDITIONS STRESS LIMITS
- 1.
Normal Conditions (a) Pm < Sh (b) PL + PB < Sh (c) SE < SA
- 2.
Upset Conditions (a) Pm < 1.2Sh (b) PL + PB < 1.2Sh (c) SE < SA
- 3.
Emergency Conditions (a) Pm <1.2Sh (b) PL + PB < 1.5(1.2 Sh)
- 4.
Faulted Conditions See Notes 4 & 5 WHERE:
Pm =
primary hoop membrane stress (pressure)
PL =
primary longitudinal membrane stress (pressure)
PB =
primary longitudinal bending stress (deadweight, seismic)
Sh =
allowable stress at temperature from USAS B31.1 Code for Pressure Piping, 1967 Edition SC =
allowable stress at 70°F from USAS B31.1 Code for Pressure Piping, 1967 Edition SE =
computed expansion stresses SA =
allowable stress range for expansion stresses (fatigue criteria) = (1.25 SC + 0.25 Sh) f (See Note 5)
F =
stress range reduction factor for cycling per USAS B 31.1 Code for pressure piping, 1967 Edition
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:
2.9-2 Page:
3 of 5 (PART C)
LOADING CONDITIONS AND STRESS LIMITS: EQUIPMENT SUPPORTS LOADING CONDITIONS STRESS INTENSITY LIMITS
- 1.
Normal Condition Working Stresses or Applicable Factored Load Design Values
- 2.
Upset Condition Working Stresses or Applicable Factored Load Design Values
- 3.
Emergency Condition Within yield after load redistribution
- 4.
Faulted Condition Permanent Deflection of Supports Limited to Maintain Supported Equipment Within Design Limits. See Note 4 Support loads are combined by algebraic summation, in plus and minus directions of the three orthogonal planes, so as to obtain the maximum positive or maximum negative value of design load.
The thermal load component is not considered when algebraic summation with this load would lessen the support design load.
The seismic load component is considered to have both a positive and a negative sign. The sign of the seismic component is chosen so as to maximize the absolute value of the support design load.
NOTES Note 1:
The limits on local membrane stress intensity (PL < 1.5Sm ) and primary membrane plus primary bending stress intensity (Pm (or PL) + PB < 1.5Sm) need not be satisfied at a specific location if it can be shown by means of limit analysis or by tests that the specified loadings do not exceed 2/3 or the lower bound collapse load as per paragraph N417.6(b) of the ASME B&PV Code,Section III, Nuclear Vessels - 1968 Edition.
Note 2:
In lieu of satisfying the specific requirements for the local membrane (PL < 1.5Sm) or the primary plus secondary stress intensity (PL + PB + Q < 3Sm) at a specific location, the structural action may be calculated on a plastic basis and the design will be considered to be acceptable if shake-down occurs, as opposed to continuing deformation, and if the deformations which occur prior to shakedown do not exceed specified limits, as per paragraph N417.6(a) (2) of the ASME B&PV Code,Section III, Nuclear Vessels - 1968 Edition.
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:
2.9-2 Page:
4 of 5 Note 3:
The limits on local membrane stress intensity (PL < 1.5Sm ) and primary membrane plus primary bending stress intensity (Pm (or PL) + PB < 1.5Sm) need not be satisfied at a specific location if it can be shown by means of limit analysis or by tests that the specified loading do not exceed 120 percent of 2/3 of the lower bound collapse load as per paragraph N417.10(c) of the ASME B&PV Code,Section III, Nuclear Vessels -
1968 Edition.
Note 4:
A plastic instability analysis may be performed for specific cases considering the actual strain-hardening characteristics of the material, but with yield strength adjusted to correspond to the tabulated value at the appropriate temperature in Table N-424 or N-425, as per paragraph N-417.11(c) of the ASME B&PV Code,Section III, Nuclear Vessel - 1968 Edition.
Note 5:
Where the sum of PL and PB stresses due to pressure, deadweight and other sustained loads is less than Sh, the difference between Sh and this sum may be added to the term 0.25 Sh in the formula for SA stated above for determining the allowable stress range SA.
(see Para. 102.3.2 of the USAS B31.1 Code for pressure piping, 1967 Edition.)
The following segments of piping systems and components have been analyzed to ASME III, Appendix F for faulted conditions:
- 1. RCP seal leak-off return line penetration piping between inside and outside containment isolation valves (CPN 37) and
- 2. Piping from the RCP seal bypass line check valves to the normally closed QRV-150 valve in the common discharge header (no CPN).
- 3. Piping from normally closed PRT drain line isolation valve and the RCDT drain line check valve inside containment to the normally closed isolation valve outside containment (CPN 40).
- 4. Accumulator fill line piping from outside containment isolation valve to the normally closed inlet valves at each accumulator and the normally closed valves in the flow path to the low head SI hot leg loops (CPN 32).
- 5. U-1 only: Piping between Primary Water supply line isolation valve outside containment to isolation valves inside containment. (CPN 33).
- 6. U-1 only: Piping between Demineralized Water supply line isolation valve outside containment to manual isolation valves for hose connections inside containment. (CPN 36).
- 7. U-1 only: Piping between sump pump discharge check valves inside containment and discharge isolation valve outside containment. (CPN 41).
- 8. U-1 only: NESW Supply to and Return from Lower Containment Ventilation Units (CPN-17, -18,
-19, & -20 for NESW supply; CPN-21, -22, -23,-24 for NESW return).
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table:
2.9-2 Page:
5 of 5
- 9. U-1 only: NESW Supply to and Return from Upper Containment Ventilation Units (CPN-26, -27,
-84, & -85 for NESW supply and return).
- 10. U-1 only: NESW Supply and Return to Instrumentation Room Ventilation Units (CPN-73 for both ventilation units NESW supply and return).
- 11. U-1 only: NESW Supply to and Return from the RCP Motor Air Coolers (CPN-26, -27, -84, & -85 for NESW supply and return).
- 12. U-1 only: Reactor Vessel Head Vent Piping from Reactor Head to Anchor 1-ARC-R626 (analyzed to Appendix F for post-accident head vent valve operation).
- 13. The Seismic Class 1 Enhanced Service Structure Components, including the lift rig assembly (without tripod), CRDM seismic platform, safety related pipe supports and safety class cable trays, bridges and associated supports are designed to Section III, subsection NF, of the 1995 ASME Boiler and Pressure Vessel Code, through 1996 Addenda.
- 14. U-2 only: Reactor Vessel Head Vent Piping from the Reactor Head to Anchor 2-ARC-R665 (analyzed to Appendix F for post-accident head vent valve operation).