ML20058F024
| ML20058F024 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/26/1982 |
| From: | Caruso R Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR LSO5-82-07-067, LSO5-82-7-67, NUDOCS 8207300272 | |
| Download: ML20058F024 (11) | |
Text
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0 July 26, 1982 Docket No. 50-29 LS05 07-067 Mr. James A. Kay Senior Engineer - Licensing Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701
Dear Mr. Kay:
SUBJECT:
SEP TOPIC III-6. SEISHIC DESIGN CONSIDERATIONS, STAFF GUIDELINES FOR SEISMIC EVALUATION CRITERIA FOR THE SEP GROUP II PLANTS During meetings with licensees concerning seismic reevaluation of SEP Group II Plants (Haddam Neck, Yankee, Lacrosse, San Onofre Unit 1, and Big Rock Point) licensee questions concerning acceptance criteria and reanalysis methods have been discussed.
In order to facilitate our reviews and respond to questions raised we are forwarding the enclosed " Reevaluation Guideline Seismic Criteria for SEP Group II Plants." These guidelines reflect the NRC decision to request seismic reanalysis for only the Safe Shutdown Earthquake and are consistent with our approach to reanalysis of other SEP facilities.
With respect to questions concerning the acceptability of your analytical methods, the staff will perform an audit review of selected analyses.
Sincerely, Qgine.1 cicnca D7I Ralph Caruso, Project Manager Operating Reactors Branch No. 5 Division of Licensing l
Enclosure:
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s Docket No. 50-29 LS05 Mr. James A. Kay Senior Engineer - Licensing Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachuesetts 01701
Dear Mr. Kay:
SUBJECT:
SEP BRANCH REEVALUATION GUIDELINE SEISMIC CRITERIA FOR THE SEP GROUP II PLANTS - SEP TOPIC III-6 In order to facilitate the staff reviews of the seismic reanalysis of your facility and ensure consistency in the licensee reanalysis and staff review, we are forwarding the attached " Reevaluation Guideline Seismic Criteria for SEP Group II Plants." The enclosed guideline seismic criteria has been developed by the SEP Branch staff in conjunctian with its consultants.
Satis faction of this criteria provides a mir v.iv acceptable level of seismic resistance for the items in your facin y only when appropriate anelyses are performed.
The acceptability of the analytical techniques will be determined based upon an audit review of your analyses.
Sincerely, Ralph Caruso, Project Manager Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
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Yankee Docket No. 50-29
. Mr. James A. Kay Revised 3/30/82 CC Mr. James E. Tribble, President Yankee Atomic Electric Company 25 Research Drive Westborough, Massachusetts 01581 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council 14th Floor One Ashburton Place Boston, Massachusetts 02108 U. S. Environmental Protection Agency Region I Office ATTN:
Regional Radiation Representative JFK Federal Building Boston, Massachusetts 02203 Resident Inspector Yankee Rowe Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge,' Massachusetts 01350 Ronald C. Haynes, Regional Administrator Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19405
REEVALUATION GUIDELINE SEISMIC CRITERIA FOR SEP GROUP II PLANTS (EXCLUDING STRUCTURES)
INTRODUCTION In support of NRC's Systematic Evaluation Program (SEP) for Group II These Plants, the following Reevaluation Criteria have been established.
criteria include recommended load combinations with allowable stresses oncrete attachments, and/or loads for piping systems, component supports, These criteria are based on linear elastic analyses having and equipment.
The acceptance criteria are generally based on the ASME been performed.
For situations not covered by these criteria, compatible criteria Code.
shall be developed by the licensee and will be reviewed on a case-by-case basis.
DEFINITIONS _
ASME Boiler and Pressure Vessel Code,Section III, Code
=
" Nuclear Power Plant Components," 1980 Edition. Winter 1980 Addenda.
This stress is equal to the General membrane stress.
P
=
average stress across the solid section under m
consideration, excludes discontinuities and concentrations, and is produced only by mechanical loads.
This stress is equal to the linear Bending stress.
P
=
varying portion of the stress across the solid section b
under consideration, excludes discontinuities and concentrations, and is produced only by mechanical loads.
2 Design or maximum operating pressure loads.
P
=
D Inertial loads due to Safe Shutdown Earthquake (SSE)
=
and design mechanical loads where applicable.
Loads due to thennal expansion of attached pipe T
=
(constraint of free end displacement).
Loads due to weight effects.
W
=
Loads due to SSE anchor movement effects.
=
Critical Buckling stress.
S
=
bk Allowable stress intensity at temperature listed in S,
=
ASME Code.
Ultimate tensile strength at temperature listed in S
=
D ASME Code.
Local membrane stress. This stress is the same as Pm P
=
g except that it includes the effect of discontinuities.
ASME Code Class 2 allowable stress value. The S
=
h allowable stress shall correspond to the metal l
temperature at the section under consideration.
Yield strength at temperature listed in ASME Code.
S
=
y SFECIAL LIMITATIONS 1.
Critical buckling loads (stresses) must be detennined taking into account combined loadings (i.e., axial, bending, and shear), initial inperfections, residual stresses, inelastic defonnation, and boundary Both gross and local buckling must be evaluated.
conditions.
Critical buckling loads (stresses) shall be determined using acceptable methods such as those contained in NASA Plates and Shells Manual or ASME Code Case N-284 The allowable load (stress) shall be limited to thus determined.
2/3 S bk Where stresses exceed material yield strength, it shall be 2.
demonstrated that brittle failures and detrimental cyclic effects are precluded, and that dynamic analysis assumptions are not noncon-Where significant cyclic effects are identified, servatively affected.
it shall be demonstrated that the structure or component is capable of withstanding ten full peak deformation cycles.
of the Where results of analysis indicate that the allowable stresses 3.
original construction code are exceeded in any of the load combinations specified herein, it shall be demonstrated that the in-situ item was designed and fabricated using rules compatible with those required for the appropriate ASME Code Class (Subsection NX2000, 4000, 5000, and In cases where compatibility with the appropriate ASME Code 6000).
Subsections was not substantially achieved, appropriate reductions in these limits shall be established, justified, and applied.
l
ACCEPTANCE CRITERIA FOR PIPING Using Code Class 2 analytical procedures (Equation (9), NC-3653-1).
the following stresses are not to be exceeded for the specified piping:
=lW + P \\+lSSd1 1.8 S Class 1:
P, + Pb D
h D + SSEl1 2.4 S Class 2:
P
+P
=W+P h
m b
The effects of themal expansion must meet the requirements of Equation (10) or (11) of NC-3653.2, including moment effects of anchor displacements due to earthquake if anchored displacement effects v?re omitted from Equation (9) of NC-3662. Class 1 analytical procedures (NB-3600) can also be utilized if appropriate allowable stresses specified in NB-3650 are used.
Branch lines shall be analyzed including the inertial and displacement of the piping to which it is attached at the input due to the response attachment point.
5-ACCEPTANCE CRITERIA FOR COMPONENT SUPPORTS a
Acceptance Criteria Imposed Load Plate and Shell Linear Combinations The higher of:
lWl P, i 1.05, Code Subsection NF or Design, Level A, and lW+Tl Level B Limits P, + Pb i 1.5 Sm The higher of:
lWl +
lSSEl +
lAMl P,1 0.45 Su Code Subsection NF or Level D Limits lW + Tl +
lSSEl + lAMl P, + Pb s 0.7 S u In addition to the above criteria, the allowable buckling stress shall be is determined in accordance with Special limited to 2/3 Sbk, where Sbk Limitation 1.
These load combinations shall be used in lieu of those specified in-In addition, for brittle types of material not a.
ASME Code Subsection NF.
specified in the Code, appropriate stress intensification factors for notches and stress discontinuities shall be applied in the analysis, i
ACCEPTANCE CRITERIA FOR CONCRETE ATTACHMENTS a
1.
Concrete Expansion Anchor Bolts Load Combinations:
Same as for component supports.
Acceptance Criteria:b Wedge type:
1/4 ultimate as specified by manufacturer.
Shell type: 1/5 ultimate as specified by manufacturer.
II. Grouted Bolts:
Replacc, b, c a
a III. Concrete Embedded Anchors Load Combinations:
Same as for component supports.
b Acceptance Criteria : 0.7 Su Base plate flexibility effects must be considered, a.
Both pullout and shear loads must be considered in combined loading b.
situations.
Unless stresses in the bolts and structure to which they are attached are shown to be sufficiently low to preclude concrete / grout / steel' interface c.
Locd combinations are the same as those for component supports.
bond failures.
J
ACCEPTANCE CRITERIA FOR MECHANICAL EQUIPMENT b
Component Loading Combination Criteria lW + Pul+(55tl+lMozzle Load 5l P,5 2.0 Sh Pressure vessels (Pm or P,) + P i 2.4 Sh h
and heat-exchangers lW
- Pgl+l55El+lNozyle Loads l P,5 1.5 S h Active pumps and other mechanical components,d a
Inactive pumps and other (W + Po[+ [55d+lNortle Loads l Psi '/ U Sh mechanical components (p or P ) + P 1. 2.4 Sh m
g b
(W + P l+lS$f. +l Nozzle Loads l Extended Structure:
Active valves,d a
O Pi 1.5 Sh m
(P or P, ) + Pbi 1.8 Sh m
Nazi.lc loads:c Inactive valves lW + Po +l55E
+ Norrie Loudsl Ixtended Structu.e:
fd 2.0 Sh m
(P er Pg) + P i 7.4 Sh m
h Nortle> Iceds:C Bolt stress shall be limited to:
tension - S but s.7.5 but i.42 S D shear
.6 y
Active pumps, valves, and other mechanical components (e.g., CRDs) are defined as those that must perfom a mechanical motion to accomplish a.
a system safety function, Nozzle loads shall include all piping loads (including seismic and themal anchor movement effects) transmitted to the component during the b.
SSE.
Piping loads at piping / active-valve interfaces shall be limited to below yield stress of the attached piping considering all piping loads c.
(including seismic and themal anchor movement effects).
It shall be demonstrated that defomation induced by the loading on these pumps, valves and other mechanical components (e.g., CRDs) do not introduce d.
detrimental effects (such as binding, irr. pact, or brittle f ailures) for pump For valve operators integrally attached to I
internals and valve operators.
valve bodies, binding can be considered precluded if stresses in the valveIn body and operator housing and supports are shown to be less than yield.
these evaluations, all loads (_ including seismic and thermal anchor movement effects) shall be included.
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.with Special Limitation 1.
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i Dynamic fluio pressure shall be considered in accordance with accep;td y
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and appropriateJprocedures; e.g., USAEC TID-7024. Horizontal and vertical!
a.
loads shall be determined by appr6priately combining the loads due to loads
.f vertical and hg.r:izontal earthquake excitation considering that tha are due to pressure fulses within the fluid. These loads sha)'
'r.
Se applied, in combinatioh wiOi other loads, in tank' support evaluations.
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