ML20058E877
| ML20058E877 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 07/26/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR LSO5-82-07-065, LSO5-82-7-65, NUDOCS 8207300239 | |
| Download: ML20058E877 (11) | |
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July 26,1982 l
Docket No. 50-409 i
LS05-82-07-065 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South Lacrosse, Wisconsin 54601
)
Dear Mr. Linder:
SUBJECT:
SEP TOPIC III-6, SEISMIC 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 perfom an audit review of selected analyses.
Sincerely,
[L1G nni cir;ned b7:
i Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
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Docket No. 50-409 LS05 Mr. Frank Linder General Manager Dairyland Power Cooperative 2615 East Avenue South Lacrosse, Wisconsin 54601
Dear Mr. Linder:
SUBJECT:
SEP BRANCH REEVALUATION GUIDELINE SEISMIC CRITERIA FOR THE SEP GROUP II P1 ANTS - 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 th'e attached " Reevaluation Guideline Seismic Criteria for SEP Group II Plants." The enclosed guideline seismic criteria has been developed by the SEP Branch staff in conjunction with its consultants.
Satisfaction of this criteria provides a minimally acceptable level of seismic resistance for the items in your facility only when appropriate analyses are performed. The acceptability of the analytical techniques will be determined based upon an audit review of your analyses.
Sincerely, Dennis H. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
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Lacrosse Docket No. 50-409 Revised May 12, 1982 4
Mr. Frank Linder CC Fritz Schubert, Esquire U. S. Environmental Protection i
/
Staff Attorney Agency Dairyland Power Cooperative Federal Activities Branch 2615 East Avenue South Region Y Office La Crosse, Wisconsin 54601 ATTN:
Regional Radiation Representative 230 South Dearborn Street O. S. Heistand, Jr., Esquire Chicago, Illinois 60604 Morgan, Lewis & Bockius 1800 M Street, N. W.
Mr. John H. Buck Washington, D. C.
20036 Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Mr. R. E. Shimshak Washington, D. C.
20555 i
La Crosse Boiling Water Reactor Dairyland Power Cooperative Mr. Ralph S. Decker P. O. Box 275 Route 4, Box 1900 Genoa, Wisconsin 54632 Cambridge, Maryland 21613 l
Charles Bechhoefer, Esq., Chairman Mr. George R. Nygaard Coulee Region Energy Coalition Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission 2307 East Avenue La Crosse,. Wisconsin 54601 Washington, D. C.
20555 Dr. Lawrence R. Quarles Dr. George C. Anderson Kendal at Longwood, Apt. 51 Department of Oceanography Kenneth Square, Pennsylvania 19348 University of Washington Seattle, Washington 98195 U. S. Nuclear Regulatory Commission Resident Inspectors Office James G. Keppler, Regional Administrator l
Rural Route #1, Box 276 Nuclear Regulatory Commission, Region III j
Genoa, Wisconsin 54632 799 Roosevelt Road Glen Ellyn, Illinois 60137 Town Chairman Thomas S. Moore Atomic Safety and Licensing Appeal Board Town of Genoa U. S. Nuclear Regulatory Commission Route 1 Genoa, Wisconsin 54632 Washington, D. C.
20555 Chairman, Public Service Commission of Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702 Alan S. Rosenthal, Esq., Chairman Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Comnission
)
1 Washington, D. C.
20555 I
j c
REEVALUATION GUIDELINE SEISMIC CRITERIA FOR SEP GROUP 11 PLANTS 1
(EXCLUDINGSTRUCTURES)
INTRODUCTION In support of NRC's Systematic Evaluation Program (SEP) for Group II These Plants, the following Reevaluation Criteria have been established.
criteria include recomended load combinations with allowable stresses and/or loads for piping systems, component supports, concrete attachments, These criteria are based on linear elastic analyses having and equipment.
The acceptance criteria are generally based on the ASME been perfonned.
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.
General membrane stress. This stress is equal to the P,
=
average stress across the solid section under 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 thermal 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 P, 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 temperature at the section under consideration.
Yield strength at temperature listed in ASME Code.
S
=
y SPECIAL 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 deformation, and boundary conditions. Both gross and local buckling must be evaluated.
3 Critical buckling loads (stresses) shall b1 detemined 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.
4 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 1 I'0 Class 1:
P, + Pb D
h Class 2:
P, + Pb"f"*'D bb il 2' b h The effects of thennal 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 were omitted from Equation (9) of NC-3662. Class 1 analytical procedures (NB-3600)canalsobeutilizedifappropriateallowablestressesspecified 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 Combinations Linear Plate and Shell The higher of:
lWl P, S 1.05, Code Subsection NF or Design, Level A, and lW+Tl Level B Limits P, + Pb s 1.5 Sm The higher of:
lWl +
lSSEl +
l AM\\
P,1 0.45 Su Code Subsection NF r
Level D Limits P
+P 1 0.7 S lW + T l +
lSSEl + l AMl m
b 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 a.
In addition. for brittle types of material not ASME Code Subsection NF.
specified in the Code, appropriate stress intensification factors for notches and stress discontinuities shall be applied in the analysis.
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
~
c.are shown to be sufficiently low to preclude concrete / grout / steel interface bond failures. Load combinations are the same as those for camponent supports.
ACCEPTANCE CRITERIA FOR MECHANICAL EQUIPMENT 4
T, T
s Loading CombirNtionb Criteria Component lW + Pul+(55tl+[ Nozzle Loads l P,5 2.0 Sh Pressure vessels and heat-exchangers (Pm orP,)+P i 2.4 Sh h
lW + P l+l55tl+lhozzle Loads] P,1 1.5 S D
h Active pumps and other mechanical components,d a
Inactive pumps and other
'W + Po
+ 55E(+lNuztle Loadsf Pmi 2.0 Sh mechanical components (p orP)+Pbi 2.4 S m
g h
Active valves,d (W + Pg +l$$[.l l Nozzle Loads l Extended Structure:
a Pmi 1.5 Sh (P ore)+Eb1 1.8 Sh m
n Nozz.lc iceds:c Inactive valves lg + pg +lsstl+ Norrle Loudsl Extended Structu.*c:
Pd 2.0 Sh m
(Pm er P,) + P i 2.4 Sh h
Nox;le Todds:C Bolt stress sh'all be limited to:
tension - S but 1 7 S D but 1 42 S D shear -16 y
Active pumps, valves, and other' mechanical components (e.g., CRDs) are defined as those that must perform a mechanical motion to accomplish a.
~
s a system safety function.
Nozzle loads shall-include all piping loads (including seismic and b.thermal anchor movement effects)' transmitted to the component during the l
SSE.
Pipingloadsa"tp[ ping / active-valveinterfacesshallbelimitedto below yield stress of the attached piping considering all piping loads c.
(including seismic and thermal anchor movement effects).
(
j It shall be detilonstrated that defomation induced by the loading on these d.pumps, valves and other mechanical components (e.g., CRDs) do not introduce i
detrimental effects (such as binding, impact, or brittic failures) for pemp For valve open tors integrally attached to 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 (.tnCluding seismic and themal anchor movement effects) shall be included.
_g_
ACCEPTANCE CRITERIA FOR TANKS l Normal Operating Loadd +lSSE Inertia Loads l Load Combinations:
a
+\\ Dynamic Fluid Pressure Loads Acceptance Criteria:
Smaller of S or 0.7 S.
In addition, the y
u allowable buckling stress shall be limited to 2/3 is determined in accordance Sbk, where Sbk with Special Limitation 1.
Dynamic fluid pressure shall be considered in accordance with accepted and appropriate procedures; e.g., USAEC TID-7024. Horizontal and vertical a.
loads shall be determined by appropriately combining the loads due to vertical and horizontal earthquake excitation considering that the loads are due to pressure pulses within the fluid. These loads shall also be applied, in combination with other loads, in tank support evaluations.
l
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