ML17054A362
| ML17054A362 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/12/1984 |
| From: | Haughey M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8401200092 | |
| Download: ML17054A362 (22) | |
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0 4 ~**4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 January 12, 1984 Docket No. 50-410 APPLICANT:
Niagara Mohawk Power Corporation (NMPC)
FACILITY:
Nine Mile Point Nuclear Station, Unit 2
SUBJECT:
SUI'IMARY OF MEETING WITH NIAGARA MOHAWK POWER CORPORATION (NMPC)
ON STRUCTURAL ISSUES RELATED TO THE OPERATING LICENSEE REVIEW FOR NINE IIILE POINT, UNIT 2 On September 28, 1983 the NRC staff met with representatives from Niagara Mohawk Power Corporation in Bethesda, Maryland to discuss structural issues related to the operating license review for Nine Mile Point 2.
Requests for additional information in the area of structural engineering were sent to NMPC in a letter to Gerald K. Rhode from A. Schwencer on August 15, 1983.
These requests were discussed and clarified during the meeting.
Much of the information to be provided in response to the requests for information was identified to be provided in the fourth quarter of 1983.
Concern was expressed by the NRC that unless this information was to be provided early in the fourth quarter, it could impact the licensing schedule.
Some of the responses to requests for information will be available or provided at the structural audit.
The Nine Mile Point Unit 2 containment was identified as being designed to ASME Code Section III, Division 1 requirements.
Concern was expressed by the NRC that the design to Division 1 might be inadequate and that interaction between the concrete and steel containment structure may not have been adequately considered.
NMPC was requested to verify that the containment was designed to Division 1 requirements and identify and justify all deviations from Division 2 requirements.
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NMPC was requested to provide a presentation at the structural audit of how SSI analysis was performed.
NMPC was provided with a set of generic guidelines for the structural audit; These guidelines are included in Attachment 1.
A list of meeting attendees is included in Attachment 2.
Attachments:
As stated cc w/attachments:
See next page Original signed by Mary F. Haughey, Project Manager Licensing Branch No.
2 Division of Licensing DISTRIBUTION:
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- LYang, SGEB
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- SPChan, SGEB DL:LB¹2 PM MFHaughey:kw Ol/4/84 DL:LB¹2/BC ASchwencer Ol/)~/84
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Nine Mile Point 2
Mr. Gerald K. Rhode Senior Vice President Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 CC:
Mr. Troy B. Conner, Jr.,
Esq.
Conner
& Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.W.
Washington, D. C.
20006 Mr. Richard Goldsmith Syracuse Uni versi ty College of Law E. I. White Hall Campus
- Syracuse, New York 13210 Mr. Jay Dunkleberger, Director Technol ogi ca 1 Devel opment Programs New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.
Box 99
- Lycoming, New York 13093 Mr. John W. Keib, Esq.
Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Jay M. Gutierrez, Esq.
U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Attachm t 1
(
APPENDIX J.
STRUCTURAL DESIGN AUDIT GUIDELINES I.
BASIC DESIGN CRITERIA A.
General Design Data 1.
Wind and Tornado a.
Wind profile b.
Design pressure on flat and curve surfaces c.
Surface coefficients d.
Windward and leeward distribution e.
Gust factors g.
h.
Conversion of wind velocities into forces Effects of missiles from tornadoes Others 2.
Snow and Ice
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a.
Design loads
...-El o.od a.
Design basis flood elevation b.
Design groundwater table elevation Earthquake Design ground motion in the free field a.
Peak acceleration or zero-period acceleration (in g's)
(i)
Operating basis earthquake (OBE)
(ii) Safe shutdown earthquake (SSE) b.
Response
spectra (i)
Time history (i)
Source:
natural or artificial (ii) Composition:
rising time, strong motion duration, decaying time (iii) Baseline correction:
check the integrated velocity and displacemnt time histories (iv) Time interval (v)
Procedure of synthesizing
5.
7.
8.
(vi) Derived response spectra corresponding to time histories, and frequency intervals used d.
Damping Soil Properties a.
Soil profile layering (i)
Elevation (ii) Depth of layers (iii) Bearing capacity at foundation (iv) Lateral soil pressure, static and dynamic b.
Physical properties of each layer (i)
Type of soil (ii) Dry weight (iii) Shear modulus and shear wave velocity (iv) Poisson's ratio (v)
Bulk modulus (vi) Damping characteristics Blast Environment a.
Class of explosives b.
Distance of blast c.
Air blast and time pressure curves d.
Ground shock e.
Missiles and fragmentation Aircraft Impact Environment a.
Weight of projectiles b.
Speed of projectiles c.
Explosion and forcing function Turbine Missiles B.
Applicable Codes, Standards and Specifications C.
Materials 3.
Structural steel - modulus of elasticity, Poisson's
- ratio, yield strength and allowable stresses Concrete - modulus of elasticity, Poisson's ratio, ultimate
- strength, and allowable stresses Reinforcing steel - modulus of elasticity, Poisson's
- ratio, yield strength and allowable stresses Others (Specify)
J-2
II.
GENERAL METHODS OF ANALYSIS AND DESIGN A.
B.
Static Analysis 1.
Overall analysis 2.
Localized analysis 3 ~
Computer codes used Seismic Analysis 1.
Selection of masses and degrees of freedom 2.
Number of modes considered 3.
5.
Consideration of three components of motion Consideration of torsional and translational response Soil-structrue interaction C.
D.
E.
F.
G.
H.
6.
Development of floor response spectra a.
.General procedures b.
Smoothing c.
Peak widening d.
Typical results 7.
Computer codes used Buckling Analysis Load Comb>nations Design Consideration for Tornado and Turbine Missiles l.
Design requirements 2.
Local damage 3.
Overall response 4.
Conformance to SRP 3.5.3 Special Considerations for Containment Structure l.
Ultimate capacity analysis 2.
Special design loads - in addition to general design loads listed in Section I a.
Dead and live loads for various operating floors and base slab b.
Internal pressure and temperature c.
Pool dynamic loads (BWR only) 3.
Analysis of penetration effects 4.
Tangential shear (concrete containment only) 5.
Steel liner analysis (concrete containment and concrete basemat only)
Interaction with Non-Category I Structures equal ity Control Criteri a J-3
III.
SUMMARY
OF ANALYSIS AND DESIGN A summary of analysis and design should be provided for each structure or item listed in Section IV.
A.
B.
C.
D.
E.
F.
G.
General layout, dimensions, sections and details Generation of applicable dead and live loads Mathematical model; including idealized
- masses, geometrical and physical properties Summary of dynamic responses Computer input (if applicable)
Computer output (if applicable)
Governing load combinations and critical sections Design parameters for proportioning structural members Summary of key results Factor of safety against overturning, sliding and flotation (for foundations only)
Verification that drawings reflect design calculations
IV.
AUDIT ITEMS A.
Containment Building 1.
Containment Shell 2.
2.
3.
4.
Internal Structures (BWR plant) a.
Drywell wall b.
Weir wall c.
Oper ating floor d.
Reactor vessel supports or predestals e.
Coolant pump supports f.
Cable trays and their supports g.
Reactor shield walls h.
Polar crane support i.
Other structures (specify)
Internal Structures (PWR Plant) a.
Reactor vessel support b.
Reactor coolant pump support.
c.
Steam generator support
-', -" Primary'shield walls e.
Secondary shield walls f.
Operating floor slab g.
Cable trays and their supports h.
Polar crane support i.
Other structures Foundation Mat Including Reactor Pit Audit of Key Designs For each key design area audited, the design calculations should be reviewed together with applicable drawings,
- sketches, etc.
Also, key details and/or sections, as appropriate, in this audit report should be included.
a.
Containment liner design (i)
Conformance with ASME BEPV Code Section III Div. 2-Article CC-3000 and Div. 1 for fatigue and tensile evaluation if liner is subjected to such loads (ii) Key liner locations (iii) Forces and displacements obtained from computer analysis J-5
(iv) Liner anchor design (v)
Key penetration design Fuel pool liner design (i)
Analysis (ii) Conformance to code (iii) Corrosion effects (e. g. pitting) on liner integrity Containment Hatch Design (i)
Model, design assumptions and analysis procedures (ii) Governing load combinations (iii) Conformance to CC-3000 Containment wall-base mat junction design (i)
Design requirements and model (ii) Governing loads (iii) Key results (Forces, moments 8 stresses)
(iv) Section showing details (v)
Any waterstop membranes at the joints their design considerations and installations (vi) Conformance to 'CC-3000 Dome to cylinder junction design (i)
Design requirements and model (ii) Governing loads (iii) Key results (Forces, moments 8 stresses)
(iv) Sections showing details (v)
Conformance to CC-3000 Seismic Analysis for Buried Piping and/or Electrical Conduits (i)
Method of analysi s (ii) Stiffness calculations (iii) Inputs (iv) Key analysis results Post"Tensioning System (i)
Tendon system used (ii) Prestressing force at transfer (iii) Tendon load under LOCA
(iv) Method used to calculate prestress losses:
Initial Creep and shrinkage of concrete Tendon relaxation or degradation Other losses h.
Buttress Oesign for Post-Tensioning System (i)
Maximum bursting stress in concrete (ii) Reinforcing provided to resist bursting stresses (iii) Stress under the anchor plate (iv) Allowable stresses (v)
Stress under tendons, anchorage
. (vi) Method for calculation of stresses Other Category I Structures Provide summary of analysis and design for structure and foundation of the following:
l.
Auxiliary Building 2.
Control Building
- 3. "'iesel Generator Building 4.
Fuel Handling Building 5.
Miscellaneous (specify)
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ttachment 2
MEETING ATTENDEES SEPTEMBER 28, 1983 Name M. F. Hauahey R. H. Pinney S.
P.
Chan C.
E. Crocker D. C. Jeng L. Yang A. M. Shah M. S. Dixit E.
R. Klein N. L. Rademacher Affi 1 iati on NRC SWEC NRC SWEC NRC NRC SWEC SWEC NMPC NMPC
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