ML17195A113
| ML17195A113 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/14/1984 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| References | |
| LSO5-84-02-026, LSO5-84-2-26, NUDOCS 8402160378 | |
| Download: ML17195A113 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Mr. Dennis L. Farrar Director of Nuclear Licensing Col!llilonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear ~r. Farrar:
February 14, 1984
SUBJECT:
. MARK I CONTAINMENT LONG TERM PROGRAM - PLANT UNIQUE ANALYSIS REPORT STRUCTURAL EVALUATION Re:
Dresden Nuclear Power Station, Unit Nos. 2 and 3 The NRC staff and its consultcnt Franklin Research Center {FRC) are reviewing
- the structural aspects of your plant unique analysis repott.
As a result of our review to date we have prepared the enclosed request for additional information.
It is requested that you provide a response within 45 days of receipt of this letter. If you deterr.iine there is a need to meet with or to have a conference call with the staff and FRC to discuss this reauest prior to responding, please contact your project manager.
In addition, if you cannot meet this response date, please notify your project manager within seven days of receipt of this letter.
This request for information was approved by the Office of Management and Budget under clearance number 3150-0091 which expires October 31, 1985.
Enclosure:
Reouest f6r Additional Information cc w/enclosure:
See*next page Sincerely, Lo
. ~r,1 ~ ll,,ffx:,L ::7'<./.l-.U~
ennis *. '{futbl'f1e d, Oper~ting Reactors B~
Division of Licensing
Mr. Dennis L. Farrar cc Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr: Douq Scott Plant Superintendent Dresden Nuclear Power Station Rura 1 Route #1 Morris, Illinois 60450 U. S. Nuclear Reaulatorv Commission Resident Inspectors Office Dresden Station Rural Route #1 Morris, Illinois 60450 Chairman Board of S~pervisors of
.. Grundy County Grundy County Courthouse Morris, Illinois 60450 U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN:
Regional Radiation Representative 230 South Dearborn Street Chicago, Illinois 60604 James G. Keppler, Regional Administrator t~uclear Regulatory Commission, Region III 799 Roosevelt Street Glen Ellyn, Illinois 60137 Mr. Gary N. Hright, Manager
. Nuclear Facility Safety Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 February 14, 1984
- ' -.~;
REQUEST FOR ADDITIONAL INFORMATION MARK I CONTAINMENT LONG TERM PROGRAM - PLANT UNIQUE
,ll.~'AL YSIS REPORT DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3
- DOCKET NOS. 50-237/249 Item l:
Provide a summary of the analysis with regard to the vacuum breaker piping systems and the vacuum breaker valves: indicate ~hether they
. are considered Class 2 components as required by the criteria [l}.
Item 2:
Provide a list indicating whether all the piping systems and their supports have been classified as essential or non-essential piping systems.
Item 3:
Provide and justify the reasons for not considering a ~180° beam model of the torus including columns, saddles, and seismic restraints in order to determine the effects of nonsymmetric loads such as SRV and chugging for Dresden Units 2 and 3.
nem 4:
With respect to Sections 5-3.3 and 5-4.3 of the PUA report (2), show that SRVDL support st*resses due to extreme environmental and emergency conditions do not exceed the Service Level C and D Limits specified in the ASME B&PV Code,Section III, Division I, Subsection NF for Class 2 or 3 linear supports.
Item 5:
Provide calculations demonstrating conformance to the 10% rule of Section 6-3.l (1) for piping systems in Dresden Units 2 and 3 that were exempted from analysis because of the 10% rule.
Item 6:
Tables 2-2.5-3 of Reference 2 indicates that the calculated values of certain stresses are close to the respective allowables.
Indicate conservatisms in the analysis to show that these calculated values would not be exceeded if a different analytical approach were to be used
- REFERENCES
- 1.
NED0-24583-1 "Mark I Containment Program Str~ctural Acceptance Criteria Plant Onique Analysis Application Guide" General Electric co., San Jose, CA October 1979 2 *. Dresden Nuclear Power Station Units 2 and 3 Plant Unique Analysis Report Volumes l, 2, 3, 4, 5, 6, and 7 - Revision 0 Commonwealth Edison Company May 1983
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