ML17202U944
| ML17202U944 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 01/11/1991 |
| From: | Olshan L, Siegel B Office of Nuclear Reactor Regulation |
| To: | Kovach T COMMONWEALTH EDISON CO. |
| References | |
| TAC-74507, TAC-74508, TAC-74509, TAC-74510, NUDOCS 9101150320 | |
| Download: ML17202U944 (5) | |
Text
Docket Nos. 50-237, 50-249, and 50-254, 50-265 Mr. Thomas J. Kovach
- Nuclear Licensing Manager Commonwealth Edison Company-Suite 300 OPUS West III 1400 OPUS Place Downers Grove, Illinois 60515
Dear Mr. Kovach:
January 11, 1991~
DISTRIBUTION NRC & Local PDRs B. Boger R. Barrett B. Siegel OGC ACRS ( 10)
W. Schafer J. Lee (Do ~I~f~:f_i)i.J PD3/2 r/f J. Zwolinski C. Moore L. Olshan E. Jordan PD 3/2 Plant File
- J. Norberg
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE PROPOSED PIPING OPERABILITY CRITERIA FOR DRESDEN UNITS 2 AND 3 AND QUAD CITIES UNITS 1 AND 2 (TAC NOS. 74507, 74508, 74509, AND 74510)
The NRC staff, with technical assistance from Brookhaven National Laboratory,.
has reviewed your proposed piping op~rability criteria for Dresden Units 2 and 3 and Quad Cities Units 1 and 2 provided in your August 17, 1989 submittal.
Although these criteria are generally consistent with similar criteria*accepted by the staff for the Palisades and Fort Calhoun Stations, the staff has determined that some additional information needs to be provided before final staff acceptance of the proposed operability criteria can be made.
The enclosure identifies the additional information needed along with staff recommendations.
It is requested that your response be provided within 60 days of receipt of this letter. If you require clarification or have a problem with the proposed.
schedule please contact the appropriate Project Manager.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Enclosure:
As stated cc:
See next page OFFICIAL RECORD COPY Sincerely, Original Signed Bv:
Byron Siegel*, P'roject Manager Project Directorate 111/2 Division of Reactor Projects IIl/IV/V Office of Nuclear Reactor Regulation Original Signed By:.
- Leonard N. Olshan, Project Manager Project Directorate 111/2 Division of Reactor Projects 111/IV/V Office of Nuclear Reactor Regulation Document Name:
KOVACH/74507/74508/74509/74510 9101150320 910111 PDR ADOCK 05000237 p
.. P,DR I
\\
Mr. Thomas J~ Kovach Commonwealth Edison Company cc:
Michael I~ Miller, Esq.
Sidley and Au_stin One First National Plaza Chicago, 11.linois 60690 Mr. J. Eenigenburg Plant Superintendent Dresden Nuclear Power Station Rural Route Iii *,
Morris, *Ill~nois 60450 U. S. Nuclear Regulatory Conunission Resident Inspectors Office
'Dresden Station
- Rura 1 Route #1 Morris, lllinois 60450 Chairman Board of Supervisors of Grundy County Grundy County Courthous~
Morris, Illinois fi0450 * *
. Regional Administrator Nuclear Regulatory Commissfon, 799 Roosevelt Road, Bldg. #4 Gl~n Ellyn, Illinois 60137 Region III Illinois Department.of Nuclear *safety Office of Nu~lear Facility Safety 1-035 Outer Park Drive Spririgfield, Illinois 62704 *
- Robert Neumann
. l Dresden Nuclear Power Station Unit Nos. 2 and 3
..,;._ (*
- ~
Mr. Thomas J. Kovach Commonwealth Edison Company cc:
Mr. Stephen E. Shelton Vice President Iowa-Illinois Gas and
- Electric Co~pany P. 0. Box 4350 Davenport, Iowa 52808 Michael I. Miller, Esq.
Sidley.and Austin One First National Plaza Chicago, Illinois 60690 Mr. Richard Bax Station Manager Quad Citi~s Nuclear Power Station 22710 206th Avenue North.
Cordova, Illinois 61242 Resident Inspector U. S. Nuclear Re.gulatory Comm-ission 22712 206th Avenue North Cordov*a ~ I 11 i noi s 61242 Chairman Rock Is land County Bo.a rd of Supervisors 1504 3rd Avenue Rock Is.land County Office Bldg.
Rock Island, Illinois 61201 Illinois Department of Nuclear Safety*
Office of Nuclear Facility Safety 1035 Outer Park Driv~
Springfield, Illinois 62704 Regional Ad~inistrator, ~egion III U. S. Nuclear Regulatory Commission 799 Roosevelt Road, Bldg. #4 Glen Ellyn,. Illinois 60137 Robert Neumann
- Office of Public Counse 1 State of Illinois Center 100 W. Randolph Suite 11-300 Chicago, Illinois 60601 Quad Cities Nuclear Power Station Unit Nos. 1 and 2
......::; (*
ENCLOSURE r1 er1a
- 1.
The use of Regulatory Guide 1.61 damp1ng with original design spectra and analysis prucedures is not pennitted. Either the FSAR damping should be used or the design spectra and analysis methods for use with current damping should be upgraded.
(Section 3.1)
- 2.
The primary stress limits for nonnal and faulted condition loads exceed ASME Code (Code) allowables but are consistent with limits accepted by NRC for interim operation of other plants. However, secondary stress limits (e.g., on thermal stresses and seismic anchor motions) are not addressed.
These limits should be defined and justification provided if they exceed Code allowables.
(Section 3.1)
\\
- 3.
The criteria does not provide.pipe stress limits for operating basis earthquake (QBE) and other occasional loads including waterhammer or steamharrmC:!r.
These limits should be defined and if they exceed Co.de allowables, th~ actions that would be taken to assure continued operability
- *~hould be explained.
(Section 3.1)
- 4.
The criteria for.flanges needs to be clarified. If faulted condition limits will be applied to nonnal load combinations, further justification should be provided.
(Section 3.2.1)
- 5.
The licensee shpuld provide the current de~ign.criteria for piping deflections and explain how it will ensure against interactions with.
adj~cent structure~ whe~ used in conjunction.with the proposed operability criteria.* (Section 3.2.*2)
- 6.
- The. pipe support loads and analysis-methods appear consistent with those '
accepted by NRC for interim operation at other plants. To ensure proper
.implementation, somt:_,examples to illustrate the method, including how the*
- worst case failure mode of a support woul~ be inco~porated-into the
.analysis_,, should be provided.
(Section 4.0)
- 7.
For standard support~ with manufactu_rer' s load* rating, the criteria are similar to those accepted by NRC for interim operation at other-plants.
However, the technical basis for the safety factors on ultimate test loads
.*and for the mul_tiplier of 1.167 Su/Sy on Level A allowables is unknown
. and should be provided. If based on ASME Code 1 the applicable Code
. edition ~nd subsection should be refetenced *. lSection 4.1.1) *
- 8.
The structural steel stress.limits are very similar to those accepted by NRC at other plants. However, the proposed use of actual yield strengths based on certified material test reports (CMTRs) is generally not acceptable.
Their use would further reduce safety factors to levels which may be unacceptable for even interim operation. The use of Code minimum yield stfengths is appropriate. (Section 4.2.1)
- 9.
The snubber load limits are consistent with other NRC accepted interim criteria*. However, the snubber criteria should also inclupe a requirem~nt that calculated movements do not exceed the travel range *
. (Section 4.3.2)
':.: