ML19254B169
| ML19254B169 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 07/17/1979 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Christenburg E NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| Shared Package | |
| ML19254B166 | List: |
| References | |
| TASK-AS, TASK-BN-79-26 BN--79-26, BN-79-26, NUDOCS 7909240512 | |
| Download: ML19254B169 (1) | |
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UNITED STATES e
EY-NUCLEAR REGULATORY COMMISSION n
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JUL 17 G7'3 I
j MEMORAllDUM FOR:
Edward S. Christenbury, Chief Hearing Counsel, Office of the Executive Legal Director FROM:
Steven A. Varga, Acting Assistant Director for Light Water Reactors, Division of Project Management
SUBJECT:
BOARD I!0TIFICATI0il - USE OF CONTAINMENT LINER LEAK CHASE CHANllELS FOR CATEGORY I SUPPORTS (B!l-79-26)
An 0IE memorandum dated June 12, 1979 from D. Thompson, I&E, forwarded information for possible Zimmer Board notification regarding the use of con-tainment leak chase channels on the Zinmer piant for the support of some Category I instrument sensing lines and electrical conduit. The potential problem is discussed in a May 1, 1979 memorandum from Region III which is enclosed.
We concur with the recommendation to notify the Zimmer Board which can be done by forwarding the enclosed memorandum. Although the means of solving this proble' has not been established it appears that corrective measures or analysis wili result in design conformance to the staff's criteria in this area.
We will provide any necessary followup ir, formation when it is available.
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/ Assistant Directdsfor Light Water Reactors Division of Project Management
Enclosure:
As Stated cc:
H. R. Denton L. Nichols E. G. Case B. Grimes D. Eisenhut J. Stolz V. Stello, IE R. Bact D. Vassallo
- 0. Parr R. DeYoung L. Rubenstein V. Moore IE (7)
H. Thornburg D. Thompson 39092405a SS3 MF
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t NUCLEAR REGULATORY COMMISSION Enclosure
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CLEN CLLYN. ILLINots 50137
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May 1, 1979 MEMORANDUM FOR:
G. W. Reinmuth, Assistant Director, Division of Reactor Construction Inspection, IE THRU:
G. Fiorelli, Chief, Reactor Construction and Engineering Support Branch, RIII FROM:
D. W. Hayes, Chief, Engineering Support Section No.1, RIII
SUBJECT:
SEISMIC SUPPORTS ATTACHED TO CONTAllMENT
~
LEAK CIU6E CHANNELS (A/I F30496Hl)
During recent inspections at one of our BWR Mark II facilities (Zi=mer) we noted that instrument sensing lines and cicctrical conduit were being anchored to the centainment leak chase channels.
The sensing lines and conduits involve safety related equipment.
Attachment A shows some typical installations.
Attachcent B lists some of the equipment involved.
Prior to this, at the time the containment leak c'aase channels were being installed, we were inforced by the licensee that they did not consider the channels to be safety related and thus outside the requirements of their QA program.
We accepted this based on licensee statements that the channels had no structural function and if a leak was detected, procedures required ic=ediate identification of the source (i.e. in the leak chase channel weld or in the contain=cnt liner veld).
Also that the channels would be pressurized and the welds successfully soap bubbic tested.
In view of the above we expressed the following concerns to the licensee:
1.
Were the contain=cnt leak chase channels welds designed for the loads, both static and dynamic, now attached to them'l Would failure compromise containment integrity and/or safety actuations.
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G.'W. Reincuth 2-May 1, 1979 f
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Did the design of containment liner anchorage include these loads that would be transmitted thru the leak chase chanacls?
3.
Considering that the QA program did not apply to the leak chase channel welds what assurance exists relative to the integrity of the welds ot..cr than the pressure bubble test?
As a result of our questions the licensee contacted his AE (Sargent and Lundy).
Subsequently wescre informed that the AE had reviewed and evaluated these installations and considered them to meet design requirccents for applicable loads.
The AE did conclude however, that no additional attacheents should be made to the vertical channels but that the anchorage, aircady attached to the vertical channels cet requirceents.
Supports continue to be attached to the horizontal channels.
khe licensee has agreed to take the results of the AE's evaluations of the installations including seismic calculations available for our review at the construction site.
Considering the nature of the evaluations and ci1culations and possible icpact on containment integrity as well as safety system functions we believe NRR should revice the design of these installations and supporting data for adequacy.
.1cr our conversation vc have contacted Irving Peltier, LPM for Zic=cr.
NRR is interested and is agreeable to send a structural review engineer to the site.
Scheduling is pending receipt of a request from IE to NRR.
A
- v D. W. Hayes, Chief Engineering Support Section No. 1 Attachments :
As stated cc w/ attachments:
J. G. Keppler R: C. Knop K. R. Naidu T. E. Vandel'-
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1 Zir.mer 50-358 I
TYPICAL SUPPORT INSTALLATIONS WELDED TO CONTAINMENT LEAK CIASE
- OIANNELS s
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ATTACIIMENT B ELECTRICAL LINE !;0.
EQUIPMENT.
FUNCTION NB.357 Reactor Water Cleanup Power feed to System Isolation Valve Motor 1G33-F001 NB 358 same as above Limit cwitch control circuit LP 029 Testable Check Valve Limit switch lEZ-F006 LP 031 same as for LP 029 Power Feed to Motor LP 045 Check Valve Bypass Eq.
Limit switch No. LAP 503F INSTRUMENT LINE 1;0.
SYSTEM 1RHASAA 3/4 Residual Heat Removal 1RHA6AA 3/4 Residual Heat Removal IRRA1AA 3/4 Reactor Recirculation Pu=p 1A 1 RIB 2BA 3/4 Reactor Core Isolation Cooling 1 RIB 2AA 3/4 Reactor Core Isolation Cooling.
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