ML20062G230
| ML20062G230 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 12/15/1978 |
| From: | Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| References | |
| HOWE-265-78, NUDOCS 7812270184 | |
| Download: ML20062G230 (3) | |
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[**.. 0i Stephen H. Howell q/
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- a. w.mo.a a:oi. csi7> 7as-o4s3 December 15, 1978 ncue-265-78 1fr J G Eeppler, Regional Director Office of Inspectien end Enforce ent US ::uclear Regulatory C==ission Eecien III r
799 Pcosevelt acad Glen Ellyn, II, 60137
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U'll? ::01, ICCIIT -
50-329 U' LIT ::0 2, ICCIIT : 0 5,,_ s PIAC':'C3 SJII.DI::G SPPAY PIPII:G 5UFFO:iTS
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Ecrerence: G H Ecuell letters to J G I:eppler; Midicnd :!uclear Plant; Unit ::o 1, Docket I:o 50-329; Unit No 2, Locket I:o 50-330; Reactor Eu11 ding Spray Piping Supports -
- 1) Serial Hove-c0-78, dated April 19, 1978
- 2) Serial Ecve-92-73, dated June 13, 1978
- 3) Serial :Icue-15!.-73 dated August 30, 1978 h) Serial Have-186-78, dated October 13, 1978
- 5) Scrial Hove-231-73, dated I!ovember 10, 1976 The referenced letters ard this letter are interin recorts. Attachment 1 previaes the status of the analy:is being conducted to resolve the questien of the adequacy cf the recctor building cpray pipinC cuppc~.s relt.tive to the /.372 3ection III Code allowable stress requirements.
Another report, either interim or final, vill be sent on er before February 1,1979 7,
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Atta:inent:
(1) ItCAR-22, Interi Repcrt #9, dated December 11, 1978.
CC: Director of Office of Inspecticn & Enforcement Att:
tr Jchn G Davis, Acting Director, U3::3C (15)
Director of Offica of ::anagenent q \\g In!cr:stien a Progrca Control, US::RC (1)
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781227013(
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Attechment U newe-265-78 Bechtel Associates ProfessionalCorporation f
Attachment to BLC-6900 i
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SUBJECT:
!! CAR #22' (Issued 3/21/78)
INTERIM REPORT #9 DATE:
December 11, 1978 4
PROJECT:
Consumers Power Company Midland Plant Units 1 & 2 Bechtel Job 7220 i
On the basis of recent results, it appears that our evaluation will be ~
that the reactor building spray anchors and system piping can be utilized i-as-is, without adverse effect upon the nuclear safety of the Midland-1 Plant, Units 1 and 2.
Status of Corrective Action and Investigation Earlier, because of the conservatism in the input data, the stipulation was that if the water hammer loads were calculated to be high, the j
actual time-history water ha=mer loading curves for the' piping.could be j
utilized for stress analyses. However, ITT Grinnell has verbally reported.
that analysis of the piping system anchors has shown that allowable j
stresses are not exceeded.
I Bechtel has completed analysis of the anchor-to-pipe veld for the maximum' water hammer forces using the stress intensification factor for an 1
unreinforced branch and has found that the stresses in the piping system are below the faulted allowable stresses, in accordance with ASMI Section III, Class 2.
I Forecast Dato for Investigation and Corrective Action A final report is scheduled for completion by January 19, 1979, 2
Submitted by:
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Apnreved by:CE$bthD rw' Concurrence by:
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