ML20053A265
| ML20053A265 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 05/17/1982 |
| From: | Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20053A266 | List: |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 17354, 80-09-#6, 80-9-#6, NUDOCS 8205250155 | |
| Download: ML20053A265 (2) | |
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CORSum8f5 POW 8r James W Cook C0mpany vic, r,,,is t - r,.i.ct,, s.si..i.,
a.J Co.,t,uctio.
d G*a* o ffices: 945 West Pernell Road, Jackson, MI 49201 * (517) 788 0453 80-09 #6 May 17, 1982 i
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Mr J G Keppler, Regional Administrator US Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 MIDLAND PROJECT - UNITS 1 AND 2 DOCKET NOS 50-329 AND 50-330 LOW ALLOY QUENCHED AND TEMPERED BOLTING 1 INCHES 4
AND GREATER IN SUPPORT OF SAFETY RELATED SYSTEMS -
FILE 0.4.9.45 SERIAL 17354 REFERENCE J W Cook letters to J G Keppler, Same
Subject:
(1) Serial 10996, dated January 9, 1981
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(2) Serial 11526, dated March 31, 1981 (3) Serial 13690, dated September 29, 1981 (4) Serial 14666, dated January 15, 1982 j
(5) Serial 16149, dated April 2, 1982 i
This letter, as were the referenced letters, is an interim 50.55(e) report concerning the subject bolting. Enclosure 1 is an APTECH Engineering Services Report which defines allowable loadings for the Reactor Coolant Pump Snubber Anchor Bolting.
1 Evaluation of the acceptability of the installed Reactor Coolant Pump Snubber Anchor Bolts will require comparison of the allowable stresses from the enclosed report to either the stresses which can be experienced by the bolts when the snubbers are loaded to their maximum capacities or by the anticipated accident snubber loads. The results of this comparison will be provided in a j
future 50.55(e) report.
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l Since the enclosed report establishes a preload allowable stress of 50.0 ksi as the lowest allowable preload for all heats of snubber anchor bolts and since this allowable preload is well above the 12 ksi (9 + 3 ksi) design specified preload for the studs, no further evaluation of preload is anticipated for the studs.
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oc0582-2031a141
'MAY 19 1982 4
8205250155 820517 L
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SERIAL 17354 80-09 #6 Another report, either interim or final, will be sent on or before July 9, 1982.
puv.s
^r$fe llSG/cl APTECll Engineering Services Report #AES-81-08-79, " Assessment of Stud Integrity for the Reactor Coolant Pump Snubber Anchor Bolting," dated May 1982.
CC RJCook, NRC Resident Inspector (w/ enc)
Midland Nuclear Plant llRDenton, NRC (w/ enc)
Office of NRR Document Control Desk, NRC (W/ enc)
Washington, DC CBechhoefer, ASLB Panel (w/o enc)
RSDecker, ASLB Panel (w/o ene)
FPCowan, ASLB Panel (w/o enc)
Jilarbour, ASLB Panel (w/o enc)
AS&L Appeal Panel (w/o enc)
MMCherry, Esq (w/o ene)
MSinclair (w/o enc)
BStamiris (w/o enc)
CRStephens, USNRC (w/o enc)
WDPaton, Esq, USNRC (w/o enc)
FJKelley, Esq, Attorney General (w/o enc)
SIIFreeman, Esq, Asst Attorney General (w/o enc)
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WilMa rshall, (w/o enc)
GJMerritt, Esq, TNK&J (w/o enc) oc0582-2031a141
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