ML20039E005
| ML20039E005 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 12/22/1981 |
| From: | Jackie Cook CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20039E006 | List: |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 15361, NUDOCS 8201060424 | |
| Download: ML20039E005 (2) | |
Text
Consumers Power James W Cook Vice President - Projects Engineering and Construction General offices: 1945 West Pa.. alt Road, Jackson, MI 49201 + (517) 788 0453 p
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]pIs December 22, 1981 9/D l.m a0 I
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j Mr J G Keppler, Regional Director XWT Office of Inspection and Enforcement ypg US Nuclear Regulatory Commission 3
.e Region III sV 799 Roosevelt Road W
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Glen Ellyn, IL 60137 j
MIDLAND PROJECT -
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MIDLAND DOCKET NOS 50-329, 50-330 F"
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.m UNIT NO 1, REACTOR VESSEL BROKEN ANCHOR BOLT -
j fQs FILE 0.4.9.35 SERIAL 15361 x
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REFERENCES 1.
CONSUMERS POWER LETTERS TO J G KEPPLER, SAME SUBJECT' a.
SERIAL 15035 DATED NOVEMBER 23, 1981 b.
SERIAL 14625 DATED DECEMBER 1, 1981 ENCLOSURE Report entitled, " Reactor Pressure Vessel Support Modification for Midland Nuclear Power Plant, Midland, Michigan, Report No 3", Revision 1, dated December 1981.
Reference 1.a was an Interim 50.55(e) report transmitting the updated technical report describing the reactor support modification, the schedule for accomplishment of that modification and the description of the analytical techniques being used, and Reference 1.b was the Final 50.55(e) report.
The two enclosures to Reference 1.a, " Reactor Pressure Vessel Support Modification for Midland Nuclear Power Plant, Midland, Michigan, Report No 3" and " Letter Report - Teledyne Engineering Services (TES) Project 5355:
Expanded Criteria for Acceptability for Service of Midland Unit 1 RV Anchor Stress", were discussed in detail with the NRC Staff in Betheda on December 2 and 3, 1981. During that meeting, the staff requested certain clarifications and supportive material.
The enclosed report to this letter which is Revision 1 to the previous Report No 3 has been revised to incorporate Staff comments and in addition includes some minor text correction of an editorial nature. The revisions to the enclosed report are indicated in the right-hand margin.
This letter and its enclosed report is intended to comprise a complete and current package of documentation describing the design concept, the analytical techniques to be used and the completion schedule for the modification of the oc1181-0965a141 8201060424 311222 PDR ADOCK 05000329 6
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SERIAL 15361 2
reactor vessel support system. Upon completion of this task, the final designs and analytical results will be reported in the FSAR.
JWC/BFH/mo CC Director of Office of Inspection & Enforc ment (15)
Director, Office of Management, Information and Program Control (1)
Atomic Safety and Licensing Appeal Board CBechhoefer, ASLB w/o MMCherry, Esq RJCook, Midland Resident Inspector FPCowan, ASLB w/o RSDecker, ASLB w/o HDenton, NRC (5)
SHFreeman, Esq, l._
't attorney General w/o JHarbour, ASLB w/o DSHood, NRC (2)
FJKelley, Esq, Attorney General w/o WHMarshall WDPaton, Esq w/o MSinclair w/o GTTaylor, Esq, Ass't Attorney General w/o l
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