ML20049A893
| ML20049A893 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/25/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, IEIN-81-08, IEIN-81-8, PLA-932, NUDOCS 8110020354 | |
| Download: ML20049A893 (2) | |
Text
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@ Pennsylvania Power & Light Company Two North Ninth Street
- Allentown, PA 18101 a 215177G5151 Cp-3?f r4-wr Norman W. Curtis Vice President-Engineering & Construction-Nuclear 215 / 770-5381 a
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A September 25, 1981
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Mr. R. C. Haynes UL,j 88 V
Director, Region I
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SUSQUEHANNA STEAM ELECTRIC STATION INTERIM REPORT OF A DEFICIENCY INVOLVING INADEQUATE LIMITORQUE OPERATOR PINION KEYS ERs 100450/100508 FILES 821-10/840-4 PLA-932
Reference:
NRC IE Information Notice #81-08
Dear Mr. Haynes:
This letter wrves to provide the Commission with an interim report of a deficiency relating to the use of type 1018 steel motor pinion keys on Litaitorque SMB 3, 4 and 5 valve operators. The deficiency was the subject of the referenced NRC I: formation Notice (#81-08), " Repetitive Failure of Limitorque SMB-4 Motor-To-Shaft Key" (The Notice incorrectly identifies the keys as being made of type 1010 steel).
Mr. A. Sabol of PP&L advised Mr. L. Narrow, NRC Region I, of the deficiency in a telephone conversation on August 17, 1981. This letter is submitted pursuant to the requirements of 10 CFR 50.55(e).
The failure of these keys, as mentioned in the notice, could have an adverse effect on valve operation of safety systems at Susquehanna SES.
The inadequate keys may be installed in Limitorque valve operators for the High Pressure Coolant Inspection i
and Residual Heat Removal System. Limitorque records do not indicate what type of steel was used on the SSES operator keys. Consequently, PP&L has concluded that the possible utilization of inadequate materials (type 1018 in lieu of 4140 or other more adequate steel) is a significant deficiency reportable in accordance with 10 CFR 50.55(e).
Rather than test the keys to determine if they are, in fact, inadequate as suggested in the notice, PP&L has decided to replace the keys in all SMB 3, 4 and 5 operators rated at 100 foot pounds t o greater. Bechtel Engineering has issued Design Control Request (DCR) #552 to effect the replacement of the indeterminate keys provided
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'8110020354 810925 DR ADOCK 05000387 PDR
o Mr. R. C. Haynes September 25, 1981 under the Bechtel scope of supply. General Electric and PP&L will be responsible for insuring corrective action for valves un er their responsibility. A final report will be issued upon finalization of the corrective action plans and will be provided prior to January 1982.
Very truly yours, f
9 N. W. Curtis Vice President-Engineering & Construction-Nuclear FLW:sab cc:
Mr. Victor Stello (15)
Director-Office of Inspection & Enforcement U.
S. Nuclear Regulatory Commission Washington, D.C.
20555 Mr. G. Mcdonald, Director (1)
Office of Management Information & Program Control U. S. huclear Regulatory Commission Washington, D.C. 20555 Mr. Gary Rhoads U. S. Nuclear Regulatory Commission P.O. Box 52 Shickshinny, PA 18655
,