ML20024G645

Advises That Reinsp of Hydraulic Shock Suppressors Completed During Scheduled Outage on 731114-17

ML20024G645
Person / Time
Site:	Monticello
Issue date:	11/30/1973
From:	Mayer L NORTHERN STATES POWER CO.
To:	Skovholt D US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9102140357
Download: ML20024G645 (4)

Text

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• - 4egulatory Docket Re NSys NORTHERN STATES POWER COMPANY MIN N E A PO Lf t. MIN N E GOTA 98401 g

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November 30, 1973 O

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DE03 t973, 1 NO$ jg7 Mr. D. J. Skovholt Assistant Director for i%

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Dear Mr. Skovholt:

MONTICELLO NUCLEAR GENERATING PIANT Docket No. 50-263 License No. DPR-22 Hydraulic Shock Suppressors and Restraints Re-inspection of hydraulic shock suppressors at the Monticello Nuclear Ca.nerating Plant was completed during a scheduled cutage November 14 through November 17, 1973.

Inspection results, corrective measures, and other inforcation requested in your letter to Mr. L 0 Mayer, dated October 1, 1973, are contained in this report.

All shock suppressor units located outside primary containment have been in-spected biweekly since aur October 9, 1973 report. All units within the primary containment were reinspected November 14, 1973.

There inspections identified no indications of inoperability or loss of oil from any of the units.

As of our October 9,1973 report all units within the primary containment

( dr/well ) had been rebuilt using vendor supplied materials which included seal materials other than ethylene propylene.

During this November 14-17, 1973 outage, all units within the drywell were again rebuilt to provido exclusivnly ethylene propylene for all internal sof t parts. Additionally the oil-fill fittings were replaced with high-temperature, high pressure leakproof fittings ci having Buna-N seats.

Internal soft parts from the units rebuilt this outage were inspected and found to be free of any indication of deterioration.

Parts unknown to be of Buna-N inaterial experienced uo deterioration in the several months service since installation and in this regard the replacement oil-fill fittings are believed to be compatible with the service of this application.

Several units within the drywell were previously equipped with TLD's and the radiation dosage determined. Additionally, four units were recently provided with thermocouples and nine others with temperature indicating tape to provide a measure of the temperature environment. Initial values of these parameters are included in the attached Table I - Radiation and Temperature Measurements for Hydraulic Shock Suppressors.

9102140337 731130 DR ADOCK 05000263 8.7SS PDR

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NOI HERN GTATED POWER Cs IPANY s.

2-ne corrective actions impicmented this outage in conjunction with the results of surveillance inspections to date are believed to provide a reasonable basis for continued operation to the 1974 sprink tofueling outage.

he surveillance inspection of units located outside the primary containment will be continued on a monthly basis and all shock suppressors within the drywell will be inspected during the 1974 spring refueling outage. During this interira period of operation those units within the drywell will be inspected only during scheduled or unscheduled outages for which drywell entry may be required for other purposes. Additionally, those units outside the drywell will be rebuilt on an individual basis, as feasible, to provide ethylene propylene internal parts.

It is anticipated that all units outside the drywell will have been rebuilt by the conclusion of the refueling outage.

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Yours very truly, L 0 Mayer, PE Director of Nuclear Support Services LW/1h cc:

J G Kcppler G Charnoff Minnesota Pollution Control Agency Attn. K Dzugan

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TABLE I - Radiation and Temperature f.basurements for ifydraulic Shock Suppressors_

UNIT IDCATION RADIATION DOSE (RBf) IVR A FORIY-NIhli DAY PERIOD SS-1 DRYWELL M\\INSTEAM 953' 6,234 SS-4BR DRYWELL RECIPE 934' 40,471 SS-5AR DRWELL RECIRC 941' 2,028 UNIT IDCATION TDIPERATURE (*F) AT 95 PERCENT POER SS-1 DRWELL M\\INSTEAM 953' 109 SS-1BR DRWELL RECIRC 922' 104 SS-3 DRWELL MilNSTFIM 950' 118 SS-20 DRWELL RilR 964' 98 I

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AEC__ D"TR2 BUTION FOR PART 50 DOCKET MA'*RI AL (TEMPORARY FORM)

CONTROL NO:

8588 FILE:

FROM:

DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Northern States Power Company Minneapolis, Minnesota 55401 11-30-73 12-3-73 X

L. O. Mayer j

10:

OR*.G CC

'OTHER SENT AEC PDR X

D. J. Skovholt i signed SENT LOCAL PDR X

CLASS UNCLASS PROP INFO INPUT NO C1S REC'D DOCKET NO:

XXXX 40 50-263 DESCRIPTION:

ENCLOSURES:

Ltr re our 10-1-73 ltr,..... furnishing inspect ion results, corrective measures and info reque

sted,

Mi 'td "* """!!'. $ '! '"""" " '"' ""

ACKNOWLEDGED hD0 NOT REMOVE I

PLANT NAME: Monticello FOR ACTION /INFORMATION 12-3-7 W,

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MORRIS LAINAS STEELE BEHAROYA HARLESS VOLINER EXTERNAL DISTRIBUTION 9/3 4 - LOCAL PDR _ Hinneapolis. Minn._

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