ML19210C870

Submits Followup to 791019 Rept of Inadequate Pipe Restraint on Spent Fuel Pool Cooling Sys.Plant Presently in Cold Shutdown.Will Complete Corrective Action Before Mode Change

ML19210C870
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	10/22/1979
From:	Yundt C PORTLAND GENERAL ELECTRIC CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML19210C865	List: ML19210C864 ML19210C867 ML19210C870 ML19210C876
References
CPY-450-79, TAC-12369, NUDOCS 7911200240
Download: ML19210C870 (1)

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October 22, 1979 CPY-45 &79 Mr. R. H. Engelken, Director US Nuclear Regulatory Commission 1990 North California Blvd.

k*ainut Creek, CA 94596

Dear Sir:

f This letter is a follow-up to a report made by F. H. latmoureaux, Assis-tant' General Manager, to M. Malmros, KRC Resident Inspector, at 7 : 00 P.

on Friday October 19, 1979, concerning a situation where, in perfor=ing an inspection pursuant to IE Bulletin 79-02, ve found a pipe restraint on the spent fuel pool cooling system that was inadequate to support the loading experienced during a Safe Shutdown Earthquake.

Ttte failure of this support could result in exceeding yield stress in the common suction line from the normal residual heat removal letdown path.

This vould result in the loss of capability of both residual heat terraval pumps from taking suction from the reactor coolant system and the refueling vater

~ torage tank.

a This discovery was made at the same time as inspections were bein5 per-formed in accordance with IE Bulletin 79-14.

It was ascen:rined that other piping restraints on the same wall could potentially fail.

Ienediate in-spections were implemented to investigate any similar support problems in the facility.

The plant in presently in cold shutdown (Mode 5).

Procedures have been instituted which vill maintain the reactor core cool in the event of a Safe Shutdova Earthquake and consequent loss of the subject line.

For equipment and systems that are requited by the tecnnical specifications to be operable for each mode, we vill ensure that corrective action is completed before auch mode change is tede.

This occurrence vill be reported to the Nuclear Regulatory Comission as a licetmea event report in accordance with our established technical specifica tions.

Sincerely, E"

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t"-C. P. Yundt Ceneral Manager 1363 304 CPY/CG:eb O

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UNITED sTA(Es CO

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NUCLEAR REGULA TORY COMMISSION

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SislTE 202. WALNUT CAEEK PLAZA s,g, WALNU( c,'4 EEK. CALIFORNIA 94593 October 22, 1979 Docket No. 50-344 m

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D,n a Portland General Electric Company q

121 5. W. Salmon Street oe W

Portland, Oregon 97204 Attention:

Mr. Charles Goodwin, Jr.

Assistant Vice President Gentlemen:

This letter relates to the steam generator tube defects and the concrete block wall-pipe hanger structural problems discussed by telephone between Mr. W. J.

Lindblad and others of your staf f and Mr. J. L. Crews of this office and other.'IRC personnel on October 22, 1979 Based on this discussion, it is our understanding that you are to take the following actions:

1.

Prior to plugging the leaking tubes in the "A" and "D" steam generators, you will provide the NRC with the results of your investigation to determine the cause(s) of the defects identified.

2.

Prior to the resumption of power operation, you will provide the NRC with your basis for concluding that operation of the plant relative to the steam generators can be safely resumed.

3.

You will complete an evaluation of all safety related pipe supports and restraints which are anchored in concrete block walls similar to RHR restaint No. 83 reported by you as being defective on October 19, 1979.

The purpose of this evaluation is to determine if any additional piping supports or restraints are not adequate to meet design basis conditions.

4.

Prior to resuming reactor power operation, you will provide the NRC with written confirmation that the evaluation of item 3 above has been completed, and that any necessary modifications and/or repairs have been satisfactorily completed.

Should our understanding as stated above not be correct, you should notify this office promptly in writing.

Sincerely, 1363 305 pas..A R. H. EngelF.en Director p//()

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DIVISION OF REAC10R DAILY EFURT%s_

ON V

.t OPERATIONS INSPECTION DATE 10/23/79

/ACILITY NOTIFICATION ITEH OR EVENT REGIONAL ACTIUN p0RTLAND GENERAL lELEPHONE CALL UPDATE UN PNU-V=79-S DATED 10/19/798 THE AN IMMEDIATE ACIIu

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ELECTRIC CO.

FROH LICENSEE UN LICENSEE HAS C0f1HENCEn FABRICATION OF HUDIFIED WAS THANSMIIILD 1U T OJAN 10/22/79 PIPE RESTRAINT SUPPORTS FOR THE RHR SUCTION LICENSEE uY'viGION

,R nN S0=344 LINE.

ADDITigNAL EVALUATION OF SIMILAR WALLS 10/22/79, id13'LL AND SUPPORTS IS UNDERWAY AND SHOULD HL CONF IHHS IHL LICEN COMPLEILD itY 10/29/19, THE FINAL PREPARATION CUMMIIHtNi TU Ph0V TO PLUG THE LEAKING TUBES IN THE

'A" AND "D" NdC INFORMAr!UN ht STEAH GENERATORS HAS BEEN COMPLETED..THE Tu THE FIPE'Nt3lHk LICENSEE DILL PROVIDE TEST RESULTS TO NRC PROBLEH'AND THE Si PRIOR 10 COMMENCING PLUGGING OPERATIONS.

THE GENtHATUR' TUBE AN9 LICENSEE HAS CONDUCTED E00Y CURRENT TESTING' PRIOR TU HESUNING AND HAS ATTEMPTED iti MEASURE THE OVALITY OF OPEHAlluN.'

THE TullLS USI JG A SPHERICAL GAUGE SETUP.

RESULT 3 HAVE tlFCN i tJC ONC L USI V E TO D ATt,

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