ML20248D421

Suppls 881004 Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. NDE Confirmed That No Existing Flaws Exist in Critical Piping Locations Re Thermal Stratification

ML20248D421
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/27/1989
From:	Cockfield D PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-88-008, IEB-88-8, NUDOCS 8910040249
Download: ML20248D421 (5)

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- David W. Cockfield Vice President, Nuclear September 27, 1989 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555

Dear Sirs:

Nuclear Regulatory Commisrion (NRC) Bulletin 88-08, Thermal Stresses in-Pipinr, Connected to Reactor Coolant Systems Portland General Electric Company (PCE) responded to NRC Bulletin 88-08 by letter, dated October 4, 1988. .In our response we noted two unfinished items whose future completion would be reported to you. The attachment provides the details of the completion of nondestructive examinations to provide assurance that there are no existing flaws in critical piping.

locations with respect to thermal stratification. It also provides the current status of the implementation of a program to provide continuing assurance that adverse temperature distributions are not occurring.

l 8910040249 890927 PDR ADDCK 05000344 I th G PNU , 'g 121 S W Sa!rnon Street. Ponand. Oregon 97204 En__________.

W Genetid MC0s:ptsif Document Control Desk September _ 27,'1989 Page 2 We would be pleased to discuss any questions or comments you have regarding this letter.

Sincerely,

- /

Attachment c: .Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. David Stewart-Smith State of Oregon Department of Energy Mr. R. C. Barr NRC Resident Inspector

. Trojan Nuclear Plant Subscribed and sworn to before me this 27th day of September 1989.

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[ Notary blic'gf Oregon My Commission Expires: _

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Trojan Nuc10Cr Pltnt Document C:ntrol Deck Docket 50-344 Septeniber 27, 1989 License NPF-1 Attachment Page 1 of 3 l Portland General Electric Coirpany (PGE) l Status of Outstanding Actions for Nuclear Regulatory 1

Commission Bulletin 88-08 One outstanding item was to complete Requested Action 2 of the Bulletin by nondestructively examining welds, heat-affected zones, and high-stress locations in any unisolable sections of the pressurizer auxiliary spray line that may have been subjected to excessive thermal stresses, to provide assurance that there are no existing flaws. During the 1989 Refueling Outage.

-dye penetrant tests (pts) and ultrasonic tests (UTs) were performed at the critical inspection locations shown in Figure 1. The examinations revealed no cracks are present. PGE action for Requested Action 2 is complete with no cracks having been found in the critical locations of the pressurizer auxiliary spray line or the safety injection and charging lines as previously reported in our October 4, 1988 response to the Bulletin.

The second item, which was in response to Requested Action 3 of the Bulletin, was to plan and implement a program to provide continuing assurance that adverse temperature distributions are not occurring. PCE reported in our October 4, 1988 response to the Bulletin that thermal monitoring data from the safety injection and charging lines had been transmitted to our Nuclear Steam Supply System (NSSS) vendor for formal evaluation, and that we would evaluate what further actions were required based on the final conclusions of this data review. Although the data review by the NSSS vendor was completed, the results indicated that additional thermal monitoring and analyses would be required before final conclusions could be reached. The analyses of additional thermal monitoring data taken during the startup from the 1989 Refueling Outage are expected to be complete by March 1990. PGE will report the results of the analyses and any plans to implement further corrective actions to assure that no adverse temperature distributions are occurring by May 31, 1990.

The NSSS vendor's analysis of the original thermal monitoring data did indicate that there is leakage into the common safety injection header, which is resulting in thermal stratification in the safety injection lines at very limited times when the in-leakage apparently initiates or terminates, or when safety injection occurs. High-cycle fatigue fluctuations have not been observed and are not expected to occur. As shown in Figure 2, the 1-inch Boron Injection Tank (BIT) bypass line was capped during the 1989 Refueling Outage to eliminate one of the potential leakage paths into the safety injection common header.

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.  : Docket 50-344 Docunsnt Control D2sk September 27, 1989 Licensa NPF-1 Attachmsnt

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