ML20210T900

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Forwards Request for Relief from Inservice Insp Requirement of Section XI of ASME Boiler & Pressure Vessel Code.Request Applicable to First 10-yr Interval Extended Through 1987 Refueling Outage.Fee Paid
ML20210T900
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 02/11/1987
From: Cockfield D
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TAC-64648, NUDOCS 8702180338
Download: ML20210T900 (3)


Text

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David W. Cockfield Vice President, Nuclear February 11, 1987 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555

Dear Sir:

Inservice Inspection Relief Request In accordance with the provisions of 10 CFR 50.55a(g), the attached request for relief from an inservice inspection (ISI) requirement of Section XI (1974 Edition with Summer 1975 Addenda) of the ASME Boiler and Pressure Vessel Code is submitted for your review and approval. The relief request is applicable to the first 10-year interval which has been extended throui;h the 1987 refueling outage.

In accordance with 10 CFR 170, an application fee of $150 is attached.

This relief request is similar to that approved for Unit 2 of the Zion Nuclear Plant on February 11, 1986, and that submitted for Unit 2 of the Diablo Canyon Nuclear Plant on January 26, 1987. Both of these nuclear plants have designs similar to Trojan.

Sincerely, Attachment c:

Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Rob Barr NRC Resident Inspector Trojan Nuclear Plant Mr. David Kish, Acting Director State of Oregon Department of Energy

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License NPF-1 Attachment

.Page 1 of 2 INSERVICE INSPECTION (ISI) RELIEF REOUEST Code Requirement Item B2.2 of Table IWB-2600 of ASME Section II, 1974 Edition through Summer 1975 Addenda, requires a 100 percent volumetric examination of the pressurizer surge line nozzle-to-vessel weld and nozzle-to-vessel inner radius section. These examinations are to be performed once during the inspection interval.

Code Daviation Request Relief is requested to perform a partial (approximately 30 percent) volumetric examination of the pressurizer surge line nozzle-to-vessel weld and nozzle-to-vessel inner radius section during the first 10-year inspection interval.

Basis for Relief The original design of the pressurizer does not permit sufficient access to inspect the areas required by Figure IWB-2500D of the Code. The configuration of the pressurizer surge line nozzle and pressurizer-heater.

cable penetrations is such that access to the weld and inner radius are restricted (see Figure B2.2 attached). The nozzle and heater cable penetrations interfere with the positioning of the ultrasonic transducer, preventing a thorough examination. Approximately 70 percent'of the required volume cannot be examined to code requirements.

In view of the restricted access, it is impractical (ie, physically impossible) to perform an ultrasonic examination of 100 percent of the weld. Use of radiography was considered and also determined to be impractical because either the source or film would have to be inserted inside the pressur-izer for which access is difficult and personnel exposures would be unacceptable. It is also not practical to modify this configuration to permit a greater percentage of the volume to be examined.

Alternative Examination A volumetric examination will be performed of the accessible. volume. The results of this examination will be compared to the baseline examination" results. The baseline examination was also a partial examination in which no indications were observed.

In addition, the subject area was visually examined during performance of the first 10-year system hydrostatic pressure. test which was conducted in 1985.

SAB/kal 1431W.187

Trojan Nuclear Plant Document Control Desk Docket 50-344 February 11, 1987 License NPF-1 Attachment Page 2 of 2 FIGURE B2.2

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