05000344/LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Encl

Forwards LER 81-011/03L-0.Detailed Event Analysis Encl

ML20030B259
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/23/1981
From:	Yundt C PORTLAND GENERAL ELECTRIC CO.
To:	Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20030B260	List: 05000344/LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Encl 05000344/LER-1981-011-03, /03L-0:on 810629,local Leak Rate Testing Results Showed That Cumulative Leakage Through Type C Containment Valves Exceeded Sts.Causes & Corrective Actions Stated in Table 1.Valves Repaired & Retested Prior to Plant Heatup
References
CPY-506-81, NUDOCS 8108060262
Download: ML20030B259 (3)

LER-1981-011, Forwards LER 81-011/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3441981011R00 - NRC Website

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.. kf((A Portland General Electric Company [yg Trojan Nuclear Plant J[j[ p7 gg P.O. Box 439

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Mr. R. H. Engelken, Director

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1990 North California Boulevard N

Walnut Creek, CA 94596

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Dear Sir:

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f The enclosed Licensee Event Report No. 81-11, concerning results of Centainment Local Leak Rate Testing, is provided pursuant to the Trojan Plant Operating License, Appendix A, US NRC Technical Specifications, Paragraph 3.6.1.2.

Sincerely, G4VM C. P. Yundt I

General Manager CP CGB:mae Attachments c:

LER Distribution List I

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8108060262 g h 4 PDR ADOCK PDR S

REPORTABLE OCCURRENCE 1.

Report No.:

81-11 2.

a.

Report Date:

July 23, 1981 b.

Occurrence Date: June 29, 1981 3.

Facility: Trojan Nuclear Plant, P.O. Box 439, Rainier, OR 97048 4.

Identification of Occurrence:

The cumulative leakage through Type C Containment valves measured during periodic local leak rate testing exceeded the Standard Tech-r' cal Specification limit.

5.

Conditions Prior to Occurrence:

The plant was in Mode 5, cold shutdown.

6.

Description of Occurrence:

Local leak rate testing (LLRT) was being conducted to verify the in-tegrity of Containment Type B and C penetrations. The LLRT equipment has a maximum flow indication of 11,000 cc/ minute, therefore, any leakage above 11,000 cc/ minute could not be quantitavely determined.

Three valves had leakage greater than 11,000 cc/ minute. As a result, cumulative leakage exceeded the Standard Technical Specification limit of 23,615 cc/ minute.

7.

Designation of Apparent Cause of Occurrence:

See Table 1 for pertinent data.

8.

Analysis of Occurrence:

This event had no effect on either plant or public safety since re-dundant valves in the affected penetrations did not exceed leakage limits. All valves were repaired prior to plant startup.

9.

Corrective Action

Each valve was repaired prior to plant heatup. All valves were then retested and found to be within acceptable limits. Table 1 delineates repairs and final leakage after retesting.

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TABLE 1 PENETRATION VALVE INITIAL LEAKAGE FINAL LEAKAGE NUMBER SYSTEM NUMBER LEAKAGE CAUSE REPAIRS CC/ MINUTE CC/ MINUTE P-57-2 Chill Water Return CV-10014 Pitted Seat Replaced Seat

>11,000 0

P-51 Recirculation Sump M0-2069A Grit on Seat Cleaned Seat 3,500 5

Suction P-50 Recirculation Sump MO-2069B Grit on Seat Cleaned Seat 7,200 802 Suction V-18 Containment Purge MO-10002 Limit Switch Setting Adjusted

> 11,000 99.8 Drifted Actuator Limit Switch V-19-1 Containment Arnos-MO-5673 Pitted Seat Lapped Seat 8,000 1,400 phere Sample P-56-1 Containment Atmos-MO-5674 Pitted Seat Lapped Seat 7,500 0

phere Sample P-58 Demineralized Water Check Pitted Seat Lapped Seat

>11,000 70.2 Valve