ML19326B664

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AO 50-313/74-11B:on 741107,reactor Bldg Spray Pump P35B Suction Line Leaked.Caused by Intergranular stress-assisted Corrosion Cracking.Cracked Sections of Piping Replaced
ML19326B664
Person / Time
Site: Arkansas Nuclear 
Issue date: 08/29/1975
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19326B653 List:
References
NUDOCS 8004170511
Download: ML19326B664 (4)


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I 1. ' Abnormal Occurrence Report No. 50-313/74-11B

2. Report Date: August 29, 1975 '3. Occurrence Date: November 7, 1974 4 ' Facility: 'Arkans'as Nuclear One-Unit 1 Russellville, Arkansas 1
5. Identification of Occurrence:

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Reactor Building Spray Pump P35B suction line leak.

6. Conditions Prior to Occurrence: --

Steady-State Power Reactor Power 0 MWth Ib t . Standby Net Output' 0 MWe Cold Shutdown X Percent of Full Power 0  %

4 Refueling Shutdown Load Changes During Routine

's Power Operation Routine Startup

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Operation -

Routine Shutdown (

Operation Other (specify)

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7. Description of Occurrence:

See Abnormal Occurrence Report No. 50-313/74-11.

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80041705'[f I

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ihrch 4, 1975 NSP-10, Rev. 2 Page 2 of 4 -

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Abnormal Occurrence Report No. S0-313/74-11B

8. Designation of Apparent Cause of Occurrence:

Design Procedure t'

thnufacture Unusual Service Condition Including Environmental Installation /

Construction Component Failure Operator Other (specify) X The apparent cause of the failure of the piping was intergranular stress-assisted corrosion cracking (IGSACC) . This was caused by a number of coexisting circumstances which were present in only Heat No. 800201 of the Schedule 10 stainle

exposed ends (i.e.10" crossover line).

The following action is to be undertaken in,the near future: ,

1) An upgraded surveillance program of both visual and volumetric examinations including:

a) Periodic walk-through examinations for leaks in areas con-

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taining pipe from Heat No. 800201 and the section of sensi-tized piping associated with Heat No. 2P-3352, to be gradually ,

phased out if no further leaks are found.

b) A volumetric inservice inspection program following the guide-lines of Article IWC-2000 of ASME Se'etion,XT 1974 edition (Table IWC-2520, CG) for piping systems containing material from Heat No. 800201 and the section of sensitized piping associated ~with Heat No. 2P-3352 will be performed until the results indicate that further inspection is no longer needed.

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2) A program of sampling and flushing of normally stagnant safety-related systems containing potentially corrosive chemical addi-tives.
3) An extensive study has been undertaken by Failure Analysis Associates for APSL' to show that a catastrophic failure will not result from a postulated crack in the Schedule 10 piping under >

design stresses.

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11. Failure Data:

See AOR 50-313/74-2 and 50-313/74-11. .

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'Narch.4, 1975 NSP-10, Rev. 2 Page 4 of 4

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