05000280/LER-1981-001-01, /01T-0:on 810225,w/unit Defueled for Steam Generator Replacement,Routine Testing Exam of Loop a Main Steam Piping Revealed Linear Indications.Caused by Corrosion Pitting.Subj Areas Will Be Repaired

/01T-0:on 810225,w/unit Defueled for Steam Generator Replacement,Routine Testing Exam of Loop a Main Steam Piping Revealed Linear Indications.Caused by Corrosion Pitting.Subj Areas Will Be Repaired

ML18139B171
Person / Time
Site:	Surry
Issue date:	03/11/1981
From:	Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139B170	List: 05000280/LER-1981-001, Forwards LER 81-001/01T-0 05000280/LER-1981-001-01, /01T-0:on 810225,w/unit Defueled for Steam Generator Replacement,Routine Testing Exam of Loop a Main Steam Piping Revealed Linear Indications.Caused by Corrosion Pitting.Subj Areas Will Be Repaired
References
LER-81-001-01T, LER-81-1-1T, NUDOCS 8103170585
Download: ML18139B171 (3)

LER-1981-001, /01T-0:on 810225,w/unit Defueled for Steam Generator Replacement,Routine Testing Exam of Loop a Main Steam Piping Revealed Linear Indications.Caused by Corrosion Pitting.Subj Areas Will Be Repaired

Event date:
Report date:
2801981001R01 - NRC Website

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LICENSEE EVENT REPORT LI.NUCLEAR REGULATORY COMMISSION CO\\'JTROL BLOCK:._I_...____.... _ _.___. _ _..____,! G) 1 6

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68 69 EVENT DATE 74 7S REPORT DATE 80 E:VE'\\IT DESCRIPTION AND PROBABLE CONSEQUENCES@

!With the unit defueled, RT examination of loops A, B, C, main steam piping.revealed C£::J]J !linear i~di~ations at the weld near the safety va~ve riser:

RT examination was

[]JI] !being conducted as *follow-up to the finding reported in LER 80-067/0lT-Oo This event!

C2:l}] jis reportable per T.S. 6~6.2.a.(9).

The indications found represent surface pitting

[)))) 1and were code allowable.

Therefore, the health and safety of the public were not [IT:] !affected.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

44 47 tfhe cause,appears to be a type of corrosion pitting usually associated with stagnant 0JJJ,oxygenated water. - ~he-subject_-areas w:t;n be r.epaired_pri)JtJ;o *startup Of the unit.

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J. L. Wilson (804) 357-3184 NAME::)!= OPEPARE=l-------~.:......--------

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f ;-*~ATTACHMENT 1, PAGE 1 OF 2.

SURRY POWER STATION, UNIT

! 1 e

DOCKET NO:

50-280 REPORT NO:

80-001/0lT-0 EVENT DATE:

02-25-81

/

TITLE OF EVENT:

MAIN STEAM PIPING DISCREPANCIES

1.

DESCRIPTION OF EVENT

With the unit defueled for steam generator replacement, RT examination of loop

'A' main steam piping revealed linear indications.

The indications are located in the vicinity of the welds that are adjacent to the safety valve riser stab-in.

The safety valve riser is located outside the containment.

The indications are in the lower third of the pipe's*circumference and at the transition of a counter bore.

RT examination was being conducted as a follow-up to the findings reported on Unit No. 1 LER 80-067/0lT~

Subsequent.RT examination of loops 'B' and 'C' main steam piping revealed similar indications at corresponding locations.

This event is being*reported pursuant. to Technical Specification 6.6.2.a.(9).

2.

PROBABLE CONSEQUENCES The indications found were allowable per ASME Section XI.

In addition, the indi-cations were substantially less than the critical flaw size as referenced in the FSAR, Appendix D.

Therefore, the health and safety of the public were not affected.

3.

CAUSE

4.

The cause appears to be a type of corrosion pitting usually associated with stagnant oxygenated water.

The "boat samples" were removed from A & C Main Steam piping and subjected to X-ray, macroscopic, and microscopic examination, revealing only corrosion pits and no cralking.

IMMEDIATE CORRECTIVE ACTION

The indications were verified by liquid penetrant examination.

5.

SUBSEQUENT CORRECTIVE ACTION:

The subject areas will be repaired prior to startup of the unit. Also, the shape of the counter-bore will be changed to reduce the stress in this area.

<:_:*,.:;-~so-'6*. *- ACTIONS TAKEN TO PREVENT RECURRENCE:

As noted above, the indications were within code allowable tolerances.

Routine surveillance as required by*T.S. 4.15" is considered adequate to detect problems in the future.

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-..... :ATTACHNENT 1, PAGE 2 OF 2-SURRY POWER STATION, UNIT NOo 1 DOCKET NO:

50-280 REPORT NO:

80-001/0lT-0

£VENT DATE 02-25-81 TITLE OF EVENT:

MAIN STEAM PIPING DISCREPANCIES

7.

GENERIC IMPLICATIONS:

e A special UT examination was conducted of the corresponding areas of main steam piping on Unit 2, while the unit was at power.

- The examination found no evidence of cracking or other significant indications that could be attributed to internal flaws.

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