ML18029A618

Responds to 850618 Request Re Pipe Insp Results & Corrective Actions for Use in Briefing Commission on Status of Pipe Insps.Final Rept Will Be Submitted at Later Date

ML18029A618
Person / Time
Site:	Browns Ferry
Issue date:	06/27/1985
From:	Mccloud D TENNESSEE VALLEY AUTHORITY
To:	Vassallo D Office of Nuclear Reactor Regulation
References
GL-84-07, GL-84-11, GL-84-7, TAC-55590, TAC-55591, TAC-55592, NUDOCS 8507020526
Download: ML18029A618 (26)

Text

1 REOULATOR1NFORMATION DISTRISUTION SOl'EM (RIDS)

ACCESSION NBR:8507020526'OC,DATE:

85/06/27 NOTARIZED; YES, DOCKET FACIL:50 260 Browns Ferry Nuc,lebr Power Stationi Unit 2i Tennessee-05000260 AUTH INANE AUTHOR AFFILIATION MCCLOUDrD ~ ED Tennessee'alley Authority RECIP ~ NAHE'ECIPIENT AFFILIATION VASSALLOiD,BE Operating Reactors Branch 2'UBJECT:

Responds to 850618 request pipe" jnsp results L corrective actions for use,'n briefing Commission on status of pipe insps.Final rept will be submited at later date, DISTRIBUTIoN CODEX'001D COPIES RECEIVED:LTR

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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II June 27, 1985 Director of Nuclear Reactor Regulation Attention:

Mr. Domenic B. Vassallo, Chief Operating Reactor Branch No.

2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Vassallo:

In the Matter of the Tennessee Valley Authority Docket Nos. 50-259 50-260 50-296 In a telephone conference call on June 18,

1985, we informed members of the NRC staff of the indications found during pipe inspections and proposed disposition of those indications on the Browns Ferxy Nuclear Plant unit 2.

During that telephone conference the NRC staff indicated that it will be briefing the Commission on the status of pipe inspections and requested that the information on Browns Ferry unit 2 be provided to NRC.

In response to that xequest, we are submitting as an enclosure the unit 2 pipe inspection results and corrective actions discussed by telephone.

The purpose of this information is for use in briefing the Commission.

A final report documenting all unit 2 pipe inspections and results will be prepared and submitted to NRC later.

If you have any questions, please get in touch with us through the Browns Ferry Project Manager.

Very truly yours, TENNESSEE VALLEY AUTHORITY E. McCloud Nuclear Engineer Sworn to a~ subscr b d before me this ~9~~ day of 1985 Nota Public My Commission Expires cc:

See page 2

8507020526 850627 PDR ADOCN, 05000260 PDR An Equal Opportunity Employer

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Director of Nuclear Reactor Regulation June 27, 1985 cc (Enclosure):

U.S. Nuclear Regulatory Commission Region II Attn:

Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NM, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Project Manager Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue

Bethesda, Maryland 20814

ENCLOSURE PIPE INSPECTION RESULTS AND CORRECTIVE ACTIONS BROWNS FERRY NUCLEAR PLANT UNIT 2 The following is an outline of the attached information which was provided verbally to NRC in the June 18, 1985 telephone conference call.

o Descriptions of ISI findings following inspection of 100 percent of inspectable welds; nine welds were discussed (KR-2-14, 36, 37, 41; GR-2-15; DRWC-2-4; DSRHR-2-SA; and JP-2-1A, 1B).

Attachment 1 describes seven of these welds, the indications, and our disposition of these indications.

o Attachments 2 and 3 are the pre-and post-IHSI information sheets, respectively, which describe in detail the indications noted on welds KR-2-14, 36, 37, and 41.

o Attachment 4 describes weld DRWC-2-4 which will be removed from service and replaced during this outage.

o Recirculation system weld GR-2-15 was also discussed in the June 18, 1985 telephone conference call.

This weld was found to be leaking from a pinhole at the toe of the weld on the fitting side.

This fitting side of the weld was considered uninspectable by ultrasonic.

Leakage was noted following IHSI treatment.

Attachment 5 shows a drawing of the overlay that is being applied to this weld for an interim repair.

A slag or lack of fusion defect was noted in RHR system weld DSRHR-2-5A.

Information on this weld has been provided informally to NRR earlier.

However, since our telephone conference, an additional area, probably another lack of fusion type defect has been noted.

We will perform additional evaluation and communicate our disposition of this weld to you at a later date.

ATTACHHENT 1 Browns Ferry Nuclear Plant Unit 2 EOC5 Outage IGSCC IGSCC Degraded Welds (Total of 7)

JP-2-1A JP-2-1B DRWC-2-4 KR-2-14 KR<<2-36 KR-2-37 KR-2-41 (4-inch safe end and 4

X 8-in'ch reducer)

(4-inch safe end and 4 X8-inch reducer)

(6-inch isolatable pipe)

(sweepolet in 22-inch ring header)

(sweepolet in 22-inch ring header)

(end cap in 22-inch ring header)

(sweepolet in 22-inch ring header)

Description of Cr acking JP-2-.1A and JP-2-1B (very extensive on safe end and on 4-inch end of 1 educer)

DRMC-2-4 (axial crack 50$ throughwall, 3/4-inch long)

KR-2-14 (one indication, 15$ through wall, 2.1-inch long)

KR-2-36 (deepest indication is 26$ throughwall,

1. 1-inch long)

KR-2-37 (lar gest indication is 20$ throughwall, 4-inch long)

KR-2-41 (largest indication is 12$ throughwall, 4-inch. long)

Recommended Fix JP-2-1A and JP-2-1B (replace)

DRWC-2-4 (replace usinj heat sink welding)

KR-2-14, KR-2~36, KR-2-37, and KR-2-41 (IHSI and continue inspections)

(overlay can be applied later if future inspections indicate that crack growth is not arrested)

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DROWNS FERRY NUCLEAR PLANT UNIT 2 MELD DSRHR-2-5A RT DEFECT EUALUATION Ob jec tive Evidence Subjective Evidence Conclusion Radiographic image is indicative of cylinderical nonmetalic inclusion Fabrication defect i.e.,

slag, porosity, LOF, etc.

2.

Good resolution of defect on RT film Cylinderical nonmetalic inclusion 3 0 Slight density changes in defect Small through wall dimension area and adjacent weld area Radiographed with beam parallel and offset at 15o the defect image is very similar in appearance on both radiographs Cylinderical nonmetalic inclusion 5 ~

Density change on 2$t pene.

and base metal vs density change on defect and adjacent area about the same.

Defect has approximately an equivalent through wall dimension 6.

RT parallel and offset at 15 the parallax locates the defect 0.2 in.

below OD surface in weld metal Fabricatzon defect 7.

Defect cannot be detected with conventional IGSCC UT Small reflective surface and/or defect is located in weld metal 8.

Cannot detect defect'pening into ID with UT Defect does not extend to ID 9.

Defect loacted in weld not base metal verified by UT and RT Fabrication defect e.g., slag, stringer, porosity, LOF, etc.

10.

Straight beam - pitch catch UT locates defect at 0.2 in.

below OD surface Fabr ication defect 11.

Cannot locate defect with large RTD 70olongitudinal wave probe.

This probe normally gives good resolution of defects near the OD surface when the sound must travel through weld metal, e.g.,

under clad cracking The defect has very small through wall dimension, i.e.,

reflective surface

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