ML18026B204

Forwards Background Info & Proposed Insp Schedule for Recirculation Inlet safe-end Thermal Sleeve Attachment Weld, Per 840830 Meeting Request

ML18026B204
Person / Time
Site:	Browns Ferry
Issue date:	09/06/1984
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8409110177
Download: ML18026B204 (10)

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REGULATORY FORMATION DISTRIBUTION SY H (RIDS)

SUBJECT!

Forwards" background info.8 proposed insp schedule -for re'cit culation inlet safei.-end thermal sleeve attachment weld/

per 840830 meeting request.

DISTRIBUTION CODE;,

ADSTD, COPIES,RECEIVED:LTR J ENCL j'IZE; TITlE'. OR Submittal: Inservice Inspection/Testing NOTES$ NMSS/FCAF icy, icy NMSS/FCAF/PH.

OL>06/26/73 NHSS/FCAF icy 'cy NMSS/FCAF/PM'L:06/28/74 NHSS/FCAF 1cy.'cy NHSS/FCAF/PMB OL'!07/02/76 05000259 05000260 05000296 ACCESSION NBR!8409110177 DOC ~ DATE! 84/09/06 NOTARIZED! YES DOCKET P'ACIL:50 259 Browns Ferry Nuclear Power, Stations Unit ii 'Tennessee 05000259 50 260 Browns Ferr y Nuclear Power Stat)one. Unit 2'i Tennessee 05000260

, 50 296 Browns. Ferry Nuclear Power Stations Unit 3i Tennessee 05000296 AUTH-',NAME A/THOR AFFILIATION MILLSEL~ M ~

'Tennessee-Valle>,Author ity REC IP ~ NAHEI RECIPIENT AFFILIATION, DENTONgH ~ RE Office> of Nucleary Reactor -Regulationi Director REC IP IENT ID CODE/NAME NRR ORB2 BC 01 INTERNAL! ADH/LFMB NRR/DE/HEB 15 NRR/DL/TAPHG RGN2 COPIES LTTR ENCL 7

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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II September 6,

1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

In the Matter of the Tennessee Valley Authority Docket Nos. 50-259 50-260 50-296 By letter from D. B. Vassallo to H. G. Parris dated August 22,

1984, we were formally notified of cr acks detected in the recirculation system inlet nozzle safe-ends on Peach Bottom Atomic Power Station unit 2.

In response to that letter TVA representatives attended a meeting on August 30, 1984 to discuss the situation of the Browns Ferry Nuclear Plant with respect to this identified cracking.

In the meeting your staff requested formal documentation of statements made by TVA representatives present regarding pr evious and futur e inspections, and TVA's plans if cr acking is detected in upcoming outages.

The information requested in enclosed.

It was stated that this information is needed for finalization of the safety evaluation being prepared in support of Browns Ferry unit 3 startup.

The enclosed information has been coordinated with your staff.

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

Very truly yours,

," "Subscribe

.~d sworn to b ore

-- 'e this

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day of TENNESSEE VALLEY AUTHORITY L.

. Mills, nager Nuclear Licensing 1984.

Notary Public My Commission Expires Enclosur e cc:

See page 2

g40qiiOi77 84090&I PDR ADQCK 05000259 8

PDR An Equal Opportunity Employer

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Mr. Harold R. Benton September 6,

1984 cc (Enclosure):

U.S. Nuclear Regulatory Commission Region II ATTN:

James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue

Bethesda, Maryland 20814

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ENCLOSURE BACKGROUND INFORMATION AND PROPOSED INSPECTION SCHEDULE FOR RECIRCULATION INLET SAFE-END THERMAL SLEEVE ATTACHMENT WELD BROWNS FERRY NUCLEAR PLANT Pursuant to NRC's request in our August 30, 1984 meeting, the following information is submitted for you to forward to NRC for their records.

Units 1

2 and 3 - Back round Information.on Sub ect Safe Ends Unit 1

Material: - Coulter Steel, Type 316, Carbon:

.05-.06 percent, installed by B 5 W

Unit 2 - Material:

Japan Special Steel, Type 316, Carbon:

.05-.06 percent, installed by IHI Unit 3 - Material:

Japan Special Steel, Type 316, Carbon:

.06-.07 percent, installed by THI Past Ins ection on Sub ect Welds Unit 1 - Xnspected 5 of 10 in 1978 Unit 1 - Inspected 2 of 10 in 1980 Unit 2 - Xnspected 10 of 10 in 1979 Unit 2 - Inspected 4 of 10 in 1982 Unit 3 - Xnspected 5 of 10 in 1978 Future Xns ections Unit 1 - 10 of 10 when removed in spring 1985 Unit 2 - 5 of 10 dur ing upcoming refuel outage in fall 1984,(2 per heat of material)

Unit 3 - 4 of 10 during upcoming refuel outage in fall 1985 (2 per heat of material)

Ins ection U

radin Contin encies Since units 2 and 3 are similar (material, vendor, vintage), unit 2 has more operating hours, and unit 3 is relatively free from intergranular stress corrosion cracking on recirculation and allied piping, TVA considers unit 2 to be a conservative representation of the two units.

- If cracking in the subject area is detected on the upcoming inspection of unit 2, the unit 2 sample will be expanded to 100 percent.

- If cracking on unit 2 is minor (i.e.,

two or more reportable indications not requiring repair), unit 3 will be inspected for similar indications within 180 days.

If more serious cracking is noted on unit 2 (i.e.,

one or more indications of cracking requiring repair), unit 3 will be inspected for a similar condition within 60 days.

- If unit 2 or 3 should develop leakage due to cracking in the subject

area, the companion unit will be shut down within 14 days to inspect for a similar condition.

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