ML20205G139

Summary of 881011 Meeting W/Util & GE in Rockville,Md Re Core Spray in-vessel Pipe Crack.List of Attendees & Ref Matls Supplied by Licensee Encl

ML20205G139
Person / Time
Site:	FitzPatrick
Issue date:	10/24/1988
From:	Labarge D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8810280197
Download: ML20205G139 (5)

Text

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. . October 24, 1988 %MNw 8 1 . , ,

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I Docket No.: 50-333 g DISTRIRUTION

• MGt,^., L Fi l e NRCPDR LICENSEE: Power Authority of the State of New York (PASNY) local PDR PDI-1 Pdg RCapra OlaBarge FACILITY: James A. FitzPatrick Nuclear Power Plant OGC EJordan l

BGrimes HAbelson

SUMMARY

OF MEETING HELD ON OCTOBER 11, 1988 TO WKoo RMcRrearty i

j DISCIISS CORE SPPAY IN-VESSEL PIPE CRACK FVitt RWemann

• YL1 ESullivan 4

JDurr WHodges HBClayton JJohnson, RI

SUBJECT:

SUWARY OF MEETING HELD ON OCTOBER 11, 1988 TO DISCUSS CORE

] SPRAY IN-VESSEL PIPE CRACK

) The meeting was held at the One White Flint North Office in Rockville, Maryland.

A list of attendees is attached as Enclosure 1.

a Enclosure 2 is the reference material supplied by the licensee. All topics on i the agenda were addressed during the meeting.

In response to comitments made in response to Bulletin 80-13 and NUREG-4523, i inspections were conducted of various Core Spray System components in the j reactor vessel during the present refueling outage. As a result, a crack was

found below the ;)ipe-to-elbow weld in the "B" Core Spray Downcomer Pipe. The i utility plans to drain down the reactor vessel to approximately 6 feet above

the top of the active fuel, decon and UT the area, and then weld a sleeve over the cracked area. In consort with the General Electric Company, a method has been designed which analysis shows will restore the pipe to at least its original criteria. The purpose of the meeting was to present this infomation and plans to the NRC staff.

The utility has comitted to supplying the additional infomation listed below prior to startup from the pr*sent refuel outage:

a. A comparison of the original stress data and analysis which shows that the repair restores the piping to this condition as a minimum,

b. Results of related UT inspections,

c. Results of visual examination on the recirculation system mar.way inspections in the reactor vessel,

d. Technical evaluation of adequacy of plant operation with the repair l in place, j

The briefing handout which was supplied by the FitzPatrick personnel contained sece information which was marked "GE Proprietary Inforvation" but was l 8810280197 $S1024 PDR P

ADOCK 05000333 i I I

PDC l

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< detemined to be non-proprietary by the GE representatives present since it contained no such infomation, but was simply general knowledge infomation ,

which came from another document which was controlled in this manner.

I i Subsequent investigations conducted on October 13, 1908 have shown that a i pup-piece (spool-piece) exists between the elbow and the pipe and that the  !

I crack is below the lower weld. The crack, therefore, exists on the  !

l pipe-to-pipe weld, not the pipe-to-elbow weld. l l l 96g1xd siped W i

1 David E. LaRarge, Project Manager  :

1 Proiect Directorate I-1 l j Division of Reactor Projects I/II  ;

j

Enclosures:

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1. List of attendees j

?. Reference Material

cc w/enclusures. ,

4 Licensee /Attendeedservice List  !

! PDI-1CN PDI-1 e N PDI-1 W i

] LA:CVogan PM:DLaBarge:vr PD:RCapra  !

10/g0/88 10/tr/88 10/11/88 l

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i Mr. John C. Brons James A. FitzPatrick Nuclear Power Authority of the State of New York Power Plant cc:

Mr. Gerald C. Goldstein Hs. Donna Poss Assistant General Counsol New York State Energy Office Power Authority of the State 2 Errpire State 01aza of New York 16th Floor 10 Columbus Circle Albany, New York 12223 New York, New York 10019  !

Resident Inspector's Office U. S. Nuclear Re.guistory Comission Regional Administrator, Region i Post Office Box 136 U.S. Nucleer Regulatory Comission Lyconing, New York 13093 475 Allendale Road King of Prussia, Pennsylvania 19406  ;

Mr. Radford J. Converse Mr. A. Klausman Resident Manager Senior Vice President - Appraisal Jarres A. FitzPatrick Nuclear and Compliance Serg 8ces Power Plant Power Authority of the State Post Office Box 41 of New York Lycoming, Ne'.' York 13093 10 Columbus Circle New York, New York 10019 Mr. J. A. Gray, Jr. Mr. George Wilverding, Manager Ofrector Nuclear Licensing - BWR Nuclear Safety Evaluation Power Authority cf the State P;wer Authority of the State of New York of New York 123 Mein Street 123 Main Street White Plains, New York 10601 White Plains, New York 10601 Mr. Robert P. Jones, Supervisor Hr. R. E. Beedle Town of Scriba Vice President Nuclear Support R. D. d4 Power Authority of the State Oswego, New York 13126 of New York

. 123 Main Street Mr. J. P. Bayne, President White Plains, New York 10601 Power Authority of the State of New York Mr. S. S. Zulla 10 Columbus Circle Vice President Nuclear Engineering New York, New York 10019 Power Authority cf the State  :

, of New York  !

1 Mr. Richard Patch 123 Main Streat i i Ct.ality Assunnee Superintendent White Plains, New York 10601 ,

J James A. FitzPatrick Nuclear L

] Power Plant Mr. R. Burns j Post Office Box 41 Vice President Nuclear Operations 3 Lycoming, New York 13093 Power Authority of tM State i i of New York i l Charlie Donaldson, Esquire 123 Main Stre:t

.tssistant Attorney tieneral White Plains, New York 10601 ,

4 New York Department of Lew 1 120 Broadway New York, New York 10271 1 1 a

s o e ENCLOSURE 1 ,

LIST OF ATTENDEES Participants Organization D. LaBarge NRC  ;

H. Abelson NRC '

i W. Koo NRC C. McBrearty NRC F. Witt NRC R. Hermann NRC Y. Li NRC E. Sullivan NRC  :

J. Durr NRC W. Podges NRC J. Gray PASNY W. Fernandez PASNY S. Toth PASNY j R. Joffe General Electric '

S. Ranganath General Electric G. Gordon General Electric G. Sor21 General Electric  !

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ENCLOSURE 2 J. A. FITZPATRICK CORE SPRAY IN-VESSEL PIPE CRACK BRIEFING OUTLINE

1. INTRODUCTION OF UTILITY AND GE PERSONNEL

2. DESCRIPTION OF J. A. FITZPATRICK  !

3. DESCRIPTION OF CORI SPRAY SYSTIM I

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a. Core Spray System Description ,

b. Drawings o Core Spray Systea o Reactor Internala '

o Core Spray Sparger Break Detection System o Detail of Core Spray Sparger

c. Basic Technical Information on Pipe / Weld in Question

4. PROBLEM FOUND/HOW/ PREVIOUS HISTORY L

a. Drawings of Crack ,

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b. Inspection Procedure Utilized I

c. History I

d. Cause of Crack I

5. REPAIR PROGRAM /SCHKOULE ,

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a. General Description

b. Repair Plan

c. Schedule i 1

d. NDE Options

6. SAFETY IMPLICATIONS f

a. ECCS/ Safety Evaluation '

b. Future Inspections l

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