ML20099D252

From kanterella
Jump to navigation Jump to search
Informs of Adherence to Guidelines of 840419 Generic Ltr 84-11 Requesting Info Re Insps for IGSCC & Leakage Detection,Including Stainless Steel Welds Susceptible to Igscc.No Mods or Further Action Required
ML20099D252
Person / Time
Site: Limerick  
Issue date: 11/09/1984
From: Kemper J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
CON-#484-203 GL-84-11, IEB-82-03, IEB-82-3, IEB-83-02, IEB-83-2, OL, NUDOCS 8411200277
Download: ML20099D252 (3)


Text

y,

=.

h/

s f

.i

. PHILADELPHIA ELECTRIC' COMPANY;

' 23O1' MARKET STREETi y

~

NOV _91984:

P.O. BOX 8699 PHILADELPHIA. PA.19101

-(215)841 45o2

.vicE+stEssDENT ~

..(NGleetERHWG AseO RESE ARCte Mr.. Darrel G.' Eisenhut, Di rector -

Docket No.:-50-352 Division of. Licensing.

.50-353

.U. S. Nuclear Regulatory ConmissIon Washington, DC 20555-

Subject:

_ Limerick Generating Station, Units 1 & 2 Inspection of BWR Stainless Steel Piping

References:

1)

Generic Letter 84-11,~ dated April 19,1984 2)

Letter d. S. Kemper to D. G. Eisenhut, j

~

dated October 5,1983

!4 Flies:

RES ~26--CIGSCC)

GOVT 1-1 (NRC)

Dear Mr. Eisenhut:

~^

Generic Letter 84-11 (Reference 1) requests information relative to inspections for. Intergranular stress corrosion crecking (IGSCC) and leakage detection. The scope includes stainless steel welds, susceptible to IGSCC, in piping that is part of or connected to the reactor coolant pressure boundary (RCPB) out to the second Isolation valve, in systems equal to or greater than four (4) Inches in diameter with an operating temperature above 200F.

Reference 2) discusses the use of nucioar grade materials for Limerick Units 1 and 2 in the reactor coolant system, emergency core -

coolant systems out to the first isolation valve and the reactor water clean-up system out to the second Isolation valve. Accordingly, there are no " nonconforming service sensitive" welds within the RCPB and as such, augmented Inservice Inspection per NUREG 0313, Revision 1, are unnecessary. This'information has been reviewed by the NRC staff and reported on in the Limerick Safety Evaluation Report (NUREG-0991),

Section 5.2.3.

Considering I.E.Bulletins 82-03 and 83-02, many of the ultrasonic techniques quallfled at the EPRI Center have since been incorporated into Limerick examination procedures and used during the later portion of the Unit 1 preservice inspection. Examiners quallfled in IGSCC detection and sizing are available at Limerick due to our participation in EPRI's sponsorship progran.

8411200277 841109 4

PDR ADOCK 05000352 G

PDR f h

[". s,'.g,q -

~^

~

i m-

. n

=2'-

s y

'o

' Any: cracks 'which may' be detected' during' normal operation.

or;the inservice inspection-program will be evaluated and repaired.in-l, accordance with ASPE Section XI. Appropriate ' methods to further

. mitigate:IGSCC in the. repaired welds will be considered in the' repair.

program.-

Regarding primary system leak detection,. existing methods and-systems described. In FSAR Section 5.2.5 are in ccznpilance with NUREG 0313, Revision 1.--Survel.11ance measures beyond those. required by

> Technical Specification 3/4.4.3 are.not required..

.. Based on the above,' Limerick Units 1 and 2 are' consistent with.

the guldelines of' Generic Letter 84-11 and no' modifications or further action is~.- required at this time. -

-If you have any~ questions or.conments', ~please do not hesitate to contact us.

Sincerely, See Attached Service List DLS/pd10108411

J.t';3., '

x

\\}:f

  • it_..

N :'

G.n.,'

n Q

^

u:

. m; - < a c.

',{;O-_

. e p

i, 3 ir

  • .i 'i n

-.t.

<, ~ 1]

^

s

-'n-i,

. d.),

t.. t e s

3 d

.h 9

g*

1cc: Judge' Helen F.LHoyt/

Judge Jerry Herbour;

pj, -

s

. ' ~

Judge Richard;F. Cole. _.

M Judge, Christine N.. Kohl.

/

JudgeLGeryLJ.'Edlest,

1' Judge Reginald L.JGotchy-Troy B. Conner, Jr.-) Esq.,.

fann-P. R4f, dun,!Esq..

~

.Mr. Frank R.: Romano b Mr.hRobert L. Anthony:

MsJ Phy111s Zitzer--

'Charl.es W. Elliot,'Esq.

~JZort G. Ferkin Esq.:

Mr., Thomas Gerusky__

Director, Penna. Emergency Management Agencyf Angus R.-Love,.Esq.

David Wersan,.Esq.

Robert J..Sugarman,'Esq.

Martha'W. Bush,;Esq.

Spence W. Pecry, Esq.;

Jay M. Gutlerrez, Esq..

. Atomic Safety & Licensing Appeal Board.

.' Atomic' Safety & Licensing Board Panel Docket & Service Section Mr. James Wiggins Mr. Timothy R. S. Campbell i

i t

j

+

It t

i v

l i

a d-

.a

,. ~...... _.. -, - - - _ _....,.. -, _ _. -..

,,,.,_._,...,__,4~

., _ -,.._.v-,-,...,__,

.,.-o,_,,.w,-..o._.._