ML20125B946

Forwards Suppl Insp Program for Sensitized Stainless Steel Matls & Welds

ML20125B946
Person / Time
Site:	Millstone, Monticello, Nine Mile Point
Issue date:	06/23/1970
From:	Case E US ATOMIC ENERGY COMMISSION (AEC)
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 9212100224
Download: ML20125B946 (3)

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iKT21: TO P. A.110RRIS TICO :UJiDED AUG?tCEED Ii4 SERVICE INSPECTION PROGPAM FOR StuSITIZED STAIi4ESS S1U.L 1%TERIALS A'iD 'CLDS -

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@#Y/ fIILLSTO,iE liUCLEAR PodER STATION UJIT - 1 p j 4 3 l'ONTICELID NUCLEAR G2iEFATIl1G PLANT U11T - 1 In accord with the ACRS recommndatims (3ctters dated June 15, 1G,1970) that the Ecculatozy Staff assure itsc1f of tne details of an augranted sitrveillanco pirya for sensitized nutcrials, the Divisico of Reactor Standanis beliews the attached cupple-nental inspection prcctums are applicable and anpropriate for the subject facilitics. Such prega=3 chould be considered as Invisions and anyrntations of the prurent inrcrvice inspection zuquircTunts contained in the AS'I Section XI - Inservice Inspection CodQ.

i These inspection progmms should properly be considered for addition to or Invision of the inservice sury.illance pluirams of the Technical Spacifications.applical1c to the operating license of the respective facilitics.

Or; m ,1 ar.ed by, EC Case 9212100224 700623 Edson C. Case, Diwetor PDR ADOCK 05000263 Division of Reactor Standarxis R PDR Enclosurus:

Supplc:xntal Inspection Programs cc w/ encl:

R. Boyd, PRL J. Skovholt, DRL R. R. i'accary, DRS

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Sucolemental Instection Procram for fEFIticello Nuclear Generatinz Plant Unit 1 (a) The folicwing critical and sensitized eJnponents shall be non-destructively examined by the methods indicated:

Ctrnponent _ Examination Methe-

1. Field clad-repaimd safe-ends PT and UT

2. Welds of field-mplaced safe-

, ends Fr and (Ur or FT)

3. Severely weld-sensitized heat-affected zones in wrcught piping (Type 304,316) PT and (Ur or RT)

4. Field clad-repaired sensitized cccoonents within reactor vessel whose failure could adverse]y affect safety Visual (b) The areas subject to examination shall include 100 percent of the exterior surfaces of clad repaired safe-ends (a)1, and 100 peent of the exterior surfaces of welds (a)2, (a)3. Weld areas to be exc. Tined shall include the base raterial for, at least, one uall th2ckness beyond the edge of weld.

i The area subject to visual examination, (a)4 shall include those

! surfaces of the cc.Tponents which are made accessible for examin-ation by removal of reactor intemals during nomal refueling l <

outages, and whenever the reactor vessel head is renoved for any f

other purposes.

' (c) All examinations shall be conducted in accord with the examin-ation techniques and procedums and ncet the acceptance standards i specified in the ASME Section XI Inservice Inspection Code, and L suppleranted where necessary by special techniques with denonstrated l capability to detect stress-corrosion cracking.

(d) The examination frequency shall confom to the folleuing schedule:

Field clad-rupaired safe-ends ('Iko) l 1. One safe-end at or within the 1st refueling outage j 2. One safe-end at or within the 2nd refueling outage

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3. Both safe-ends over the Iwnaining 1st-10 year inspection f

interval

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4. Both safe-ends over each subsequent 10 year inspection interval Welds of field-reolaced safe-ends (six safe-ends)

1. 'No safe-ends at or within the 1st refueling outage

2. 'iko safe-ends at or within the 2nd refue3ing outage 1

3. Ec.uinin:: two r,afe-ends within the 1st 10 year inaccction i interval

4. 100 percent over each subsequent insocction interval in ecofort.unce with the inspection progre n defined in IS-242 of the .M Sedian XI Ccde.

Severely weld-sensitized heat-affected zones in wrought ~

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1. 10 perm nt at or within the 1st refueling outage l

2. 10 percent at or within the 2nd mfueling outage

3. 5 percent over the remaining 1st-10 year inspection interval

4. 25 percent over each subsequent 10 year inspection interval Field clad-repaired sensitized components within reactor vessel

1. Examination to the extent practicable at the 1st and 2nd mfueling outage, and whenever the reactor vessel head is l recoved for any other purposes, within the 1st and 2nd mfueling.

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2. Examination at each subsequent refueling outage at appmximately.

3 ye.ar intervals.

I '(e) In the event any of the excminations of (d) reveal-indications of structural defects which upon evaluation require repairs, the specified examinatien frequency shall be subject to review by the Comnission.

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