ML20117L097

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Submits Supplementary Info Addressing Augmented Insp Requirements in Generic Ltr 84-11 Re Disposition of Nonconforming Welds in Recirculation & RHR Sys During Pipe Replacement Activities,Per Ga Gears 850501 Request
ML20117L097
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 05/14/1985
From: Cooney M
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Stolz J
Office of Nuclear Reactor Regulation
References
GL-84-11, NUDOCS 8505160090
Download: ML20117L097 (12)


Text

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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 (2is) a415o2o M. J. COONE Y M AN AGER u.c,,Nc"'//o'o"c"o."o'0Ar-wr

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May 14, 1985 Docket No. 50-277 Mr. John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

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SUBJECT:

Supplement to Peach Bottom Atomic Power Station Unit 2 Justification for Continued Operation i

Following Current Refueling / Major Modification Outage

REFERENCE:

Letter to J.

F. Stolz from S. L.

Daltroff, dated April 15, 1985

Dear Mr. Stolz:

This letter provides supplementary information regarding the disposition of nonconforming welds in the Recirculation and Residual Heat Removal systems during pipe replacement activities on Peach Bottom Unit 2.

This information is provided in response to a request by G. A. Gears of your staff during a telephone conference with Philadelphia Electric Company Licensing Section staff on May 1, 1985 and addresses the augmented inspection requirements in NRC Generic Letter 84-11 for Peach Bottom Unit 2.

Recirculation System All nonconforming welds, as defined in NUREG-0313, Rev. 1, in the recirculation system have been eliminated during the current pipe replacment outage.

h0' 8505160090 850514 PDR ADOCK 05000277:

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'Bes'i$ual Heat 4 Removal System-w; kil~ nonconforming welds..in the:RHR system have.been. eliminated during'the pipe' replacement outage with the-exception of three g

welds located outside ~of ;the containment penetrations cut the-containmentLside of the second-isolation' valves of the RHR-y' suction and return piping.

These welds-are categorized as-follows:-

Weld 10-0-17, is a dissimilar metal (carbon steel pipe,to n

stainless l steel" containment penetration.N-12) weld inLthe

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isolable portion-of the RHR shutdown cooling suction 20-inch piping'as'shown on' Attachment 1.

This weld is categorized as a

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" nonconforming'nonservice' sensitive weld",in that the operational

. temperature is-less that 200 degrees Fahrenheit and there is no

' flow _during reactor power 1 operation.

Therefore, this weld is subjectito the augmented inservice inspection requirements contained 11n paragraph ~IV.B.l.b of NUREG-0313,.Rev. 1,.and is

.~inspectedfat.least once in-no more than 80-month intervals.

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Previous ultrasonic andLvisual examinatio'n was performed on.this f-

'weldLin 1980 andino' reportable ~ indications were discovered.

k During this pipe replacement outage, an internal surface,

'flourescent penetrant examination wns performed on-this weld and no-reportable indications.were discovered.

Welds 10-1B-2 and~10-1A-2 are located-in:the.. isolable portion-of

' theta and B'24-inch RHR' return-lines outside containment penetration:N-13A'and N-13B,~respectively, as shown in Attachments 2;and 3.

These welds are nonconforming welds.(304

. stainless steel' pipe to 304 stainless steel valve) and-nonservice n

sensitive.in'that the operating temperatures--of.this piping is P

less.than;200= degrees Fahrenheit and therefis no-flow during-

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' reactor: power _ operation.

i These; welds (10-IA-2 and-10-IB-2) are no'rmally inaccessibleafor x

_ inservice ~ inspection in accordance-with ASME Code Section XI requirements.-

However,'with portionscof pipe removed during u

recent pipe replacement; activities, an internal surface fluorescent typerliquid. penetrant 1 examination was performed and

,no-indications were observed.:

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' Residual Heat Removal ~ Head' Spray-A11Lnonconforming1relds.in the RHR head spray piping have been 1 eliminated as a.resu'.t of the pipe replacement modifications with

the exception of.two welds.

The two remaining: nonconforming 6-inch metal (carbon steel to stainless steel) pipe weldstare dissimilar welds 10-HS-3 and 10-HS-6' L~

. and-theirilocations are shown in Attachment 4.

The welds are i'

l categorized as nonconforming nonservice sensitive in that normal

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

m Mr. John F. Stolz May 14, 1985 Page 3 L

l operating temperature is less than 200 degrees Fahrenheit and there is no flow in the head spray piping during reactor power l

operation.

Welds 10-HS-3 and 10-HS-6 are in the isolable portion of the head spray piping.

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These welds are subject to the augmented inservice inspection g

requirements contained in paragraph IV.B.l.b of NUREG-0313, Rev.

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1, and are inspected at least once in no more than 80-month intervals.

The first and second 80-month interval ultrasonic and visual examinations were performed on weld 10-HS-3 in 1977 and 1985 and on weld 10-HS-6 in 1978 and no reportable indications i

were discovered.

Weld 10-HS-6 is scheduled for the second 80-

]g month interval examination during the next Unit 2 refueling outage.

Reactor Water Cleanup System i

All non conforming welds as defined in NUREG-0313, Rev. 1 in the gl reactor water cleanup system out to a point beyond the second g

isolation (MO-18) have been eliminated as a result of the current g

pipe replacement modifications.

Previous partial replacement of the reactor water cleanup system from the residual heat removal tee to just inside the contaiment penetration utilizing 316 stainless stecel was performed in 1982.

During the current outage, the penetration and piping from the penetration to a point just downstream of valve MO-18 was replaced (with 316 stainless steel).

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Core Spray System

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Partial pipe replacement of core spray loops A and B performed y

prior to the current outage has eliminated all nonconforming service sensitive welds in the nonisolable portion of these lines with the exception of one weld in each loop.

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The remaining welds are categorized as nonconforming nonservice sensitive in that the operating temperature is less than 200 h

degrees Fahrenheit and there is no flow in the core spray piping

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during reactor power operation.

These dissimilar metal welds are l-located in the isolable portions of each line and are identified

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as weld 14-A-12 in the

'A' loop piping and weld 14-B-ll in the l

'B' loop piping as snown in Attachments 5 and 6.

These welds are subject to the augmented inservice inspection requirements contained in paragraph IV.B.l.b of NUREG-0313, Rev.

1, and are inspected at least once in no more than 80-month E

intervals.

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Mr. John F. Stolz May 14,.1985 Page 4 Surface and volumetric examinations were performed on these welds during the current pipe replacement outage and no' reportable

' indications were discovered.

Table 1 provides a summary of'the-nonconforming welds in piping greater than'4 inches in diameter out to the second isolation-valve,.their categorization and inspection requirements that remain;as airesult of_the current pipe replacement-activities..

z None of the' welds. listed in Table l'are subject to inspection in-accordance-with Genciic Letter 84-11~, paragraph 2, in that none of'the weld' operating' temperatures' exceed 200 degrees Fahrenheit (as~specified.in the Generic Letter.

The inspection, plan for

" nonconforming nonservice' sensitive welds", as defined by NUREG-

0313 on these welds, and results of inspections performed on these welds, present adequate assurance that'the unit can be Loperated safely.

.Should you require any. additional 1information, please do not hesitate to contact us.

V truly yours,

/

/

cci T. P. Johnson,. Resident Site' Inspector l.

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TABG 1

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NNONEDRMING WELD DPfrA -

REACTOR COOLANT PRESSUIE BOWDP@( PIPING 14 INGES

1) WELD ISOUULE
2) WELD TEW. DURING ICRMPL OPER.

INSPECTION SYSTEM WELD No.

3) FLON RATE DURING REACIOR OPER.

WELD CIASSIFICATICN REQUIREMENTS Recirculaticn System None RWCU System None

'RHR System 10-0-17

1) Yes Dissimilar Metal NUREX3-0313,.

(S/D Cooling)

2) < 200 degrees F Nonconforming Rev. 1
3) 0 gpm Nonservice Sensitive 10-IA-2
1) Yes Nonconforming Inaccessible 10-IB-2
2) < 200 degrees F Nonservice Sensitive for Inspection
3) 0 gpm RHR System 10-HS-3
1) Yes.

Dissimilar Metal NUREG-0313 (Head Spray) 10-HS-6

2) < 200 degrees F Nonconforming Rev.

1

3) 0 gpm Nonservice Sensitive Core Spray 14-A-12
1) Yes Dissimilar Metal NUREG-0313 System 14-B-ll
2) < 200 degrees F Nonconforming Rev. 1
3) 0 gpm Nonservice Sensitive

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