ML20084M766

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Forwards Supplemental Response to IE Bulletin 82-03, Stress Corrosion Cracking in Thick-Wall,Large-Diameter Stainless Steel Recirculation Piping at BWR Plants
ML20084M766
Person / Time
Site: Oyster Creek
Issue date: 05/25/1983
From: Fiedler P
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
REF-SSINS-6820 IEB-82-03, IEB-82-3, NUDOCS 8306020341
Download: ML20084M766 (29)
v • d • e


Text

's.

h GPU Nuclear Q

g7 P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dia: Number:

May 25, 1983 Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Sir:

Subj ect: Oyster Creek Nuclear Generating Station Docket 50-219 IE Bulletin No. 82-03 Previous letters to you dated December 1,1982 and February 25, 1983, responded to question Nos.1 and 4 of the subject Bulletin. The purpose of this letter is to supplement our response to question Nos. 4.a.(1) and (2) and to provide our initial response to question Nos. 2 and 3.

The attached Topical Report No.12 presents these responses in sequence, as noted above in IE Bulletin 82-03 format.

In the event that any comments or questions arise regarding the information provided herein, please contact Mr. J. Knubel at (201) 299-2264.

Very truly yours, 1

f&Abu PeEer B. Fiedler Vice President and Director Oyster Creek PBF:PFC:jal At tachment zi Sworn to and subscribed to before me this o?$ ~ day of

~fr/ g

, 1983.

V-W b el W 61 Notary Public d&

MICHAEL LAGGART 8306020341 830525 NOTARY PUBLIC OF NEW lERSEY DR ADOCK 05000 m, omrmsson boires hurrber 31.1985 GPU Nuclear is a part of the General Public Utilities System gt"I

=

4 Regional Administrator Page 2 ec:

U.S. Nucleat Regulatory Commission Document. Control Desk Washington, D.C. ' 20555 NRC Resident Inspector Oyster Creek Nur_lcar Generating Station Forked River, NJ 08731 9

OYSTER CREEK RECIRCULATION SYSTEM PIPING INSPECTION PROGRAM Response to NRC I&E Bulletin No. 82-0 3, Rev. 1 Topical Report No. 012 (Rev. 0)

Project No.:

328025 R. A. Pinelli R. Ostrowski AUTHORS DATE May 10. 1983 AP PROVALS :

1 5

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DEPART}ENT MANAC1R DATE' wt C b %

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3 VICE PRESIDENT DATE TECHNICAL FUNCTIONS (SIGNIFICANT l'! PACT REVIEW)

Abstract The augmented inservice inspection program for I&E liulletin 82-03 'for Oyster Creek's Recirculation System has been performed.

Prelimina ry results of this ultrasonic inspection reveal that two welds contain indications similar to those of IGSCC and several welds possess geometric / fabrication indications.

Some of these indications cannot he completely characteri zed a t this time.

Follow-up internal examinations are required to provide more complete inf ormation.

These incpections are scheduled following re ac tor vessel drain and the disassembly of recirculation system suction and discharge valves.

OYSTER CREEK RECIRCULi. TION S?ST91 PIPING INSPECTION PROGRAM INTROD UCTION In October, 1982, the NRC issued I&E Bulletin No. 82-03 pertaining to "Stre ss Corro sion Cracking in Thick-Wall Large-Diameter, Stainless Steel, Recirculation System Piping at BWR Plants".

The bulletin concentrated on Nine Mile Point's recirculation system pipe cracking experiences. With Oyster Creek being identified as an addressee of the bulletin and being most similar in design to Nine Mile Point, GPUN developed and implemented an Inspection Program for ultrasonic examination of recire. system piping welds which would satisf y the new requirements.

Below is a supplemental re sponse to Action Items 4, 2, and 3 of the bulletin.

METHODS 4.a.(1) & (2)

As part of the Inspection Program, GPUN and its NDE contractor, utilizing GPUN approved procedures and calibration scandards, qualified inspection teams on cracked pipe sections from NMP at Battelle Columbus Laboratories in accordance with the Bulletin's requirements.

The initial inspection sample size, as shown in Figure 1 and reported in GPUN's 82-03 submittal dated December 1,1982, was 16 welds. The selection of the welds to be inspected was not a random sampling. Rather, the welds

. selected were those which would be more susceptible to ICSCC cracking, based on.th ree conditions (1) high stress rule indices, (2) weld repairs performed during construction and (3) welds being similacly located to those at Nine Mile Point where cracks ~ were initially detected.

Prior to the start of in spec tio n, further information became available concerning weld repairs -

during construction.

Accordingly, additional welds were included in the inspection plan,-increasing the size to 22 welds (Figure 2).

Af ter prelini-nary inspection re sults reve aled ' two locations 'with possible ICSCC, the inspection plan was again increased to include all similarly' located welds on the remaining recirculation loops (Figure 3), for a total of 31 welds in spected.

4.a.(3)'

Previously re sponded to by Ref.1.

4.a.(4)

Previously~ re spo nsed to by Re f.1.

4.b. th rou gh 4.d Previously re sponded to by - Re f.1.

INSPECTION RESULTS 2,.,

The original inspection results revealed tha t only two welds contain.

indications which may be intergranular stress corrosion cracking (1GSCC) and five welds with indications characterized as fabrication / geometric-type.

i While further evaluation-is needed on the two welds with possible ICSCC, inspections were scheduled for nine additional welds.

These nine included all

- welds similar in location to the two above mentioned welds plus those selected a

under the requirements of ASME Section XI Inservice In s pe c t ion.

.. The additional inspections are complete. The results of the additional in spec tions reveal' diree welds with indications which have been preliminarily characterized as fabrication or geometric conditions. Appendix 1 provides a detailed summa ry of the inspection re s u l t s.

PLAN OF ACTION 3_.,

Bounding fracture mechanics analyses of. the two possible IGSCC indica-tions reveal that both indications can be lef t as found (i.e., will not.propa-gate beyond acceptable limits) for the next_ opera ting cycle without any form of weld repair.

Further characterization of the 2 welds indicative of 'IGSCC and five of the remaining eight welds with fab /geome try indications.will require both.

- radiography and internal, remote (visual and/or liquid pr.netra nt) examina-

. tion s. These examinations shall-be performed after fuel of f-load, re act or ve ssel drain and recire, valve disassembly.

RECOMMENDATION 3 3.I(Cont'd.)

Final disposition of the 13 welds with indications shall be. made af ter a

. review of the additional internal examinations scheduled following reactor ve ssel dra in. -

Howeve r, possible courses of action being considered include weld over-lay ' repair for. the two welds containing IGSCC-type indications and induction -

heating stre ss improvement for welds repaired during construction and welds with.high SRI's (gre a t er tha n 1.4).

. REFERE NCES 1) letter to Ronald C. Ilaynes from Peter B. Fiedler dated December 1,.

1982, Re: Oyster Creek Nuclear Generating, Station Docket 50-219, I&E Bulletin 82-03.

2)

Letter to Ronald C. Ilaynes from Peter B. Fiedler dated February 25, 1983, Re:

Oyster Creek Nuclear Generating Station, Docket 50-219, I&E Bulletin 82-03.

FIGl'PF 1 - OPIGI!' ALLY PPOPOSFD REACTOR fW.c nRCUL.nTIO N PWui

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REACTOR. RE CIR C UL ATIO N PIPitM., TYPIC AL LOOP OYSTER CREEL'.

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Int:r-Sffico Mcm(jg,:,w y 4

crcndum Date April 5, 1983 SPPCO-83-614 UC ear Subject Recirc. Piping Examination Results To T. J. Patterson Location Oyster Creek The following information delineates the current status of examination results obtained from the initial " Quick Look" for IGSCC on the recirculation piping system.

The initial " Quick Look" sample was comprised of twenty two (22) welds (Attachment-1)..The sample size was later expended.during the examination to include four (4) scheduled ISI welds and five (5) welds which closed out the inspection sets for areas where recordable indications were found. These additions brought the total number of welds examined during the " Quick Look" to thirty one (31). -

As a result of the examinations the following data was generated:

1.

Twenty one (21) weld heat affected zones (HAZ) were found clear, that is, there were no recordable indications per the requirements of the Ultrasonic procedure used (6130-QAP-7209.08 Rev. 0).

2.

Ten (10) weld heat affected zones were documented as having recordable indications per the requirements of the U.T.

procedure.

Locations, evaluations, 'and repair status of these 10

/

welds are shown in Attachments 2, 3, 3A, and 4.

Two (2) weld (llAZ) are considered at this time to have indications characteristic of IGSCC (NG-D-ll and NG-B-5).

I Planning for supplemental examinations is as follows.

Remote visuals are to be conducted on the two welds characterized as IGSCC.

If results of these examinations are not conclusive a remote surface examination (Dye Penetrant) will have to be performed.

In addition, radiography is currently planned for l

four (4) welds which were evaluated as geometry / fabrication indications and

~

the remaining weld (NG-B-5) characterized as IGSCC.

Plans are also underway to utilize an ultrasonic signal characterizer (ALN-4060) to be provided thru the EPRI Institute, as a means to further evaluate the recordable indications referenced in Attachment 3.

The use of the 4060 is scheduled for the week of April 11.

Except for the examinations utilizing the ALN-4060 all other supplemental exams will be scheduled after vessel drain, now scheduled for April 27.

l AOOOO648

h, Page 2 T. J.-Patterson 4

A further update concerning these examinations will be made as the supplemental' examinations are completed and the welds dispositioned.

w A

R. Ostrowski Supervisor,: Corporate ISI RO/dg, Attachments-cc:

M. Allgaler w/ attachments J. Chardos w/ attachments R. DeMuth w/ attachments N. Kazanas w/ attachments R.-Pinelli w/ attachments S. Pruitt w/ attachments C. Tracy w/ attachments 9

9

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IMSPECTION OF RECtRCULATION P!P[NC WEl.DS - 1983' J'

i.-

k HAZ 4 Fu11 Vol. IGSCC Addfelaas Recordabte Suppiaavacal Emaninations ISI Welds lVMh Indications tetests Examinations Monitored NC-A-14

' Yes NG-A-14 @. 60 @ 45 @

Yes 0

8 MC-8-1 Yes -

Yes NC-C-12 Yes Yes NG-D=1 Yes 60* h n.T.. Video

'NG-A-5 @

NG-8-2 NC-8-2 NC-B-4 Yes NC-B-4 Yes NC-C-9 NG-C-98 @ '

Yue (2)

NG-D-3 F- -

41

t

.a NC-E-2 NC-E-4 Yes-i['

NC-E-13 @

(

NC-A-1 NC-C-22 Yes f

NC-C-23 Yes Yes NC-8-5 Yes R.T., Video.

NC-8-24 NC-B-24A @

Yes

(

NC-A-24 @.

f NG-A-25 Yes NC-8-1A

[,

NC-8-24 @ C-l*23 @ -

NC-B-23'@

N i

NC-C-2 @

M l

NC-D-2 @

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4

?

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Yes NC-E-1A @

NC-E-22 5

NC-E-24@

NG-E-24 5

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Yes

.Yes NG-0-4 (

Yes Yes NC-E-6 t

i t

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LECEND Yocal: 5 Total: 22 Yotal: 5

@ Emaalaatton Team Number l

^

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(E Loop)

NG-C-23 (C Loop)

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NG-B-5 (B Loop)

NG-C-4 (C Loop) 4 NG-D-4 (D Loop)

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NG-A-14 (A Loop)

=

NG-B-12 (B Loop)

NG-C-12 (C Loop) o g-NG-D-ll (D Loop)

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. 5.

Attacnm nt J PRELIMINARY RESULIS OF INSPECTION TEN WELDS WERE NOTED TO HAVE RECORDABLE INDICATIONS TO DATE PLANNED WELD ADDITIONAL ADDITIONAL FINAL N0.

VARIABLE EVALUATION NDE NDE DISPOSITION NG-B-12 SIDE-1 Ind.#200-Lack of thru-wall dimension discounts IGSCC SIDE-1 Ind.#201-Location, Lack of length (spot) and lack of thru-wall dimension discounts IGSCC SIDE-1 Ind.#202-Location and CRT pattern amplitude preclude possibility of IGSCC SIDE-1 Ind.#203-Location discounts IGSCC NG-C-12 SIDE-1 Ind. #200-Fabrica tion /geome try condition SIDE-1 Ind.#201-Fabrication / geometry condition NG-D-ll SIDE-1 Ind.#200-Characteristic of IGSCC 0

60, R.T.

Video 0

Ind.#201-Characteristic of IGSCC 60, R.T.

Video NG-E-4 SIDE-1 Ind.#200-Fabrication, geometry condition Ind.#201-Fabrication, geometry condition IG-C-22 SIDE-2 Ind.#200-Fabrication, geometry condition IG-C-23 SIDE-2 Ind.#200-Fabrication, geometry R.T.

condition SIDE-1 Ind.#201-Fabrication, geometry R.T.

condition SIDE-1 Ind.#202-Fabrication, geometry R.T.

condition NG-B-5 SIDE-2 Ind.#200-Fabrication, geometry R.T., Video condition SIDE-2 Ind.#201-Fabrication, geometry R.T.,Vi deo condition SIDE-2 Ind.#202-Fabrication, geometry R.T'., Video condition SIDE-2 Ind.#203-Characteristic of IGSCC R.T., Video SIDE-2 Ind.#204-Characteristic of IGSCC R.T., Video NG-C-4 SIDE-2 Ind.#200-Fabrication, geometry condition NG-D-4 SIDE-2 Ind.#200-Fabrication, geometry R.T.

condition Ind.#201-Fabrication, geometry R.T.

condition J

.At tuclamen t ~3A 9

PRELIMINARY ~PISULTS OF INSPECTION.

TEN WELDS WERE NOTED TO HAVE RECORDABLE INDICATIONS 1

TO DATE' PLANNED WELD' ADDITIONAL ADDITIONAL FINAL

'NO.

- VARIABLE EVALUATION NDE NDE

. DISPOSITION-

'NG-A-14. " SIDE l' Ind.#200-Fabrication condition 600 R.T.

Ind.#201-Fabrication condition R.T.

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W LD DATE OF-LOCATION NATURE NO.

FABRICATION OF REPAIR OF REPAIR o -

NG-A-14

^ Pre-1969 3:00 I.P. (3 spots) - repaired NG-B-12 6:00-12:00 I.P. -Lrepaired 6:00-10:00 Gas Pockets / Porosity - repaired NG-C "

6:00 to 9:00 I-P. -' repaired NG-D-11 5 of 6 on film I.P. and Slag Inclusions-repaired NG-E-4

'None NG-C-22 None - Elbow was removed during construction and rewelded NG-C-23 None - Elbow was removed,during construction,and rewelded r

NG-B-5 2-3 on film I.P'. - repaired NG-C-4 None NG-D-4 None u.-

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'i EXAMINATION TEAMS

\\;

TEAM NO.

EXAMINERS / LEVEL U.T.

L

-1 McCaully, II/Liebold, II 2-Reichert, II/ Trotter, I L'

3,

McCaully. II/D. Rosa, I 4

Deskiewicz,LII/Valden. I 5

Radlbeck, II/D. Rosa, I.

6 Deskiewicz,':II/Floyd, I 7

Deskiewicz, II/C. Rosa, I

.p

~8' Collins, II/Butkiewicz, I'

'9 :

Radlbeck, II/Floyd, I 11 0 -

Minyon, III/Valden, I 11 Liebold, II/Valden, I

.12 Reichert, II/Liebold, II

't 13 Collins, II/Minyon, III

'14

.Reichert,-II/C.' Rosa, I' t

15 Radlbeck, II/Valden, I 16

'Minyon, III/McCaully, II 17 Reichert,'II/Minyon, III

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