IR 05000454/1988017

Insp Rept 50-454/88-17 on 880914,20-22,27-29 & 1017.No Violations Noted.Major Areas Inspected:Inservice Insp Activities,Including Review of Program (73051),procedures (73052) & Observation of Work activities(73753)

ML20155J257
Person / Time
Site:	Byron
Issue date:	10/19/1988
From:	Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20155J255	List: IR 05000454/1988017 ML20155J251
References
50-454-88-17, NUDOCS 8810250445
Download: ML20155J257 (6)

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U. S. NUCLEAR REGULATORY COMMISSION j i REGION !!!  !

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Report No. 50-454/88017(DRS) ,

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' Docket No. 50-454 License No. NPF-37 ;

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Licensee: Comonwealth Edison Company .

Post Office Box 767 i

' Chicago, IL 60690 j i

Facility Name: Byron Station, Unit 1  !

l i Inspection At: Byron Site, Byron IL  !

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Inspection Conducted:' September 14, 20-22, 27-29, and October 17, 1988  !

I Inspector:M. D. Ward d}14Le w'-n 1 i L l 16//9/F6 [

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/ Date s Approved By:

49fdbe- hw D. H. Danielson, Chief /6//#/Ali I l

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Materials and Processes Da te' ;

Section j (

i Inspection Sumary  ;

i i Ins ection on September 14, 20-22, 27-29, and October 17, 1988 (Report N ~

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]i - 3T[8'8017(DRS)) l Areas Inspected: Routine, unannounced safety inspection of inservice [

, inspection (ISI) activities including review of program (73051), procedures  !

(73052), observation of work activities (73753), and date review (73755);  !

i stress relievin modifications (g steam generator tube U-bends (37701); and various

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Results: No violations or deviations were identified. The following are the general conclusions reached during the inspection:  !

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The inservice tspection program was properly implemente l

Personnel performing nondestructive examinations, heat treating, and I L, modification activities appeared to be knowledgestle and conscientious  !

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Management inve.1vement in inservice inspection, heat treating, and the  !

modification activities was eviden ,

Activities examined were accomplished in accordance with established procedures by qualified personne !

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DETAILS Persons Contacted Comonwealth Edison Company (CECO)

• L. Sues, Assistant Superintendent. Technical Services ,

• D. Winchester, Station QA Superintendent  !

• R. Flahive, Technical Staff Supervisor i

• D. Robinson, Nuclear Safety Group. Onsite Supervisor  !

• M. Snow, Regulatory Assurance Supervisor l

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• J. Harkness, Technical Staff, ISI l

• H. Kennedy, Technical Staff. Engineer

• J. Smith, Technical Staff. Engineer i

• E. Zittle, Regulatory Assurance Staff G. Sorensen, Construction Superintendent ,

., W. Wolber, QC Supervisor [

] Nuclear Regulatory Comission (NRC)  !

• P. Brochman, Senior Resident Inspector

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• N. Gilles, Resident Inspector i . EBASCO Services (EBASCO)  ;

J. Semgenberger, Supervisor  ;

, N. Bollingno, UT Level II  :

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S. Busby, PT Level II i Hunter Corporation (HC)

J. Smith, Quality Control Weld Inspector, Level II Babcock & Wilcox Company (B&W)

, i R. Rawlings, QC Specialist

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l R. Shope, QC Supervisor  !

E. Mayhew, Quality Programs Specialist (Auditor)  :

l Hartford Steam Boiler Inspection and Insurance Company (HSB)

l J. Hendricks, AN!!

The inspector also contacted and interviewed other licensee and contractor employee * Denotes those present at the exit interview conducted October 17, 198 [

j Inservice Inspection (ISI) - Unit 1 General This is the second outage of the first period of the first ten-year  !

ISI pla EBASCO personnel perfonned the ISI in the methods of

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ultrasonics (UT), magnetic parti 'a (MT), and liquid penetrant examinations (PT). B&W personnel ,,erformed the eddy current examinations (ET) on the tubes in steam gencrators (SG) A, B, C, and D. CECO personnel performed the visual examinations (VT). The examinations were all performed in accordance with ASME Section XI, 1983 Edition, Summer 1983 Addend The UT was performed by EBASCO using pulse-echo UT flaw detection instruments and various angles and MHZ transducer There were several EBASCO personnel who had been trained and qualified by EPRI in detecting Intergranular Stress Corrosion Cracking (IGSCC). Program (73051) and Procedures (73052)

The NRC inspector reviewed the ISI program and procedures and found them to be acceptable. Where these rules were detennined to be impractical, specific relief was requested in writing. The NRC inspector reviewed the specific relief requests and related documentation, Review of Data, Audits and Certifications of Material, Equipment and Personnel (73753) ,

The NRC inspector reviewed documents relating to the following:

(1) Ultrasonic instruments, calibration block, transducers and couplant certification (2) Liquid penetrant, cleaner and developer material certification (3) Magnetic particle, materials and equipment certification (4) Eddy current equipment certification (5) NDE personnel certificatiuns in accordance with SNT-TC-1 (6) Audits /Surveillance (7) ISI Data Reports, including 1977 radiographs of the !'A" steam l generator girth weld, There was an acceptable slag indication ;

found by ultrasonic examination this outage that had not been found by ultrasonic examinatiun during the preservice inspection. i In reviewing the 1977 radiographs of the girth wcid, the NRC inspector detennined that the indication has always been in the weld, The slag indication was radiograph examined this outage, but because of a "T" type configuration of where the weld is located, the area could not be successfully radiographed. The indication will continue to be monitored, j (8) Eddy Current Reports -

Steam Generator A - 3 tubes were plugged, a total of 39 tubes are now plugge . .  ;

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Steam Generator '3 - 4 tubes were plugged, a total of 16 tubes are now plugge ,

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Steam Generator C - 4 tubes were plugged, a total of 9 tubes are now plugge *

Steam Generator D - 3 tubes were plugged, a total of 11 tubes now plugged, Observation of Work Activities (73753)

The NRC inspector observed work and had discussions with personnel j during the following ISI activities. The related documentation was i also included as part of this revie (1) B&W personnel using the following equipment evaluating eddy current data from the ', team generator tubes:

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(a) The ZETEC Model 00A-4 analysis equipmen (b) Automated data screening equipmen (c) Data management software syste The B&W personnel described in detail the purpose and the accuracy of the equipment in discriminating between the important and the irrelevant dat (2) B&W personnel performing eddy current examinations on many steam generator tube (3) An ultrasonic instrument being decontaminated by radiation chemistry personne (4) An EBASCO PT Level II individual performing a liquid penetrant examination on Line #1RH01BA-12", Weld #C7, long sea (5) EBASCO UT Level II individuals performing calibrations and ultrasonic examinations on Line #1FW81AC-6", Weld iC5 FW331, ;

l and on Line #1MS01CC-32 & 3/4", Weld #C2, long sea '

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(6) The authorized nuclear inservice inspector performing his duties.

l (7) The B&W auditor performing her dutie No violations or deviations were identifie . Stress Relieving the Steam Generator (SG) Tube U-Bends (37701)

Primary side Intergranular Stress Corrosion Cracking (IGSCC) has been noted by B&W in the U-bend region of the first and second row of the

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Alloy 600 tubes in PWR recirculating steam generators. Destruction examinations have shown the cracks to be primarily at the apex and near the tangents of the bends on the extrados (outside bend radius) and in the sides near the small radius of the curvature portion of the oval corner Heat treating was performed to reduce tube residual stresses and to minimize primary and secondary side stress corrosion cracks. This was accomplished by heating the tubes to a predetermined temperature and time range. The heat treating was performed by B&W on the 3/4" OD tubes, Rows 1 ond 2 U-bends in Steam Generators A, B, C, and Individuals involved in stress relieving were trained on a mock-up prior :

to the actual stress relieving of the steam generator's tube U-bend Tests were given to the individuals prior to performing the heat treating.

4 B&W personnel walked the NRC inspector through the heat treating process t l in detail which included the equipment and how it operated in the tube

, U-bends. The NRC inspector also observed, by video, the heat treating .

i process in operation on the steam generators. The NRC inspector reviewed l j procedures, drawings, reports, and other related documentatio After heat treating, the U-bends were eddy current examined using the f j B&W Eddy-360 system and found to be acceptabl No violations or deviations were identifie .

4 Modifications (37701) Easier Access Thr'ough Penetrations Modifications were implemented to allow easier access to the containment during outages by replacing welded closure plates with blind flanges. The removal of closure plates on penetration sleeves fP-63, #P-64 and #P-74 easily allowed outage related eddy current examining power cables and sludge lancing hoses to pass into the containmen All work for this modification was performed in accordance with ASME Section Ill,1974 Edition, Sumer 1975 Addenda, and ASME Section XI, 1983 Edition, Summer 1983 Addenda. The NRC inspector reviewed i drawings, travelers, 10 CFR 50.59 safety evaluation, and NDE and welding related documentatiol.. The NRC inspector also observed '

a part of the installation and a fit u No violations or deviations were identified,

, Snubber Reduction

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This modification altered the support arrangement of piping systems and other areas by removing the snubbers or replacing the snubbers ,

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with rigid struts. The snubber reduction modifications reduced the overall snubber population and therefore, reduced the scope of the surveillance and testing program. The main intent of this modification was the removal of snubbers and/or replacement of snubbers with rigid struts, minimizing hardware changes.

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All work for this modification was performed in accordance with ASME Section XI,1983 Edition, Summer 1983 Addenda. The NRC inspector reviewed drawings, field changes, work requests, and other NDE and welding related documentation. The NRC inspector also observed fitups and visually examined the final welding and installation of many rigid strut No violations or deviations were identifie . Exit Intervi_ew (30703)

The inspector met with site representatives (denoted in Paragraph 1) at ;

the conclusion of the inspection. The inspector summarized the scope and findings of the inspection noted in this report. The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any such documents / processes as proprietar r i

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