IR 05000304/1990012

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Insp Rept 50-304/90-12 on 900430-0510.Major Areas Inspected: Inservice Insp Related Activities,Steam Generator Indications,Mods,Erosion/Corrosion & Pipe Supports
ML20055G230
Person / Time
Site: Zion File:ZionSolutions icon.png
Issue date: 06/29/1990
From: Harris R, Kerch H, Strosnider J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20055G228 List:
References
50-304-90-12, NUDOCS 9007200268
Download: ML20055G230 (10)


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U. S. NUCLEAR' REGULATORY 4 COMMISSION.

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REGION I

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lR'epo'rt"No'. : 50-304/90-1]

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Docke.t No.-1 50-304

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Commonwealth Edison Company

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P. O. Box 767

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Zion Nuclear Power Station n-q

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Inspection At:

Zion, Illinois

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Linspection' Conducted: gr31230 - P,.ay 10,1990

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IH, W, Kepch, Pro,iect Manager N6f

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Nbt Technician

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. Processes Section', EPB, ORS, Region 1

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ulnspgtjeniSumma',ry.ana C-on:1dyion: - A' routint, enouheed inspection was condu:tec ' q.

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.by.;the NEC Mobile.. Nondestructive Examination (NDE)LTeam at Zion Nuclear Power *

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" Station-on April 30 through May 10,'1990.

-(Report No'.. 50-304/90-012)-

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The inspection focused on-iriservice ^inspe'etionirdlated activities.csteamt

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u generatorJindications, modifications, erosion-corrosion and: pipe supports.:

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Implementation ofJthe ISI program.and-the_ISI contractor!s
performance were

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DETAILS

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1.0 Persons Contacted (30703)

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Commonwealth Edison Company (CECO)

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  • G..Beale. Regulatory Assurance
  • T. Saksefski, Engineer ISI
  • T,.Reick.. Technical Support l

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W. T'Neim, Technical Staff Supervisor

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  • G. Ponce Quality Control (NDE)

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  • D. Chrzanowski, Nuclear Engineering ISI
  • R.

Wulf, Technical Staf' ISI

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  • T. Van De Voore, Quality Assurance Supervisor

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  • Ri Tolentino, Coordinator ISI

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  • J. W. Yost, Quality Control Inspector

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  • J. Madden, Technical Staff Westinghouse Nuclear Services Division (NSD)-

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  • B. Letebre, Coordinator, ISI i
  • J. A. Johnson, Coordinator

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U.S. Nuclear Regulatory Comm sgen I

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  • R. S. Leeman, Sr. Resident Inspector, RIII
  • K. Ward, Reactor Inspector, RIII

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  • Denotes those attending entrance and exit meeting.

L The above listed personnel were present at the exit meeting.

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inspector also contacted other administrative and'te ?nical personnel during the inspection.

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2.0 In' dependent Measurements - NRC Nondestructive Examination and Quality,

' Records Review of Safety Related Systems

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During the period of April 30 through May 10, 1990, an onsite-independent-O s

. inspection was conducted at Zion Nuclear Power Station..The' inspection a

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'was conducted by.NRC regional based inspectors, The objectives of this inspection were to assess the adequacy of the licensee's inservice inspection

program, steam generator-shell inspection activities, welding quality w

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control ~ program, pipe modification program and the licensee's actions:

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regarding maintaining the "as-built" configuration of pipe hangers and

supports.. This was accomplished by repeating _ examinations performed by

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the licensee in accordance with applicable ' regulations and codes and then comparing the results of the independently performed NRC inspections with

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the-results of the licensee's inspections.

The following paragraphs define p

the~ scope-of the examinations performed and the results.

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2.1 Nondestructive Examination (NDE)

2.2 Visual Examination (57050)

Seven (7) safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were visually examined in accordance with NRC procedure NDE-10, Rev.1, Appendix A; the licensee's procedure entitled " Visual Examination of Pipe Systems and Attached Components," and associated QC documents, isometric and as-built drawings.

During this inspection, ASME Class 2 pipe weldments were selected from the Safety (SI), Main Steam (MS), and Feedwater (FW)

systems.

The examinations were performed specifically to identify any cracks or linear indications, gouges, leakage, arc strikes with

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craters, or corrosion which may infringe upon the minimum pipe wall thickness. Mirrors, flashlights and weld gauges were used to aid in the inspection and evaluation of the weldments.

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R_e sults:

The welding and overall workmanship inspected were satisfactory.

No violations were identified.

2.3 Visual inspection Hanger / Support (57050)

During this inspection, twenty one (21) safety related piping hangers and supports were visually inspected per NRC procedure NDE-10, Revision I., 4pendix A and B. in conjunction with site procedurc> f or visuai es cination of pipe systen and attached components, OC documents and associated isometric drawings.

Included in this inspection were hangers and supports selected from the Main Steam (MS), Service Water-(SW), Component Cooling Water (CCW), and Auxiliary Feedwater ( AF)

Systeas.

In the area of welds acce:.sible surface area and adjace t N sc meta! for a d.:+ance of one-half inch on either side of the weld were examined.

In the aren vi component integrity, specific attributes 1,apected were proper installation, configuration or modification of supports; evidence of mechanical or structural damage; and corroded, bent, missing or broken members. Attachment 2 is a list of specific hangers and supports inspected.

Results: Welding and overall workmanship were acceptable. No violations were identified.

24 Liquid Penetrant Examination (57060j

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Two (2) safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were examined using the visible dye, solvent removable liquid penetrant method per NRC procedure NDE-9, Revision 0, in conjunction with the licensee's procedure and associated QC records, included in this inspection were ASME Class 2 stainless steel weldments selected f rom the Safety injection (SI) System.

Results:

The surface areas examined were properly prepared for the examination.

No violations were identified.

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F 2.5 Magnetic Particle Examination (57070)

Six (6) safety related pipe weldments.and adjacent base material (1/2

U inch on either side of the weld) were examined using the direct contact i

i magnetic' particle method (Yoke), with dry powder as.the inspection K

medium.

The examination was performed in accordance with NRC procedure

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.NDE-6, Revision?1 in conjunction with the licensee's procedure and.

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Included in this examination were ASME Class.

p 2 pipe, weldments selected from the Main Steam (MS) and Feedwater (FW).

Systems.

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No violations were identified.

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2.6 Ultrasonic Examination (57080)

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using a.Krautkramer USL-48 ultrasonic flaw detector in accordance

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with NRC procedure NDE-1, Revision 1; site procedures and associated l

ultrasonic test ~ data.. Instrument' calibration (linear verification)'

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was performed using NRC procedure.NDE-2, Revision 1

' A distance amplitude correction! curve (DAC) was. constructed using the ~ licensee's.

l calibration standard CWE-3.

To ensure repeatability of the ultrasonic

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~ examinations, instrument settings and search units. (transducers) were

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matched as near_possible to those indicated ?v the licensee's ultrasonic i

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Results1 No violations were identified.

.i 2 7 -Erosion-Corrosion-(57080)

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Twenty (20) pipe components'were examined for erosion-corrosion using r

a nova D-100 digital thickness gauge.

The method and procedures usec

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were in accordance'with NRC' procedure NDE-11 Revision 0, the 4" ensee's

. procedures, and quality assurance records. The erosion-corr - an examinations were performed on selected pipe ccmponuits to ostermine

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if wall thinning was present and, if so, us it being o"operly evaluated and monitored by the: licensee.

The thickness measuraments were taken

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Jat predetermined locations on the systems selected and were on.a 1-

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inch, 2 inch,'or 3 inch grid pattern depending on the diameter of the component.

Included in this inspection were various size components selected from the Feed Water (FW), Heater Drain (HD) and Condensate -

(CD) systems.

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~Results:

Based on the inspections performed, there were no violations

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identified. The licensee's erosion-corrosion program appeared to be

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effective based on site documentation and repeatability of results.

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E2.8 Steam Generator Shell Inspection (57080/57060)

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This inspr.ction was, performed to eva12 ate the licensee's activities'

related to the inspection,. evaluation and' disposition of indications

found by the licensee's contractor on the shell of Steam Generator "D".

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A magnetic particle examination was performed by_the NRC on the inside.

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surface of the steam generator shell using,the direct contact magnetic i

le particle method (yone) with dry powder as-the inspection medium.

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of Steam Generator _"D"'using.a Sonic Mark'1: ultrasonic flaw detector.

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The aforementioned examinations were performed using tae NRC approved

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procedures-in conjunction with the licenseefs' procedures and associated.

quality control. records.. A distance amplitude correction curve was,

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established usi19 the=11censee's calibration block CWE-32. The specific

areas examined are as follows.

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STM.-GEN.

ISO /DWG WELD AREA-TYPE INSP.

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"D" STM.' GEN.

"D" 3-6

MT/VT

"D" STM. GEN.

"D" 3-6 OD UT/VT

e Results:

After metal condi_tioning ars reexamination, the results' of

the magnetic examination on the inside surface of the steam generator

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particle or the visual examination.

As a result of the ultrasonic

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and visual edmination-on the outside surf ace (OD), it was verifies '

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,that the indications recorded by the licensee's ultrasonic technicians i

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were:as' stated in the ultrasonic data reports. ~No apparent visual j

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_ indications were found.

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3.0 Inservice _Inspecti:n 151 Program (737531-s The'. inspector reviewed the following documents to ascertain compliance

- with ~ applicable ASME code requirements, ' licensee commitments and regulatory.

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requirements.

l ISI Summary of' Interval 1, dated January 22, 1986 d

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.lSI Schedule and Plan' for 2nd Interval, dated 1984-1994

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.lSI Relief Requests

NDE Personnel Qualifications r

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, Program Plan for Interval 2, Period 2, Outage 2F

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Based on the foregoing, it was determined that the licensee's ISI program

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is: intended to meet the requirements of the ASME Boiler and Pressure Vessel

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Code,JSection XI, 1980 Edition through winter 1981 addenda.

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Result's:. The inspe'ctor concluded that Zion's ISI Program,was adequately staffed by appropriate 1y' qualified site and contractor personne1'to properly

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ASME Section.XI, article IWA-2600 and mandatory. Appendix III,. Supplemen. 2, requires.-that a marking system be established to provide a reference to.

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- the centerline of the welds requiring volumetric examination.

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found that the-licer.see has not marked the centerline of welds within the

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ISI program.., Piping welds on Attachment 1 have not had the center 11nes

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marked.- The' licensee stated that they are not required to physically mark

- the centerline of welds for piping:in.the.ISI program.

They also feel

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. that they have an exemption from the pre-service examination (centerline

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marking) requirements due to their (construction permit prior to

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January.1, ~1971). This item is considered as unresolved pending P

- determination of the licensee's exemption. status.

(50-304/90-12-01)

Results:

No violations were identified.

Exam'ination Data The inspector observed that limitations listed on the ultrasonic-(UT)

- examination reports.are not limitations-but are scan obstructions ~.

Site personnel h've stated.that-the words " limitations" on the ultrasonic-a reports will be changed to " scan obstruction" this will take care of the;

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problem;

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Results:

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No vi.olations were identified.

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Review Of' Site NDE procedures and Manuals-

-4.0 The' following. procedures were' reviewed in the regional. of fice during this '

inspection period for-compliance to the: licensee's FSAR commitments and.

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' applicable codes,4 standards and specifications.

Commonwealth 101 son-Company (CECO) Inservice Inspection'Nondestructi g _

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lxamination Pfocedures;

.P 0cedure' title Number / Revision

- VT-3/4 Visual Inspection Performed

'VT-3/4-1,-Rev. 1

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a for Section XI-b Nondestructive Testing Procedure NDT-C-42, Rev. O

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- Inservice Inspection /B0P.

TSS 15.6.20 y

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' Westinghouse Nuclear Services Integrated Divdion (NSID)

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nl Visual-Examination ISI-8, Rev. 9 w

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Liquid Penetrant Examination:

ISI-11, Rev. 10

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Manual UlUasonic Examination 151-47, Rev. 4

h of WeldsLin Vessels-

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Magnetic Particle. Examination 151-70, Rev. 2

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Manual. Ultrasonic Examination of Welds'

151-206, Rev. 1

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0593-129-Pi-01 i

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Erosion corrosion V.T. Inspection

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Program Expansion

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'U1trasonic Inspection Data'She'et and 0593-129-Pl-02 l

Field Work-Monitoring Requirements

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Results:.No violations were identified.

The inspector identified a concern

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.in that;the procedures reviewed may nut effectively assure that changes in l

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piping configurations are reflected in the ISI program. The licenseeLstated-

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that' procedure TSS 15.6.20 will be changed to. include how changes made as i

g, a result of: r:epairs.or replacernents wil1'be incorporated in-the 1S] Program.

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F 5.0 Attachments

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h Attachme No. 1 is a tabulation of specific pipe weldments and components

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examined and the results. 'Attacnment No. 2 is a tabulation-of hanger and.

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support l components examined and the results.

Attachment No.-3 is a

j tabulation of specific areas examined, selected from the site erosion-j'

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corrosion plan, and the results.

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6.0 Unresolved Items

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cunresolved items are matters about which more information is required

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1An unresolved item is: identified'in Section 3.0.

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7.0c Management Meetings (30703)

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Licensee management was informed of the scope'and purpose of the inspection

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at the entrance interview on January 8,1990.

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Pr The findings of the inspection were discussed with the licensee representa-f tives during the course of the-inspection and presented to licensee management

at the exit interview.

(see paragraph 1.0 for attendees)

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1At no time:during the. inspection was written material provided to d e x

licensee by the inspector.

The-licensee did not_ indicate that proprietary

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information-was involved within the scope of this inspection.

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ATTACHMENT #1 INDEPENDENT MEASUREMENTS INSPECTION SHEET 1 OF-1

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SITE: ZION NDE PIPING /WELDMENTS DATE: 4/30-5/11/90 ISO /DWG ID SYS CL.

RT MT PT UT VT ACC REJ COMMENTS

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COM-2-2401

FW

X X

X X

COM-2-2401

FW

X X

X X

COM-2-2301

FW

X X

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COM-2-2100

MS

X X

X

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COM-2-2300A 12W MS

X X

X SLIDE SUPPORT i

STM GEN'"D" 3-6 SG X

X X

ID 70% GIRTH WELD

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STM GEN

"D" 3-6 SG X

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OD GIRTH WELD COM-2-2524

SI

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X X

COM-2-2524

SI

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X X

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' ATTACHMENT #2 INDEPENDENT MEASUREMENTS INSPECTION SHT 1 OF 1 I

SITES ZION HANGER / SUPPORT DATE 4/30-5/11/90

DWG/ ISO HANGER / SUPPORT SYS CL CAT ACC REJ COMMENTS COM-3-3103 H1 AFW

X COM-3-3103 H2 AFW

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COM-3-3104

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COM-3-3104 3R23 AFW

X Y

COM-3-3107 H6 AFW

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COM-3-3107 H8 AFW

X-COM-3-3107 H11 SW

X COM-3-3154 H1 SW

X COM-3-3154 H1 SW

X COM-2-2100 H11 MS

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- COM-2-2100 H12.

MS

X COM-2-2200 H11 MS

X COM-2-2200 H12 MS

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COM-3-3214 H1 CC

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COM-3-3214 H2 CC

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COM-2-2302 H1 AS

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COM-2-2302 H2 As

X COM-2-2302 H3 AS

X COM-2-2102 H1 AS

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COM-2-2102 H2 AS

X COM-3-3153 H1 SW

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I ATTACHMENT # 3

'EROSIOM/ CORROSION EXAMINATION SHT l'OF 1

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' SITE: ZION DATE: MAY. 90 LINE PIPE / COMPONENT SYSTEM GRID COMMENTS

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l 2FW33-1 12" NOZZLE FEEDWATER 1X2" 2FW33-2 12" NOZZLE FEEDWATER 1X2" i

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2HD77-1 8"X14" RED.

HEATER DRAINS 1"

2HD77-2 8"X14" RED.

HEATER DRAINS 1"

2HD48-1 8"X14" RED.

HEATER DRAINS 1"

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2HD48-2 8"X14" RED.

HEATER DRAINS 1"

i-t 2CD82-1 14"X10" RED.

CONDENSATE 2"

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2CD82a2 14"X10" RED.

CONDENSATE 2"

2C082-3 14" PIPE CONDENSATE 2"

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2CD82-4 14" ELBOW CONDENSATE 2"

2CD82-5 14" PIPE CONDENSATE 2"

l 2CD81-1 18" NOZZLE CONDENSATE 2"

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2CD81-2 18"x24" RED.

CONDENSATE 2"

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2CD81-3 24" ELBOW CONDENSATE 3"

2CD81-4 24" PIPE CONDENSATE 3"

2CD85-1 1.5" PIPE CONDERSATE 1"

20D85-2 1.5" PIPE CONDENSATE 1"

l 2CD85-3 1.5" PIPE CONDENSATE 1"

2HD78-1 14"X8" RED.

HEATER DRAINS 1"

2HD78-2-14"X8" RED.

HEATER DRAINS 1"

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