IR 05000455/1985031

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Insp Rept 50-455/85-31 on 851015-25 & 28-1107.No Violation Noted.Major Areas inspected:safety-related Piping Weldments Fabricated to ASME Code,Section Iii,Classes 1 & 2
ML20138L086
Person / Time
Site: Byron Constellation icon.png
Issue date: 11/26/1985
From: Harris R, Kerch H, Lodewyk A, Wiggins J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20138L083 List:
References
50-455-85-31, NUDOCS 8512190163
Download: ML20138L086 (26)


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U.S. NUCLEAR REGULATORY COMMISSION l

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REGION I

Report No. 50-455/85-31 Docket N License N CpPR-131 Priority -

Category A Licensee: Commonwealth Edison P.O. Box 767 Chicago, Illinois 60690 Facility Name: Byron Station Unit 2 Inspe:: tion At: Byron, Illinois Inspection Conducted: October 15-25 and October 28 - November 7, 1985 Inspectors: d // b Harry inf. Kerc Lea Reactor Engineer Date h '

ich d }i ." Ha rr,i s , . E Technician N/2 ff Dite'

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Approved by: y // 6!/5 Jamel 'T. Wiggggg), Chief Date Matei1als and W ocesses Section Inspection Summary: Inspection on October 15-25 at Region I office and October 28 - November 7,1985 at Byron site (Report No. 50-455/85-31)

Areas Inspected: A routine, announced NRC independent measurements inspection was conducted using the NRC Mobile Non-destructive Examination (NDE) labora-tory. Selected safety related piping weldments fabricated to ASME Code, Sec-tion III, Classes 1 and 2 were inspected. Three region-based inspection per-sonnel assisted by two NRC NDE contracted personnel were utilized during this inspectio _The inspection involved 462 onsite hours and 104 offsite hour Results: No violations were identifie O

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DETAILS Persons Contacted Commonwealth Edison

  • R. Tuetken Startup Superintendent
  • V. I. Schosser Project Manager
  • E. L. Martin, QA Superintendent
  • J. L. Woldridge QA Supervisor
  • G. Sorensen Project Construction Manager
  • B. E. Harl Staff Assistant QA
  • J. T. Porter Construction Supervisor R. Friedel PCD
  • R. J. Moravec Project Mechanic'al Supervisor E. Wolber QA Inspector M. V. Della Betta QA Supervisor R. B. Klingler Project QA Supervisor EBASCO
  • J. Sengenberger PSI /ISI Site Supervisor Pittsburgh' Test Lab. (PTL)

J. Becker Site Manager G. Schmolze Assistant Manager

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U.S. NRC J. M. Hinds Senior Resident Inspector

  • K. D. Ward Reactor Inspector
  • P. G. Brochman Resident Inspector
  • Attended exit meetin . 0 Independent Measurements - NRC Nondestructive Examination and Quality Records Review of Safety Related Systems:

During the period of October 15 - 25, 1985 quality records received from Byron Nuclear Power Plant, Unit 2 were reviewed in the Region I office for completeness and for compliance to the licensee's FSAR commitments to ap-plicable codes, standards and specification Subsequently, an onsite independent verification inspection was conducted during the weeks of October 28 through November 7, 1985 using the NRC Mobile Nondestructive Examination (NDE) laboratory. This inspection was

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. 3 performed by NRC Region I personnel in conjunction with NRC contracted NDE personne The purpose of this examination was to verify the adequacy of the licen-see's welding Quality Control program. This was accomplished by dupli-cating those examinations required of the licensee by regulations and codes, and evaluating the results. In addition to those examinations, several other confirmatory examinations designed to verify conformance with material specifications were performed and compared to quality as-surance record 'The NRC inspectors performed the examination on randomly selected weld-ments representing samples of piping systems, components, pipe sizes, shop and field weldments fabricated to ASME, Section III Cod The items selected were previously inspected and accepted by the licensee, as indicated by vendor shop and onsite QA/QC record .1 Quality Documents Review Forty-seven safety related piping systems documentation packages, covering the items shown in Attachment #3, were reviewed. The review also included other documents which provided background information and acceptance criteria necessary for the conduct of the inspectio The following documents were reviewed:

Document Attributes Reviewed Material Certifications (CMTRS) Material chemical and phys-(Base) ical (Base) properties were compared to standards and code requirement NDE Records Examinations were verified to meet codes and standard re-quirements, licensee proced-ures and other commitment Personnel were verified to be properly qualified. Appro-priate examinations were performe Fabrication Records A review of fabricators, traveler and fabrication rec-

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ords was conducted and ,-

these records were compared against other corresponding

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records and sign off sheets.

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Drawings (Isometrics) Drawings were reviewed for design of weldments, lo-cation and classificatio Procedures Procedures were reviewed for completeness, and to verify the implementation of the licensee's commitments to code requirement Welding Material Material certifications for welding materials were reviewed to determine if physical and chemical prop-erties were as required by licensee's commitments to codes and industry standard Results: No violations were identifie .2 Nondestructive Examination Nondestructive examinations were performed using NRC procedures with addenda written specifically to comply with the licensee's PSAR commitment.to the ASME B&PV Code. The intent of these examinations was to duplicate, to the extent practicable, the techniques and methods of the original examination The following nondestructive examinations were performed:

Radiographic Examinations Thirty-six (36) safety related pipe weldments were radiographed using an-Iridium 192 source. The technique and procedure'were in accord-ance with NRC procedure, NDE-5, Rev. O and addendum BR-2-5-1, Rev. The weldments examined were ASME Class I and 2. The resulting ra-diographs were evaluated per applicable code requirements and com-pared to the licensee's corresponding radiograph >

During a field walkdown of Southwest Fabrication and Welding C spool piece RH-14-1 the inspector noted two (2) weldments on the spool piece identified as weld W2 by the weld stamps. The Inspector then reviewed the documentation packages for these two welds and found that there were, in fact, two separate packages, each labeled as weld W2. However based on a review of the data in these packages, the inspector determined that correlation between each weld package and its associated weld was possibl .

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. 5 The inspector. then reviewed the Southwest Fabrication and Welding Co's drawings for this spool piece and found that a pipe modifica-tion had been made and new identification numbers had been assigned to the above identified spool piec Weld W2.on the manufacturers records sheet for spool piece Q6050 RH-60RR (R4-14-1) was reassigned and replaced with weld W7. On November 7, 1985 the licensee issued letters to Hunter Corp. and Ebasco Services Inc. which directed changes to be made to the site drawings to reflect actual conditions found on spool piece. This item is considered unresolved pending completion of drawing changes and NRC verification (50-455/85-31-01).

Results: No violations were identifie Liquid Penetrant Twenty-six (26) safety related pipe weldments and adjacent base ma-

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terial (h" either side of weld) were examined using color contrast

liquid penetrant techniques per NRC procedure NDE-9, Rev. O and ad-dendum BR-2-9-1, Rev. Samples included ASME Class 1 and 2 stain-less steel type-316 and 30 Results
No violations were identifie Thickness Measurements Twenty-two (22) pipe weldments and adjacent base materials were ex-

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amined for wall thickness using a NOVA-D 100 digital thickness gag Examinations were performed per NRC procedure NDE-11, Rev. Minimum wall thickness was determined by use of ASTM standard pipe size and nominal thickness chart.

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Results: No violations were identified.

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Ferrite Measurements:

Eleven (11) safety related pipe weldments were checked for delta ferrite content using a Type II ferrite indicator (Severn Gauge).

This test was intended to verify that welding filler metal composi-tion had achieved adequate as-deposited microstructure with delta ferrite content adequate to eliminate possible hot cracking.

. Results: No violations were identified.

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Visual Examination:

Forty-nine (49) safety related pipe weldments were visually examined per NRC procedure NDE-14, Rev. The examinations were performed using visual aids such as lights, mirrors and English welding gage Examinations were performed to determine the general condition of the. piping weldment and the adjacent surfaces specifically checking for reinforcement, cracks, misalignment or other rejectable visual indication Results: No violations were identifie Ultrasonic Examination:

Two (2) safety related pipe weldments were examined ultrasonically using a Sonic Mark I ultrasonic flaw detector per NRC procedure NDE-1 Rev. O and Ebasco Ultrasonic data sheets UT-A-23 and UT-A-3 The weldments identified were 2RH01AB-12" J3 and 2RH01AB-12" J35 as indicated on UT data sheet Instrument calibration was performed using NRC procedure NDE-2, In-strument linearity verification. Distance Amplitude Correction (DAC)

was constructed using Ebasco Calibration Block 12-A-316-1.08- In-strument settings and search unit (transducer) were matched as closely as possible to those indicated by UT data sheets in an at-tempt to duplicate the original examinatio During the ultrasonic examination and review of the ultrasonic data reports it was noted that the associated data did not reflect the proper contour, or thickness of the area for the actual welds teste Also during this review, the data reports referenced a Delta tech-nique which had been used to determine the ultrasonic beam angle within the material. An inquiry was made to see if there was an approved procedure that referenced the use of this delta techniqu The licensee was unable to furnish any procedure or other reference to this techniqu The inspector expressed concern over these two findings to the

~1icensee. The licensee agreed to review these concern Results: This area is considered unresolved pending completion of the licensee's review of the above described NRC concerns.(50-455/

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31-03).

Alloy Analyzer:

Four (4) safety related pipe weldments and adjacent base material were examined using a Texas Alloy Analyzer. The Alloy Analyzer is

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capable of making selected qualitative and quantitative nondestruc-tive analysis of metal alloys and verification of material type Results: No violations were identifie Hardness Measurements:

Eleven (11) safety related pipe weldments and adjacent base material were tested using the Equo-tip hardness tester per NRC procedure NDE-12, Rev. O. Measurement values taken from the impact device are processed into "L" values as a digital read out; the numbers ("L" values) are then converted to Brinell hardness values and approximate tensile strength by means of a conversion tabl Results: No violations were identifie Magnetic Particle Examination:

Six (6) safety related pipe weldments and adjacent base materials were examined by the magnetic particle method per NRC procedure NDE-6, Rev. O and addendum BS-2-6- Samples examined were ASME Code Class Results: No violations were identifie .0 Review of'NDE Procedures

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The following NDE procedures were reviewed to verify their technical adequacy and conformance to code requirements:

Pittsburgh Testing Lab (PTL)

Magnetic Particle Examination QC-MT-2 Rev. 5 Liquid Penetrant Testing QC-PT-1 Rev. 9 Radiographic Examination QC-RT-1 Rev. 11 Southwest Fa Magnetic Particle Examination MT-3 Rev. O Liquid Penetrant PT-3 Rev. O Radiographic Examination RT-74-2 Rev. O Results: No violations were identifie .0 Radiographic Review A sampling of the licensee's radiographs was reviewed. The inspector reviewed radiographs for twenty shop welds and one hundred and six field welds to verify compliance with ASME III code requirements, accuracy of radiographic film interpretation and the adequacy of the licensee's ra-

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diographic program. Twenty-six of the welds were re-radiographed by the NRC during this inspection and the NRC film was compared to site file film to independently verify that correct radiographic file film was on hand (see Attachment #2, line items with asterisk). During review of radio-graphic films for welds 2H-FSK-57-7 FW54R1 and 2HFSK-57-8 FW55, the in-spector noted that each film contained an apparent indication which was not properly documented on the licensee's radiographic reader sheet. In response to these findings the licensee and NRC performed an ID surface check to resolve the indications. The welds were found to contain ID mismatches which should have been documented on the radiographic inspec-tion reports. The inspector determined, however, that the actual welds were acceptable to code requirements. The NRC had no further concern Results: No violations were identifie .0 Preservice Inspection (PSI) Program The inspector reviewed various PSI ultrasonic data reports. Data reports for weld 2RC03AD27hJ12 did not clearly reflect the extent of the weld joint volume which had oeen ultrasonically examined. The weld joint data sketch illustrated the volume required to be examined by the ASME cod However a thorough review of the data by the inspector revealed that 25%

of the ASME code required volume had not been examined for this wel Discussions with the ISI vendor personnel indicated that he had known the exact extent of the volume which had been examined. To avoid confusion, the licensee should consider methods to more clearly show the extent of the weld examine Further review of the licensee ultrasonic data revealed that the cast stainless steel elbows in the primary piping system were not scheduled for complete ultrasonic examinations (see Attachment #4 for listing of welds and extent of examinations). A meeting was conducted on November 5, 1985, with the licensee regarding the cast stainless steel elbow ultrasonic examinations and Steam Generator ID girth indications. This meeting did not resolve these issues. On November 7, 1985, the inspector held a phone conversation with a representative of NRR: MTEB regarding the examinations of the primary loop elbows. The outcome of this conversation was NRR's intent that the licensee perform the required ASME code examinations for each of the cast stainless steel elbow welds and subsequently report the examination result Results: The NRC concerns regarding clarification of the PSI records and the examination of the cast stainless steel elbow welds remain unresolved pending licensee's evaluation and subsequent NRC review (50-455/85-31-02).

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. 9 6.0 Attachments Attchment No. 1 is a tabulation of the specific items examined and the results achieved. Attachment No. 2 is a list of specific radiographs reviewed. Attachment No. 3 is a list of specific document packages

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reviewed. Attachment No. 4 is a list of welds and extent of examinatio Attachment #5 is a list of attendees to a meeting to discuss cast elbow examination .0 Unresolved Unresolved items are those for which more information is necessary for the NRC to determine whether the items are acceptable, violations or deviations. Unresolved items are contained in paragraph 2.2, and .0 Exit Interview An exit interview was held on November 7, 1985 with members of the licen-see's staff. The inspector summarized the scope and findings of this inspection. No written material was provided to the licensee during this inspectio .-

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ATTACHMENT 2

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C - CRACK LF - LACK FUSION A - ARTIFACTS

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SL - SLAG IP - INADEQUATE PENETRATION S - SURFACE P - POROSITY LI - LINEAR INDICATION CC - CONCAVITY T - TUNGSTEN UI - UNFUSED INSERT CV - CONVEXITY Page 1 of 6 l SYSTEM /LINE l WELD 10 lACCIREJI CISLI Pl TILFIIPILIlull Al SICClCVI COMMENTS l l l 1 I I I I I I I I I I I I l l l IRL-11 lFW979R2 l Xl l l l l l l 1 l l l l l l l l l l l l 1 1 I I I I I I I I I I I IMS60A lFW452 lXl l l l l l l l l l l l l l l l I l l l l l l l l l l l l l l 1

IMS56A IFW343 l Xl l l l l l l l l l l l l l l l l l l l l 1 l l l l l l l l l l l

IFW28A l FW824 iXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l 1 1

IFW27A lFW828 lXl l l l l l l l l l l l l l l l 1 1 I I I I I l l l l l 1 1 I I I ICV-18 lFW617 lXl l l l l l l l l l l l l l l l l l 1 l l l l l l l l 1 l l l l l lWO7-1 lFW691 1Xl l l l l l l l l l l l l l

l l 1 1 I I I I I I I I I I I I I I I JCS-16 lFW194 lXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l lCS-15 lFW85 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l

lWQ5-1A lFW610 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l lSX-42 (RI) lXl

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l l l l l l l l l l l 1 1 1 I I i l I

ISI-29 lFW774 1Xl l l l l l l 1 l l l l l l l l l l l l l l 1 1 I I I I I I I I I

151-33-11 IFW992 l Xl l l l l l l l l l l l l l l l l l l l 1 I I I I I I I I I I I I

JSI-37 (R3) IFW626 lXl l l l l l l l l l l l l l 1 1 1 I I I I I I I I I I I I I I I I lSX-39-2 lFW2613 lXl l l l l l l l l l l l l l l l l l 1 1 I I I I I I I I I I I I l-lAF-27 lFW672 lXl l l l l l l l l l l l l l l l- 1 I I I I I I I I I I I I I I I I

IAF-27-1 lFW673 lXl l l l l l l l l l l l l l I I I I l i I I l l l 1 1 I I I I I I lCS-10 lFW20 lXl l l l l l l l l 1 l l l l l l 1 1 I I I I I I I I I I I I I I l IFSK-318-3 lFW3388 lXl 1 l l l l l l l l l l l l l l l 1 I I I l l l l l l l l l l l l lM5608 (1) -

lFW328 1Xl l l l l l l l l l l l l l l l l l 1 1 I I I l l l l l l l l 1 '

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l lFW27A lFW721 lXl l l l l l l 1 l l l l l l I

  • Those licensee file film compared with NRC film to verify correctness of file film

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ATTACHMENT 2

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C - CRACK LF - LACK FUSION A - ARTIFACTS SL - SLAG IP - INADEQUATE PENETRATION S - SURFACE P - POROSITY LI - LINEAR INDICATION CC - CONCAVITY-T - TUNGSTEN UI - UNFUSED INSERT CV - CONVEXITY Page 2 of 6 l SYSTEM /LINE l WELD ID lACCIREJI CISLl Pl TILFlIPILIIVII Al SICClCVI COMMENTS l l l l l l l l l l l l l l l l l l l IFW74 lFW764 lXl 1 l l l l l l l l l l l l l 1 -

1 I l l I I I I I l l I I l i i i IFW70 IFW982 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l 1 IM5578 lFW506 l Xl l l l l l l l l l l l l I l l l l l l l l l l 1 I l l l l l l l lMS-61-3 IFW516 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l 1 l l 1 1 I I l l I l l l l l l l l 1 1 I l l l l l l l l l l l l l JCSK-57-7 l l l l l l l l l l l l l l l l l 1 1 I I I I I I l l l l l l l l l l FSK-57-8 lFW55 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l 1 l l l

. IFP-81 l2630R1 l Xl l l l l l l l l l l l 1 l l l l l l l l l l l l l l 1 1 I I I I IFP-81 lFW2629R1 1 X l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l 1 1 IFP-67-4-BMR-R1 lRRWD-787 l Xl 1 l l l l l l l l l l l l l l l l 1 l l l l l l l l l l l l l l IFP-66-13 IFW2718 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l IFP-81-6BMR-R1 lRS-1 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l l 1 1 I l lFP-24-12BMR- lR1 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l IFP-28-4BMR lR1 l Xl l l l l l l l l l l l l l . l I I I I I I I I I I I I I I I I I l lFP-81 lFW2628 lXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l IFP-66 lFW2719 l Xl l l l l l l l l l l l l l l l l l 1 I I I I I I I I I I I .

I IFP-66 lFW2720 l Xl 1 l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l 1

'IFP-15-9BMR 1R1 l Xl l l l l l l l l l l l l l l l l l 1 I I I I I I I I I I I I I I lFW-54-5 IFW1115 lXl l l l l l l l l l l l l l 1 1 I l l l l l l l l l l l l l l lFP-81 lFW2723 l Xl l l l l l l l 1 l l l l l 1 1 1 1 I I I I I I i l I I I .

I I FP-81 IFW2724 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l IFP-HSL-100-71BMR lR1 l Xl l l l l l l l l l l l l l l

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I I I I I I I I I I I I I I I l l l lCV-001-299 IFW7250 l Xl l l l l l l l l l l l l l l

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

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. 3 ATTACHMENT 2

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C.- CRACK LF - LACK FUSION A - ARTIFACTS iSL - SLAG IP INADEQUATE PENETRATION S - SURFACE iP --POROSITY LI - LINEAR INDICATION CC - CONCAVITY T - TUNGSTEN UI - UNFUSED INSERT CV - CONVEXITY

-. Page 3 of 6 i SYSTEM /LINE I WELD ID lACCIREJl CISLI Pl TILFlIPILIIVII Al SICCICVI COMMENTS I i l I I i l l- l 1. I I I i l I i i l I l X '

CV-001-299

'

FW3005 l- l l l l .I l l l l l l l

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l .

I I .I I I I I I I I I I l ,

I I ICV-001-299 lFV3006 lXl l l l l l l l l l l l l 1 1 I I I I I l l l l 1 -l I ,

ICV-001-299 FW3008 lX1 l l l l l l l l l l l l l l l l l 1 1 I I I i l l I I l

. CV-001-299 IFW3009 l X l- l l l l l l 1 l l l l- l l l l l l l l l l l l l 1 1 I I I l CV-001-299 lFW3010 l X l' l l l l l l l l l l l l l l

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1 I l .I I I I I I I I I l l I I l CV-0011-299 'FW3011A lXl l l l- l l l l l l l l 1 -l

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-l l I I I I I I I I i i 1 I I I FW-54 lFW585RI lXI l l- l l l l l l l l l l l l

,

I I I l l I I l l l l l l l l l l

lCBE-1 IFW-188 l X -l l l l l l l l l l l l l l l- 1 I I I I l- 1 I I I I I I I I .

I 1RH-10-1 lW2 1 X-l l l l l l l l l

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-1 l l -l

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l I . 1 I I i 1 -l l I I l, 1 I I l lCS-18'(RI) lFW-207 lXl l l l l l ~l I l l l l l 1 I I l l- l l 1l I i .I l .I l l l l I i 1C5-18 lFW-204 lXl l l- l l -l -l l .I i l l l l .

I l -

I l l l I i l l I I I I I CS-18 FW-202 lXl l .I l l l l l l l 1l l l l

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'ICS-18 '-

lFW-203 .IX ll 1 l l l l l l l l l 'l l L I +

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I I I l l CS-18 lFW-205 l X' l l -l I l l 1 l l l l  !

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I I I I Il l l CS-16-6 " IFW-485*si Xi l l I I I l l

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' I r AN I l l -171 I I I I I I .

I I I h CS-16-14 . ' / FW-f31 *.(3Xl l 4 l l l l l l l l

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.. . CS-16-10 N IFW-537 Xl l l l l l l l l 1 l l 1

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Il l l- 1 i .I I l 'l - 1 I I I I ICS-16 IFW-470 l-X l l l l l 'l I l' l l l l l l N I 4 l 'd .I I I I Il 1l I i i l i I I f 1C5-16-3 IFW-475 lXl l' l l l l l 1/ l l l l l 1 l

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, ATTACHMENT 2

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~ C - CRACK LF - LACK FUSION A - ARTIFACTS SL - SLAG IP - INADEQUATE PENETRATION S - SURFACE P - POROSITY LI - LINEAR INDICATION CC - CONCAVITY-T - TUNGSTEN UI - UNF'3ED INSERT CV - CONVEXITY Page 4 of 6 l SYSTEM /LINE l-WELD ID lACCIREJi CISLl Pl TILFlIPILIlull Al SICClCVI COMMENiS l l l l l l l l l l l l l l l 1 I I I lCS-16 lFW-476 lXl l l l l l l l l l l l l 1 l

.I .

I I I I I I I I I I I I I I I I l lCS-16-11 lFW-481 l Xl l l l l l l l l l l l l l l l l I I I I I I I I I I I I I I I I lCV-19 lFW-630 lXl l l l l l l l l l l l l l l l l l 1 1 I I I I I I I I I I I I I CV-19 lFW-629 lXl l 1 I l l 1 l l l l l l l l l l 1 1 I I I I I I I I I I I I I ICV-19 IFW-634A lXl l l l l l l l l l l l l l l-l l I I I I I I I I I I I I I I I I ICV-19 lFW-635 iXl l l l l l l l l l l l l l l l l 1 I I I I I I I I I I I I I I I ICV-19 RI lFW-636 l Xl l l l l l l l l l l l l l l l l l l l l 1 l- I .

l l l l l l l lCV-19 lFW-631 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l- 1 I I I I I lMS-57-2 IFW-505 lXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l lRC-14 lFW-331 l Xl l l l l l l l l l l l l l l l l l l l l l l l 1 l l l l l l l l

lRC-11-12 lFW-394 l Xl l l l l l l l l l l l l l I I I I I I I I I I I I I I I I I I I

1RC-11-3 IFW-378 lXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l 1 1 I i

1RC-14-5 lFW-327 l Xl l l l l l l l l l l l l l 1 1 1 1 I l l l l l l l l l l l l l l

IRC-14-4 lFW-330 lXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l lRH-15 lFW-296 l Xl l l l l l l l l l l t l l l l l .I l l l l l l l l l l l i l I l lRC-10 IFW-101 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l ,

I I I I lRC-13 (R2) lFW-375 lXl l l l l l l l l l l l l l l l l l l l 1 I I I l l l l l l 1

151-29-1 lW-4 1Xl l l 1 l l l l l l l l l- l l 1 1 I I I I I I I I I I I I I I I I ISI-32-2 IW-2 lXl l l I l l l l l 1 l l l

l l l l l l l l l l l l 1 1 I I I

151-34-10 IW-5 l Xl l l l l l 1 l l l l l l l I I I l l l l l l l l l l l l 1 1 I I

"SX-39-2 IW-4 IXl l l l l l 1 1 I l l l l l l 1 I I I I I I I I l l I I l l I I I

lSX-42-1 lW-5 l Xl l l l l l l l l l l l l l I

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ATTACHMENT 2

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C - CRACK LF - LACK FUSION .

7, A - ARTIFACTS '

SL - SLAG '

IP - INADEQUATE PENETRATION Ss- SURFACE P - POROSITY LI - LINEAR INDICATION' CC'- CONCAVITY T - TUNGSTEN UI - UNFUSED INSERT 1 '

CV)- CONVEXITY >

\ Page 5 of 6 i SYSTEM /LINE I WELD ID IACCIREJl CISLI Pl TILFlIPILIIVIJ Al SICCICVI COMMENTS l l .I I I I I I I I I L 'l' I I I I I i 105-17-3 IW-5 l Xl l l l l l l 1 1 1 l l l l l

l l I l l l l l 1 l l 1 l l .I l l l 105-18-3 lW- l Xl l 1, I l l l l l 1: l l l I

l l l 'l l I I I_I I I I I I, I I I I l

3 lCV-17-17" lW-2 lXl l l .I 1. I Iil i 1 l l l l l L

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.. Al l I I i 1 I l<l l I I I I I I

I

.lCV-18-4 '

IW-2 21 J l l l l 5 l l l l l l l l l I; I I i I :l l l l l l l l l l l l l l lFW-7[-2 lW-6 -

lXl l l l l l l l l l l l l l l

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l , f I I I I I I I I I I I i l i I

IMS-57-5 '

(W-5 ICX l l l l l l l l l l l l 'l l l l l 1 1 I l 1l l l l l l l l l l

l lMS-61-7 IW-3 1Xl l l 4 'l l I l l l l l l l l l l l l l l l l' l l l l l l l l l /l

IRC-14-5 lW-6 l Xl l l l l l l l l l l 1 l l l 1 1 I I I I 'l l l I l i I I I I l lRH-9-6 *

lW-3 l Xl l l _1__ l l l l l l l l l l l l l l l l 'l 1 I I I I I I I I I I I IAF-27-1- lW-2 -1 X l l l I I l l l l l l l l l

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l 1 1 I I I J l i I I I I I i l- 1 *

I lAF-27-6 lW-3 lXl l l 1 l l l l l l l l I! l* l

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l . I I l I l l l l I I l I l' I i i l

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ICS-16-1 lW-2 IXl l l l l l l l l l (- l I l l I I I I I I l'l ,! 1 li i 1. I I l ,1 1 I

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L ICBE-4 lFW-50 l Xl l l .

1 1 Fl l l 'l l l l'

l I I I I I I I I l P l I l l I l '

I IMS-578 t IFW-319 l Xl ! l l l l l l l l 1 l l l l l .

> l l l l l l l l .I l l l l l l 1 ti ).

ICBE-3 IFW-204 l Xl l l l l l l l l l lil l 1< l'

I I I 4 I I I I l 'I I I I I I I I  ; I ICBE-3 IFW-205 lXl l l l l l >l l l l l'l l l l

'l t i I I I I I I I I I I I L0 1 I I JCBE-4 'L >

lFW-54 l Xl l l l l 1 l l l l l,I l l l l I I I I I I I I I I I I I I I I I lCBE-4 lFW-53 lXT I -l l l l l l l l l l 1 l l l l ) 1 ,

I I I I I I I I I si l l lCBE-1 IFV-181 .I X l l l l l l l 1 l l l l l !. l l rc l ~l I I I I I I I I I I I I I I I lRH-14-1-60 lW-2 l' X l l l l l l l l l l l l l l s I

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l I I l P I I I I I I I I I I I l l lRH-14-1-60 RR IW-2 lXl l l l _l l l l l l l l l' l l l l l l l l 1 ) i l l I I I I i i I IFW-53 lFW-600 l Xl l l l ,L l l l ( l l l l l l

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A 'y 1 s p _

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ATTACHMENT 2

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C - CRACK LF - LACK FUSION A - ARTIFACTS SL - S LAG - -IP - INADEQUATE PENETRATION S - SURFACE P - POROSITY LI - LINEAR INDICATION CC - CONCAVITY T - TUNGSTEN UI - UNFUSED INSERT CV - CONVEXITY Page 6 of 6 l SYSTEM /LINE I WELD ID lACCIREJl CISLI Pl TILFlIPILIlUll Al SICCICVI COMMENTS l-l l I I I I I I I I I I I I I I l l

FW-69 lFW-593 l Xl l l l l l l l l l l l l l l l l ,

I I I I I I I l l l l l l IFW-288 lFW-738 lXl l l l l l l l l l l l l l l l l l l 1 1 I I I l l l l l l l l l IFW-68 lFW-613 -l Xl l l l l l l l l l l l l l l l l l 1 I I I I I I I I I l l l l l

~lFW-298 lFW-716A lXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l IFW-25B IFW-750 lXl l l l l l l l l l l l l l l l l l l l 1 1 I I I I I I I I I I I IMS-61B .

IFW-329 l Xl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l lMS-60B IFW-324 iXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l lMS-568 lFW-314 iXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l 1-l2H-CBE-2 lFW-193 lXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l 1 1 I l2H-CBE-2 IFW-189 l Xl l l l l l l l l l l l l l l l l 1 I l l l l l l l l l l l l l l 12H-CBE-2 lFW-200 l Xl l l l l l l l l l l l l l l 1 l l 1 1 l l l l l l l l 1 l l l l 12H-CBE-3 (RI) IFW-201 l Xl l l l l l l l l l l l l l l 1 1 I I I I I I I I I I I I I I I i 12H-CBE-1 IFW-180 l Xl l l l l l l l l l l l l l l l 1 -

1 I I I I I I I I I I I I I I I 12H-CBE-2 IFW-192 lXl l I l l l l l l l l l l l l l l l l l l l 1 I I l l I I I I I I l2H-CBE-3 lFW-212 lXl l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l l 12H-CBE-1 (RSI) lFW-177 l Xl l l l l l l l l l l l l l l L

t

, ATTACHMENT 3

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REVIEW OF 00CUMENTATION PACKAGES Page 1 of 3 l LINE N0/ ISO l WELD NO l REVIEW l COMMENTS l l l l l l 12H-CBE-Surge l FW 45 l ACC l N/A l 1 1 I I I

" "

l2H-CBE-1- l FW 188 l l l l l l l l

" "

lWO-7-1 l FW 691 l l l l l l l l

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lH-WO-5-1A l FW 610 l l l l l l l l

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l2SX-42-1 l FW 2693 l l l l l l l l

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' lSX-39-2 l FW 2613 l l l I I l l l

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151-37 l FW 626 l l l l l l l l

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lSI-33-11 l FW 922 l l l l 1 I l l

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lSI-29-2 l FW 774 l l

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l l l 1 l l

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lRH-15-1 l FW 296 l l l l l l l l

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lRH-13-5 l FW 375 l l l l- 1 I l l

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lRH-10-7 l FW 101 l l l l l l l l

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!RC-14-5 l FW 327 l l l l l l l l

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lRC-14-4 l FW 330 l l

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l l l 1 1 I

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RC-14-4 l FW 331 l l l l l 1 1 RC-11-12 l FW 394 " - "

l l l

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I I I l

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lRC-11-3 l FW 379 l l l l 1 1 l

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l

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lRC-11-3 l FW 378 l l l I I I I l

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..lMS-60-8 l FW 452 l l l l l l l l

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lMS-56A-9 l FW 343 l l l

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ATTACHMENT 3

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l LINE N0/ ISO l WELD N0 i REVIEW l COMMENTS l l l 1 1 I

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lFW-28-A l FW 824 l l l l l l l l

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IFW-27-A I FW 828 l l l l l l l l

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lCV-18-4 I FW 617 l l l 1 1 I l l

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105-18-3 i FW 206 l l l l l l l l

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lCS-16-11- l FW 194 l l l l l l l l

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lCS-15-9 l FW 85 l l l l l l l l

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lAF-27-5 I FW 672 l l l l l l l l

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IAF-27-1 l FW 673 l l l l l l l l

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lSX-39-2 l SWF 4 l l l l l l l l

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AF-27-1 l SWF 3 I l l I I I I

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'CS-17-1 1 SWF 2 I l l l l l l

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lAE-27-6 l SWF-2 l l l

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l l l l l 1C5-16-1 l SWF-2 l l l l l l l l

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lCS-18-3 l SWF 2 I l l 1 1 I l l

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ICV-17-17 l SWF 2 l l l 1 l l l l

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lCV-18-4 l SWF 2 l l l l l l l l

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IFW-77-2 l SWF 6 l l l l l l l l

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lMS-57-5 i SWF 5 l l l l l l l l

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lMS-61-7 l SWF 3 l l l I I I i 1

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lRC-14-5 l SWF 6 l l l l l l

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I 1RH-9-6 l SWF 3 l l l l l l l l

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lRH-10-1 l SWF 2 l l l l l l l l

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lRH-14-1 l SWF 3 l l l l l l l l

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15I-29-1 l SWF 4 l l l l l l l l

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lSI-32-2 l SWF 4 l l l

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Page 3 of 3 I

I LINE N0/ ISO -l WELO NO l REVIEW l COMMENTS l-1 i -

1 l l lSI-34-10 'l SWF 2 l

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l-l l l l 1

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ATTACHMENT 4 Page 1 of 2 CAST STAINLESS ELBOW AREA DESCRIPTION EXTENT OF VOLUMETRIC EXAMINATION Loop A 27h" 2-Pipe to Elbows Pipe Side only 29" 1-Steam Generator to Elbow SG side only 2-Elbow to Valve No Volumetric 31" 1-Steam Generator to Elbow SG side only 4-Pipe to Elbow Pipe side only 1-Elbow to Pump No volumetrics

,

Ltop B ;274" 2-Pipe to Elbow Pipe side only 29 1-Steam Generator to Elbow SG side only 1-Elbow to Valve No volumetrics 31" 1-Steam Generator to Elbow SG side only 4-Pipe to Elbow Pipe side only

-

1-Elbow to Pump No volumetics Loop C 27 2-Pipe to Elbow Pipe side only 29" 1-Steam Generator to Elbow SG side only 1-Elbow to Valve No volumetrics

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ATTACHMENT 4 Page 2 of 2 Lcop C _31" 1-Steam Generator to Elbow SG side only 4-Pipe to Elbow Pipe side only 1-Elbow to Pump No volumetrics Loop D 27h" 2-Pipe'to Elbow Pipe side only 29" 1-Steam Generator to Elbow SG side only 1-Elbow to Valve No volumetric *

31" 1-Steam Generator to Elbow SG side only 4-Pipe to Elbow Pipe side only 1-Elbow to. Pump No volumetrics Material Elbows Cast Stainless Steel SA-351-CF8A

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ATTACHMENT 4 Page 2 of 2 Loop C 31"' 1-Steam Generator to Elbow SG side only 4-Pipe to Elbow Pipe side only 1-Elbow to Pump No volumetrics Loop D 27h" 2-Pipe'to Elbow Pipe side only 29" 1-Steam Generator to Elbow SG side only 1-Elbow to Valve No volumetric *

31" 1-Steam Generator to Elbow SG side only 4-Pipe to Elbow Pipe side only 1-Elbow to Pump No volumetrics

' Material Elbows Cast Stainless Steel SA-351-CF8A

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ATTACHMENT 5 BYRON PROJECT CONSTRUCTION / NUCLEAR REGULATORY COMMISSION MEETING OF NOVEMBER 5, 1985 Attendance Name Title Organization R. P. Tuetken Start-Up Superintendent Ceco. Byron Station Ram Gaitonde Supervising Staff Engineer Ceco. System Material Analysis Department W. W. Witt- General Supervisor NDE Ceco. System Material Analysis Department R. Moravec Lead Mechanical Engineer Ceco. Project Construction Department D.'Christiana Mechanical Engineer Ceco. Project Engineering Department J. Porter Construction Supervisor Ceco. Project Engineering Department H. Kerch Lead Reactor Engineer USNRC RI K. Ward Lead Reactor Engineer USNRC RIII

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