IR 05000413/1994014

Insp Repts 50-413/94-14 & 50-414/94-14 on 940509-20.No Violations Noted.Major Areas Inspected:Isi & Flow Assisted Corrosion

ML20149F618
Person / Time
Site:	Catawba
Issue date:	06/03/1994
From:	Blake J, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20149F599	List: IR 05000413/1994014 ML20149F595
References
50-413-94-14, 50-414-94-14, NUDOCS 9408110037
Download: ML20149F618 (16)

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UNITED STATES NUCLEAR REGULATORY COMMISSION

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E 101 MARIETTA STREET, N.W., SUITE 2900 L-j ATLANTA, GEORGIA 30323-0199 t

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Report Nos.:

50-413/94-14 and 50-414/94-14 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos..

50-413 and 50-414 License Nos.: NPF-35 and NPF-52 Facility Name: r.atawba 1 and 2 l

l Inspection Conducted: May 9-13 and 16-20, 1994 Inspect r:

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i '~ P. Kleinsorge P.E.

Date Signed R ac or Inspector Approved by:

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Jerom J. Blalpf, Chief Date Signed Mate als anf Process Section Engi eering Branch Division of Reactor Safety l

SUMMARY Scope:

This routine, announced inspection was conducted in the areas of Inservice Inspection (ISI) and Flow Assisted Corrosion (FAC).

Results:

The Review of the licensee's Inservice Inspection (ISI) program indicates adequate management and control of the program currently in place.

The inspector noted a programmatic weaknesses in the administrative controls for the NDE manual, which could lead to hardware problems in the future. Notwith-standing the NDE procedures were noted to be very detailed, well organized and technically effective in implementing the applicable code requirements with minor exceptions.

The licensee's ISI Coordinator, Level III examiner, and NDE supervisors were actively involved in the resolution of technical issues

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and ensuring that all quality objectives were properly addressed by examiners.

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The inspector noted a weakness in the licensee's control of the application of coatings on pipe supports.

Some welders exhibited a lack of understanding of welding interpass tempera-ture control and, purge and shielding gas flow control.

Some of the licen-see's Welding Procedure Specifications, though in compliance with the letter 940811oo37 940617 gDR ADOCK 05000413 PDR

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of the Code, had very wide ranges for welding current and voltage, thus

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rendering them not very useful to the welders.

It appears that the licensee has established an effective program to maintain I

high energy carbon steel piping systems within acceptable wall thickness limits.

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In the areas inspected, no violations or deviations were identified.

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REPORT DETAILS 1.

Persons Contacted Licensee Employees

• C. Cauthen, Program Manager Steam Generator (S/G) Maintenance J. Cherry, Quality Assurance (QA) Specialist-Quality Assurance Technical Services (QATS)

• J. Forbs, Engineering Manager

• R. Giles, Inservice Inspection (ISI) Coordinator

• C. Kelly, Program Support Manager

• J.

McArdle, NDE Level III W. McCollum, Station Manager

• K. Nicholson, Compliance Specialist

• R. Pettit, Nondestructive Examination (NDE) Supervisor

• D. Rehn, Site Vice President D. Smith, Nuclear Generation Engineer

• Z. Taylor Regulatory Compliance Manager

• T. Tucker, NDE Level III Other licensee employees contacted included, engineers, technicians, security force members, and office personnel.

NRC Resident Inspectors

• R. Freudenberger, Senior Resident Inspector (SRI)

P. Hopkins, Resident Inspector (RI)

J. Zeiler, RI

• Attended exit interview.

Acronyms and initialisms used throughout this report are listed in the last paragraph.

2.

Inservice Inspection (ISI)

The inspector reviewed documents and records, and observed activities, as indicated below, to determine whether ISI was being conducted in accor-dance with applicable procedures, regulatory requirements, and licensee commitments. The applicable Code for ISI, for both Unit I and Unit 2, is the ASME B&PV Code,Section XI, 1980 Edition with Addenda through Winter 1981 (80W81). Unit 1, in their eighth fuel cycle, is operating in the third 40 month period, of the first ten year ISI interval (P3,II)

scheduled to end June 28, 1995. Unit I was granted a Construction Permit August 7, 1975, received their operating license on January 17, 1985 and commenced commercial operations on June 29, 1985.

Unit 2 was granted their Construction Permit August 7, 1975, received their operating license May 15, 1986, and commenced commercial operations on August 19, 1986. Unit 2 is in their sixth refueling outage E006 (End of Cycle 6)

the first outage of the third 40 month period, of the first ten year ISI interval (01,P3,II) scheduled to end August 18, 199 _ _ _ _

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j The licensee's nondestructive examination personnel are performing liquid i

penetrant (PT), magnetic particle (MT), ultrasonic (UT), visual (VT), and

eddy current (EC) examinations, under the umbrella of the Duke QA

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Program.

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a.

ISI Program Review, Units 1 and 2 (73051)

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The inspector reviewed the following documents relating to the ISI

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program to determine whether the plan had been approved by the licensee and to assure that procedures and plans had been estab-

lished for the applicable activities.

Procedures were also reviewed l

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for technical content.

i Procedures Reviewed

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ID Rev.

Title

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NISIRUNB-

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E006 Inservice Inspection Plan QAISIO2

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5/2/94

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Unit 2 Ten Year Inservice Inspec-l 4/27/94 tion Plan The Plan procedures were well written and appropriate for their

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l intended application.

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Review of NDE Procedures, Units 1 and 2 (73052)

The inspector reviewed the procedures listed below to determine whether these procedures were consistent with regulatory require-

ments and licensee commitments.

The procedures were also reviewed i

for technical content.

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Procedures Reviewed

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ID Rev.

Title

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NDE-25 15 w/

Magnetic Particle Examination FC 94-05 Procedure and Techniques (5/18/94)

FC 94-01 (5/11/94)

FC 93-36 (9/14/93)

FC 93-32 (8/27/93)

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Procedures Reviewed

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ID Rev.

Title NDE-35 14 w/

Liquid Penetrant Examination FC 94-06 (5/18/94)

FC 93-26 (5/26/93)

FC 93-18 (4/28/93)

NDE-90 Referencing System For Layout i

2/27/91

and Marking of Welds i

2/23/94

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NDE-A

Nondestructive Examination Pro-

5/18/94 gram Procedure f

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Training Qualification and Cer-

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1/27/93 tification of NDE Personnel NDE-C 4 w/

Calibration / Verification of NDE

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3/4/92 FC 93-29 Equipment

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(8/30/93)

FC 92-13 (7/9/92)

QAL-13

Inservice Inspection (ISI) Visu-l 3/19/93 al Examination VT-1 i

QAL-14

ISI Visual Examination VT-3 and

11/2/92 VT-4 l

QAL-15

Inservice Inspection (ISI) Visu-3/18/94 al Examination VT-2 Pressure

Test

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The NDE Manual, in four volumes, recently reissued with green covers, contains the procedures prefixed by "NDE."

In examining t

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the "NDE " procedures the inspector noted the following:

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o The NDE Manuals are not required to be, and are not in prac-l tice, identified with a manual serial numbers or the identifi-i-

cation of the manual holders.

The concern here is the poten-tial of comming1tng of volumes between multiple manual sets in the same work space, o

The licensee indicated that there is up to a 30-day turn-around period for revisions to NDE Manual procedures.

In order to continue the flow of work, and to avoid delays in examination activities, Procedure NDE-A, Revision 13, " Nondestructive Examination Program Procedure," provides for " Working Copies"

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of revised procedures to be issued in advance of the normal distribution of the NDE Manual procedure revisions. With the exception of the " cognizant NDE Supervisor" and the Manager, Quality Assurance / Technical Services, the distribution of

" Working Copy" documents is undefined. There is no mechanism to notify manual holders, who did not receive the " Working Copy" documents, that there are NDE Manual procedure changes in

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effect.

The concern here is, with two revisions of NDE Manual procedures "on-the-street" at the same time and an undefined distribution list, that NDE Manual holders, with oversight or collateral responsibilities, may not be aware of the NDE Manual procedure revisions.

o NDE-A, Revision 13, dated May 18, 1994, requires commitments to revise NDE Manual procedures resulting from the Problem Inves-tigation Process (PIP), be identified in the procedure change i

and be referenced to the PIP number.

Field Change (FC) 94-05, applicable to NDE-25, and FC 94-06 applicable to NDE-35, both issued on May 18, 1994, do not reference PIP 1-C93-1064, which

mandated the FCs.

The above represents programmatic weaknesses in the administrative controls for the NDE manual, which could lead to hardware problems

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in the future.

Procedure QAL-14, Revision 13, "ISI Visual Examination VT-3 and VT-4," requires examiners to report " excessive corrosion," but does not define " excessive."

With the exception of the above, the procedures were well written and appropriate for their intended application.

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Observation of Work and Work Activities, Unit 2 (73753)

i Tne inspector observed work activities, reviewed certification records of NDE equipment and materials, and reviewed NDE personnel qualifications for personnel who had been utilized in the ISI examinations during this outage.

The observations and reviews conducted by the inspector are documented below.

Activities Observed j

Liquid Penetrant Examination (PT)

The inspector observed PT examinations of the welds listed below.

The observations were compared with the applicable procedures and the Code. The inspector performed an independent evaluation of the indications obtained to confirm the NDE examiner's evaluation.

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PT Examinations Observed Item No.

Weld Component Comments B05.040.003A 2PRZ-W3SE Pressurizer Noz-No relevant indi-zle to Safe-End cations i

B05.040.004A 2PRZ-4ASE Pressurizer Noz-No relevant indi-

zle to Safe-End cations

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B05.040.005A 2PRZ-W4BSE Pressurizer Noz-No relevant indi-zle to Safe-End cations B09.0ll.061A 2NCll2-05 Reactor Coolant No relevant indi-

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Safe-End To 6" cations Elbow

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l B09.0ll.064A 2NC119-01 Reactor Coolant No relevant indi-Safe-End To 6" cations Pipe B09.0ll.065A 2NC119-03 Reactor Coolant No relevant indi-6" Pipe to Elbow cations 809.011.072A 2NC163-01 Reactor Coolant No relevant indi-Safe-End To 6" cations

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Elbow

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809.0ll.073A 2NC163-03 Reactor Coolant No relevant indi-

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6" Elbow to Pipe cations B09.0ll.074A 2NC163-04 Reactor Coolant No relevant indi-6" Pipe to Elbow cations 809.0ll.075A 2NC163-06 Reactor Coolant No relevant indi-6" Pipe to Flange cations The inspector reviewed the certification, qualification, and visual acuity documentation for the PT examiners (See paragraph 2.d below).

i The performance of the exam + ations was satisfactory.

Magnetic Particle Examination (NT)

The inspector observed MT examination of the weld listed below. The observations were compared with the applicable procedures and the Code. The inspector performed an independent evaluation of the indications obtained to confirm the NDE examiner's evaluation.

MT Examinations Observed Item No.

Weld Component Comments C05.021.404A 2SM-12-01 32" Steam Genera-No relevant in-tor Nozzle to dications Pipe Weld

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The inspector reviewed the certification documentation for the MT powder, the yoke, and the 10 lbs. test weight (See Paragraph 2.d below).

The inspector reviewed the certification, qualification, and visual

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acuity documentation for the MT examiners (See paragraph 2.d below).

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The examination was performed satisfactorily.

Ultrasonic Examination (UT)

The inspector observed UT examinations of the welds listed below.

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The observations were compared with the applicable procedures and the Code. The inspector performed an independent evaluation of the i

indications obtained to confirm the NDE examiner's evaluation.

i UT Examinations Observed Item No.

Weld Component Comments B09.011.200 2ND66-04 Residual Heat Re-No relevant indi-moval 12" Pipe to cations Elbow B09.011.202 2ND66-07 Residual Heat Re-No relevant indi-

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moval 12" Pipe to cations Elbow B09.011.203 2ND66-12 Residual Heat Re-No relevant indi-

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moval 12" Pipe to cations Elbow The inspector reviewed the certification documentation for the UT instruments, transducers, and couplant (See paragraph 2.d below).

The inspector reviewed the certification, qualification, and visual acuity documentation for the UT examiners (See paragraph 2.d below).

The examinations were performed satisfactorily.

Visual Examination (VT)

The inspector observed VT-3 VT examinations of the supports /-

restraints listed below. The observations were compared with the applicable procedures and the Code. The inspector performed an

independent evaluation of the indications obtained to confirm the NDE examiner's evaluation.

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VT-3 Examinations Observed Item No.

Support No Support Type Comments

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F1.02.941 2-R-SV-1606 Main Steam Vent to Paint on Atmosphere spherical bearing Rigid Support ball F1.02.943 2-R-SV-1608 Main Steam Vent to Paint on Atmosphere Rigid spherical bearing Support-bal1

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F1.02.948 2-R-CA-1028 Auxiliary Feed-Spherical bearing

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water Rigid Sup-out of position, port paint on spheri-cal bearing ball l

F1.01.469 2-R-NI-1845 Safety Injection No significant

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Rigid Support conditions noted F1.01.312 2-R-ND-1016 Residual Heat Re-Loose strut lock moval Rigid Sup-nut, paint on

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port spherical bearing ball, and NPT tag missing rivets F1.02.169 2-R-CF-1000 Feedwater No relevant indi-Mechanical Snubber cations F1.02.172 2-R-CF-1002 Feedwater Spherical bearing

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Mechanical Snubber out of position, Paint on spheri-cal bearing ball With regard to the VT examinations above, the inspector noted paint on the spherical bearings of the first two supports examined, one of the supports appeared to be frozen as a consequence of the painted bearing. After the VT-3 examiner indicated that the two supports were acceptable, the inspector informed the VT-3 examiner of the paint on the spherical bearings.

The VT-3 examiner then annotated the painted bearings on the examination report for those two sup-

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ports and on the subsequent supports with similar conditions.

Although procedure QAL-14, Revision 13, "ISI Visual Examination VT-3 and VT-4," does not specifically identify paint on spherical bear-ings as an attribute for VT-3 examinations, paragraph 5.11.2 of QAL-14 states in part:

" Examine VT-4, Category F-C supports for:... d.

paint... f. other foreign material on moving parts...."

Qual-14, Table E states in part:

" Supports exhibiting any of the following items shall be considered unacceptable for continued service without supplemental NDE or evaluation:.. 8.... Paint,...or Other Foreign Material on Moving Parts or Interfaces Which Would Prohibit Required Freedom of Movement..

10.... Paint,...on close tolerance machined or sliding surfaces (Sic)." Maintenance Procedure MP/0/A/7650/096,

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" Catawba Nuclear Station Administrative Control of Applied Coat-ings," dated November 17, 1992, paragraph 11.3.5 states in part:

"The supervisor or his designee shall verify that equipment or items to be coated /or blasted are adequately protected. This includes the following items... Pipe Supports (hangers, snubbers hydraulic cylin-

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ders and struts)... Swivel Bearings..."

The coating supervisor or his designee did not adequately protect the spherical bearings prior to coating application.

In addition the VT-3 examiner did not identify a condition adverse to quality as defined in:

QAL-14, paragraph 5.11.2 and Table E; and MP/0/A/7650/096, paragraph 11.3.5.

The above is a weakness in the licensee's control of the application of coatings on pipe supports.

The licensee indicated that they are tracking this issue in PIP 2-C94-0683.

Notwithstanding the licensee's weakness in the area of control of coatings and the paint on spherical bearing surfaces, the inspector came to the conclusion that paint on the bearing surfaces would not affect the ability of the supports to perform their intended safety-related function.

Except as noted above, the examinations were performed satisfactorily.

Repair and Replacement The inspector observed repair and replacement activities associated with the Feedwater (CF) and Auxiliary Feedwater (CA) systems, which is discussed further in paragraph 3 below, d.

Data Review and Evaluation, Unit 2 (73755)

The inspector reviewed completed ISI examination records and the supporting certification for:

examiner qualification, certification and visual acuity; PT cleaner, penetrant and developer; MT powder, yokes and 10 lbs. test weights; and UT instruments, transducers, and couplant. The inspector also reviewed baseline data of the welds to determine whether the indications were previously recorded and if so, were there any noticeable differences in the recorded informa-tion.

Records for the following welds and the supporting data were reviewed:

Examination Records Examined Item No.

Weld /Com-Component Examination ponent ID Method B03.110.004 2PRZ-W4A Pressurizer Safety UT Nozzle to Upper Head Inner Radius

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i Examination Records Examined

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Item No.

Weld /Com-Component Examination F

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ponent ID Method B05.040.003 2PRZ-W3SE 6" Pressurizer UT Nozzle to Pipe 805.070.005A 2SGC-IN-Reactor Coolant PT LET-SE Nozzle on Steam Generator B05.070.006A 2SGC-0VT-Reactor Coolant PT

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LET-SE Nozzle on Steam i

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Generator-B05.130.011A-2NC13-03 31" Reactor Cool-PT i

ant B05.130.011A 2NC13-03 31" Reactor Cocl-PT ant B06.040.039 2RPV-Reactor Vessel UT THREAD-39 Threads in Flange B06.040.040 2RPV-Reactor Vessel UT THREAD-40 Threads in Flange B06.040.041 2RPV-Reactor Vessel UT

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THREAD-41 Threads in Flange B09.011.061B 2NC112-05 6" Pressurizer UT Nozzle to Pipe i

B09.021.152 2NV185-01 3" Chemical and PT Volume Control i

B09.021.153 2NV185-02 3" Chemical and PT

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Volume Control i

B09.040.039 2NC141-02 1.5" Reactor Cool-PT

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ant B09.040.040 2NC141-04 1.5" Reactor Cool-PT ant 809.110.072B 2NC-163-01 6" Pressurizer UT Nozzle to Pipe C02021.005A 2SGB-SB-11 16" Feedwater Noz-MT

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i NDE Equipment and Consumables Records Examined Equipment /Consumables Serial No/ Heat No./ Lot No./

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Batch No.

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PT Cleaner 126-86 and 92006K PT Developer 216-Y56 and 93L0lK PT Penetrant 124-854 and 78E084 MT Orange Powder 850037 MT 10 lbs. Test Weight MTC-1 MT Yoke ES-6-1 UT Instruments 32810-795, 32810-775, and 975K UT Transducers G07879(SP),G10063,224-93002 33240, and J19024(SP)

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UT Couplant 09300 Thermometers MCNDE 27024 and MCNDE 27016 Qualification, certification, and Visual Acuity Records Examined Examiner Method-Level JKT PT-II MY-II RT-II GEH MT-II VT-II JAE MT-II UT-II WCL UT-II RS UT-II i

MTW UT-II I

RBC UT II l

JS PT-II l

Records support the conclusion that examinations were conducted in accordance with applicable procedures and regulatory commitments.

Within the areas examined no violations or deviations were identified.

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3.

Flow Accelerated Corrosion (FAC) (49001)

The licensee has established a FAC inspection program which implements the CHECMATES EPRI (Electric Power Research Institute) computer code, industry experience, and previous inspection data as predictive tools for

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determining and prioritizing inspection locations. The inspector conducted interviews with licensee personnel and reviewed records as

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indicated below.

Observations / Findings During E006, the licensee planned to examine 87 locations in their FAC program. At this writing the licensee had examined 77 locations and identified one FAC degraded component for replacement. The licensee indicated that the sample size has been significantly reduced as a result of significant replacement of carbon steel piping with stainless steel

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piping and modification of secondary water chemistry.

The licensee was in the process of replacing approximately 460 feet of carbon steel pipe with stainless steel pipe in the CA and CF systems.

The need for this replacement was identified during previous outages.

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The inspector observed welding activities associated with welds 2CA131-23, 2CA131-24, 2CA69-2, 2CA69-3, 2CA69-68, and 2CA69-69.

In addition t b inspector visually inspected:

inprocess welds 2CA69-64, 2CA69-65, 2CA69-66, and 2CA69-67; and completed welds 2CA37-79, 2CA37-80, 2CA37-81, 2CA37-82, and 2CA37-83.

The observations were compared with the applica-ble procedures and the Code.

Relative to the examinations indicated above the inspector noted the following:

o The welder of record for weld Nos. 2CA131-23 and 2CA131-24 did not appear to understand the proper implementation of welding procedure interpass temperature control. The inspector discussed the impor-tance of interpass temperature control with both the welder and licensee management.

o The welder of record, for weld:, Nos. 2CA69-68, 2CA69-69, 2CA69-2, and 2CA69-3, did not understand the necessity for the site glasses in purge and shielding gas flow meters to be in the vertical posi-tion.

The inspector discussed the importance of flow meter sight glass position with the welder and licenses management.

The licensee indicated that they would discuss both issues with welders to assure understanding in both areas.

The inspector examined welder qualification certification documentation, Quality Control (QC) inspector qualification certification and visual acuity documentation, welding filler material certified material test reports (CMTRs), and welding procedure specifications (WPSs) and their associated procedure qualification records (PQRs), for the welders, QC inspectors, materials, and procedures employed to make the following welds:

2CA153-52, 2CF97-18, 2CA-73-51, 2CA73-48, 2CA153-48, 2CF37-73, 2CA153-46, and 2CA153-59. The inspector examined CMTRs for selected base materials joined by the above welds. The documents were examined for compliance with licensee procedures and Sections II, IX and XI to the ASME B&PV Cod.

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Welding Filler Material CMTRs Examined Type Size Heat / Lot No.

AE-308EB 5/32" E4252T-308 ER-308 1/8" PF-506 ER-308 1/8" 467832

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ER-308 3/32" PG-850 ER-309 1/8" PF-511

Welder's Qualification Certification Documentation Examined i

H6244, L9406, C8419, M6713, and F1462

f QC Inspector Certification and Documentation Examined

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BC Welding, JEH PT-II and VT-II, KLW RT-II, and DAT RT-II

WPSs Examined WPS PQR

L-365, Revision 4 L-145A L-262, Revision 3 L-111 L-232, Revision 12 L-112, L138 and L-108 i

The WPSs examined above were all properly supported by PQRs, however the non-essential variables of welding current and welding voltage, -in WPS L-232 and L-365 had extremely wide ranges. Typical example is30-180 Amps at 7-14 Volts for all passes, for sizes 1/16", 3/32" and 1/8" diameter filler material and both 1/8" and 5/32" diameter consumable inserts. The WPSs meet the letter of the code but are not very useful tools for welder.

The welds were made by properly qualified and certified welders, using appropriate welding materials in accordance with properly qualified welding procedure specifications.

The licensee is in the process of converting their Unit 2 CHECMATES data to CHECWORKSS which operates in the Microsoft Windows * environment.

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13 The licensee has established and continues to implement an effective program to maintain high energy carbon steel piping systems within acceptable wall thickness limits.

Within the areas examined, no violations or deviations were identified.

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Followup (92701)

i (Closed) Violation: 50-413,414/93-32-01:

Failure to Include Code Re-l quired Welds Subject to Examination in Facility ISI l

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This violation concerned the licensee's failure to provide for Code required surface examinations on safe-end to pipe welds in each of the four safety injection accumulator tanks for Catawba Units 1 and 2.

The NRC has reviewed the licensee's letter of response dated March 10, 1994, and found it acceptable.

In their letter of response the licensee admitted to the violation and attributed the cause of this violation to an oversight during the development of the original First Interval Inservice Inspection Plan for Catawba Units 1 and 2, in 1984 through 1985. The licensee has added the eight welds to the respective ISI pl ans. The four welds in Unit I were examined during U1E0C7, and the four welds in Unit 2 are scheduled to be examined during U2E0CS in the spring of 1994.

The inspector is satisfied that the licensee has corrected the specific discrepant conditions, and performed the necessary survey to determine the full extent of the problem. The inspector examined the licensee's corrective actions as described in their letter of response, and determined that the licensee has taken appropriate actions to prevent recurrence.

This matter is considered closed.

(Closed) Unresolved Item:

50-413,414/92-30-01:

" Priority 2 IAE Pro-cedure Upgrades Due April 30, 1993" This issue concerns approximately 556 Priority 2 Instrumentation and Electrical (IAE) procedures that the licensee committed to upgrade by April 30, 1993. The licensee has completed the upgrade of all the IAE Priority 2 procedures. The inspector examined a sample of the revised procedures. This issue is considered closed.

(Closed) Unresolved Item:

50-413,414/92-30-02:

"Pr;nrity 3 IAE Pro-cedures Upgrades Due August 1, 1994" This item was opened to track an original population of approximately 557 Priority 3 IAE procedures that the licensee committed to upgrade by August 1, 1994.

Since December 1992, the total population has changed due to a combination of the following:

new procedures added to the population; procedures dropped from the population; and the combination of procedures. To date the licensee has completed 315 procedure upgrades with 246 procedures remaining to be upgraded. The licensee has document-ed this upgrade program in PIP 0-093-0546.

The licensee committed to provide the SRI a quarterly report of the IAE procedure upgrade status.

The licensee indicated that they would complete the task by September 1,

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1995. As this item was opened only to track the IAE procedure upgrade j

status, which will now be tracked by the PIP and the quarterly status reports to the SRI, this item is no longer necessary and is here by l

closed.

(Closed) Unresolved Item:

50-413,414/93-32-02: "Use of Gray Magnetic Powder on Bright Metal Finish Weldments" This issue concerns the marginal contrast quality obtained between bright metal finished weldments and the gray magnetic particle powder used for MT examinations at Duke sites. The inspector of record suggested that if the licensee wished to continue the present practice (using gray magnetic particle powder on bright metal finished weldments during MT examinations) they should be prepared to prove, by demonstration, the adequacy of using gray magnetic j

particles over a wide color spectrum of welds and materials under field conditions. The licensee agreed to pursue this matter further and report back during a future RII inspection.

The licensee documented this issue in PIP l-093-1064. On May 11, 1994, the licensee issued NDE FC 94-01 to procedure NDE-25, " Magnetic Particle

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Examination Procedure and Technique," Revision 15 applicable to all Duke

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nuclear stations, which prohibits the use of No.1 gray dry powder on freshly ground or polished surfaces. This issue is considered closed.

(0 pen) Unresolved Item:

50-413,414/93-33-01:

" Pipe Support Insulation Removal Problems During the ISI Inspection"

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This item concerns loose bolts found on two pipe supports:

1-R-SV-1514 and 1-R-SV-1515. The loose fasteners were identified when the NRC inspector of record requested that insulation be moved in order to examine pipe supports fasteners obscured from view by soft insulation.

NRC IR 50-413,414/93-33 reported that the QC inspector's interpretation and his supervisor's interpretation of their procedure and code require-ments, was that there is no need to remove insulation during the ISI except when an integral weld exists between the support members and pipe.

The licensee identified this issue in PIP 0-C94-0289.

The licensee corrected the discrepancies with Work Order (W/0) 93041191.

PIP 0-C94-0289 indicated that the "S" dimension for the clamp separation was measured and found acceptable and that there were no operational con-cerns.

The proposed resolution, as indicated in PIP 0-C94-0289, was to remove insulation as necessary and inspect, for loose bolting on all Sup-ports / Restraints (S/R), which utilize pipe clamps, scheduled for ISI i

examination during Unit 2 E0C6. The expected sample population is approximately 100 S/R. This sample will be used as the basis for deci-sions and future actions concerning insulation removal.

The above examinations are in progress at this writing.

This item remains open pending the completion of the licensee's inspections and

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engineering evaluations of the resulting data and subsequent NRC review.

The expected completion date is August 31, 1994.

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Weakness:

IR 50-413,414/93-32 The inspector of record for IR 50-413,414/93-32, identified a lack of consistency in weld identification and referencing. The inspector of record identified this matter to the licensee as a programmatic weakness l

which required appropriate action to preclude possible problems.

l The licensee addressed this issue in PIP 1-C93-1064.

This PIP indicated

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that the corrective action taken was a revision to Procedure NDE-90, l

" Referencing System for Layout and Marking of Welds," Revision 2, dated l

March 10, 1994. This inspector reviewed NDE 90 and noted that NDE-90 only addressed UT examinations. This inspector informed the licensee that ASME B&PV Code Section XI, paragraph IWA-2600 requires a referencing system be established for welds and areas subject to both volumetric and surface examinations. These welds and areas shall be located and identified by a system of reference points. The licensee responded by amending the surface examination procedures (NDE-25 and NDE-35 with FC 94-05 and FC 94-06 respectively) to address the requirements of IWA-2600.

This inspector has no further questions in this area.

Within the areas examined no violations or deviations were identified.

5.

Exit Interview The inspection scope and results were summarized on May 20, 1993, with those persons indicated in paragraph 1.

The inspector described the areas inspected. Although reviewed during this inspection, proprietary information is not contained in this report.

Dissenting comments were not received from the licensee.

6.

Acronyms and Initialisms ASME -

American Society of Mechanical Engineers B&PV -

Boiler and Pressure Vessel

CA

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Auxiliary Feedwater CF

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Feedwater j

CMTR -

Certified Material Test Report EC Eddy Current

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E0C -

End of Cycle EPRI -

Electric Power Research Institute FAC -

Flow Accelerated Corrosion FC

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Field Change

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IAE -

Instrumentation and Electrical ID

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Identification IR

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Inspection Report

ISI

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Inservice Inspection

MT

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Magnetic Particle

NC

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North Carolina

NC

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Reactor Coolant

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ND

-

Residual Heat Removal

NDE -

Nondestructive Examination

NI

-

Safety Injection

NPF -

Nuclear Power Facility

NRC -

Nuclear Regulatory Commission

NV

-

Chemical Volume and Control

P.E. -

Professional Engineer

PIP -

Problem Investigation Process

PQR -

Procedure Qualification Record

PRZ -

Pressurizer

PT

-

Liquid Penetrant

QA

-

Quality Assurance

QATS -

Quality Assurance / Technical Support

QC

-

Quality Control

RI

Resident Inspector

-

RPV -

Reactor Pressure Vessel

S/G -

Steam Generator

S/R -

Support / Restraint

South Carolina

SC

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SM

-

Main Steam

SRI -

Senior Resident Inspector

SV

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Main Steam Ver.c to Atmosphere

UT

-

Ultrasonic

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w/

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with

W/0 -

Work Order

WPS -

Welding Procedure Specification