IR 05000413/1980024

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IE Insp Repts 50-413/80-24 & 50-414/80-24 on 800902-05. Noncompliance Noted:Inadequate Measures for Storage & Abandoned Welding Matl
ML19290G622
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 10/07/1980
From: Herdt A, Kleinsorge W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19290G609 List:
References
50-413-80-24, 50-414-80-24, NUDOCS 8012180150
Download: ML19290G622 (7)


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'o UNITED STATES 5,y h. #, [7 8 'y NUCLEAR REGULATORY COMMISSION

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ATLANTA, GEORGIA 30303

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Report Nos. 50-413/80-24 and 50-414/80-24 Licensee: Duxe Power Company

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422 South Church Street Charlotte, NC 28242 Facility Name:

Catawba License Nos. CPPR-116 and CPPR-117 Docket Nos. 50-413 and 50-414 Inspection 1 e

< i South Carolina Inspector: fk h:2 opff

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P. K1dinsorge Date Signed

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/(J A. R. Herdt, Section Chief, RC&ES 3 ranch Dite/digned SUTIARY Inspection on September 2-5, 1980 Areas Inspected This routine, resident inspection involved 32 inspector-hours onsite in the areas of licensee action on previous inspection findings, post weld heat treatment, equipment s to ra ge (Units 1 and 2), welding filler material control (Unit 1), chloride control, visual inspector qualification, reactor coolant pressure boundry piping observation of work and work activities (Unit 2), safety related piping observation of work and work activities (Unit 2) containment (structural steel welding)

observation of work and work activities (Unit 2)

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and review of non-conformance reports.

Results Of the ten areas inspected, no items of noncompliance or deviations were identified in eight areas; one item of noncompliance was found in each of two areas.

(Infraction - " Inadequate Measures for Storage" paragraph Sc; Deficiency -

" Abandoned Welding Materials" -Paragraph 5d.)

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DETAILS 1.

Licensee Employees Persons Contacted D. G. Beam, Project Manager

  • D.

L. Freeze, Project Engineer

  • R. A. Morgan, Senior QA Engineer R. G. Rouse, QA Technician
  • J. C. Shropshire, QA Engineer (QAE) Mechanical, Welding
  • S. W. Dressler, Senior Construction Engineer
  • L, R. Davison, Senior QC Engineer L. L. Atkins, QA Other Jicensee employees contacted included ten construction craftsmen, three technicians, and four engineers.

Other Organizations Hartford Steam Boiler Inspection and Insurance Company C. F. Toegel, Authorized Nuclear Inspector (ANI)

  • J. W. Kosko, ANI
  • B. Wood, ANI 2.

Exit Interview The inspection scope and findings were summarized on September 5, 1980 with those persoca indicated in Paragraph 1 above. The inspector identified the areas inspected and discussed in detail the items of noncompliance and the unresolved items. No dissenting comments were received f rom the licensee.

3.

Licensee Action on Previous Inspection Findings (Closed) Deficiency 413, 414/80-15-03 " Failure to Document QC Welding Sur-veillance", Duke Power Company letter of response dated August 19, 1980 has been reviewed and determined to be acceptable by Region II. The inspector held discussions with the Project Engineer and examined the corrective actions as stated in the letter of response. The inspector concluded that Duke Power Company nad determined the full extent of the subject noncompliance, performed the necessary survey and follow-up actions to correct the present conditions and developed the necessary corrective actions to preclude recur-rc:ce of similar circumstances. The corrective actions identifiad in the letter of response have been implemented.

4.

Unresolved Items Unresolved items are matters about which rore iaformation is required to determined whether they are acceptable or may involve noncompliance or deviations.

New unresolved items identified during this inspection are discussed in paragraph 5e and 5.

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-2-5.

Independent Inspection Effort Construction Activities (Units 1 & 2)

a.

The inspector conducted a general inspection of the Unit I and 2

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containments, auxiliary building, fuel building, pipe fabrication shop and electrode issue station to observe construction progress and construction activities such as welding, material handling and control, housekeeping and storage.

b.

Post Weld Heat Treatment (Unit 1)

The inspector observed post weld heat treat (PWHT) activities on steam generator upper lateral support welded joint no.

1-1-A, accomplished in accordance with post weld heat data sheet C-8 Revision 0, Equipment Storage (Units 1 and 2)

c.

On September 3, 1980, the inspector accompanied by a repiesentative of the licensee made a general inspection of the staging area adjacent to the east side of the auxiliary building. The inspector noted six safety related valves, listed below, stored outdoors.

Classification Valve No.

ASME Class Level IND 090

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IND 091

C IBB 104

C IKD 30

C IBW 001

C IFD 50

C Duke Quality Assurance Program Procedure P-3 Revision 12, " Storage Inspection", paragraphs 2 and 4.1.1 require storage to be in accordance wi th ANSI N45.2.2. ANSI N45.2.2-1972, " Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants (During the Construction Phase), " Paragraph 6.1.2 (3) states " Level C iten.3 shall be stored indoors".

Paragraph 6.1.1 of ANSI N45.2.2, requires the above storage requirement to be in effect until the item is placed in its final location (e.g.,

installation). Duke Construction Procedure CP-371, Revision 3 " Pro-tection and Preservation of Installed Equipment", is the field imple-mentation procedure that establishes requirements to insure that equipment is adequately protected and perserved, from the time the item is removed from storage until after the item is installed.

Construction procedure CP-371 does not prohibit outdoor storage of Level C items.

Therefore the conflict bet een the program procedure and the implementation procedure appeared to result in the improper storage of six safety related valves.

Failure to establish adequate

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-3-measures to control storage is in noncompliance with 10 CFR 50 Appendix

"B" Criterion XIII. This is an infraction and is assigned item No. 413, 414/80-24-01: " Inadequate Measures for Storage" d.

Welding Filler Material Centrol (Unit 1)

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On September 3, 1980, the inspector accompanied by a representative of the licensee made a general inspection of the auxiliary building. The inspector noted an abandoned welder's pouch containing approximately 12 unused welding electrodes and bare welding rods.

Duke procedure H-3, Rev. 11 " Identification and Control of Welding Materials", para-graph 5.5.2 requires all unconsumed welding filler materials to be returned to the welding material issue station. Therefore, the welder issued the welding filler material failed to follow welding material control procedure.

The licensee documented the above occurance in Nonconforming Item Report No. 9391.

Failure to follow established procedures is in noncompliance with 10 CFR 50 Appendix B, Criterion V.

The inspector determined that the above was an isolated case. This noncompliance is being catagorized as a deficiency and was assigned item no. 413/80-24-02:

" Abandoned Welding Materials".

Prior to the completion of this inspection tha condition was documented and corrected.

Actions were taken to prevent recurrence. This is considered to be a no response required noncompliance.

e.

Chloride Control During the general inspection of paragraph Sa above the inspector noted several cans of "Winbro Tapfree" thread cutting fluid containing 1, 1, 1, Trychloroethane. At the time of this inspection it could not be determined whether the above material was consistent with paragraphs NB-4712, NC-4712 and NC-4712 of the ASME B and PV Code. In addition it could not be determined whether the licensee's site procedures addressed, the requirements of paragraph NB-4713, NC-4713 and ND-4713 of the AStE B&PV Code and the requirements of Paragraph C4 of Regulatory Guide 1.37.

The licensee indicated that they would look further into the matter. The inspector stated that the above would be an unresolved item and identified as 413, 414/80-24-03: " Chloride Control".

f.

Visual Inspector Qualification The inspector reviewed the Duke program for qualification of visual inspectors for compliance with ASME Code requirea.ents.

Article NB-5000, " Examination" of Section III of ASME, paragraph NB 5521 states, in part " Personnel performing nondestructive examination shall be qualified in accordance with SNT-TC-1 A..... For nondestructive exam-ination methods not covered by SNT-TC-1A documents, personnel shall be qualified by the Manufacturer or Installer to comparable levels of competency by subjection to comparable examinations on the particular method involved..... "

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-4-The practical portion of the qualification shall be performed using the manufacturer's or Installer's procedure on parts representative of the Manufacturer's or Installer's products". Futhe rmore ; Article 1

" General Requirements", of Section V of ASME paragraph T-170 (b)

states, "When the referencing Code Sect. ion requires a manufacturer's Quality Assurance Program or Quality Control System and also specifies the use of examination methods not presently included in SNT-TC-1A (e.g., leak testing and visual examination), the manufacturer shall be responsible to develop training pregrams, written procedures, examina-tions, and practical demonstrations, equivalent to those required for the other examination methods covered by SNT-TC-1 A.

These shall establish the capability of the personnel to perform the required examinations" Paragraph 9.6. lf of SNT-TC-1A, June 1975 Edition requires personnel records of certified individuals to include as a minimum---descriptions of practical test objects. At the time of this inspection the formal personnel qualification record folders for welding inspectors (visual inspectors) did not include a description of the practical test objects.

The licensee stated that all the test cbjects were available for examination. The inspector noted the test object identification in the qualification record was not directly traceable to the test objects.

The licensee indicated that they would look further into the matter.

The inspector stated that the above would be an unresolved item identi-fied as 413, 414/80-24-04: " Description of Practical Test Objects".

In the areas examined, no items of noncompliance or deviationt except as described in paragraphs Sc and 5d were identified.

6.

Reactor Coolant Pressure Boundary Piping Observation of Work and Work Activities The inspector observed welding work activities for reactor coolant pressure boundary (RCPB) piping. The applicable code for installation of RCPB piping is the ASME B and PV code,1974 edition plus addenda through summer 1974.

The inspector observed field welding of reactor coolant pressure boundary piping at various stages of weld completion.

The inspector examined weld joint fitup prior to welding, to determine a.

whether weld identification / location, joint preparation and alignment, evidence of QC cerification meet applicable procedures. The following wcId joints were examined:

Joint No.

Unit No.

Isometric Size System NI-74-8

2-NI-74 3/4" to 6" Safety Injection NI-74-3

2-NI-74 6"

Safety Injection

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b.

The inspectors observed activities at weld material issue stations to determine adequacy of weld material storage / segregation, oven tempera-tures, issue records and return of unused weld material. Also observed work areas for uncontrolled weld material.

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Within the areas examined, there were no items of noncompliance or deviations identified.

7.

Safety-Related Piping Observation of Work and Work Activities (Unit 2)

The inspector observed welding work activities for safety-related piping outside of the reactor coolant boundary.

For the applicable code see paragraph 6.

The inspector observed field welding of safety-related piping outside the reactor coolant pressure boundary at various states of weld completion.

The inspectors examined weld joint fitup, prior to welding, to determine a.

whether weld identification / location, joint preparation and alignment, evidence of QC verification meet applicable procedures. The following weld joint was examined:

Joint No.

Unit No.

Isometric Size System ND-5-3

2-ND-5 3/4" to 14" Residual Heat Removal b.

The inspector examined weld joints of pipe to pipe / fitting (PPF) and pipe to components (FC) where welding was beyond the root pass to deter-mine; weld / welder identi fica tion, qualifieo welder-weld procedure, periodic checxs of welding variables, use of specified weld material, proper interpass temperature and where applicable pre-heat and post-weld heat treatment and physical appearance of weld (e.g., starts, stops, undercut and surface imperfections).

The following weld joints were examined:

Joint No.

Unit No.

Isometric Size System NV-64-5

2-NV-64 4"

Chemical & Volume Control KC-197-6

2-KC-197 6"

Chemical & Volume Control KC-197-5

2-KC-197 6"

Chemical & Volume Control c.

The inspector observed activities at weld material issue stations to determine adequacy of weld mat erial storage / segregation, oven tempera-tures, issue records and return of unused weld material. Also observed work areas for uncontrolled weld materia.

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-6-Within the areas examined, there were no items of noncompliance or deviations identified.

8.

Containment (Structural Steel Welding) - Observation of Work and Work Activities (Unit 2)

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The inspector observed field welding activities associated with steel containment structures and steel supports for major equipment within the containment at various stages of weld completion. The applicable code for containment structural welding is the ASME B and PV code, 1971 edition plus addenda through Summer 1972.

The inspector observed welding activities where welding was in progress a.

to determine conformance with specifications and procedures in the areas of; weld identification, specified purge (if applicable); repair procedures, specified NDE being performed and periodic checks of welding variables.

Structures / Support Weld No.

Weld Type Containment P-4-15-R Butt Containment P-4-13-R Butt Containment P-4-11-B Butt b.

The iispector observed activities at veld material issue stations to determine adequacy of; weld material storage / segregation, oven temper-atures, issue records and return of unused weld material. Also observed work areas for uncontrolled weld material.

c.

During observation of welding activities there did appear to be a sufficient number of qualified inspection personnel at the work site.

Within the areas examined, there were no items of noncompliance or deviations identified.

9.

Review of Nonconformance Reports The inspector reviewed the following nonconforming item (NCI) reports to determine whether the reports were complete, legible, retrievable and properly closed out:

Report Number Unit 5029

4992

5337

5669 1&2 5605 1&2 6769 1&2 7973

7115

7266

Within the areas inspected no items of noncompliance or deviations were identified.