IR 05000313/1989006

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Insp Repts 50-313/89-06 & 50-368/89-06 on 890221-24.No Violations Noted.Unresolved Items Re Radiographic Exam Procedures for Penetrameters Noted.Major Areas Inspected: Mods to Unit 1 Hpis & Repair of Unit 2 Refueling Water Tank
ML20236D487
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 03/09/1989
From: Barnes I, Gilbert L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20236D475 List:
References
50-313-89-06, 50-313-89-6, 50-368-89-06, 50-368-89-6, NUDOCS 8903230124
Download: ML20236D487 (5)


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APPENDIX U.S. NUCLEAR REGULATORY _ COMMISSION

REGION IV

NRC Inspection Report: 50-313/89-06-Operating Licenses:- DRP-51 50-368/89-06 NPF-6 Dockets:

50-313 50-368 Licensee: Arkansas Power & Light Company (AP&L)

Facility Name: Arkansas Nuclear One (AN0), Units 1 and 2

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Inspection At:.AN0 Site, Russellville, Arkansas j

Inspection. Conducted:

February 21-24, 1989

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Inspector:

5/F[ff L.' D./ Gilbert, Reactor Inspector, Materials

' Dete and Quality Programs Section, Division.of Reactor Safety j

o Approved:

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rotjrams(jChief, Materials and QualitySection, Division of Reactor Safetyi Inspection Summary j

Inspection Conducted February 21-?4, 1989 (Report 50-313/89-06;50-368/89-06)

Areas Inspected:

Reactive, unannounced inspection including modifications to the Unit 1 high pressure injection system and repair to the Unit 2 refueling water tank.

Results: Within the two areas inspected, no violations were identified.

However, two unresolved items are identified in paragraph 2 concerning the radiographic examination procedure requirements for selection of penetrameters and_the hardness testing of valve bonnet nuts.

Unresolved items are matters about which more'information is required to ascertain whether they are acceptable items, deviations, or violations, gRO3230124 890309 G

ADOCK 05000313 PNU

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i DETAILS l

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Persons Contacted AP&L

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' J. D. Vandergrift, Operations Manager

  • J. McWilliams,' Maintenance Manager

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  • J. Taylor-Brown, Quality Control / Quality Engineering Superintendent
  • R. P. Wewers, Work Control Center Manager

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  • C. Shively, Plant Engineering Superintendent i
  • M. Durst, Project Engineering Superintendent

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  • J. Ray, Nuclear Quality Engineer j
  • D. Lomax, Plant Licensing Supervisor l

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  • P. Michalk, Licensing Engineer.

B. Michalk, Mechanical-Engineer T. Freeman, Construction Engineer

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D. Crabtree, Engineering Program Supervisor M. Hall.. Welding Engineer D. Payne, Inservice Inspection Coordinator United States Testing Company R. Jones, Radiographic Examiner, Level III NRC j

  • W. Johnson, Senior Resident Inspector i

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i The NRC inspector also interviewed other licensee employees during the l

inspection.

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  • Denotes attendance at exit interview conducted on. February 24, 1989.

2.

High Pressure Injection System Modifications (55050, 57060, and 57090)

The NRC inspector reviewed licensee information regarding high pressure injection (HPI) check valve backflow and the planned corrective actions.

These actions included the replacement of fittings that may have been overstressed and modifications.to the HPI system piping and supports to prevent recurrence. These modifications included installation of'

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additional check valves in series with the. existing HPI discharge line check valves. The NRC inspector observed work ~in progress ~on the HPI-system and selected the welds shown in the Attachment for review of the material certification, welding, and nondestructive examination of -

components.

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The' welders and welding procedures used for welding the components were verified by the NRC inspector to have been cualified in accordance with

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- the requirements of Section IX of thefASME Boiler '&' Pressure Vessel Code.

The NRC inspector reviewed the liquid penetrant and: radiographic _

examination reports.-and 44' radiographs which were applicable to the welds j

listed in the Attachment. The radiographs were consistent with the-a requirements specified in.the U.S.-Testing, Company Procedure 20.A.69, Revision 3524-4 for radiographic-examination. The NRC inspector noted

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that the penetrometer selection table for the single wall technique was; not consistent with the radiographic examination requirements specified in-Section III 'of. the ASME Boiler & Pressure. Vessel. Code,1980 Edition through Winter.1981 Addenda.

Since the double wall technique was.used.for the above radiographic examinations, this will be considered an unresolved item pending correction of the procedure and. review by.the licensee to determine if the' single wall technique'was performed on other

' safety-related components using incorrect penetrameters.

(313/8906-01; 368/8906-01)

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An'in-office review.of material certifications for HPI system welds, i

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valves, and piping materials was performed during the week of February 27 through March 3, 1989. The welding filler materials and piping. materials were consistent with'the material specification requirements of ASME

Roiler & Pressure Vessel Code Sections 1II' and III for. Class 1 components, i

L except'for' the certification of the bonnet nuts. for Valve MU-66B.. The

1000*F heat treatment used for the hardness test on the bonnet nuts is not i

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consistent with the 1100'F temperature required in SA 194,= paragraph 8.B l

of ASME Boiler & Pressure. Vessel Code Section II Part A.

The hardness l

testing of the. bonnet nuts is an unresolved item pending-clarification by the licensee or testing at the higher' temperature.

(313/8906-02)

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No violations or deviations were identified in this area of the

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inspection, j

3.

Refueling Water Tank Repair-Unit 2 (55050)

The NRC inspector reviewed Condition Report CR-2-89-067 which documented that the refueling water tank (Tank 2T-3) was leaking,'but not inoperable, The tank was not considered inoperable because the leak was at a location.

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that did not cause the water level to go below the minimum required level of the Technical Specifications. The type of defect also did not cause the l

tank to deviate from seismic criteria.

The apparent cause of.the leak was l

determined by plant engineering to be a defective tack weld approximately

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3 inches from the top of the tank side wall. The welder apparently burned

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through the thin stainless steel tank wall while tack welding the 1-inch

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-thick support ring to the 3/16-inch tank wall during installation'of the

support ring specifici in Design Change Package -(DCP) 80-2052. The

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instructions for the repair of the pin hole leak in the tank wall were specified in Plant Engineering Action Request No. 89-0220 and Welding l-Request # 89-0093. These instructions included weld ~ repair-of the hole l

using Welding Procedure Specification (WPS) P8-T-AG, liquid penetrant and

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ultrasonic examination of the repair weld, and hydrostatic test of the repaired area. The requirements of the ASME Boiler & Pressure Vessel L-

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Code,Section III, Subsection NC,1980 Edition through Winter 1981 Addenda were specified for the repair.

No violations or deviations were identified in this area of the inspection.

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Exit Interview The NRC inspector met.with tbe personnel identified in paragraph 1 on February 24, 1989, to discuss the findings and conclusions reached during the inspection. The NRC inspector was. informed that a preliminary review

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of the past radiographic examination. records indicated that no single wall I

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techniques were performed using incorrect penetrameters.

No.information'

was presented to the NRC inspector that was identified by the' licensee as

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proprietary. The licensee was notified on March 7, 1989, that an

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additional unresolved item had been identified during the in-office review l

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of the material test reports for the. bonnet nuts of Valve MU-668.

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ATTACHMENT..

Listing of Welds Reviewed in HPI Modification

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Activities

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Drawing No. 17-MU-26;. Welding Request WR # 89-0083; Welds'FW-80 and FW-81.

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.DrawingNo.17-MU-23;WeldingRequestiWR# 89-0082; Welds FW-85 and FW-86

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Drawing No. M714 Sheet 2; Welding Request WR #'39-0081; f

Pipe Weld FW-89

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o Drawing No.17-MU-27;. Welding Request' WR # 89-0086; Pipe Welds FW-43C-1, FW-48C-1, FW-63C-1,'FW-73AC-1, Rf-107 and FW-108C-1

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o Drawing-No. 17-MU-27; Welding Request WR # 89-0084; ' Pipe Welds FW-96,.

FW-97, FW-98, FW-99, FW-100, FW-105 and FW-106 o

Drawing No.17-MU-30; Welding Request WR # 89-0085; Pipe Welds FW-120, FW-126 and FW-128 o

Drawing No. 17-MU-30; Welding Request WR # 89-0087; Pipe Welds FW-105AC-1 and FW-134 o

Drawing No. MU-157; Welding Request.WR # 89-0089;-

Pipe Support Welds FW-1 through FW-10

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o Drawing No, MU-178; Welding Request WR # 89-0089; i

Pipe Support Welds FW-1 through FW-4

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Drawing No. MU-176; Welding' Request WR # 89-0089;

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Pipe Support Welds FW-1 through FW-5

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o Drawing No. MU-175; Welding Request WR # 89-0089; Pipe Support Welds FW-1 through FW-7 o

Drawing No. MU-197; Welding Request WR # 89-0089; Pipe Support Welds FW-1 and FW-2 o

Drawing No. MU-211; Welding Request WR # 89-0089; i

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Pipe Support Welds FW-1 through FW-7

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o Drawing No. MU-212; Welding Request WR # 89-0089; Pipe Support Welds FW-1 through FW-5 o

Drawing No, MU-200; Welding Request WR # 89 0089; Pipe Support Welds FW-1 and FW-2 j

o Drawing No. MU-201; Welding Request WR # 89-0089; l

Pipe Support Welds Bl-1 through FW-10 l

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