IR 05000313/1986037

Insp Repts 50-313/86-37 & 50-368/86-37 on 861103-06.No Violations or Deviations Noted.Major Areas Inspected: Implementation of Repair & Replacement Program,Design Changes & Mods & Closeout of Followup Items

ML20214Q628
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/26/1986
From:	Hunnicutt D, Greg Pick NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20214Q582	List: IR 05000313/1986037 ML20214Q579
References
50-313-86-37, 50-368-86-37, NUDOCS 8612050220
Download: ML20214Q628 (5)

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APPENDIX U.S. Nuclear Regulatory Commission Region IV NRC Inspection Report: 50-313/86-37 Licenses: DPR-51 50-368/86-37 .NPF-6

Dockets: 50-313 50-368 Licensee: Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203 . -

Facility Name: Arkansas Nuclear One, Units 1 and 2 Inspection At: Arkansas Nuclear One (AN0) Site, Russellville, . Arkansas, and U.S. NRC RIV Office

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Inspection Conducted: November 3-6, 1986 ,

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Inspection: [# d #$ N j G. A. Pick, Reactor Engineer, Operation D' ate /

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Approved: b bl)

D. M. Hunnicutt, Chief, Operations Section

///A / 8d D6te-Inspection Summary Inspection Conducted November 3-6, 1986 (Reports 50-313/86-37 and 50-368/86-37)

Areas Inspected: Routine, unannounced inspection onsite in areas relating to implementation of the repair and replacement program, design changes and modifications, and close out of followup item ;

8612050220 861201 PDR ADOCK 05000313 G PDR L j

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-2-DETAILS

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- Persons Contacted AP&L

• H. Jones, Plant Modifications Manager

• E. Ewing, General Manager, Plant Support

• Stroud, Project Engineering Superintendent

• D. Lomax, Plant Licensing Supervisor

• P. Campbell, Plant Licensing Engineer S. Maddox, Electrical Engineer G. Goodson, Project Engineering Supervisor NRC Personnel

• D. Johnson, Senior Resident Inspector

• C. C. Harbuck, Resident Inspector

• J. E. Bess, Reactor Inspector

• G..A. Pick, Reactor Engineer Closecut of Followup Items (Closed) Deviation example "a" 50-313/8614-01. A licensee letter dated September 22,1986(SCAN 098604), from J. Ted Enos, Manager, Nuclear Engineering and Licensing, provided, for accessible systems, a listing of more extensive analysis evaluations and their disposition. This item is close (Closed) Deviation example "b" 50-313/8614-02. The licensee response dated September 22, 1986 (SCAN 098604), provided, for inaccessible systems, the results of a reanalysis of 31 isometrics and the method used to bring those that previously had exceeded construction code allowables within specifications. This item is close (Closed) Deviation example "c" 50-313/8614-03 and 50-368/8614-01. The licensee response dated September 22, 1986 (0CAN098604), was provided by the Bechtel Power Corporation BLG-1488, dated September 26, 1980. This letter explained the field survey / random sampling testing technique that verified the adequacy of the load capacities of Phillips Redhead Anchors used before mid-1977. This item is close (Closed) Deviation example "d" 50-313/8614-04 and 50-368/8614-02. A licensee letter dated September 22, 1986 (0CAN098604), provided for Units 1 and 2 copies of the Bechtel Power Corporation reports, "The Investigation of the' Structural Strength Concrete Block Walls Supporting o

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Seismic Category 1 Pipes." These reports explained the adequacy of block ^

walls supporting seismic category 1 piping. This item is close (Closed)OpenItem 50-313/8614-06. A licensee letter dated September 22, 1986, transmitted the applicable portions of Specification APL-M-2410,.

" Technical Specification of Installation, Modification, Inspection, and Documentation of Piping Systems and Pipe Supports, Hangers, and Restraints for Nuclear Process Piping and ANSI B31.1 Hanger Critical Piping," as committed to on May 23, 1986. This item is closed.' Closecut of IE Bulletin 79-02 and IEB 79-14 As discussed in NRC Inspection Report 50-313/86-14 and 50-368/86-14 and after the NRC inspector reviewed the information received in AP&L letter (SCAN 998694), dated September 22, 1986, (sce paragraph 2) IEBs 79-02 and 79-14 are considered close . Review of Modifications The purpose of this inspection was to followup the inspection conducted in NRC Inspection Report 50-313/86-32; 50-368/86-32 concerning Design Change Packages (DCP) 82-1111 and 82-1111A, " Expansion of Colors 1E 120 Vac Capability." The documents reviewed are listed below:

Plant Scoping Report, dated June 20, 1986 Drawings

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S0 5837-CE1

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E-83 Sheet 4 Revision N

- E-431 Sheet 3, Revision 2-1

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E-1 , Revision 12-1

- E-513 Sheet 6, Revision N

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E-669 , Revision 48-1

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E-662 , Revision 45-1

- E-670 Sheet 1, Revision 49-1

• Purchase Orders ,

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- 47084

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Penetration Log Revision Form Field Change Notices (Nos. 1-6)

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-4-The NRC inspector determined that a method was in place to assure that various electrical loads added to the emergency diesel generators (EDG)

through DCPs were accounted for and that the total electrical load did not exceed the load limit on each EDG. After discussions with licensee e.nployees, the NRC inspector determined that a plant procedure existed for Unit 2. This procedure satisfied the Technical Specification surveillance requirements concerning electrical overloading of the Unit 2 EDGs. A method existed and was followed on Unit 1 during this refueling outage to preclude exceeding the EDGs electrical load capacit No violations or deviations were identifie _

5. Repair / Replacement Program Implementation ,

The NRC inspector reviewed the implementation of Arkansas Nucl~ ear One's (AN0) ASME,Section XI, Repair / Replacement Program implementatio The two methods for conducting Section XI repairs were Plant Engineering Action Requests (PEAR) and DCP ~

The two methods had certain forms that were required in each Section XI

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repair / replacement package such as: joborder(J0) form,J0 attachment, radiation work permit request, suggested tagging list, materials list, a

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copy of related PEARS, Ignition Source Permit (if required), a sketch or drawing, Welding Traveler and Checklist (Form Nos. 1000.37A and 1000.37AI), Filler Material Withdrawal Authorization, and Material Ticke The following PEARS were reviewed:

PEAR R Subject 86-2679 715177 Repair of Valve 2RCP-1001C 86-2733 717039 Reinstallation of pipe (RAC 2-86-194) support 2 DBB-4-H12 86-1355 710794 Repair of service water coil leak The difference in usage between a PEAR and a DCP was dependent upon the extent of the repair / replacement and whether any other activities were involved. DCPs usually involve more that one J0 to complete whereas each PEAR had only one J0. Sumaries of the DCPs reviewed including their extent and purpose are listed below:

DCP 85-2112 - This change was instituted to install one flange pair to the service water inlet of coolers 2VUC-1A,1E,1F; 2VUC - 11A and 11B; and 2VUC-20A and 20B. The change also modified hangers 2HCC-278-1-H18, 2HCC-279-1-H11 & -H12 for the addition of spool pieces to coolers 2VUC-1A, 2VUC-1E, and 2VUC-1F, respectivel Calculations were included through Field Change Notice (FCN) N Each of the flanged connections was completed through individual J0s and repair / replacement package l L

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-5-DCP 840-2065 - This effected a change in installed' gaseous radioactive waste EPG Ball Valves, 2CV 2457 and 2CV 2447, from electrically operated to pneumatically operated valves manufactured '

by Canadian Worcester Controls. The repair / replacement was conducted under J0 710773 to replace the then current EPG valves, since these valves were prone to failur *

DCP 83-2185 - This DCP initiated installation of a removable monorail above the Unit 2 personnel air lock. This activity was conducted

, under J0 711234.

t No violations or deviations were identifie . Exit Interview The NRC inspector met with the licensee representatives denoted in paragraph 1, and Mr. W. D. Johnson, NRC Senior Resident Inspector,-on

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November 6 1986, and summarized the scope and findings of-the inspectio .~~ ,

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