IR 05000313/1984034

Insp Rept 50-313/84-34 on 841126-30.No Violation or Deviation Noted.Major Areas Inspected:Containment Type B & C Leak Tests,Inservice Insp Data & Facility Mods

ML20136G900
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/05/1985
From:	Ireland R, Norman D, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20136G859	List: IR 05000313/1984034 ML20136G853
References
50-313-84-34, NUDOCS 8511220495
Download: ML20136G900 (5)

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APPENDIX U. S._ NUCLEAR REGULATORY CO MISSION

REGION IV

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NRC Inspection Reporti ' 50-313/84-34 License: DPR-51

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Docket: '50-313 Licensee: Arkansas Power and Light P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO) Unit 1 Inspection At: ANO Site, Russellville, Arkansas Inspection Conducted: November 26-30, 1984 Inspectors: -

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R.'C. Stewart, Reactor Inspector Date Reactor Safety Branch / Operations Sections b Y $ +-2 m W H/ N D. E. Norman, Reactor Inspector Date Reactor Safety Branch / Operations Section Approved: . /7/Ie E. Ireland, Acting Chiief, Operations Section

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Inspection Summary Inspection Conducted November 26-30, 1984 (Report 50-313/84-34)

., Areas Inspected: Routine, unannounced inspection of containment type 8 and'C leak test, in-service inspection (ISI) data, and facilities modification. The inspection involved 62 inspector-hours by two NRC inspector Results: Within the three areas inspected, no violations or deviations were identified.'

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I Details l Persons Contacted

• Chris Shively, Engineering Superintendent

• Larry Dugger, I&C Superintendent Don Payne, ISI Coordinator Jerry Newman, I&C Senior Technician

• G. D. Provencher, QA Supervisor

• Patty Campbell, Licensing Engineer

• T. H. Cogburn, Special Projects Manager

'*E. C. Ewing, Engineering and Technical Support Manager

• J. M. Levine, ANO General Manager The NRC inspectors also contacted other licensee employees, including administrative, quality assurance, clerical and maintenance personne * Denotes those attending the exit intervie . Containment, Type B and C Leak Rate Testing This inspection was performed to ascertain whether the type B and C leak rate testing was in conformance with regulatory requirements and FSAR commitments. Implementing instructions for performing the test are contained in the following procedures which were reviewed by the NRC inspector:

• Procedure No. 1304.20, Revision 1, dated September 19, 1984, " Reactor Building Access and Ventilation Leak Rate Testing"

• Procedure No. 1304.23, Revision 8, Change 3, dated October 30, 1984,

" Local Leak Rate Testing" Instructions for the two personnel access penetrations and the reactor building ventilation penetrations are included in Procedure 1304.20 while Procedure 1304.23 contains instructions for the remaining type B and C tests and calculations for all type B and C test Each component is assigned a maximum allowable leakage rate and a job order is issued to repair or replace components when out-of-tolerance conditions are found. A Report of Abnormal Conditions (RAC) is issued if the total leakage of all components exceeds 60 percent of the allowabl The NRC inspector reviewed implementation of the procedures by examining test data and job orders. M irregularities were identified during the inspection; however, several items remained to be tested and total leakage had not been determined. This inspection effort will be continued during a future inspectio No violations or deviations were identified.

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i -3-t 3. Reactor Nozzle Inservice Inspection This inspection was conducted to determine if the ASME Code and Technical Specification requirements for examining the reactor vessel nozzle welds during the first inspection interval had been complied wit NRC letter dated April 18, 1983, approved the ISI program which included the following requirements in respect to the nozzles:

• Inspection in accordance with Section XI of the ASME Code, 1974 edition through summer 1975 addenda, except where specific written t

relief has been granted by the NRC. In respect to the time of RV nozzle inspections, the original requirement that 25 percent of required examinations be completed by the end of 40 months (1/3 interval), 1 percent of required examinations be completed by the end of 80 months (2/3 interval) and the remaining be completed by 120 months (or.e interval) was replaced with the following requirement:

• 100 percent inspection of both outlet nozzles to be completed by 3-1/3 years, from the nozzle bor * 100 percent inspection of all nozzles from inside the vessel with vessel internals removed, by 120 month The following B&W procedures were reviewed relative to the inspection:

151-130, Revision 18, dated October 5, 1982, " Ultrasonic Examination of Vessel Welds and Nozzle Radius Sections" ISI-131, Revision 8, dated October 8, 1982, " Remote Ultrasonic Examination using the ARIS Device" '

151-132, Revision 3, dated July 2, 1981, "ARIS Operating Procedure" Additionally, Inservice Inspection Results for Arkansas Nuclear One, Unit 1, for Refueling outage Number 5, 1982-1983, were reviewed and there were no indications of flaws in the nozzle The following unresolved items were identified as a result of the inspection (Unresolved Item 313/8434-01) ASME Section XI requires, in respect to primary nozzle-to-vessel welds and nozzle inside radius sections, that a volumetric examination be completed of the weld and specified area adjacent to the sel Information available was not sufficient to show that the required volume had been examine There were also notes associated with several scans which indicated that scans were limited because of interference problem Form NIS-1, "0wners' Data Report for Inservice Inspections", dated September 20, 1983, certified inspection results for the interval from December 19, 1974, to December 19, 1984. Only five of the eight

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vessel nozzles had been listed on the repor m

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' Data showed calibration sheets for several transducers; however, s

' transducer identification numbers were not listed on data sheets for

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the nozzle examination .There was no documented evidence of either B&W or AP&L QA/QC overview of the ISI proces No violations or deviations were identified, l

l 4. _ Facility Modifications During this inspection, the NRC inspector reviewed the design change modifications being accomplished during this plant outage on the ' Unit 1

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emergency feedwater system (EFW).

} The modification is the result of the functional requirements needed to properly interface the EFW with the Nuclear Steam Supply System (NSSS) in conjunction with; NUREG-0578, Short Term Lessons Learned Report; Draft

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NUREG-0667, Transient Response of B&N Designed Reactors; and criteria ne'cessary to upgrade the EFW to comply with the Standard Review Plan, Section 10.4.9, Branch Technical Position ASB10- The EFW modification is being accomplished by Bechtel contract in accordance with AP&L Design Change Package #80-108 The NRC inspector reviewed the principle Babcock & Wilcox Design Technical Document 15-1119467-03, entitled " System Description For Emergency Feedwater System For ANO-1, in conjunction with AP&L Design Packages

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DCP#80-1083A, B, & F. In addition, the inspector reviewed applicable AP&L procedures including the following:

Procedure Number Title 1032.01 Design Control 1032.02 Installation Technical Support 1000.13 Control of Station Modifications 1004.01 QC Program Implementation The NRC inspectors did not witness or review the subcontractor work activities. However, the NRC inspector expressed a concern in the area of AP&L QA involvement in contractor surveillance during constructio Although the licensee representatives stated that QA surveillance L

activities were being performed, the NRC inspector was unable to find documented evidence that the surveillance activity was verifying the contractors effectiveness of quality control during construction modification. (10 CFR 50, Appendix B, Critieron VII).

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5 Exit Interview The NRC inspectors met with licensee representatives and the NRC resident inspector at the conclusion of,the inspection on November 30, 198 The NRC inspectors summarized the scope and findings of the inspectio The licensee stated that the unresolved items and NRC inspector concerns would be r'eviewe .

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