IR 05000313/1986003

Insp Repts 50-313/86-03 & 50-368/86-03 on 860201-28.No Violation or Deviation Noted.Major Areas Inspected: Operational Safety Verification,Maint,Surveillance,Measuring & Test Equipment Program

ML20140E850
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/17/1986
From:	Craig Harbuck, Hunnicut D, Johnson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20140E837	List: IR 05000313/1986003 ML20140E832
References
50-313-86-03, 50-313-86-3, 50-368-86-03, 50-368-86-3, NUDOCS 8603280213
Download: ML20140E850 (12)

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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION REGION IV '

NRC Inspection Report: 50-313/86-03 Licenses: DPR-51 50-368/86-03 NPF-6 Dockets: 50-313 50-368 Licensee: Arkansas Power & Light Company (AP&L)

P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2 Inspection At: AN0 Site, Russellville, Arkansas Inspection Conducted: February 1-28, 1986

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Inspectors: (4/MMmm W.D.g6hnson,SeniorResident

1. 6/d'4 D'a te'

Reactor Inspector (pars. 2, 3, 4, 5, 6, 8)

Yb4hv L C. C. Harbuck, Resident Reactor 3ldfEd Date Inspector (pars. 4, 5, 6, 7)

Approved: * fN Quf D.11. ifunnicutt, Acting Chief, J//7/Ff

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Project Section B, Reactor Project Branch 8603280213 860318 PDR ADOCK 05000313 G PDR I

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Inspection Summary Inspection Conducted Februc.ry 1-28, 1986 (Report 50-313/86-03)

Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, measuring and test equipment program,

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condensate storage tank construction, followup on licensee event reports, and

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followup on previously identified item The inspection. involved 59 inspector-hours (including 10 backshift hours)

onsite by two NRC inspector Results: Within the seven areas inspected, no violations or deviations were identifie r Inspection Summary

Inspection Conducted February 1-28, 1986 (Report 50-368/86-03)

Areas Inspected: Routine, unannounced inspection including operational safety

., verification, maintenance, surveillance, measuring and test equipment program, condensate storage tank construction, followup on licensee event reports, and followup on previously identified item The inspection involved 91 inspector-hours (including 8 backshift hours) onsite by two NRC inspector Results: Within the seven areas inspected, no violations or deviations were identifie .

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-3-DETAILS Persons Contacted

• J. Levine, Director, Site Nuclear Operations S. Arnwine,. Engineering Technician R. Ashcraft, Electrical Maintenance Supervisor

• B. Baker, Operations Manager C. Bean, Quality Control Supervisor M. Bishop, Special Projects Coordinator M. Bolants, Health Physics Superintendent J. Bruni, Shift Maintenance Supervisor D. Bullington, Computer Support Superintendent B. Cameron, Bechtel Engineering Coordinator

• P. Campbell, Licensing Engineer B. Converse, Plant Performance Supervisor A. Cox, Operations Technical Support K. Dickerson, Mechanical Engineer

• E. Ewing, Engineering & Technical Support Manager L. Gulick, Unit 2 Operations Superintendent W. Hada, Health Physics Supervisor C. Halbert, llechanical Engineering Supervisor W. Hinton, Operations Tcchnical Support H. Hollis, Security Coordinator P. House, Labeling Coordinator

• D. Howard, Special Projects Manager

• L. Humphrey, Administrative Manager D. Johnson, Licensing Engineer H. Jones, Field Construction Manager -

P. Jones, Instrumentation and Controls Superintendent D. Lomax, Licensing Supervisor J. McWilliams, Unit 1 Operations Superintendent J. Montgomery, Human Resources Supervisor J. Orlicek, Field Engineering Supervisor G. Parks, Senior Quality Control Inspector V. Pettus, Mechanical Maintenance Superintendent

• D. Provencher, Quality Engineering Supervisor J. Remer, Maintenance History Supervisor J. Roberson, Instrumentation and Controls Supervisor P. Rogers, Plant Licensing Engineer  ;

R. Roussele, Electrical Maintenance Supervisor 1 L. Sanders, liaintenance llanager l

• L. Schempp, Nuclear Quality Control Manager M. Shehorn, Instrumentation and Controls Supervisor C. Shively, Plant Engineering Superintendent R. Sinnons, Planning and Scheduling Supervisor L. Smith, Anderson Engineering E. Steiner, Bechtel Quality Control Engineer

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-4-C. Taylor, Operations Technical Support J. Teeter, Operations Technical Support D. Wagner, Health Physics Supervisor R. Wewers, Work Control Center Manager G. Woolf, Operations Technical Support C. Zimerman, Operations Technical Support

• Present at exit intervie The NRC inspectors also contacted other plant personnel, including operators, technicians, and administrative personne . Followup on Previously Identified Items (Units 1 and 2)

(Closed) Open item 313/8513-01; 368/8513-02: Implementation of improved maintenance history and job order tracking system The licensee has implemented the station information management system (SIMS).

This computer-based system includes an effective means of tracking job order status and an easily accessible component maintenance histor (Closed) Violation 368/8327-01: Station battery inoperabl The' NRC inspector reviewed the licensee's actions to prevent recurrence of the station battery inoperability which resulted in the assessment of a civil penalty. Licensee Event Report (LER) 368/83-44 reported this event to the NRC. This LER was reviewed in conjunction with the violation followup. The NRC inspector verified performance of the corrective actions comitted to by the licensee in the LER and in the

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written response to the notice of violation. These actions included the following key items:

. Technical Specification training was provided for maintenance technicians and supervisors to give them a better understanding of the Technical Specification surveillance and operability requirements' for the plant equipment on which they perform maintenance and surveillance testin . Surveillance procedures were revised to ensure that Technical Specification limits were clearly identified as such and to include instructions for notification of the shift supervisor when acceptance criteria were not met. The NRC inspector reviewed a sample of surveillance procedures and found that all but one of the grocedureshadbeenrevisedascommitted. This procedure (2306.06, Main Steam Code Relief Valve Testing") was scheduled for revision by the maintenance department prior to its next usag . The licensee now issues a monthly Quality Indicators Report and provides copies to appropriate managers and superintendents. This

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-5-I report tracks and plots many quality indicators and is _ intended to i identify trends and potential problem areas.

, . A short-term action involved issuance of a management directive to i instruct personnel to identify all deviations from limits in surveillance tests as potential Technical Specification violations.

J This was done to ensure compliance prior to revision of surveillance procedures. A special . audit was performed by quality control personnel to verify that plant-personnel understood and were

implementing this directive. A special audit was performed by l quality assurance personnel which included review of completed surveillance tests to verify compliance. Licensee management held

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meetings with about 500 managers, superintendents, supervisors, and technicians to discuss this incident and the necessary corrective

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action . A task force was formed to review and revise the administrative system governing procedure development and control. The revised

procedures developed by this task force were scheduled to be

implemented in March 198 . . A technical review was conducted by licensee personnel to verify 1 that all Technical Specification surveillance requirements were properly covered in surveillance testing procedures. Corrective j actions resulting from this review have been completed.

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. The licensee reviewed previous battery ~ surveillance testing results and a sample of other surveillance testing results. Discrepancies were reported in letters to the NRC and in LERs.

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(Closed) Violation 313/8522-01: Failure to check position of fire system val ves.

f As discussed in a letter from NRC Region IV to the licensee ~ dated January 10, 1985, this item was determined to not be a violation of i

Technical Specification '

) Licensee Event Report (LER) Followup (Units 1 and 2)

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Through direct observation, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent l' recurrence has been accomplished in accordance with Technical i Specifications.

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4 Unit 1 85-009-00 "liechanical Snubbers" (Also covers Unit 2)

j 85-011-00 " Reactor Trip" i

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-6-Unit 2 83-044/01X-1 " Station Battery 2D11 Inoperable" 84-002-00 "Potentially Nonconservative Addressable Constants Loaded into the Core Protection Calculators (CPCs)"

85-012-00 " Inoperable Core Operating Limits Supervisory System" (COLSS)

85-019-00 "liain Steam Isolation System Actuation" Unit 2 LER 83-044 reported the inoperability of station battery 2D1 The NRC inspector- reviewed this LER in conjunction with the followup of violation 368/8327-01. See paragraph 2 of this repor Unit 2 LER 84-002 reported potentially nonconservative addressable constants which were loaded into the CPCs during' low power physics testing. The NRC inspector reviewed RAC-2-84076 and reviewed the following procedures:

. 1022.02, Revision 4, " Core Protection Calculator Software Change Control"

. 2312.11, Revision 1, "CPC Trip Buffer Report (Snapshot)"

. 2312.12, Revision 1, "CPC Disk Control and Loading" .

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. 2312.13, Revision 0, "CPC Addressable Constant Disk Generation" Procedure 1022.02 was being revised to eliminate duplication of information in Procedure 2312.13 concerning generation of new CPC addressable constant disks. These new and revised procedures and the training which has been provided to potential users of these procedures should prevent recurrence of this type of even Unit 2 LER 85-012 reported inoperability of the COLSS due to an input error made during the cycle 5 update. The NRC inspector reviewed PAC-2-85198 and discussed the corrective action to prevent recurrence with the licensee's computer sup In coordination with l4iddle South Services (11S5) port

, an superintenden integrated software test is being developed. !4SS will independently input cycle 6 COLSS data into their computer, run a number of test cases, and compare the results with those

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obtained by site personnel using the installed COLSS. Discrepancies in the resulting COLSS calculated power operating limits would indicate an error in data input. Any such errors would be corrected prior to startup after refuelin No violations or deviations were identifie . Operational Safety Verification (Units 1 and 2)

The NRC inspectors observed control room operations,: reviewed applicable

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logs, and conducted discussions with control room operators. The inspectors verified the operability of selected emergency systems, reviewed tagout records, verified proper retun to service of affected components, and

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-7-ensured that maintenance requests had been initiated for equipment in need of maintenance. The inspectors made spot checks to verify that the physical security plan was being implemented in accordance with the station security pl an. The -inspectors verified implementation of radiation protection controls during observation of plant activitie The NRC inspectors toured accessible areas of the units to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibration. The inspectors also observed plant housekeeping and cleanliness conditions during the tours. The Unit 2 upper north piping penetration room was observed to be in need of housekeeping attentio The NRC inspectors walked down the accessible portions of the Unit 2 emergency feedwater system. The walkdown was performed using Procedure 2106.06 " Emergency Feedwater System Operations," Attachment

'A', Revision 14, May 14, 1984, and Drawings M-2204, M-2229, M-2202, M-2206, and M-2212. The following items were identified:

. Three valves had no metal tag label (2EFW-0713C, 2CV-0795-2, 2EFW-18).

. The position indication faceplate for 2CV-1075-1 had fallen off rendering the indication unreadabl These two items were corrected promptly by the licensee. Additional items identified were:

. EFW pump 2P7A steam supply isolation solenoid bypass control valve (2SV-0205) was not depicted on Drawing H-2202. The apparent reason for this is that DCP 82-2077, which installed the valve has not yet been closed out. Plant Engineering Action Request 85-3783 had been prepared on December 10, 1985, to address this discrepanc . Valve 2CV-1050-2 had a packing steam leak. The licensee issued Job Request 75679 to correct this previously unidentified proble During routine tours, the NRC inspectors identified two other equipment discrepancies and notified the licensee so job requests could be prepare A steam leak was identified downstream of MS-54 on an emergency feedwater indication and control system pressure sensing line. The output voltage meter on the-Unit 2 green battery charger (2D32) was found to be inoperable in that the paint on the meter face was cracked and peeling, interfering with the meter's needle movement. These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under Technical Specifications,10 CFR, and administrative procedure l No violations or deviations were identifie . Monthly Surveillance Observation (Units 1 and 2) l The NRC inspector observed the Technical Specification-required surveillance testing on the Unit 1 high pressure injection pump P36B

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-8-(Procedure 1104.02, Supplement II) and on the Unit 2 high pressure safety injection pump 2P89B (Procedure 2104.39, Supplement II) and verified th_at

. testing was perforned in accordance with adequate procedures, test instrumentation was calibrated, limiting conditions for operction were met, removal and restoration of the affected components were accomplished, test results conformed with Technical Specifications and procedure requirements, test results were reviewed by personnel other than the individual directing the test, and any deficiencies identified.during the

, testing were properly reviewed and resolved by appropriate management personnel .

The NRC inspector also witnessed portions of the following test activities:-

! . Unit I hydrogen purge system test. (Procedure 1104.33, Supplement II)

. Unit 1 emergency feedwater pump P7B monthly test. (Procedure 2106.06,

Supplement II)

. Unit i emergency diesel generator DG2 monthly test. (Procedure 1104.36, Supplement II)

. Unit 2 emergency feedwater pump 2P7A monthly test. (Procedure 2106.06, Supplement I)

. Unit 2 battery 2D13 quarterly surveillance. (Procedure 2403.22)

The NRC inspector identified one broken flame arrestor (safety vent)

during the surveillance. Subsequent investigation by the licensee found 8 more on 2D13, 4 on 2D12, and one on 007. Job Orders 709089 and 709092 were issued to replace the broken safety vent No violations or deviations were identifie . Monthly !!aintenance Observation (Units 1 and 2)

Station maintenance activities of safety-related systems and components listed below were observed to ascertain that they were conducted in accordance with approved procedures, Regulatory Guides, and industry codes or standards; and in conformance with Technical Specification The following items were considered during this review: the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were perforned prior to returning components or systems to service; .

quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used dere properly certified; l radiological controls were implemented; and fire prevention controls were l implemente j t

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. Work requests were reviewed to determine status of outstanding jobs and to ensure that priority is assigned to safety-related equipment maintenance which may affect system performanc The following maintenance activities were observed:

. Installation of boots on diesel generator exhaust line (DCP-85-1082, J0 703778)

. Investigate failure of Hydrogen Purge Pump VSF-30B to start. (JO 0182)

. Repair handwheel operator on Unit 2 v~alue 2SI-5A. (JO 755715)

. Testing of P7A with various steam supply flow paths to verify operation of CV-2667 and new check valves MS-271 and MS-272 following implementation of design change DCP-86-1005. (Work P1an 1409.72)

. Repair of leak on outboard plunger of charging pump 2P36 (Procedure 2402.32, JO 708152)

No violations or deviations were identifie . Measuring and Test Equipment Quality Assurance Program (Units 1 and 2)

The purpose of this part of the inspection was to ascertain that the licensee has developed and implemented a quality assurance program relating to the control of measuring and test equipment (M&TE) that is.in conformance with regulatory requirements, FSAR commitments, and industry standard The NRC inspector reviewed the following procedures governing the control and use of M&TE:

. AP&L - T0P/1A, Revision 6, " Quality Assurance Manual Operations."

. I&C Administrative Procedure 1035.06, Revision 5, December 12, 1983,

"AN0 Master M&TE List."

. Technical Analysis Administrative 1072.003, Revision 0, March 2, 1983,

" Control of Technical Analysis M&TE Standards."

. I&C Administrative Procedure 1035.05, Revision 4, March 6, 1985, "M&TE Calibration and Repair."

. Materials Management Procedure 1033.09, Revision 5, July 12,1985,

" Storage, Issue and Return of M&TE."

. General Radiation Worker Procedure 1622.023, Revision 4, April 8,1985,

" Control and Calibration of HP Instruments "

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. Overall Plant Administrative Procedure 1000.14, Revision 7, December 6, 1984, " Control of M&TE and Standards."

From this review and through discussions with licensee personnel responsible for the control and use of M&TE, the NRC inspector verified that the licensee's program for the control and use of M&TE appears to meet the FSAR commitment to the following standard:

. IEEE Std 498-1980 "IEEE Standard Requirements for the Calibration and Control of Measuring and Test Equipment used in the Construction and Itaintenance of Nuclear Power Generating Stations."

Thus, the NRC inspector concluded that the licensee's program appears to satisfy the requirements of Criterion XII-Control of Measuring and Test Equipment, of Appendix B to 10 CFR Part 5 This program review verified that the following elements were included:

. Criteria and responsibility for determination of calibration frequenc . Formal means of identification of each device and its calibration statu . Formal means of adding and deleting equipment from the M&TE calibration progra . Method for documenting M&TE calibration history.

. A requirement to identify calibration standards used and their traceability to nationally recognized standard . A requirement that M&TE shall have an error less than or equal to the instrument being calibrate . Required actions if M&TE or reference standards are found out of calibration, or missing.

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. Recall system for calibratio . Requirement which prohibits use of M&TE which is not calibrated and controls to prevent inadvertent us . Storage requirement i . System to control issue of M&TE to only qualified, authorized personne . Responsibilities have been assigned to ensure that the controls specified by the procedures are implemente . -. . - .

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i-11-The NRC inspector verified that implementation of the QA program for M&TE was in accordance with the approved procedures by:

. Reviewing calibration record . Inspecting storage location . Talking with M&TE supervisor . Inspecting the Metrology Lab and the Health Physics (HP) Calibration La . Reviewing equipment storage and issue record . Verifying the calibration status of M&TE used during surveillance test observation . Reviewing traceability records for standard . Reviewing the most recent licensee quality assurance audit of the M&TE progra One problem was identified concerning the long term issue / storage records for the H&TE instruments controlled by the Health Physics organization (Section BB and CC on the Master M&TE list). Procedure 1033.09, paragraph G.1.2, requires that the primary storage location (in this case, the HP instrument control center) maintain inventory / tracking records for all active instruments on the applicable portion of the H&TE master list. Further, paragraph 6.3 requires the use of Form 1033.098 to record long term issue / storage. The NRC inspector found that the records for the BB and CC sections of the master list were not up to date, and that an outdated form was being used. Af ter notifying the licensee of this problem, the NRC inspector verified that corrective action was begun to prepare a long term storage / issue record file in accordance with the procedure. Until this file is completed and verified to be accurate, this problem will remain as an open ite (50-313/8603-01)

(50-368/8603-01)

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The NRC inspector also noted the following:

. On February 9,1986, a trainee drew a clamp-on ampmeter from the ISC tool room but failed to record the name of the authorized user for whom he apparently had obtained the meter. The trainee was not on the authorized user lis . On February 13, 1986, a broken HP instrument (RM 036) was found stored unsegregated from in calibration, ready to use instrument The technician stated that the broken status had not previously been identified, and promptly dispositioned the instrument for repair and recalibration.

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Other than the examples noted above, the NRC inspector found no problems in the licensee's implementation of the M&TE QA program. Thus, it appears that the licensee is implementing the program in accordance with it's approved procedure The NRC inspector expressed the opinion that the overall governing >

administrative procedure for M&TE (1000,14) was too genera Specifically, the procedure should clearly define, by title, which individuals are responsible for the equipment for each part of the master

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M&TE list, define their responsibilities, the applicable procedures, and denote differing requirements for different equipment categories, i Condensate Storage Tank Construction (Units 1 and 2)

The NRC inspector reviewed Design Change Package (DCp) 82-2086; Field Change Notices 1, 2, 3 and 5; and AP&L Technical Specifications C-2401 and C-2405. Activities observed by the NRC inspector included drilling of holes for ccr.densete ;'erese tank foundation piers, placement of pier concrete, slump testing of concrete, and compression testing of concret The AP&L quality control inspection plan for this DCP was discussed with quality control personne ,

No violations or deviations were identifie . Exit Interview The NRC inspectors met with Mr. J. M. Levine (Director, Site Nuclear Operations) and other members of the AP&L staff at the end of this i inspection. At this meeting, the inspectors sunmarized the scope of the inspection and the finding !

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