IR 05000313/1986038

Insp Repts 50-313/86-38 & 50-368/86-38 on 861101-30.No Violations or Deviations Noted.Major Areas Inspected: Operational Safety Verification,Followup on IE Info Notices & Cold Weather Preparations

ML20207E963
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/19/1986
From:	Craig Harbuck, Hunter D, Johnson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20207E952	List: IR 05000313/1986038 ML20207E946
References
50-313-86-38, 50-368-86-38, NUDOCS 8701050257
Download: ML20207E963 (11)

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APPENDIX U. S. NUCLEAR REGULATORY COMf1ISSION

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REGION IV

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NRC Inspection Report: 50-313/86-38

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Licenses: DRP-51 50-368/86-38 NPF-6 l Dockets: 50-313 L 50-368 Licensee: Arkansas Power and Light Company (AP&L)

P. O. Bcx 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2 I Inspection At: AN0 Site, Russellville, Arkansas >

Inspection Conducted: November 1-30, 1986

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Inspectors: /2/n O d_

W. D. Joyson, Senior Resident Reactor

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(pars.2,3,4,5,6,7,8,9)

/d Sd C. C. Harbuck, Resident Reactor Date Inspector (pars. 2, 4, 5, 6)

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Approved: Jd D. R. Hunter, Chief, Reactor

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I li Date Project Section B, Reactor Projects Branch

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l 8701050257 861222 hDR ADOCK 0500o31o PDR

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-2-Inspection Summary Inspection Conducted November 1-30, 1986 (Report 50-313/86-381 Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, followup on previously identified items, followup on IE Information Notices, cold weather preparations, and liquid radioactive waste discharge Results: Within the seven areas inspected, no violations or deviations were i der.ti fie Inspection Summary Inspection Conducted November 1-30, 1986 (Report 50-368/86-38)

Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, followup on previously identified items, followup cn licensee event reports, followup on IE Information Notices, cold weather preparations, and liquid radioactive waste discharge Results: Within the eight areas inspected, no violations or deviations were identifie ___ - __ ____-_- __ _ _

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DETAIM Persons Contacted

• J. Levine, Director of Site Nuclear Operations B. Baker, Operations Manager

• T. Baker, Technical Support Manager D. Bennett, Mechanical Engineer D. Bowlby, Bechtel Field Engineer

• P. Campbell, Licensing Engineer J. Conners, Startup Engineer A. Cox, Unit 1 Operations Superintendent D. Engle, Westinghouse Engineer -

E. Ewing, General Manager Technical Support B. Garrison, Operations Technical Support R. Gillespie, Technical Analysis Superintendent J. Gobell, Mechanical Engineer B. Godwin, Startup Engineer J. Grisham, Administrative Manager L. Gulick, Unit 2 Operations Superintendent C. Halbert, Mechanical Engineering Supervisor H. Hollis, Security Seperintendent D. Horton, Quality Assurance Manager D. Howard, Specials Projects Manager

• L. Humphrey, General Manager, Nuclear Quality

• H. Jones, Plant Modifications Manager P. Kearney, Project Engineer

• R. Lane, Engineering Manager

• D. Lomax, Licensing Supervisor B. McCord, Quality Control Inspection Supervisor A. McGregor, Engineering Services Supervisor J. McWilliams, Maintenance Manager V. Pettus, Mechanical Maintenance Superintendent D. Provencher, Quality Engineering Supervisor

• S. Quennoz, General Manager, Plant Operations P. Robbins, Assistant Chemistry Supervisor P. Rogers, Plant Licensing Engineer C. Shively, Plant Engineering Superintendent M. Smith, Reactor Engineering Supervisor S. Smith, Senior Engineer C. Taylor, Operations Technical Support Supervisor

• J. Taylor-Brown, Quality Control Superintendent R. Tucker, Electrical Maintenance Superintendent

• J. Vandergrift, Training Manager B. West, Instrumentation and Controls Supervisor

• R. Wewers, Work Ccatrol Center Manager

• Present at exit intervie l

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-4-The inspectors also contacted other plant personnel, including operators, technicians, and administrative personne . Followup On Previously Identified Items (Units 1 and 2)

(Closed) Unresolved Item (313/8507-01): Fire Door 19 would not stay shu The licensee has installed another door through the wall of the upper south piping penetration room to serve as a vent in case of a high energy line break in the room. Since Fire Door'19, which leads to the emergency feedwater pump room, was no longer required to provide a vent path, it was provided with a latching mechanism. This item is close (Closed) Open Item (313/8506-07): Possible installation of hydrogen recombiners due to problems in the design and operation of the hydrogen purge system The licensee installed redundant hydrogen recombiners inside the reactor building during refueling outage 1R7. This was performed under Design Change Package 84-106 Technical Specification Amendment 102 has been issued to specify operability and testing requirements for the new recombiners and to delete the purge system operability and testing requirements. The NRC inspector obe d various phases of the installation of the recombiners and sssociated control, power, and instrumentation. The NRC inspector also observed the performance of the heater temperature indication circuit string check for one of the unit Other tests observed included the preoperational_ system test and the initial heatup test on one of the two unit These were performed in accordance with approved test procedures. Although other aspects of this installation will be inspected during subsequent inspection periods, the open item is considered close (Closed) Unresolved Item (368/8627-05): Concern about cleanliness practices during construction of the seismic condensate storage tank and associated piping systems supplying emergency feedwater to both unit The NRC inspector continued to observe construction activities, but noted no additional problems regarding cleanliness. The NRC inspector also witnessed part of the piping flush for Unit 1 and verified that it was being performed in accordance with the procedure. Additionally, samples of the debris collected in the filters during the fluching of the piping in both units were examined. Only small particles and remnants of paper wiping towels were found, indicating that adequate cleanliness had been maintained. Based on these observations, this item is considered close No violations or deviations were identified.

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-5-3. Licensee Event Report (LER) Followup (Unit 2)

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 recurrence has been accomplished in accordance with Technical Specification Ventilation system charcoal analysis error 86-005-00 Reactor trip in mode 3 86-009-00 Reactor trip during controlled shutdown 86-010-00 Sleeping fire watch personnel LER 86-002-00 reported an error made in the analysis of samples from the charcoal filters in three plant ventilation systems. The error was

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identified and corrected by the licensee in 1984, but at that time the error was believed to be in the conservative direction. Further review, following a review of control room habitability by the NRC Office for {

Analysis and Evaluation of Operational Data, revealed that the error was not conservative and resulted in this LE LER 86-009-00 reported a reactor trip on axial shape index during a controlled plant shutdown. A software change made to the core protection ce.lculators during the last refueling outage is expected to prevent future trips of this typ No violations or deviations were identifie . Operational Safety Verification (Units 1 and 2)

The NRC inspectors observed control room operations, reviewed applicable logs, and conducted discussions with control room operators. The inspectors verified the operability of selected emergency systems, reviewed tagout records, verified proper return to service of affected components, and ensured that maintenance requests had been initinted 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 plan. 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 tour The NRC inspectors observed a portion of the core reloading activities which were ccmpleted during this inspection period. No problems were identified during these observations, but the inspectors were informed that a problem was identified during the core verification following refueling. The wrong fuel assembly had been placed in one core location due to an indexing error in the spent fuel pool. This error was corrected by the license (

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-6-The NRC inspectors walked down the. accessible portions of the Unit 2 low pressure safety injection system (LPSI). The walkdown was performed using Procedure 2104.40 and drawings M-2232 and M-223 Several minor discrepancies were noted and are listed below. These were identified to the licensee who then issued job requests (JRs), some of which are also noted:

. The accumulator for 2CV-5093 had no local pressure gage; the accumulator for 2CV-5091 had a pressure gage. (JR 771484)

. The handwheel was off of valve 2SI-1016. This had been previously noted by the licensee. (JO 719549 issued September 6, 1986).

. Valve 28S-5636 had no identification labe Other items not associated with the'LPSI system were also identified:

. Check valve 2SI-12 in the high pressure pressure injection (HPSI)

system had rusty nuts on the cover plate. (JR771487)

. Each of the following seismic supports had a loose nut on one of the concrete expansion anchors on their-baseplate (1) HPSI line pipe support 2-CCB-12-H12 (Report of Abnormal Conditions (RAC) 2-86-499)

(2) HPSI' injection valve 2CV5036-1 motor operator support (JO 724574).

The licensee's response to Violation 368/8627-03 for the same type of problem has not been received ye . The cover on the terminal board for the remote position indication transmitter for valve 2CV5016-2 was not tightened down properl (JR 770434)

. Valve 2CV5859, "B" steam generator sarnple isolation valve, had a packing leak of approximately 60 drops per minute. (JR771442)

. The emergency feedwater (EFW) piping upstream of header check valves 2EFW-9A and 2EFW-7A felt warmer to the NRC inspector than expected. The licensee's investigation determined that leakage past these valves from the niain feedwater line to the "A" steam generator was approximately.10 milliliters per minute. The normally shut isolation valve 2CV1026 upstream of these valves was also determined to be leaking a small amount; however, there was apparently no adverse effect on EFW Pump 2P7A. All the flow was going through the minimum recirculation line to the startup and blowdown demineralize RAC 2-86-500 and JRs 771532, 771533, and 771534 were issue An atte:npt to scat check valve 2EFW-7A was attempted using EFW Pump 2P7A to establish flow to the "A" steam generator through the

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-7-check valve for a short tim The attempt was not fully successfu The licensee was continuing to monitor and evalualte the conditio Monthly Surveillance Observation (Units 1 and 2)

~ The NRC inspector observed that the Technical Specification required surveillance testing on the "B" high pressure safety injection pump, 2P89B, (Procedure 2104.39), and verified that testing was performed in accordance with adequate procedures, test instrumentation was calibrated, limiting conditions for operation 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 ware properly reviewed and resolved by appropriate management personne The inspector also witnessed portions of the following test activities:

. Endurance test of Number 2 diesel generator (Procedure 1104.36, Supplement X)

. Electrical inspection and test of Number 1 diesel generator (Job Order 716501, Procedure 1307.26)

. Diesel fire pump engine inspection (Job Order 529157, Procedure 1306.27)

. Monthly test of Number 1 diesel generator (Procedure 2104.36, Supplement I)

. Unit 1 seismic condensate storage tank modification flow operability test (Procedure 1409.86)

. Number one diesel generator (Unit 1) K4A governor adjustment (Procedure 1407.01)

No violations or deviations were identifie . Monthly Maintenance Observation (Units 1 and 2)

Station maintenance activities of safety-related systems and ccmponents 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

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-8-as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and fire prevention controls were implemente 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:

. Replacement of diesel generator jacket cooling water pump (Job Order 722913, Procedure 2402.57)

. Replacement of valve CV-3806 (Job Order 722895, DCP 84-1046A)

. Preventive maintenance on diesel generator starting air compressors (Job Order 529313, Procedure 1402.050)

. Service water pump P4C inspection and preventive maintenance (Job Order 716952, Procedure 1402.61)

. Replacement of valve CV-3807 (Job Order 722553, DCP 84-1046A)

. Repair of diesel fire pump engine starter (Job Order 706425),

. Diesel fire pump engine flywheel replacement (Job Order 724191, Procedure 1406.034)

. Inspection of diesel generator cooling system for corrosion (Job Order 716821)

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. Diesel generator service water pipe support installation (Job Order 720012)

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. Limit switch adjustment on valve 2CV-3037-1 (Job Order 723837)

. Replacement of reactor trip breaker ECBS relay (Job Order 723907)

No violations or deviations were identifie . Followup on IE Information Notices (Units 1 and 2)

The NRC inspector reviewed the licensee actions taken in response to IE Information Notices (IENs) issued in 1985 and 1986. The IENs included in this review were 86-01 through 86-54 and the 1985 IENs for which the licensee review had not been completed at the time of the last NRC inspection in this area. The review included verification that the notices were

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t-9-received by the licensee, that they were distributed to appropriate personnel for an applicability review, and that appropriate corrective actions were taken or schedule The NRC inspector found that the licensee had received the IENs and that a system for distributing the IENs for review and for assignment and tracking of responsive actions was established. The NRC inspector reviewed the documented licensee reviews and responsive actions for the completed IENs and found the reviews to be appropriate in scope and depth and the responsive actions to be comprehensiv '

In most cases, the licensee's review of IENs was found to be timel At the tirre of this inspection, review of the following IENs was not complete:

85-21 86-07 85-27 66-11 85-28 36-16 85-45 86-19 85-53 86-20 85-59 86-25, Supplement 1 85-84 86-26 85-85 86-42 85-86 86-49 Since a number of these IENs had licensee assigned due dates for review as far back as June or July of 1985, the NRC inspector concluded that the licensee should improve its system for followup and completion of IEN revie No violations or deviations were identified.

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8. Cold Weather Preparations (Units 1 and 2)

i The NRC inspector reviewed the current implementation status of the licensee's program to ensure that systems and components susceptible to

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freezing in cold weather are adequately protected.

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The latest revision of Procedure 1307.37, " Plant Freeze Protection Testing," Revision 4, was reviewed by the NRC inspector. This procedure i had been recently performed under Job Order 528737. The NRC inspector noted that this procedure will need to be revised upon completion of the l

installation of the new condensate storage tank and the associated outdoor piping.

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The NRC inspector found that the operations department has initiated use of freeze protection logs which require the checking of certain important freeze protection equipment during operator tours. The Unit 1 log (1015.03A-18) was completed each shift during the months of October through Apri The Unit 2 log (1015.038-14) was completed daily on the mid-shift during the months of October through Marc .

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-10-Two new procedures were issued on November 12, 1986. These procedures, 1306.018 and 2306.011, require an inspection to verify that piping systems are properly insulated for freeze protection. These procedures were scheduled to be performed for the first time in December 198 The NRC inspector concluded that the licensee has established and was implementing a comprehensive program to ensure that important plant equipment was protected from freeze damag No violations or deviations were identifie . Resin in Liquid Radioactive Waste (Units 1 and 2)

The NRC inspector received a telephone call from an unidentified person who said that resin beads had been found in the discharge canal. This call was handled as an allegation (4-86-A-120), and the NRC ins 1ector performed a review to determine its validity and significanc Discussions with licensee personnel and review of records yielded the following information:

. In September 1986, the licensee found resin beads in the liquid radwaste system of Unit . Discharge canal shoreline and bottom samples were collected from many location . Analysis of these samples indicated the presence of a few resin beads, but the sample activity was essentially unchanged from previous samples taken semi-annually over the past few year . The Unit 1 T16 tanks were drained and cleane Some resin was found

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Due to its lack of radioactivity, the resin in the discharge canal was believed to have come from the Unit 1 or 2 neutralizing tank .

Prior to discharge, the liquid radwaste tanks were analyzed for suspended solids. The tanks were mixed prior to sampling, and the suspended solids content had been measured at 6 to 25 percent of the limit of 100 milligrams per lite .

The licensee was evaluating possible design changes, such as the addition of strainers in the lignid radwaste system, to reduce the likelihood of inadvertent discharge of resin bead The NRC inspector concluded that resin had been found in the discharge canal, that the licensee was aware of the situation and had taken appropriate actions, and that no regulatory limits appeared to have been exceede No violations or deviations were identifie . __ -- .-. - -

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10. Exit Interview The L' ispectors met with Mr. J. M. Levine, Director, Site Nuclear Operat as,.and other members of the AP&L staff at the end of this inspection. At this meeting, the inspectors summarized the scope of the inspection and the finding