IR 05000313/1986008

Insp Repts 50-313/86-08 & 50-368/86-08 on 860301-31.No Violations or Deviations Noted.Major Areas Inspected: Operational Safety Verification,Maint,Surveillance & Condensate Storage Tank Const

ML20197J526
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/23/1986
From:	Craig Harbuck, Hunter D, Johnson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20197J501	List: IR 05000313/1986008 ML20197J498
References
50-313-86-08, 50-313-86-8, 50-368-86-08, 50-368-86-8, NUDOCS 8605200066
Download: ML20197J526 (8)

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APPENDIX'

U. S. NUCLEAR REGULATORY COMMISSION 4 - REGION IV NRC Inspection Report: 50-313/86-08 Licenses: DPR-51 50-368/86-08 NPF-6

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

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

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Inspection Conducted: March 1-31, 1986

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Inspectors: /A/ DC -

Jotypon, Senior Resident 4 42.2/ # 6 Dhte '

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. ReactoV Inspector

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C. C. Harbuck, Residen't Rihrsur D&te ' '

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Inspector

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. Approved: b[ m D. R. Hunter, Chief, Project Dhte a d?g Section B, Reactor Projects Branch t

8605200066 860513 9 PDR ADOCK 05000313 G PDR *

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Inspection Summary Inspection Conducted March 1-31, 1986 (Report 50-313/86-08)

Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, condensate storage tank construction, and followup on previously identified item .Results: Within the five areas inspected, no violations or deviations were identifie Inspection Summary Inspection Conducted March 1-31, 1986 (Report 50-368/86-08)

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Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, condensate storage tank construction, and followup on previously identified item Results: Within the five areas inspected, no violations or deviations were identified.

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DETAILS

, Persons Contacted J. Levine, Director, Site Nuclear Operations R. Ashcraft, Electrical Maintenance Supervisor

• B.sBaker, Operations Manager

• P. Campbell, Licensing Engineer li. Carpenter, I&C Supervisor

• E. Ewing, Engineering & Technical Support Manager M. Goodson, Civil Engineer L. Gulick, Unit 2 Operations Superintendent H. Hellis, Security Coordinator

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• D. Howard, Special Projects Manager D. Johnson, Licensing Engineer

• H. Jones, Field Construction Manager

• D. Lomax, Licensing Supervisor M. McFarland, Quality Control Engineer J. McWilliams, Unit 1 Operations Supervisor V. Pettus, ficchanical flaintenance Superintendent

' G. Parks, Quality Control Senior Inspector R. Poole, Assistant Radiochemistry Supervisor

• D. Provencher, Quality Engineering Supervisor

• L. Sanders, Maintenance Manager L. Schempp, Nuclear Quality Control flanager C. Shively, Plant Engineering Superintendent C. Taylor Operations Technical Support T. Tucker, Electrical Maintenance Superintendent

• R. Wewers, Work Control Center Manager G. Wrightam, I&C Supervisor S. Yancy, Mechanical Maintenance Supervisor

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

(Closed) Open Item 368/8234-03: Operator confusion between old and new fire alann panel As discussed in NRC Inspection Report No. 50-368/85-22, this item remained open pending completion of the training for the Unit 2 operators on the present status of the old and new fire alarm panels, and establishment of a method to ensure operators were kept up-to-date as changes between the two panels were made. The NRC inspector reviewed the training attendance reports for the training noted above and found that all applicable persons had attende The NRC inspector also determined that training on future

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changes to the fire alarm system panels would be initiated as part of the normal design change closeout process. Through discussions with several control room operators the NRC inspector determined that the confusion over the fire alarm panels appeared to no longer exist. The NRC inspector reviewed Operating

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Procedure 2203.09 " Fire Protection System Annunciator Corrective Action," of May 23, 1985, Revision 1, which provided specific guidance for each indication on the new panels (2C-343-1, 2, and 3) and directed operator attention to the old panel (2C22) when applicable. The NRC inspector concluded that this procedure was useful for operators to evaluate indications on the fire alarm panels. This item is considered close (Closed) Violation 368/8524-01: Failure to maintain system operating procedure up to dat The NRC inspector reviewed the licensee's response to this violation dated November 25, 1985. The series of events which caused this apparent violation were as follows. The identification numbers of four low pressure safety injection (LPSI) system drain valves (2SI-1082,1083,1084, and 1085) were inadvertently duplicated in a design change for the high pressure safety injection (liPSI) system. Subsequently, this duplication was identified and a Plant Engineering Action Request (PEAR) was written. The action taken was to renumber the LPSI valves, change the P&ID, and update the master manual valve list. However, the Unit 2 operations technical support group was not notified of these changes. So the procedure containing the LPSI valve lineup '2104.30)

and the valve labels themselves were not change The NRC inspector verified that the procedure and labels had been changed to

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reflect the new valve numbers. The NRC inspector also verified that operations technical support (for both units) is now routinely notified of all drawing

' changes as they are routed to the control room to enable appropriate procedural and labeling changes to be initiated. This item is considered close , (Closed) Violation 368/8524-02: Failure to properly maintain a pipe suppor This. violation involved the application of an unanalyzed horizontal stress on a seismic class I pipe support (2HCC-32-H16) by a tensioned chain fall. The NRC inspector verified that the corrective actions discussed in the licensee's November 29, 1985 letter had been completed. The licensee identified the locations on the pipe which were stressed the highest and performed a dye-penetrant test on e6ch location. The results indicated no damage. Additionally, the chain fall was removed, and managers were actioned to emphasize to their personnel the importance of proper restorotion following maintenance. This item is considered close (Closed)OpenItem 313/8522-02: Low temperature overpressurization (LTOP)

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The licensee has issued revisions to Procedure 1015.01, Revision 5, to implement administrative controls to ensure the operability of the LTOP system and the associated alarm when required by plant conditions. This item is considered close 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 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 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 tours. The following problems were noted:

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A loose nut on an anchor bolt for a non-seismic pipe support on the Unit 2 component cooling water supply to the letdown heat exchangers (located at penetration 2048-0010 in the lower north piping penetration room).

. The handwheel for valve 280-1034 had fallen of These two material deficiencies were promptly corrected by the license Additionally, the NRC inspector observed that the cooling air inlet screens were missing from the ' A' and 'C' service water pump motors in Unit 1. The air screens on the 'B' service water pump motor were dirt This was brought to the licensee's attention and corrective action was initiate During a control room tour, while the reactor was at power, the NRC inspectorobservedthatUnit2startupchannel2(2JITS-9003-2)wasoutof service. Operations personnel were informed, and J0 75721 was initiated to repair the channe The NRC inspector walked down the accessible portions of the Unit 1 and Unit 2 emergency diesel generator auxiliary support system, (the air starting system; the fuel oil transfer, storage, and supply system; the lubricating oil system; and the applicable portions of the service water system). The walkdown was performed using Procedures OP-2104.36 (attachments A and B), and OP-1104.36 (attachments 1 and 2), and

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Drawings M-217, M-210, M-2210, and M-221 The following problems were noted during the walkdown:

. Unit i valves F0-158 and FO-157 were designated as F0-5216 and FO-5217 on attachment 2 of OP-1104.36. It was determined that this error had been 4dentified earlier by the licensee and a procedure change had been initiate . The labels on PI-5241 and PI-5242 for the Unit 1 'B' EDG were interchange . Unit 2 EDG turbocharger flange connections to the air supply suction duct and to the exhaust gas duct were found to have numerous loose bolts. A job order (J0) was issued to scope and correct the problem and RAC 2-86053 was written to determine the cause and initiate preventive corrective actio These reviews and observations were conducted to verify that the selected facility operations were in conformance with the requirements established under Technical Specifications,10 CFR, and administrative procedure No violations or deviations were identifie . Monthly Surveillance Observation (Units 1 and 2)

The NRC inspector observed selected Technical Specification required surveillance testing, including Unit I reactor protection system (RPS)

channel 'C', monthly test (Procedure 1304.28); and the Unit 2 high pressure safety injection (HPSI) system motor operated valve quarterly stroke test (Procedure 2103.29, Supplement 4). The inspector verified that the 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 confonned with Technical Specifications and procedure requirements, test results were reviewed by personnel other than the individual directing the test, and ony deficiencies identified during the testing were properly reviewed and resolved by appropriate management personne The inspector also witnessed the following test activities:

Unit 1

. Post-maintenance operability test on the motor driven fire water pump (Procedure 1104.32, Supplement 1).

. P7A monthly test (emergency feedwater turbine driven pump)

(Procedure 1106.06). Two steam traps (ST-75 and 14) were observed to be " blowing by" during the test, causing the EFW pump room to becone

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aF hot and humid. The traps were isolated and JO 710260 and J0 710258

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were issued to repair the trap i

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. Reactor building hydrogen purge standby system monthly 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> test (Procedure 1104.33).

. Portions of the reactor protection system, channel 'B', monthly test, (Procedure 1304.38). During this test a problem with the fiber optic connections for channel 'O' of the emergency feedwater initiation and t control (EFIC) system was found. Channel 'D' was supplying an erroneous bypass signal to the other three EFIC channels which prevented their being placed in bypass. This resulted in an unexpected trip on EFIC channel 'B' when the RPS channel 'B'

auxiliary power supply was deenergized per step 7.4.3 of the procedur RAC 1-86-56 was issued to resolve the proble . Quarterly station battery test (Procedure 1307.06).

Unit 2

. 2P358, containment spray pump, monthly and annual test (Procedure 2104.05).

. Containment spray system 18 month integrity test and leak determination, train 'B', (Procedure 2305.09).

. Emergency diesel generator 'B' operability test (this was performed

' due to EDG ' A' being declared inoperable) (Procedure 2104.36).

No violations or deviations were identifie . Monthly Maintenance 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 activity; the activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality

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control records were maintained; the 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

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ensure that priority was assigned to safety-related equipment maintenance which may affect. system performanc '

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The following maintenance activities were observed:

Unit 1

. Repair body to bonnet leak on the 'A' steam generator inlet check valve,FW-7A(Procedure 1072.02, JO 708586).

. Repair of NI-5 power imbalance circuit (JO 709288).

. Repair of EFIC channel 'D' bypass function (JO 709648).

Unit 2

. Spent fuel pool pumps 2P40A and 2P40B mechanical seal replacement (J0s 706480 and 700766), Procedure 2402.13, Revision 0, of March 12, 1982). The NRC inspector noted that a different type of seal was being installed than described by the procedure. It was verified that the applicable technical references and the seal manufacturer were consulted to ensure proper installation. A revision to the procedure to detail the installation of the new type seals was being prepare . Spent fuel pool pump 2P408 discharge valve repair (JO 705793).

No violations or deviations were identifie . Condensate Storage Tank (CST) Construction (Units 1 and 2)

The NRC inspector periodically observed, during the inspection report period, CST construction activities including the placement of the concrete support piers, rebar installation, valve pit excavation, concrete slump testing and concrete 7 day and 28 day strength testing. It was noted that a portion of pier S-19 was placed with concrete with slump of nine inches which was above the design specification. Subsequent concrete test cylinder strength tests for pier S-19 were less than the design strength of 3000 psi. Non-conformance Report (NCR) 86-014-0 addressed this problem, and was closed out on the basis that the actual strengths were within allowed tolerance No violations or deviations were identifie . Exit Interview The NRC inspectors met with Mr. E. Ewing, Acting Director, Site Nuclear Operations, and other members of the AP&L staff at the end of this inspection. At this meeting, the inspectors sunmarized the scope of the inspection and the findings.