IR 05000313/1986015

Insp Repts 50-313/86-15 & 50-368/86-15 on 860501-31. Violations Noted:Failure to Lock Manual Valve in Position & Failure to Have Adequate Controls Over Installation of Temporary Scaffolds

ML20212A058
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/11/1986
From:	Craig Harbuck, Hunnicutt D, Hunter D, Johnson W, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20212A028	List: IR 05000313/1986015 ML20212A024 ML20212A034
References
50-313-86-15, 50-368-86-15, NUDOCS 8607280105
Download: ML20212A058 (20)

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APPENCIX B

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U.S. NUCLEAR REGULATORY COMMISSION

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REGION IV

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NRC Inspection Report: 50-313/86-15 Licenses: DPR-51

  . . _ , 50-368/86-15   NPF-6 Dockets: ' 5d-313 50-368 Licen'see: Arkansas Power and Light Company (AP&L) .
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P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2 Inspection At: AND Site, Russellville, Arkansas Inspection Conducted: May 1-31, 1986 Inspectors: 7' I QW. D. J6hnsg4 S(nior Resident Reactor Date~ Inspector (pars. 3, 4, 5, 6)

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       '~2 8 Q C. C. Harbuck, IWhi gnt Reactor Inspector  Oste '
   (pars. 2, 4, 5, 6, 7)

h) D. M. Hunnicutt, Chief, Operations Section, Yl/O $$ 0' ate / Reactor Safety Branch (pars. 2, 8, 9, 10) h R. C. St'ew' art, Reactor Inspector 06te /

       /O b (par. 11)

8607280105 860723 PDR ADOCK 05000313 G PDR ,

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Approved: ll D. R. Hun'ler, Chief, Project Section B, Date Reactor Projects Branch Inspection Summary Inspection Conducted May 1-31, 1986 (Report 50-313/86-15) Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, followup on previously identified items, condensate storage tank construction, receiving inspection and procurement control, and procurement document contro Results: Within the seven areas inspected, one violation was identified (failure to calibrate admixture liquid dispenser, paragraph 11).

Inspection Summary , Inspection Conducted May 1-31, 1986 (Report 50-368/86-15) Areas Inspected: Routine, unannounced inspection including operational safety verification, maintenance, surveillance, followup on Licensee Event Report, followup on previously identified items, condensate storage tank construction, implementation.of vendor operation and maintenance recommendations, receiving inspection and procurement control, and procurement document contro Results: Within the nine areas inspected, three violations were identified (failure to lock a manual valve in position as required, paragraph 4, failure to have adequate controls over the installation of temporary scaffolds in the vicinity of safety-related equipment, paragraph 4, and failure to calibrate admixture liquid dispenser, paragraph 11).

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DETAILS Persons Contacted

 *J. Levine, Director of Site Nuclear Operations B. Baker, Operations Manager C. Bates. Shift Maintenance Supervisor
 *D. Bennett, Mechanical Engineer
 .R. Breese, Maintenance Support Group Supervisor
 *P. Campbell, Licensing Engineer S. Capehart,'I&C Maintenance Engineer H. Carpenter, I&C Supervisor T. Cogburn, General Manager, Nuclear Services A. Cox, Operations Technical Support Supervisor
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 *E. Ewing, General Manager, Technical Support L. Gulick, Unit 2 Operations Superintendent
 *J. Hale' Bechtel, Engineer
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_ H. Hollis, Security Coordinator

 *D. Howard, Special Projects Manager
 *L. Humphrey, General Manager, Nuclear Quality D. Johnson,-Licensing Engineer
 *H. Jones, Field Construction Manager
. P.' Jones, Acting Maintenance Manager
 *R. Lane,~ Engineering Manager
 *D. Lomax, Licensing Supervisor
 * McFarland, QC Inspector
 *J. McWilliams, Unit 1 Operations Superintendent
 *J. Orlicek, Field Engineering Supervisor
 *G. Parks, QC Inspector
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V. Pettus, Mechanical Maintenance Superintendent i R. Poole, Assistant Radiochemistry Supervisor

 *D. Provencher, Quality Engineering Supervisor
*S. Quennoz, General Manager, Operations and Maintenance
*J. Remer, Maintenance History Supervisor P. Rogers, Plant Licensing Engineer
*D. Saunders, Engineering Supervisor
*L. Schempp, QC Superintendent
*C. Shively, Plant Engineering Superintendent R. Simmons, Planning and Scheduling Supervisor t  C. Taylor, Operations Technical Support Supervisor

! D. Wagner, Acting Health Physics Superintendent

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

, *Present at one or more exit interviews.

l ' The inspectors also contacted other plant personnel, including operators, technicians, and administrative personnel.

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4 Followup on Previously Identified Items (Units 1 and 2)

(Closed) Open Item (313/8603-01, 368/8603-01): Health Physics measuring and test equipment long term storage / issue record fil The NRC inspector verified that this file had been prepared, was accurate, and was being used according to the governing procedure (1033.09). This item is considered close (Closed) Violation (313/8335-01; 368/8335-01): Failure to detect discrepant conditions in accordance with Procedure No. 1033.0 The NRC inspector determined that the licensee had completed corrective actions related to the Notice of Violation (NOV) and paragraph 2 (Receiving Inspection) of NRC Inspection Report No. 313/83-35; 368/83-3 These documents reported that the licensee had accepted fastener certifications from Cardinal Industrial Products and Southern Bolt &

Fastener which did not comply with certain documentation requirements of the applicable purchase orders. The NRC inspector determined that the licensee had completed corrective actions which resolved the specific NOV and related discrepant conditions identified by the NRC. The NRC inspector.further determined that the effectiveness of the licensee's overall QA program has shown improvemen The three purchase order packages reviewed indicated that the licensee was adhering to procurement control commitments and previously reported corrective actions. This item

. is considered close (Closed) 0 pen Item-(313/8335-02; 368/8335-02): Practices used to establish engineering and quality requirements for Q-list replacement part As discussed in NRC Inspection Report No. 313/83-35; 368/83-35, this area remained open pending completion of a detailed inspection of practices used to establish engineering and quality requirements for Q-list replacement part The NRC inspector reviewed three documentation packages applicable to purchase orders (P0s) for Q-list items. The review of these three packages verified required vendor documentation submittals were complete and that receiving inspections had been performed to assure compliance of received items with the respective P0 requirements. This item is considered close No violations or deviations were identifie . Licensee Event Report (LER) Followup (Unit 2)

Through direct observation, discussions with licensee personnel, and review of records, the following event report was 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 _ _ ._

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LER 85-027 provided an information report concerning the discovery of the undervoltage trip device armatures on two reactor trip circuit breakers in a mid position. The NRC inspector reviewed Report of Abnormal Condition 2-85321 and the procedure changes which were made in response to this event. Steps were added to the following procedures to verify that the undervoltage device armatures are in the proper position: 2102.08 - Approach to Criticality 2105.09 - CEDM Control System Operation 2102.02 - Plant Startup

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The NRC inspector'also verified that the licensee had considered the _ , applicability of,this event to the Unit 1 reactor trip breaker This LER

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No violations or deviations were identifie ,,

- Operational Safety Verification (Units 1 and 2)
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The NRC.in'spectors 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

  'componen'ts, and ensured that maintenance requests had been initiated for
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 . . 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 pla 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 walked down the accessible portions of the Unit 2

, containment spray system. The walkdown was performed using Procedure 2104.05 and Drawing M-2236. No system lineup discrepancies were identified but several valves with missing tags were identified, and several motor operated valves were found to be missing their stem housing end caps. The licensee was informed of these minor discrepancies so corrective action could be initiated.

l l The sodium hydroxide tank has a 3-inch drain line which is normally I isolated by two closed manual valves in series. Drawing M-2236 and Attachment A of Procedure 2104.05 indicate that these two valves should be locked closed. The NRC inspectors found that these two valves, 285-1015 and 285-1016, were closed as required, but that 2BS-1016 was not locked in position as required. This is an apparent violation of TS 6. (368/8615-07) ' . _. _ . _ _ . _ _ _ __ __ _ ,_ _ _ , _ _ _ _ ._

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During a plant tour-on. May 23, 1986, the NRC inspector observed that

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temporary scaffolds were being supported by seismic category I piping in the vicinity of .the:' A' containment spray pump on elevation 317 in the Unit 2 auxil.iary building. The two sections of piping involved were 2DCB-511-2", high pre ~ssure safety injection pump recirculation pipe, and 2HCB-38-4",. sodium hydroxide pump suction pipe. The licensee could provide-no analysis to justify using seismic category I piping to support scaffolds and modified the scaffold supports. During a tour of the same

 , area on May 28, 1986, the NRC inspector observed that the scaffolds had been modified such that seismic category I piping was no longer supporting
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the scaffolds. However, the scaffold vertical support poles were wired to

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the piping' sections mentioned above and to 2HCB-15-20", the containment spray and low pressure safety injection suction pipe, and 200B-2-4", the combined recirculation pipe for the 'A' containment spray, low pressure safety injection and high pressure safety injection pumps. Again, no analysis was available to justify this scaffold configuratio On May 30, 1986, the NRC inspector verified that the scaffolds in this area were no longer connected to seismic category I pipin Based on these observations and discussions with licensee personnel, the NRC inspector concluded that the licensee's controls on the erection of temporary scaffolds in the vicinity of safety-related equipment were inadequate. This is an apparent violation of Criterion II and Criterion V of Appendix B to 10 CFR 50. (368/8615-08) 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 . Monthly Surveillance Observation (Units 1 and 2) The NRC inspector observed the Technical Specification required surveillance test of the Unit 2, 'A' high pressure injection pump on May 25, 1986, (Procedure 2104.39, Supplement 1) 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 were properly reviewed and resolved by appropriate management personne The NRC inspector noted an inconsistency during the conduct of this tes The local discharge pressure gage (a high accuracy heise gage permanently installed as part of a plant design change to enhance the accuracy of inservice testing data for safety-related pumps) indicated 1452 psig while the remote pressure transmitter indication in the control room indicated 1490 psi A review of the procedure (Supplement 1 to 2104.39) showed that the local pressure was recorded for information only and that the pump head, being compared to the acceptance criteria, was computed using the control room indication. (The suction pressure was obtained from a

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local gage). The NRC inspector discussed this item with the Unit 2 operations technical support supervisor and questioned the use of the remote, instead of the local, indication in light of the fact that the local gage was closer to the pump outlet, was more accurate, was calibrated more frequently, and was installed for that purpose. In this case, the NRC inspector suggested that the noted difference in readings might indicate that the remote indication was in need of calibratio The NRC inspector was informed that a plant engineering action request (PEAR) would be initiated to resolve the inconsistency in the local and remote readings. It should be noted that even using the local indication, the pump head was still within the normal range of values stated in the procedur As this item will require further review, it is designated for tracking purposes as an open item concerning the use of local test gages for pump inservice test dat (368/8615-09) The inspector also witnessed portions of the following test activities:

. . Calibration of 'D' safety irjection tank instrumentation (Job Order 705453, Procedure 2304.75)
. Calibration of 'C' safety injection tank instrumentation (Job Order 705452, Procedure 2304.74)
. Local leak rate testing of electrical penetrations (Job Order 704939, Procedure 2304.15)
. Engineered safeguards actuation system number 2 channel test (Job Order 712318, Procedure 1304.46)
. Monthly test of the Unit 2 emergency diesel generator 'A'
 (Procedure 2103.36, Supplement 1)
. Quarter,1y channel test of the fuel handling area exhaust ventilation
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radiation monitor 2RX-9830 (Job Order 712180, Procedure 2304.151)

. Channel 'B' of the plant protection system monthly test (Procedure 2304.38)
. Main steam isolation valve quarterly partial stroke test-(Procedure 2106.16, Supplement 1)

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 . . . - = . _ . _ .

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     '8 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 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:

 . Preventive maintenance overhaul of service water pump 2P4C (Job

, Order 758911, Procedure 2402.34) .

 . Preventive maintenance on service water pump motor 2PM4C (Job
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Order 526487,- Procedure 2403.04)

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Inspection of emergency DC lighting system batteries (Job Order 712614)

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 . Replacement of air vent connection on 2P4C (Job Order 712675)
 .- Inspection.of 2P4A discharge strainer (Job Order 707904)

s Preventive maintenance on service water pump motor 2PM4A (Job

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Order 525589, Procedure 2403.04)

 . Repair of check valve 55-495 in the post-accident sanipling system (JO 712547)
 . Repair of plant protection system auctioneered power supply, PS-4 j  (JO 712797)

, l No violations or deviations were identified.

l l Licensee Implementation of Vendor Operation and Maintenance l Recommendations (Unit 2) i The purpose of this area of inspection was to ascertain whether or not the licensee had incorporated the operations and maintenance recommendations l given by the Fairbanks-Morse Service Information letter (SIL) of November 15, 1984, concerning the Unit 2 emergency diesel engines to prevent damage to the scavenger air blowers. The SIL was written in , i l response to a failure of the scavenger air blower on the same model diesel l engine used at ANO for Unit 2 (38TD8-1/8). The SIL stated the most likely cause of the failure was thermal deformation of the aluminum housing due

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to localized heating while running for extended periods under no load conditions during warmup or cooldown operation The SIL made two recommendations to prevent this problem: ,

 . Limit no load operation to a maximum of 5 minute . Check for proper blower to casing clearances at each refueling outag The NRC inspector found that the second recommendation had been incorporated into licensee maintenance Procedure 2306.05, " Preventive Maintenance Emergency Diesel Generator," Revision 3, Change 9 of April 9, 198 However, the licensee's operation and surveillance test procedure-for the diesel generators (Procedure 2104.36) did not specifically limit no load operation to a maximum of 5 minutes. Until this recommendation is fully assessed by the licensee for incorporation into this and all other applicable procedures, this issue will remain as an open ite (368/8615-10) Receiving Inspection and Procurement Control (Units 1 and 2)

The NRC inspector co'nducted an inspection of the receiving inspection and procurement document control areas. The purpose of this inspection was to

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review the corrective-actions completed by the licensee to assure full compliance with'NRC regulations and licensee commitments related to a potential escalated enforcement action item (later a NOV was issued and a

 ' civil penalty imposed) and an open item reported in NRC Inspection Report No. 313/83-35;'368/83-35, paragraphs 2 and 3, respectivel The NRC' inspector reviewed licensee procurement control commitments contained in the following:
, : AP&L Topical Report APL-TOP-1A, Revision 5, Section 4
. AP&L Procedure No. 1000.10, " Control of Procurement," Revision 9

AP&L Procedure No. 1000.11, " Purchase Requisition Preparation and Control Procedure," Revision 14 AP&L Procedure No. 1033.01, " Receipt Inspection," Revision 13

' Letter dated August 24, 1984, from John R. Marshall, Manager Licensing AP&L, to R. C. DeYoung, NRC, which responded to NRC letter l dated July 25, 1984 The NRC inspector reviewed the following P0s to verify that the licensee l had completed corrective action and was adhering to procurement control commitments and reported corrective actions (reference: In a letter dated August 24, 1984, from AP&L to the Director, Office of Inspection and l }

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Enforcement, NRC, in response to the NOV and Proposed Imposition of Civil Penalty sent to AP&L with an NRC OI&E letter dated July 25, 1984): P0 No. 73555 sP0ho.75400 P0 No. 82820 d., P0 No. 32258

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The.NRC inspector determined that the licensee had performed the required reviews and completed. corrective actions appropriate to remedy the items brought to-the licensee's attention through the potential escalated enforcement action (later issued as an NOV) and open item discussed in paragraphs 2 and 3 in NRC Inspection Report 313/83-35; 368/83-35. The summary of licensee's response discussed in the Appendix to ORDER IMPOSING A CIVIL MONETARY PENALTY was reviewed to assure that the licensee's .

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corrective actions had been completed as liste No violations or, deviations were identifie . Procurement Document Control (Units 1 and 2) ) The NRC inspector reviewed the P0 document packages for three selected purchases. ~ Each document package consisted of a P0, Purchase Requisition (PR), material test report (MTR), Receipt Inspection Report, inspection required, packing list, and other pertinent information and

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data.

l P0 45497 (PR No. 72835) was for eight 5/8" diameter by 8" long stud CFR Part 21 was applicable. The material was from heat No. 63844 and was quenched and tempered. The material was purchased to ASME Section III, Division 1, 1980, Ed., S-82 add., Class The NRC inspector determined that this P0 document package was complete and met the licensee's requirements and commitment P0 31756 (PR No. 42040) was for eight 7/8" diameter by 4" long bolts.

, 10 CFR Part 21 was applicable. These bolts were replacement bolts for I service water strainers and were from heat No. 62150. The material was purchased to ASME Section III, Division 1, 1980 Ed.,'S-82 add., j Subsection NC. The NRC inspector determined that this P0 document package j was complete and met the licensee's requirements and commitments.

l P0 28370 (PR No. 28370) was for a set screw; cup point 3/8"-16 by 1/2".

l This item was "Q-Listed," but did not require QA documentation or require i

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10 CFR Part.21 compliance. The type 316 stainless steel met ASTM A-27 The NRC inspector determined that this P0 document package was complete

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ano met the licensee's; requirements and commitment =Th'e NRC ' inspector's review of licensee's corrective actions, issued P0s, and procedures indicated that appropri.3te corrective actions had been _ co,mplete . The open item referenced in NRC Inspection Report No. 313/83-35; 368/83-35 is considered close . No violations or deviations were identifie . Review of Licensee Actions to Resolve NOV for Accepting Fastener Certifications Which Did Not Comply With Certain Documentation Requirements of Applicable P0s (Units 1 and 2) The NRC inspector reviewed the licensee's corrective actions related to the NOV for received materials, which did not conform to procurement requirements. This included a review of document packages for P0 Nos. 73555, 75400, and 93800. The licensee performed an audit of the ' Cardinal Industrial Products facility of November 2-4, 1983. The licensee commenced independent testing of studs purchased on P0 No. 73555 and verified that these studs conformed to ASME and material specification The nuts for these studc were rejected due to the independent testin The licensee determined that the service water valve replacement fasteners purchased on P0 No. 93800 did not meet ASME Section III, Class 3 requirements. Material on P0 No. 93800 which did not meet requirements was qualified by the licensee under ASME Code Case N-242- The licensee documented that there were no safety concerns associated with the use of fasteners (bolting materials) from P0 Nos. 73555 or 93800. The licensee resolved the documentation deficiencies associated with these two P0s. The licensee identified the P0s under which materials had been purchased from the two suppliers listed in the NRC NOV and completed appropriate corrective actions to assurc apliance of the materials with ASME and materials specification The licensee increased their QC es a's tr d in the review of procurement documentation and in receipt inspection activitie The licensee also improved their training program for QC personnel in this area to increase the quality of procurement activity related inspection The licensee had formalized a contract with an independent testing laboratory. The licensee had established procedural guidelines for sample selection. The laboratory analyses were used to verify the validity of vendors' certification programs. P0s now contain a statement that QA documentation is required and that materials are subject to confirmatory test and analysis after receipt by AP&L.

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3 The NOV was issued on July 25, 1984, subsequent to the issuance of NRC Inspection Report No. 313/83-35; 368/83-35. The licensee's response dated August 24, 1984, described the corrective actions the licensee had implemented and/or commitments to be implemented. These had been completed by the licensee prior to this NRC inspectio This item is considered close No violations or deviations were identifie . Inspection of Concrete Production and Production Facilities Relative to DCP-82-2086 (Units 1 and 2) During the period May 29-30, 1986, the NRC inspector conducted an inspection of activities relative to the production and placement of category I structural concrete associated with DCP-82-2086, T418 condensate storage tank addition. The inspection was to determine by direct observation and independent evaluation whether work and inspection relative to structural concrete were being accomplished in accordance with specifications, codes, standards, and NRC requirement During the inspection, the principle contractor was completing the forming, placing embeds, and installation of reinforcing steel in preparation for concrete placement of the condensate stcrage tank support slab, Document Review During the inspection, the NRC inspector revi'ewed 15 concrete production batch tickets (concrete control document, Form C-2405-1) for concrete pier placements completed April 3, April 10, and April 17, 1986. These records reflected that concrete production batching was within the mix proportion envelope specified for design mix 1A,'l-1/2" aggregate.- In addition, the NRC inspector reviewed the concrete design mixes '

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certi fications.'

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p , No violations or, deviations were identified during the above revie Batch Plant Walk-Down During the inspection, the NRC inspector conducted a walk-down of the licensee's concrete supplier facility in Russellvill During the inspection, the inspector cbserved that calibration stickers were absent on both the batching water meter and the (manual control) air

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entrainment liquid dispenser. In discussing these matters with the licensee representatives, the inspector was informed that the air entrainment liquid dispenser system had been modified some 2 weeks earlier by Master Builders Inc. - Admixture Supplier and it was

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,'    13 assumed that a recalibration was performed at that time. However, the batch plant superintendent stated that he did not have any documentation that would support this assumption, nor was there available documentation to support checklist item, 2.4.3. , contained in the National' Ready Mixed Concrete Association (NRMCA)

certification dated November 11, 198 The licensee's failure to assure that the admixture dispenser is within proper calibration is an apparent violation of Criterion XII of Appendix B to 10 CFR Part 50 and Section 12 of the AP&L QA (313/8615-01; 368/8615-01) In addition to the above, the following findings are considered to be unresolved issues:

 . Although a letter from the batch plant water meter vendor stated that calibration of the meter was accomplished, there was no
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reference to a standard to which the calibration related (i.e., checklist Item 2.5.3, NRMCA Procedure). (313/8615-02; 368/8615-02)

 . NRMCA, Item 7, " agreement to regularly check scales, volumetric batching devices, and dispensers," page 17, required that checks be done at-intervals not exceeding 90 days. There was no documented evidence that these checks have been made since November 11, 1985. (313/8615-03; 368/8615-03)
 . AP&L specification, APL-C-2401, Section 9.4 delineated responsibilities of the concrete batch plant inspecto Items 9.4 3)a. through o. were only partially documented, contrary to the requirements of Section 9. (313/8615-04; 368/8615-04)
 . AP&L specification, APL-C-2401, page 29, table 7, Item 5.1 mixer uniformity, ASTM C-94 (C-94, paragraph 11.5 through 11.9) and checklist Item 5, of NRMCA procedures, address certain requirements relative to truck mixer uniformity tests and blade inspections. There was no documented evidence that would verify that these requirements were accomplished. (313/8615-05; 368/8615-05)

l . It was observed by the NRC inspector that the mixer water tank sight gages on delivery trucks may not have been calibrated prior to us (313/8615-06; 368/8615-06) 1 Exit Interview The NRC inspectors met with the Director or Acting Director, Site Nuclear Operations, and other member:: si Lhe AP&L staff at the end of various segments of this inspection. At these meetings, the inspectors summarized the scope of the inspection and the finding ., - -

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e NRC FORM 7es ' U.S.NJCLEAR REGULATORY COMMLSSION PRmCIP tiL INSPECTOR (Name. tJr. Arst. aruf mdpo imbsp Q'E0as . - JdHMSON , WILLIAH INSPECTOR'S REPORT , n y,,,,, ,

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Office of Inspection and Enforcement g gy 7 EA , DoRWlN WSPECTOd 5 J'0HHSO N . H/\RGuck - N o ,. - r'c ts , YG su c k ' TON ' UCENSEE/ VENDOR "yypg DOCKET NO.te ckeital OR LtCENSE No. tty PRODUCTitt3 digits 3 N SE M Y '~**'" A A t<AAJS A S PouGtt E LIGHT ~ [ " - *Oo'" 0 S 0 0 0 3 I 3 O S 0 0 0 2 G 8 8 6 1 5 ^

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_ 8 G i 5 D - DELETE C _ A - REPLACE D

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PERIOD OF INVESTIGATON/ INSPECTION l WSPECTON PERFORMED BY ORGANIZATION CODE OF REGION /MO CONDUC FLOM 70 1 - REGONAL OFFICE STAFF mO ACTrnTv <$ au,c om . em r ner g

         ]OTHER M DAY Y M DAY Y X 2 - RESIDENT INSPECTOg       REGION  D8VtSiON BASNCM l Ql/ gl6 l   g g 3 - PERFORMANCE APPRAl$AL TEAM       h   2  1 N.D.Y @25 2QW[Wy331 g$dQAQirtiie MMFMfMX,MSC,C,WyMM,M.6,C         17WM WM3    M ~ 35 '

REGONAL ACTON * TYPE OF ACTivtTY CONDUCTED (Check onelion oneyl I 02 - SAFETY 06 - MGMT.vlSIT 10 - PLANT $E WOutRY l - NIC FORM 901 03 - INCIDENT 07 - $PLCIAL 11 - mVENT.VE INVESTsGATiON

)( 2 - E.EGIONAL OFFICE LETTER   04 - ENFORCEMENT   OS - VdNDOR  12 - $MIPMENT/ EXPORT 06 - MGMT. AUDIT   09 - MAT. ACC BMPORT N*d iks d $ d 5RI N 38 M M M II
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INEPEGTONnNVE5T4GATON FINDAGE TOTAL NUMBER ENFORCEMENT CONFERENCE MPOR 7 CONTAIN 2.790

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