IR 05000285/1984018

Insp Rept 50-285/84-18 on 840801-0930.Violations Noted.Major Areas Inspected:Operational Safety Verification,Surveillance Testing,Maint Activities,Followup of Previously Identified Items & NRC Meetings

ML20247F294
Person / Time
Site:	Fort Calhoun
Issue date:	10/24/1984
From:	Dubois D, Martin L, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20247F272	List: IR 05000285/1984018 ML20247F269 ML20247F280
References
50-285-84-18, NUDOCS 8904030396
Download: ML20247F294 (15)

Text

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. APPENDIX B

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> U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-285/84-18 License: DPR-40 Docket: 50-285 Licensee: Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102 Facility Name: Fort Calhoun Station Inspection At: Fort Calhoun Station, Blair, Nebraska Inspection Conducted: August 1-September 30, 1984 Inspector: 10/9/94 L. A. Yandell, Senior Resident Reactor Inspector, Date Fort C oun uclear ower Station Inspector: _ W M to!23 Y

.ji.. DyBFis, Se$ior Resident Rehctor Inspector, Date coopdr Nuclear Power Station Approved: dJ e - g0 L. E. Martin, Secti an Chief, Project Section Date Reactor Project Branch 2 Inspection Summary Inspection Conducted August 1-September 30, 1984 (50-285/84-18)

Areas Inspected: Routine, announced inspection of operational safety verifica-tion, surveillance testing, maintenance activities, followup of previously-identified items, and NRC meetings. The inspection involved 144 inspector-hours by two NRC inspectors, of which 33 were offshift hour Results: Within the five areas inspected, two violations were identified (fail-ure to provide authorized escort - paragraph 2 and failure to use current pro-cedure - paragraph 3).

8904030396 841025 .

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DETAILS Persons Contacted R. L. Andrews, Division Manager, Nuclear Production

• K. J. Morris, Manager, Administrative Services

• W. G. Gates, Manager, Fort Calhoun Station L. T. Kusek, Supervisor, Operations R. J. Mueller, Supervisor, I&C and Electrical Field Maintenance J. A. Drahota, I&C Engineer M. R. Core, Supervisor, Maintenance M. E. Kallman, Supervisor, Administrative Services & Security J. J. Fisicaro, Licensing Administrator Supervisor, Nuclear Regulatory and Industry Affairs

• A. W. Richard, Supervisor, Technical J. F. Bailey, Electrical Engineer V. G. Morris, Supervisor, Technical Support J. K. Gasper, Manager, Reactor & Computer Technical Services T. J. McIvor, Manager, Operations-Technical Support Services D. L. Feighert, Emergency Planning Coordinator S. Gambhir, Manager, Nuclear & Electrical Engineering H. J. Faulhaber, Lead Electrical Engineer K. C. Holthaus, Supervisor, Reactor Performance Analysis

• F. F. Franco, Manager, Radiological Health & Emergency Planning K. R. Henry, Test Engineer R. A. Johansen, Test Engineer J. J. Fluehr, Reactor Engineer J. Dyer, QC Inspector T. L. Patterson, Supervisor, Training Services

• Denotes attendance at exit interview on August 31, 198 The NRC inspectors also talked with and interviewed other licensee employees during the inspection. These employees included licensed and unlicensed operators, craftsmen, engineers, and office personne . Operational Safety Verification The NRC inspectors performed activities as described below to ascertain that the facility is being maintained in conformance with regulatory requirements and that the licensee's management control system is effectively discharging its msponsibilities during power operatio The NRC inspectors made several control room tours to verify proper shift manning, operator adherence to approved procedures, adherence to selected Technical Specifications, and operability of the reactor pro-tective system and engineered safeguards equipment. Selected logs,

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records, recorder traces, annunciators, panel indications, and switch

, positions were reviewed to verify compliance with regulatory require-

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ments. The licensee's equipment control was reviewed for proper im-plementation by reviewing the tag-out log and verifying selected safety-related tag-outs. Several shift turnovers were observed and shift turnover sheets were reviewed during this inspection period, The NRC inspectors toured the plant at various times to assess plant and equipment conditions. The following items were observed during these tours:

. general plant conditions

. vital area barriers not degraded or appropriately manned by security personnel

. adherence to requirements of radiation work pennits (RWPs)

. proper use of protective clothing and respirators

. plant housekeeping and cleanliness practices including fire hazaids and the control of combustible material

. work activities being performed in accordance with approved activities

. physical security

. HP instrumentation is operable and calibrated It was noted by the NRC inspector that overall cleanliness in the aux-111ary building had improved, particularly in those areas discussed in NRC Inspection Report 84-1 The NRC inspector verified operability of the following safety-related systems by performing a walkdown and switch ver;fication of the acces-sible portions of the system:

. Containment Spray System per Checklist CS-1-CL-A

. High Pressure Safety Injection System per Checklist SI-1-CL-A

. Auxiliary feedwater per Checklist ST-FW-1-CL-A On August 14, 1984, the NRC inspector and a contractor person completed the licensee's general employee training program as a prerequisite to being badged for unescorted access into the plant protected area. Pend-ing approval and processing of their badge requests, the NRC inspector

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-4-and contractor person were given escorted access into the protected area by the licensee. On the afternoon of August 14, 1984, the NRC inspector observed the contractor person standing in the machine shop alone and noted that no escort was within visible site of the person. It appeared I that the person was left unescorted in the protected area for approxi-mately 15 minutes. Procedure G-39, " Security Instruction," states in Section 5.1.4 that " escorted personnel will be escorted by an authorized l escort at all times during which they are in the protected area . . . ."

l This failure by the licensee to provide a required escort for the con-tractor person is an apparent violation against Technical Specifica-i tion 5.8.1 which requires that " written procedures . . . be established,

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implemented, and maintained that meet or exceed the minimum requirements of Sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix A of USNRC Regulatory Guide 1.33 . . ." and Procedure G-7 which states in Section that " adherence to the Operating Manual is mandatory." (285/8418-01)

Once this condition was identified, the licensee immediately provided an authorized escort to remain with the contractor perso e. The NRC inspector observed portions of Containment Purges 84042 and 84045 and noted the following for each:

. the X/Q log was maintained, the limiting X/Q was established, and the readings were within limits

. VIAS was tested using RM 061 or RM 060

. the stack dewpoint and annubar readings were taken

. the tritium sampler was in place and the sample was taken

. the recommended release rate was established, and the actual flow was lower than that authorized

. radioactivity analyses were performed

. the required effluent monitors and recorders were operational

. the permit was reviewed and signed off properly, and the temina-tion tine was established

. the required auxiliary building exhaust fans were operating

. 01-VA-1,Section IV.G was attached to the permit

. both the initial and final readings of the stack flow integrator were noted on the recorders

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-5-The NRC inspector observed initiation of CP-84042 from the control room l

and observed the testing of VIAS using RM 06 As discussed in NRC Inspection Report 84-01, paragraph 2.g, the licensee requisitioned the services of two contract engineers to assist OPPD in upgrading the Fort Calhoun Station annunciator system. The objective of this effort was to have: (1) no annunciator lit during normal power operations, (2) no nuisance alarms, and (3) no annunciators used for status. The bulk of the " Annunciator Upgrade Project" was performed during the recent outage, and the contractors Status Report P-6860-0712, dated August 7,1984, to Mr. Randy Mueller of OPPD discusses 49 specific items that address 77 annunciators. Of this number, 37 have been re-viewed and modified as necessary and the remainder are being evaluated .

to determine the need for design changes. The NRC inspector considered

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this effort by 0 PPD to utilize the guidance of NUREG/CR 3217, "Nea Term Improvements for Nuclear Power Plant Control Room Annunciator Systems," as a positive step toward eliminating one source of confusion in the control room during abnormal plant condition The NRC inspector initiated review of the Qualified Life Program (QLP)

instituted by the licensee and described in Procedure G-56, " Qualified Life Program." The purpose of the program is to " establish and maintain i

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the qualified life of safety-related equipment installed in a harsh environment." This work was initiated in response to IE Bulletin 79-01B and represents several years of interaction between the NRC and OPP As further background to this program the NRC inspector reviewed:

(1) the NRC Safety Evaluatio: Report for Eny'ronmental Qualification of Safety-Related Electrical Equipment, dated January 11,1983, (2) OPPD Letter LIC-84-121, dated May 3',1984, in response to this SER and the meeting held with the NRC on March 23,1984, and (3) the OPPD Electrical Equipment Qualification Manual issued on April 19, 1984. The plant staff is just now fully implementing the QLP and has recognized the need for a full-time coordinator to be assigned to this effor Special Proce- i dure SP-EEQ-1, "LOCA Qualified Electrical Equipment Identification Check,"

had been issued to ensure that special markings are attached to all LOCA qualified electrical equipment controls / indicators as an aid to the operators. The NRC inspector performed an independent check using SP-EEQ-1 and verified that the markings were in place. The NRC inspector is following this work and has informed the licensee that the NRC will be perfonning a site verification inspection of this area some time in 198 No additional violations or deviations were identifie . Surveillance Testing The NRC inspector witnessed portions of the following surveillance tests: ) ST-RPS-13, F.1 (Monthly) Incore/Excore Calibration (Channel A only) ]

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-6- ST-RM-1, F.2 (Monthly) Area Monitors ST-ICI-1, F.1 (Monthly) Radial Peaking Factors ST-ICI-2, F.1 (Monthly) Incore Detector Alarm Limits ST-ESF-6, F.2 (honthly) Diesel Generator Check ST-ISI-CVCS-3, F.1 (Quarterly) CVCS Pump Test Calibration Procedute 051, " Electronic, Secondary, and Primary Calibra-tion Procedure for Stack / Containment Gas Monitor." The NRC inspector reviewed Section III (Electronic & Secondary Calibration portion) and noted that Technical Specifications 2.1.4(4), 2.9(2)e, and Tables 2-1 and 2-4 were referenced, that test equipment was identified and record-ed, that all signoffs were complete, and that QC hold points were ob-served. The NRC inspector observed Section IV (Primary Calibration portion) being performed and witnessed the technician inserting the test gas and coordinating this work with the control room personne On Septem b r 4, 1984, following the completion of ST-RM-1, the NRC inspector reviewed the test and determined that Revision 18 was verified incorrectly and used when Revision 19, dated August 7, 1984, had been issued and was available in the Official Copies of the Plant Manual. This failure by the licensee to use the correct procedure is an apparent violation against Technical Specification 5.8.1 which requires that " written procedures . . .

be established, implemented, and maintained that meet or exceed the minimum requirements of Sections 5.1 and 5.3 of ANSI 18.7-1972, and Appendix A of USNRC Regulatory Guide 1.33 . . ." and Standing Order G-7 which states in Section 2.2 that "it is the responsibility of each individual using a pro-cedure to check the Official Copies . . . to ensure they have the most current revision." (285/8418-02)

No other violations or deviations were identifie . Maintenance Activities The NRC inspector witnessed portions of the work performed on the following maintenance items: Maintenance Order (M0) 84277A, " Pressurizer Quench Tank." While oper-ating HCV-155, Pressurizer Quench Tank Vent Valve, noise spikes occurred on the 'A" and "C" Channels of the Thermal Margin Low Pressure (TMLP)

RPS trip circuits causing a plant trip. The NRC inspector reviewed the M0 and observed efforts by OPPD personnel to troubleshoot the proble To alleviate the noise spikes on the TMLP calculators, noise suppressors were installed across the HCV-155 Solenoid Valve coil electrical leads, leads of an associated control relay, and administrative controls were

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-7-established to bypass the "A" and "C" Temperature Inputs to the RPS prior to operating the valv In addition, Modification Request MR-FC-84-139 had been initiated to install capacitors at certain locations within the RPS TMLP calculators to eliminate any noise of the type caused by cycling HCV-155 from affecting the calcu-lators. It proved necessary to perform this. modification on Channel "C" only, and noise spikes have been reduced significantly, MO 842906, "RM 051." The containment gaseous monitor (RM 051) was found by the operators to be reading low. The M0 was reviewed by the NRC inspector and it was noted that QC was required to witness operability after repairs, that' proper signoffs and approvals were present, and that parts and materials used were identified on the M0 for record pur-pose EEAR/FC-84-44, " Waste Disposal System and Waste Evaporator Malfunction Alarms." This design change was imple ented to avoid a continuous nuisance alarm in the control room. Control room Annunciator A-21, Windows A-7L and A7U were constantly "on" because one of several mul-tiple alarms feeding each window was present at the local Panel A1102/10 This modification revised the alarm logic to allow the remote control room alarm to be cleared once the local alarm had been acknowledged. This design package is one example of several initiated by the licensee to up-grade the plant annunciator system as discussed in paragraph 2.f of this repor The NRC inspector reviewed the design package and verified that the following documents were present and filled out properly:

. Fonn A, " Engineering Evaluation and Assistance Request"

. Form C, " Assignment of Design Responsibility"

. Form D, " Modification Design Transmittal" l . Form E, " Modification Completion Report"

r orm G, " Design Change Order." This document was signed off through

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Lile " modification completed" sectio . Form H, " Pre-Installation Modification Control" The NRC inspector observed final testing and QC witnessing of operability prior to releasing the system back to the shift supervisor for normal operation MD 841708, " Fire Barriers." The licensee initiated a two-month effort to upgrade temporary fire barriers into permanent barriers and to grout con-duit penetrations. An outside contractor was hired to perform the wor The NRC inspector reviewed the M0 for proper signoffs and approvals,

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-8-QA/QC instructions, and appropriate Technical Specification reference Maintenance Procedure MP-FP-2, " Fire Barrier Penetration Seals," was PRC approved and utilized the contractor's procedure. The NRC L inspector reviewed several data sheets and observed QC-inspection of various repairs. Over the past three weeks the NRC inspector has ob-l served work in the switchgear room and noted that OPPD electricians were l present at all times, that hourly tours were made by a designated fire watch when the rollup doors between the switchgear areas were open, and tnt these tours were documented on daily signoff sheets at the work area . About 350 fire barriers are being upgraded which will reduce significantly the effort required by the QC department to perform the temporary fire barrier inspection each quarte e. M0 842948 "HC-103-1." When HC-103-1, the controller for PCV-103-1, (Pressurizer Spray Valve) was placed in AUT0, the controller output from PRC103X or Y (whichever was selected) drove below zero. This was disabling pressure control in both AUT0 and MANUAL. The NRC inspector reviewed the PRC approved procedure, "PCV-103-1 and 2 Control Circuit Troubleshooting," and the completed M0 for signoffs and approvals. The switch was replaced, but plant response seemed to indicate that the valve was not moving. Later that day the NRC inspector made a containment entry with OPPD technicians to observe the operation of the spray valve and noted that the valve appeared to be stroking properly. Further i troubleshooting included operation of the auxiliary spray valve and l proper plant response was observed. The plant staff considered the ;

check valve as the next item to be examined. During the performance of this work the NRC inspector verified that Technical Specification re- 1 quirements were observed, that qualified craftsmen were assigned to the ;

task, and QC requirements were observe ;

f. M0 843493, "RM 050/51." Plant personnel had observed the activity in the auxiliary building, particularly Room 69, gradually increasing, i This was traced to a leak at the housing gasket of RM 050/051, allowing containment pressure (and activity) to seep through. The NRC inspector observed the disassembly of the unit by the craftsmen, noted that proper radiological precautions were taken, and that this effort was coordi-nated with control room personnel to ensure that no Technical Specifica- ;

tion limit was exceeded. The housing seal was eventually repaired and l tedeo satisfactorily the next da ;

i g. MG 842983, " Electric Fire Pump (FP-6A) Discharge Strainer." The dis- l chtrge strainer drain plug had developed a leak, and FP-6A had to be tagged out and isolated to perform repairs. The NRC inspector reviewed the M0 for completeness and noted that the ANI was infomed of the out-age and that the appropriate tag was hung on the switch. Tag-0ut 84-1408 was assigned to this job, and Technical Specification 2.19(4) was appli-cable. The NRC inspector observed repairs being completed and witnessed operability of the pump with a QC representativ i

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, M0 843003, "AC-3A Pump Shaft." This MO was written as a result of the equipment operator observing that the pump shaft was " hunting." Main-tenance Procedure MP-AC-3, " Overhaul of Component Cooling Pumps," was assigned to cover this work, and Technical Specification 2.4 applie The NRC inspector reviewed the M0 for proper approvals and noted that QC was identified to " verify repairs and witness operability," that qualified craftsmen were assigned to the job, and that Surveillance Test ST-ISI-CC-3, " Component Cooling Pumps Inservice Testing," was.to be performed following repairs. The NRC inspector observed disassembly of the pump and witnessed HP surveying the rotor to allow it to be taken to the shop. As the rotor was removed from the auxiliary building the NRC inspector noted that proper HP precautions were observed and a guard was present while the rollup door was unlocked. Following repairs, the NRC inspector reviewed the maintenance procedure for signoffs and verified that the surveillance test was run to prove operabilit i. M0 841886, "No. 3 Battery Charger." The No. 3 Battery Charger had grounds on both the AC and DC sides that required replacement of the transformer. The NRC inspector reviewed the M0 at the jobsite and noted that it had been properly. approved, that Technical Specification refer-ence 2.7 was identified, that Tag-Out 84-1430 had been issued to cover this work, and that qualified craftsmen were assigned to the job. It was noted by the NRC inspector that a PRC procedure was issued for this work, with QA/QC hold points established,and a safety evaluation com-pleted and attached. The NRC inspector observed the disassembly of the faulty unit and later verified that the repaired unit had been tested and declared operationa j. SRDC0 83-47/FC-82-141, " Component Cooling Water Dechromation." This design change was performed to install a pipe connection on the discharge of each component cooling water pump to allow for faster dechromation of the system when required. The NRC inspc.:.cor observed this job over a period of several days and reviewed the following documents in the design package:

. Form F, " Safety-Related Design Change Order"

. FC-154, " Safety Evaluation"

. Attachment E, " Component Cooling Water Dechromation Installation."

This document was PRC approved and included applicable drawings and the appropriate Technical Specification referenc . FC-182, " Liquid Penetrant Inspection Report," for welds 15 and 16 as shown on Figure 3 of the packag . FC-145, " Welding and Test Control Record," for welds 3 through 7 (AC-1116),13 and 14 (AC-1117), and shop welds for AC-1118 installa-tion.

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. Form H, " Pre-Installation Modification Control"

. FC-379, "ALARA Review Checklist"

. Procedure Change 11462 which allowed the craftsman to flame cut through the discharge pip The NRC inspector reviewed the hydrostatic report for AC-1118, and observed the penetrant test of Point 2 on AC-3C for AC-1116 performed by the QC inspector. The NRC inspector observed the final fitup and closecut of the system for the piping on the discharge of AC-3 MO 842952, "B RPS Wide Range." The "B" Channel RPS Wide Range Percent Power Meter was hanging-up around 10 percent power. The NRC inspector reviewed the M0 for completeness, and verified that Technical Specification 2.15 was referenced, that QC requirements were established, and that Calibration Procedure CP-NI-002," Wide Range Channel NI-002,"

was required to be performed. A new meter was installed and the NRC inspector noted that spare part information was recorded on the M0 for tracking purpose No violations or deviations were identifie . Followup of Previously Identified Items IE Bulletin 83-06, "Non-Conforming Materials Supplied by the Tube-Line Corporation." In OPPD Letter LIC-83-312 dated December 16, 1983, the licensee responded to the bulletin and identified four concentric reducers furnished by the Tube-Line Corporation on the raw water drain lines from the four component cooling heat exchangers. One of the four was hydrotested satisfactorily and the other three were radiographe To complete their plan for demonstrating that the reducers are suitable for their intended service, the licensee performed a Brinell hardness test and a chemical composition analysis. OPPD Letter LIC-84-045 dated April 13, 1984, describes these tests and the results obtained. The NRC inspector reviewed the hardness test results and noted that only one reducer had an average Brinnel Hardness Number (BHN) not falling within the specified 197-123 range. This reducer had an average BHN of 204, but had a yield strength of 35,000 psi minimum. This was considered accept-able in light of the expected pressure the device would see during service. The NRC inspector concurs with the licensee's assessment and considers 6his item close LER 81-011 " Containment Air Monitor, RM 050/051." During cold shutdown following refueling, this monitor was taken out of service to perform leak rate testing on it's containment isolation valves, During this period the containment air was sampled and found to be bclow unrestricted M. The air flow from the containment was classified as ventilation

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-11-only, therefore Technical Specification 2.9.3.IV did not apply and the containment purge valves were opened. The licensee failed to realize that footnote 4 in Technical Specification Table 2-1 requires these containment purge valves to be closed if RMs 050/051 are inoperable with

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respect to the containment. The oncoming operating shift secured the l ventilation and performed a calculation to verify that the release did i not violate any Technical Specification limits. Personnel were re-I trained in this. area and a. change to the Technical Specifications was considered. The licensee concluded their review of this matter and determined not to process a Technical Specification change. This item is closed.

' LER 82-011 "HCV-2507A Was Closed on Sampling Line for Steam Generator B." This item was discussed in NRC Inspection Report 83-07, paragraph 5 and remained oper pending installation, test, and operation of an auto-matic closure feature on the blowdown system isolation valves when blow-down sample flow is lost. During the 1984 outage, Field Change FC-82-071 covered the installation of this design feature. The NRC inspector reviewed portions of the installation package, witnessed the final system test, and observed closure of the steam generator blowdown isolation valves at the control room panels on loss of sampling flow during plant operatio This item is close_ Unresolved Item 8416-01, "0 PPD Reorganization." On July 1,1984, the licensee implemented a reorganization that established a new Division of Nuclear Production separate from the Division of Production Operation This was considered an unresolved item pending issuance of the Tech-nical Specification amendment incorporating these organizational change Amendinent No. 84 to the Fort Calhoun Station Operating License No. DPR-40 was issued on September 7, 1984, and incorporated those changes into Section 5 of the Technical Specifications. This item is close NUREG 07W , Item II.B.3.2, " Post-Accident Sampling System (PASS)."

This item had been discussed in NRC Inspection Reports 82-26, 82-32, 83-23, and 83-32. The NRC inspector attended the August 29, 1984, Systems Acceptance Committee (SAC) meeting at which the system was not accepted because the gross gamma decector calibration was not complete, the intrinsic germanium detector calibration was unacceptable, and chemistry technician training was incomplete. Other administrative items had to be completed but none that would prevent the system from being accepted with d;screpancies. The calibratic- und training were completed and on September 28, 1984, the SAC completed another review of the system and accepted the PASS with outstanding discrepancie The plant system description and draft changes to the USAR are still required, but the system is operational, training has been performed, and procedures to use the PASS are in place. The NRC inspector had observed portions of the system tests, and will continue to observe technicians operating the system. This item is close _ ______ _ __--_.__ _ - __ _ __ I

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-12- NUREG 0737, Item III.D.3.4 (SRDC0 84-65), " Toxic Gas Monitoring System."

This item had been discussed in NRC Inspection Report 84-14, paragraph The NRC inspector reviewed a supplementary design package that provided for "the addition of override switches for the alarm, trip, and annun-ciator of each monitor to entirely bypass the toxic gas circuit." The design package was properly signed off, a PRC approved procedure was used to control the work, and QC hold points were observed. The NRC inspector observed the testing of individual switches and the combined bypass switch on Panel AI-44. It was noted that Jumper 84-081 had to be removed and the NRC inspector verified that the jumper log entry was properly signed off. The SAC met on September ~28, 1984, to review the status of the system and accepted it with one identified discrepancy; the output signal to the ERF computer was inoperable. The NRC inspector re-viewed 01-PAP-12, " Toxic Gas Accidents," and discussed the procedure with operators and chemistry technicians. A sari 1pling of chemistry technicians have denionstrated to the NRC inspector their understanding of the proce-dure, their responsibilities, how to use the manual sampling valve and the MSA gas detector tubes, where the portable monitors are located, and what precautions need to be taken. This item is close . NRC Meetings a. The NRC inspector and the NRR project manager met with licensee personnel on August 27, 1984, at the Jones Street office. The following items were discussed:

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Generi c Letter 82-33, including; Safety Parameter Display System, detai'ied control room design review, Regulatory Guide 1.97, upgrade  ;

of emergency operating procedures, and the emergency response facilit .

Generic Letter 83-28, Salem ATWS

. Inadequate Core Cooling System

. Status of the PASS

. Status of the Toxic Gas Monitor On August 30, 1984, Messrs. J. B. Baird and J. L. Montgomery of the NRC Region IV office and the NRC inspector met with licensee personnel at the Jones Street office to discuss communications as they relate to emergency response capabilities and the annual dril On September 21, 1984, Messrs. W. E. Miller, R. L. Andrews, W. G. Gates, and T. L. Patterson of OPPD attended a management meeting in the Region IV office in Arlington, Texas, with Messrs. J. T. Collins, D. R. Hunter, R. Cooley, S. McCrory and L. A. Yandel The purpose of

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-13-the meeting was +,o discuss the licensee's operator licensing program in response to Mr. Collin's letter of August 13, 1984, to Mr. Mille The licensee described the independent evaluation that was performed, the immediate actions being taken in preparation for the November candidates, near term plans, and long term plans. Plant training was discussed by the Fort Calhoun Station Manager, and the newly established offsite Training Services Department was described. The NRC requested that the licensee document these proposed actions in their response to the NRC Examination Report dated August 8, 1984, from D. R. Hunter to R. L. Andrew . Exit Interview The NRC inspector met with licensee representatives on August 31, 1984, and the plant manager on October 5,1984, to sumnarize the scope and findings of the inspection.

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