IR 05000483/1985024
| ML20154J709 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/26/1986 |
| From: | Forney W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML18023A056 | List: |
| References | |
| RTR-NUREG-0588, RTR-NUREG-0660, RTR-NUREG-0737, RTR-NUREG-0830, TASK-***, TASK-TM 50-483-85-24, IEIN-86-003, NUDOCS 8603110026 | |
| Download: ML20154J709 (13) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-483/85024(DRP)
Docket No. 50-483 Licensee No. NPF-30 Licensee: Union Electric Company Post Office Box 149 - Mail Code 400 St. Louis, M0 63166 Facility Name: Callaway Plant, Unit 1 Inspection At: Callaway Site, Steedman, M0
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Inspection Conducted: December 17, 1985 through February 10, 1986 Inspectors:
B. H. Little C. H. Brown Approved By:
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Reactor Projects Section 1A Date Inspection Summary Inspection on December 17 through February 10, 1986 (Report No. 50-483/86024(ORP))
Areas Inspected: Routine unannounced safety inspection by the resident inspectors of previous inspection findings, TMI action plan requirements, regional request, surveillance, operational safety, maintenance, and crew training.
In addition, an Incident Reduction Program status meeting was held. The inspection involved a total of 312 inspector-hours onsite by two NRC inspectors including 67 inspector-hours onsite during off-shifts.
Results: No viMations, deviations cr safety concerns were identified in the areas reviewed.
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DETAILS 1.
Persons Contacted D. F. Schnell, Vice President, Nuclear
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- S. E. Miltenberger, General Manager, Nuclear Operations
- D. C. Poole, Consultant
- A. P. Neuhalfen, Manager, Quality Assurance
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"J. D. Blosser, Assistant Manager, Operations and Maintenance J. F. Hogg, Supervisor, Quality Assurance
- W. R. Robinson, Superintendent, Instrument and Controls
- J. R. Peevy, Assistant Manager, Technical Services
- C. H. Naslund, Manager, Operations Support
- Denotes those present at one or more exit interviews.
In addition, a number of equipment operators, Reactor Operators, Senior Reactor Operators, and other members of the Quality Control (QC),
Operations, and Maintenance staffs were contacted.
2.
Followup on Frevious Inspection Findings (Closed) Open Item 483/84021-01(DRP): Review of Fuel Handling Equipment Problems. Minor fuel handling equipment problems were experienced during the initial fuel handling operations. Most of the problems related to equipment electrical controls and interlocks which were corrected by setpoint and interlock adjustments. On one occasion, fuel handling opera-tions were temporarily suspended when the Nuclear Source Range Channel N-32 initiated a containment evacuation alarm. The licensee's investigation determined that the detector cable connector contained a crimped 0-ring which allowed moisture to enter the connector and caused signal spiking.
The inspector has reviewed the incident reports which documented the equipment deficiencies and determined that the licensee has taken appropriate corrective action.
(Closed) Open Item 483/84035-03(DRSS): Acceptability of Using Fire Hose-to Supply Filter System Deluge System. The licensee's filter housings are equipped with temperature monitors (High Temperature Annunciator Alarms) and employ manually actuated spray systems. The Callaway Plant Alarm Response Procedure specifies securing the subject fan and connecting a hose to the spray connection.
The acceptability of Callaway's system /
practice (use of a fire hose) was discussed with NRC Region III Fire Protection Specialist and NRR Fire Protection Reviewer. Based on this discussion, the inspector determined that Callaway's filter deluge system /
practice is acceptable to the NRC.
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(Closed) Open Item 483/84041-01(DRS): Control Room Inaccessibility Procedure Walkdown. On August 7, 1984, the licensee accompanied by a NRC inspector, performed a procedural walkdown of Procedure No. OTO-ZZ-00001 (Control Room Inaccessibility). During the walkdown, delays were experienced in gaining access to two rooms which contained equipment that would need to be operated in the event of a control room evacuation due to fire.
Room access delays resulted from the correct keys not being included in the set of master keys assigned for the walkdown.
The licensee has added the keys to the shift supervisors' master key ring and performs a semiannual key surveillance.
The. inspector has reviewed the licensee's completed semiannual key inventory forms for the emergency key boxes and the shift supervisors' key ring; and determined that the licensee has implemented an appropriate key verification program.
(Closed) Violation 483/85004-01(DRS):
Failure to Properly Document Test Acceptability. This matter relates to deficiencies which were identified during the NRC review of the licensee's startup engineering test data. The test result packages contained deficiencies which had not been identified or corrected during the licensee's review process. The inspector deter-mined that the nature of the deficiencies did not adversely impact acceptability of the tests. The test results package deficiencies have been corrected.
(Closed) Open Item 483/85004-02(DRS): Class 1E 480 Volts AC (VAC) Normal Operating Procedure Has No Pre-Energization Checklist. During a review of the licensee's normal operating procedures, a NRC Inspector determined that the licensee had not developed a pre-energization checklist for the 480 VAC electrical distribution system.
In response to the inspectors questions in this matter, the licensee evaluated the desirability of having a pre-energization checklist and determined that their existing procedural controls for system line up and energization was preferable.
The procedural controls in place assures system line up is complete prior to providing electrical power to the components.
In the event the electrical distribution system is deenergized for maintenance, Workmens'
Protection Assurance procedures provide tagging and re-energization controls. The inspector determined that the licensee has implemented adequate procedural controls for the energization of electrical systems.
No violations or deviations were identified.
3.
Inspection of TMI Action Plan Requirements This inspection concerned licensee actions relative to certain NRC requirements developed as a result of the Three Mile Island (TMI) Unit 2 accident. These requirements were contained in NUREG-0737, " Clarification of TMI Action Plan Requirements," and were assigned item numbers for identification.
Completion of certain licensee actions required by the items reviewed during this inspection was previously verified by NRC inspection personnel.
This inspection was conducted to establish a correlation between individual
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items (by number and title assigned in NUREG-0737) and the NRC Inspection Reports which document these verifications.
This inspection was also conducted to supplement previous inspection activities as necessary to verify completion of required licensee actions for all items reviewed.
I. A.1.1, Shif t Technical Advisor (STA): The staff found that the licensee's staffing and training programs were acceptable in Callaway Safety Evaluation Report (SER) NUREG-0330 Section 13.1 and 13.2.
The staff's review determined that the licensee's commitments with regard to STAS, met the requirements of Action Plan Item I.A.1.1 of NUREG-0737.
These commitments included education, training, experience, and independent reporting. The STA manning requirements are specified in Callaway Technical Specifications (TS) Section 6 (Minimum Shift Crew Composition).
Region III inspections of operational staff and staff training are documented in NRC Inspection Reports No. 50-483/83032(DRP) and 50-483/
84020(DRP). The licensee conducted special training programs which included the Control Board Certification and Mitigation of Core Damage courses. The STAS were included in these special courses. The inspectors determined by the review of training records, personnel interviews, and direct observations that the licensee has implemented the required STA program.
I.A.I.2, Shift Supervisor's Administrative Duties: The staff found licensee's management directives and commitments regarding the Shift Supervisors' authorities and responsibilities acceptable in SER NUREG-0830 Section 22 as meeting the requirements of Action Plan Item I.A.1.2.
The inspector determined by review of plant administrative procedure APA-ZZ-00010 (Conduct of Operations - Operations) that the licensee has administrative procedures in place which define the Shift Supervisors'
duties, responsibilities, and authority. The administrative procedure establishes the Shift Supervisor as the senior licensed management representative on site during back-shifts and directly responsible for overall plant operations.
Routine NRC inspections have determined the licensee's implementation of this commitment is in accordance with regula-tory and procedural requirements.
I.A.1 ?, Shift Manning:
In Callaway SER Section 22, the staff found that the licensee's commitments regarding Shift Manning met the requirements of Action Plan Item I.A.I.3 of NUREG-0737 The staff's review was based on licensee letter dated August 19, D81, and Callaway Final Safety Analysis Report (FSAR) Site Addendum, Revision 3.
The Calbsay Technical Specifications Section 6, provides licensee's staff organ */ation structure and specifies minimum shift crew composition. The Calla w riant Procedure APA-ZZ-00130 provides limitations of staff working hours.
The inspector determined by discussions with licensee personnel, review of licensee commitments and Technical Specifications, and observation of shift manning that the licensee had established shift crews which exceed the requirements of NUREG-0737.
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I.A.2.1, Immediate Upgrading of Operator and Senior Operator Training and Qualification:
In Callaway SER Section 22, the staff determined that the licensee's training and qualification commitments, as described in the Callaway FSAR Site Addendum Section 13.1, satisfied the requirements of Action Plan I.A.2.1 of NUREG-0737. The licensee's commitments, regarding operator training and qualification, were reviewed and found acceptable during previous inspections and documented in Inspection Reports No. 50-483/83032(DRP) and 50-483/84020(DRP).
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The Callaway Plant Operating License NPF-30, contains plant specific operating staff experience requirements.
To satisfy these requirements, the licensee implemented the Shift Operating Advisor Program.
NRC Inspection Report No. 50-483/84020(DRP) documented that the licensee had implemented the required training program.
During routine inspections Resident Inspectors (by direct observation and personnel discussions)
verified required shift staffing of operating advisors and determined that they were effectively utilized in overall plant operations.
I.A.2.3, Administration of Training Programs for Licensed Operators:
The staff concluded in Calliway SER, Section 22, that the licensee's commit-ments as described in the Callaway FSAR Site Addendum Section Item 13.2 complied with the requirements of Action Plan I.A.2.3 of NUREG-0737.
NRC Inspection Reports No. 50-483/83032(DRP) and 50-483/84020(DRP) document that the licensee's training program commitments contained in the Callaway FSAR Site Addendum Section 13.2 had been fully implemented. Prior to
" cold licensing", the instructors were Westinghouse instructor certified.
During the initial NRC " cold licensing", three instructors were licensed at the Senior Reactor Operator level.
Since then three additional instructors have received NRC Senior Reactor Operator licenses and one instructor holds a NRC Instructor Certification and is a licensed Reactor Operator.
I.B.I.2, Independent Safety Engineering Group (ISEG):
In Callaway SER Section 13.4, the staff found that the licensee's organization, program for the review of plant operations and commitments met the requirements of Action Plan Item I.B.1.2 of NUREG-0737. Callaway Technical Specifics-tions, Section 6, contains ISEG requirements.
The NRC inspector determined by review of the licensee's staff
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organization, personnel inu wiews, and observations that the licensee's l
ISEG staffing exceeds the A: tion Plan and Technical Specification I
requirements. The ISEG -e: arts off site, independent of plant management.
The ISEG is comprised of " Men engineers, all but one are Shif t Technical Advisor (STA) certified.
Two of the STAS hold NRC Senior Reactor Operators'
licenses.
I.C.1 Short Term Accident and Procedure Review:
Callaway SER Supplement 3, Section 22, provides staff evaluation and acceptance of this Action Plan Item. The staff review consisted of an evaluation of (1) the applicant's plant-specific technical guidelines, including the planned method for developing plant-specific Emergency Operating Procedures (EOPs) from
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approved generic technical guidelines that are based on the reanalysis of transients and accidents, as described in NUREG-0660,Section I.C.1, and clarified in Item I.C.1 of NUREG-0737; (2) the applicant's plant-specific writer's guide, detailing the specific methods to be used in preparing E0Ps based on the technical guidelines to ensure that the E0Ps are useable, accurate, complete, readable, convenient to use, and acceptable to control room personnel; (3)-the applicant's program for verifying and validating E0Ps to ensure that they accurately reflect the technical guidelines and the writer's guide, and that the E0Ps will guide the operator in mitigating transients and accidents; and (4) the applicant's program for training operators on E0Ps to ensure that the operators will be adequately trained prior to implementing the upgraded E0Ps.
The staff determined that the licensee had adequately responded to Item I.C.1 with the exception that the licensee needed to provide additional analysis to identify operator tasks and information and control needs (Function and Task Analysis). Callaway Operating License NPF-30, Condition Item 7.(a) required the licensee to submit the results of the function and task analysis for NRC review and approval.
This item is tracked under Action Plan Item I.D.1. of NUREG-0737.
NRC Inspection Reports No. 50-483/84013(DRP) and 50-483/84020(DRP) document the inspectors' review of licensee's administrative, normal, off-normal and emergency procedures.
These inspections included a review of procedure verification, validation, and training activities.
The deficiencies noted during this review were satisfactorily resolved by the licensee prior to fuel load.
I.C.2, Shift and Relief Turnover Procedures: Based on the staff's review of the licensee's commitments contained in Callaway FSAR Site Addendum regarding administrative procedures which govern shift and relief turnover, the staff found that the requirements of Action Plan Item I.C.2 of NUREG-0660 were met.
NRC Inspection Report No. 50-483/84048(DRP) documents the inspector's review of Callaway Operation Ocpartment Procedure No. 00P-ZZ-00003 (Shift and Relief Turnover).
Implementation of the procedure had been observed frequently by both NRC resident and region based. inspectors during perfor-mance of the NRC augmented inspections as documented in NRC Inspection Report No. 50-483/84042(DRP).
I.C.3, Shift Supervisor Responsibilities: This Action Plan Item was included in the staff's review of Item I.A.1.2 and found acceptable. The inspector determined by review of the licensee's administrative procedure APA-ZZ-00010 (Conduct of Operations) that the licensee has specified management responsibility and command authority of the shift supervisor.
I Callaway Technical Specification Section 6.1.2 specifies that the shift supervisor shall be responsible for the control room command function and requires that a management directive to this effect be reissued on an annual basis.
The inspector verified that the licensee reissues Nuclear Function Ofrective NFD-20 (Shift Supervisor Duties anc Responsibilities)
on an annual basis.
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The inspector verified that the licensee has continued to reissue management directives which emphasize primary management responsibility and clearly establish the command authorities of the shift supervisor.
The resident inspector's observations made during routine inspections had indicated that these procedures and directives were effectively implemented.
I.C.4, Control Room Access:
In SER Section 22, the staff found the licensee's commitments regarding control room access, as described in Chapter 18 of the Callaway FSAR Site Addendum, to be acceptable to meet the requirements of Action Plan Item I.C.4 of NUREG-0660.
By review of Callaway Plant Administrative Procedure APA-ZZ-00010 (Conduct of Operations - Operations), Section 6.8, " Control Room Access", the inspector determined that the licensee has developed administrative procedures which assign responsibility and authority for access control.
This procedure limits access to designated personnel during normal and emergency conditions.
The resident inspector's observations during routine inspections indicate that the procedure was effectively implemented.
I.C.5, Procedures for Feedback of Operating Experience to Plant Staff:
In Chapter 18 of the Callaway FSAR Site Addendum, the licensee committed to assign to the Independent Safety Engineering Group (ISEG) the task of independent review of reactor operating experience at the Callaway Plant and other facilities.
Based on the staff's review of the licensee's administrative Procedure AP-A-20 (Review of Recent Reactor Operating Experience) the staff determined that the licensee meets the requirements of Action Plan Item I.C.4 of NUREG-0660.
The inspector determined by ret 10w c' wa! licensee's administrative procedures and training recordt J at the licensee has satisfied its commitments and has implementec v. acomrable operating o<perience review program.
The inspector has reviewed t'c following procedures:
NSEP-NS-00600 Operating Experience Review Program (this procedure supersedes AP-A-20)
QS-21 Review of Current Operating Experience TOP-ZZ-00009 Course Deficiencies These procedures assign the ISEG responsibility for review of operating events identified in various utility and NRC reports including " Nuclear Network" and "See-In" publications.
The licensee has included the Operating Experience Review Program results in the operating staff's training program.
I.C.6, Verify Correct Performance of Operating Activities:
In Chapter 18 of the Callaway FSAR Site Addendum, the licensee is committed to having procedures which ensure an effective system of verifying correct perfor-mance of operating activities.
In a letter dated August 14, 1981, the licensee provided a rough draft procedure addressing the requirements of
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Item I.C.6 of NUREG-0737. Based upon the staff's review of the rough draft
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procedure and Chapter 18 of the FSAR Site Addendum, the staff found the
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j licensee meets the requirements of Action Plan Item I.C.6'of NUREG-0737.
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During this inspection the following procedures were reviewed:
j APA-ZZ-00310 Workman's Protection Assurance and Caution Tagging e
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j APA-ZZ-00380 Temporary System Modifications
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j ODP-ZZ-00002 Equipment Status Control
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00P-ZZ-00003 Shift Relief and Turnover
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J ODP-ZZ-00004 Locked Component Control i
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The inspector determined that.the procedures satisfy the licensee's j
commitments regarding this Action Plan Item.
These procedures provide j
for independent verification of system alignment and return to service
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of safety related equipment.
Included are instructions for tagging, l
logging, and transfer of operating equipment status information at shift
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change. NRC Inspection Reports No. 50-483/84042(DRP) and 50-483/84048(DRP)
document the inspector's review and observations in this area. These i
inspections determined that the licensee has implemented an effective i
system of verifying correct performance of operating activities.
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I.C.8, Pilot Monitoring of Selected Emergency Procedures for Near-Term
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Operating License Applicants:
In the SER, the staff stated that the staff
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does not plan to conduct a pilot monitoring review of selected emergency
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operating procedures in accordance with guidelines for Item I.C 8.
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The licensee had committed to implement emergency operating procedures lj based on the review of Westinghouse owners group guidelines. The staff
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review of the licensee's program for developing emergency operating j
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i Supplement 3 c' the SER that the Item I.C.8 was considered to be resolved.
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II.B.2. ; ant Snielding to Provide Access to Vital Areas and Protect Safety
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Equipw r.: ter Post recident Operation: The requirement was for the j
licensee te w form a design review of the shielding to verify protection F
for operators (time-dose rates) performing required post accident functions and to show that equipment necessary for mitigation of, or recovery from, an a:cident would be functional during this time period.
The staff reviewed the licensee's evaluation program and found it to be acceptable as doct.mented in Supplement 2 of the SER.
Region III inspectors reviewed the etaluation results and noted one sampling area for which a time and motion study had not been performed; results of the inspection are docurerted in Inspection Report No. 50-483/84016(DRS).
The licensee subsequently performed a time and motion study for the sampling area and
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fourd the area to be within the guidelines. As documented in Inspection Report No. 50-483/84027(ORS), the results of the study were reviewed by a Region III radiation specialist and found to be acceptable.
The require-ments of Action Plan item II.B.2 of NUREG-0737 are considered to have been met.
II.K.2 2 and.13, Orders on Babcock and Wilcox (B&W) plants:
These items are not applicable to Callaway and are being closed to maintain continuity of the NRC tracking system.
I11.0.1.1, Integrity of Systems Outside Containment Likely to Contain Radioactive Material for Pressurized Water Reactors: The Licensee was required to evaluate leak-tightness of systems that may have radioactive water outside of containment and to maintain leakage at a very low level.
The staff reviewed the commitments from the licensee to perform walkdowns and leakage tests of these systems and perform maintenance to maintain the leakage at a " low as practical" level.
Leakage tests are to be per-formed on a refueling cycle basis.
The staff considered the commitments adequate to meet the requirements of this action item and closed this item in the SER.
The inspectors, during routine tours and inspections, have not noted a leakage or maintenance problem with these systems.
Leakage testing procedures have been developed and the tests are scheduled to be performed during the upcoming refueling outage. The results of applicable "Section XI" code tests are being factored into the leak reduction program.
The controlling administrative procedures defining the responsibilities appear to be adequate. This item is considered complete.
III.D.3.3, Improved Inplant Iodine Instrumentation Under Accident Conditions: The licensee was required to provide equipment, procedures, and training necessary for accurately determining the airborne iodine concentration. The staff reviewed the licensee's commitments for the improvement of determining radioactive concentrations under accident conditions and considered them sufficient to meet the requirements of this action item.
Inspection Report 50-483/84016(DRMSP) documents the inspectors' review of the licensee's capability to obtain and analyze iodine air samples under accident conditions and found no problems.
4.
Followup on Regional Request Limitorque Valve Operators - Environmental Qualifications (EQ). NRC Region III memorandum from E. Greenman dated December 13, 1985, advised resident inspectors of non-environmentally qualified wire found in some Limitorque Valve Operators, and requested that the licensee be appraised of the potential problem. On December 26, 1985, the inspector met with members of the licensee's Quality Assurance (QA) Department advising them of this problem. QA's response in this matter was to perform a special surveillance to assess the EQ status of wiring used in the Limitorque Motor Valve Operators installed in Callaway Plant.
Subsequently, on
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January 14, 1985, the NRC issued IE Information Notice No. 86-03 to all nuclear power reactor facilities, which informed licensees of this potential problem.
The licensee has completed its review in this matter. QA Surveillance Report No. P8601-12 documents that, "Each Limitorque Mctor Valve Operator was inspected using a startup work request to verify the type of wiring used. The types of wiring used fell into two categories:
(Rockbestoes Firewall III or Raychem Flamtrol). Both categories were analyzed and submitted under Revision 3 to the SNUPPS " Report of Independent Review of Environment Qualification Programs to NUREG-0588".
Both categories were concluded to be environmentally qualified".
The inspector reviewed QA Surveillance Report No. P8601-12 and Startup Work Request No. KC-266 with attachments (inspection checklists and wiring identification) for Limitorque Valve Operator KC-HV-253.
Based on this review, the inspector determined that this matter was given prompt and thorough evaluation by the licensee QA staff, and that the licensee has documentation which demonstrates that the wiring in Limitorque Valve Operators installed in the Callaway Plant meet EQ requirements.,
5.
Surveillance The inspector reviewed / observed the following Technical Specifica' tion required surveillance testing:
Surveillance Procedure Test OSP-SE-0004 NIS Power Range Heat Balance ISL-GS-00428 Containment Hydrogen Concentration (Surveillance Task Sheet No. 0011226)
ISF-SE-00N43 I&C Surveillance Functional (Nuclear Power Range N-43)
ISP-BB-0TN431 I&C Surveillance Functional (Temperature - Loop - 3)
ISL-AB-0P546 I&C Loop Calibration Surveillance (Steam Generator-D-Pressure)
ISF-AB-0P546 I&C Functional Test (Steam Generator-D)
ISL-GT-00R31 I&C Calibration Surveillance (Containment Atmos. Radiation Detector)
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ISL-EG-000L2 I&C Calibration Surveillance (CCW Surge Tank Level)
ISF-SB-00A29 and
"A" Train Functional OSP-SB-00001 (Reactor Trip Breakers)
Items which were considered during the inspection included: that testing was performed in accordance with adequate procedures; that test instru-mentation was calibrated; that test results conformed with Technical Specifications and procedure requirements and were reviewed by personnel other than the individual directing the test; and, that any deficiencies identified during the testing were reviewed and resolved by appropriate management personnel.
No violations or deviations were identified.
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Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators throughout the inspection period. The inspector verified the operability of selected safety related systems, reviewed tagout records, and verified proper return to service of affected components. Tours of the auxiliary and turbine buildings were conducted.
During these tours, observations were
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made relative to plant equipment conditions, fire hazards, fire protection, adherence to procedures, radiological control and conditions, housekeeping, security, tagging of equipment, ongoing maintenance and surveillance, containment integrity,'and availability of safety related equipment.
No violations or deviations were identified.
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Maintenance i
Station maintenance activities of safety related systems and components listed below were observed / reviewed to ascertain that they were conducted
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in accordance withtapproved procedures, regulatory guides, industry codes
or standards, and in conformance with Technical Specifications.
The following items were considered during this review:
the limiting
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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; parts and materials used were properly certified; radiological controls were implemented; and fire prevention controls were implemented.
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g The following maintenance activities were observed / reviewed:
Number Activity
'!? 'WR 52578 Troubleshoot Loop Pressure Steam Generator-D
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(Lead Lag Time Bistable Setpoint)
WR 053130 Essential Servic'e Water Pump Room Fan "A" Train WR 54041 Continuous Air Monitor Strip Chart Recorder (Fuel Building)
Replace Fan Motdr DC-GL-038B (CMP 840271A) (Auxiliary WR 000094 i
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Building-Exhaust)
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WR 300095:
Install Cdntrol CircQit (CMP 840271A) for Damper GLD009 Equipment ID Install Scaffolding (Non-Safety Over Safety (II/I))
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No#viola' ions or deviations were identified.
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Crew Training c
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On February 3,1986, the inspector observed off-shift crew fire brigade
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-training. The training included a brieffng, simulated fire in the
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equipmentoperators' room,andcritiqueofthefire) brigade'sferformance during the fire drill. The brigade members' performance during the drill wds business-like and indicated that they 8 id been adequately trair.ed in the use of firejfighting equipment.
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No violations or deviations were identified.
9.
Incident Reduction Program Status Meeting On February 5, 1986, thd lihensee met with the NRC Region III Administrator
,and, staff members at Glen Ellyn, Illinois.1 The meeting was held to brief NRC staff on the lic4nseef s' Incident Reduction Program (IRP) and Quality Assurance organizational' changes. During the meeting, the licensee
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presented IRP status, IRP findings of root causes,' trends, and the corrective measured taken to reduce the frequency of reactor trips. The presentation high'1 hted lidensee attention and determination toward
significants improvement in thf s area.
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No violations or deviatic c sere identified.
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10. Exit Interview The. inspector met with licensee representatives (denoted under Persons Contacted) at intervals during the inspection period. The inspector summarized the scope and findings of the inspection. The licensee.
representatives acknowledged the findings as reported herein. The inspector also discussed the likely informational. content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any such documents / processes as proprietary.
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