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Insp Repts 50-413/86-11 & 50-414/86-15 on 860202-25.No Violation or Deviation Noted.Major Areas Inspected:Lers, Review of Inspector Identified Items,Tmi Action Items, Emergency Exercise Evaluation & Preparation for Refueling
	ML20205M759
Person / Time
Site:	Catawba
Issue date:	04/04/1986
From:	Brownlee V, Skinner P, Van Doorn P; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20205M741	List: IR 05000413/1986011; ML20205M738;
References
	TASK-1.A.2.1, TASK-1.D.2, TASK-1.G.1, TASK-1.G.2, TASK-2.F.1, TASK-2.F.2, TASK-2.K.3.09, TASK-3.D.1.1, TASK-TM 50-413-86-11, 50-414-85-15, 50-414-86-15, NUDOCS 8604150369
	Download: ML20205M759 (9)
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. v Mc UNITED STATES g o NUCLEAR REGULATORY COMMISSION y' ", REGION 18 J* ,, j 101 MARIETTA STREET, N.W.

l t ATLANTA, GEORGt A 30323 l

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v Report Nos.: 50-413/86-11 and 50-414/86-15 Licensee: Duke Power Company l 422 South Church Street

! . Charlotte,- NC 2824 :

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Docket Nos.: 50-413 and 50-414 -

License Nos.: NPF-35 and NPF-48 Facility Name: Catawba 1 and 2 -

Inspection Conducted: February '> - 25, 1986 i Inspector: .

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P. K. V~n Doo Date Signed

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Inspector: -

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~ H. Skinner D' ate Signed Approved by: [ stM $7 0V b V."L.B[pwnlee,SectionChief 'Ora te Signed Projects Branch 3 '

Division of Reactor Projects SUMMARY Scope: This routine, unannounced inspection entailcd 163 inspector-hours on site inspecting in the areas of review of licensee event reports (Unit 1); review of

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inspector identified items (Units 1 and 2); plant operations review (Units 1 and -

2); design changes and modifications (Units 1 and 2); review of TMI action item '

(Units 1 and 2); emergency exercise evaluation (Units 1 and 2); preparation for f refueling (Unit 1); surveillance observation (Unit 1); maintenance observation i (Unit 1); operational staffing (Unit 2); preoperational test program l implementation (Unit 2); observation of initial fuel loading (Unit 2).

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( Results: Of the 12 areas inspected, no violations or deviations were identifie t ,- 1

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REPORT DETAILS Persons Contacted Licensee Employees H. B. Tucker, Vice President, Nuclear Production G. R. Vaughn, General Manager, Nuclear Stations J. W. Hampton, Station Manager E. M. Couch, Project Manager H. L. Atkins, QA Engineering Supervisor

H. B. Barron, Operations Superintendent W. F. Beaver, Performance Engineer W. H. Bradley, QA Surveillance T. B. Bright, Construction Engineering Manager B. F. Caldwell, Station Services Superintendent J. W. Cox, Superintendent, Technical Services T. E. Crawford, Operations Engineer J. R. Ferguson, Assistant Operating Engineer

t. L. Hartzell, Licensing and Projects Engineer R. A. Jones, Test Engineer J. Knuti, Operating Engineer

*P. G. LeRoy, Licensing Engineer l

W. R. McCullum, Superintendent, Integrated Scheduling l C. E. Muse, Operating Engineer i D. B. O'Brien, Administrative Methods Supervisor

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G. Robinson, QA Engineer, Operations F. P. Schiffley, II, Licensing Engineer G. T. Smith, Maintenance Superintendent D. Tower, Operating Engineer J. W. Willis, Senior QA Engineer, Operations Other licensee employees contacted included technicians, operators, mechanics, security force members, and office personne * Attended exit interview Exit Interview The inspection scope and findings were summarized on February 25, 1986, with those persons indicated in paragraph I above. The inspector described the areas inspected and discussed in detail the inspection findings. .No dissenting comments were received from the license The licensee did _not-identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio . Licensee Act:on on Previous Enforceme,t Matters (Units 1 and 2) (92701)

, (Closed) Unresolved Item 413/84-106-02: Follow-up of Determination of

,' Opert.bility of Systems / Components. The Inspector reviewed his area and

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determined that the following procedures: Operations Management Procedure 2-29, Technical Specifications (TSs) Actions Item Logbook, Maintenance Management Procedure 1.0, Work Request Preparation, and Station Directive 3.1.15, Activities Affecting Station Operations or Operating Indications, address operability of systems and components l' and if properly followed would identify system / component operabilit Based on this review, this item is close (Closed) Unresolved Item 413/85-20-01, 414/85-16-01; Verification of Adequate Installation of Instrumentation. Further review of this item disclosed that Design Engineering personnel had not considered the weight of heat trace insulation in seismic calculations for the Refueling Water Storage Tank water leve However, recalculation has shown that this oversight was technically insignificant. In addition, the licensee has shown that the mounting of the level transmitters for these instruments is acceptabl Licensee actions are acceptable, (Closed) Unresolved Item 413/85-26-01: Verification of Adequate Control of Hanger Installation. The technical aspects of this item have been previously reviewed and licensee actions acceptable. However, the licensee committed to provide special training for operations personnel relative to hanger damage. The inspector reviewed the new training program and verified the program has been implemented. Licensee actions are acceptabl ' (Closed) Unresolved Item 414/85-32-01: Review of Electrical . Interfaces

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L Between Units. The licensee has completed the review of electrical interfaces for both safety-related and non-safety-related loads. A few non-safety-related interfaces were noted but all have an automatic swapover featur One safety-related interface was noted involving Valve Nos. I and 2NV188A, 252A, 1898 and 253B. It was determined that these valves would fail to the safe positions upon loss of power, however, for better control of operations"'the licensee proposed modifications for these valves. The Unit 2 modifications have been completed and verified by the inspector. Licensee actions for Unit 2 are acceptabl The Unit 1 portion of this item remains open pending modifications. Appropriate interim-actions have been implemente No violations or deviations were identifie . plant Operations Review (Unit 1) (71707 and 71710) The inspectors reviewed plant _ operations throughout the reporting period to verify conformance with regulatory ' requirements, TSs, and administrative controls. Control room logs, danger tag outs, TS Action Item Log, and'the remeval and restoration log were routinely reviewe Shift turnovers were' observed to_ verifyf that they were conducted in accordance with approved procedure '

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The inspectors verified by observation and interviews, that measures taken to assure physical protection ~cf the facility met current requirements. Areas inspected included the security organization, the establishment and maintenances of gates, doors, and isolation zones in the' proper condition, that access control and badging were proper and procedures followe In addition to the area discussed above, the areas toured were observed for fire prevention and protection activitie These included such ,

things as combustible material control, fire protection systems ano materials, and fire protection associated with maintenance and construction activitie I On February 3, 1986, the licensee requested a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the time allowed under the Action statement of TS 3/4.4.6.2 for operational leakage. The computer program used for this calculation was believed to be inaccurate because of an inability to isolate an output from the pressurizer relief tank. Relief was granted based on discussions ,

between NRR, Region II, the Resident Inspectors and the licensee. This '

action is documented in a memo to file dated February 13, 198 On February 14, 1986, the licensee requested a 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months extension to the time allowed under the Action statement of TS 3/4.7.7 for the Auxiliary Building Filtered Exhaust System. TFis request was made due to ' failed heaters in the system. The 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months allowed by the Action statement j

was not sufficient to replace the heaters and also perform the required -

testin Relief was granted based on discussions between NRR, Region II, the Resident Inspectors and the licensee. The licensee has addressed this issue in a letter to Region II dated February 19, 198 No violations or deviations were identifie . Design, Design Changes, and Modifications (Units 1 and 2) (37700)

The inspector reviewed the licensee's program for temporary modification The program was reviewed to assure that controls were established to review and approve temporary modifications, that reviews required by TSs chapter 6.0 and 10 CFR 50.59 were performed, that formal records were maintained and periodic reviews were conducted. In addition, requirements for. independent verification associated with installation and removal were reviewe Station Directive 4.4.5, Temporary Station Modification, revision 5, details the licensees' program. The inspector also reviewed 26 electrical temporary modifications and 16 mechanical modifications for implementatio No violations or deviations were identifie . Evaluation of Exercises for Power Reactors (Units I and 2)(82301)

During this reporting period the inspectors assisted the Emergency Preparedness Team evaluate the conduct ' of ' the annual emergency drill

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conducted February 20, 1986. The comments of the inspectors were provided to the team leader and incorporated into Inspection Report 50-413/86-08, 414/86-1 No violations or deviations were identifie . Preparation for Refueling (Unit 1) (60705)

The inspector reviewed preparations for refueling of Unit 1 presently scheduled to commence in August 1986. This review was concerned only with the receipt, inspection and storage of fuel in the fuel storage area. This process was performed in accordance with approved procedures and used instrumentation that had been recently calibrated in accordance with -

calibration requirement In addition, the inspector reviewed training _

records of various personnel handling the new fuel and crane operation Only two fuel assemblies were observed (D-49 and D-51).

No violations or deviations were identifie . Surveillance Observation (Unit 1) (61726)

During the inspection period, the inspector verified plant operations were in compliance w th various TS requirements. Typical of these requirements i

were confirmat .on of compliance with the TS for reactor. coolant chemistry,

, refueling water tank, emergency power systems, safety injection, emergency safeguards systems, control room ventilation, and direct current electrical power source The inspector verified that surveillance testing was performed in accordance with the approved written procedures, test instrumentation was calibrated, limiting conditions for operation were met, appropriate removal and restoration of the affected_ equipment was accomplished test results met requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personne Typical of the :orveillance items that were witnessed in part of in -full were various calibrations of the nuclear instrumentation, radiation monitoring systems instrumentation, auxiliary- feedwater sy tem testing, and turbine stop. valve testin No violations or deviations were identifie . Maintenance Observations -(Unit 1) (62703)

Station maintenance activitiec of selected systems and components were observed / reviewed to a ascertain that they were conducted in accordance with the requirement The inspector verified licensee conformance to the requirements in 'the following areas of inspection: .the activities were accomplished using approved procedures, and functional _ testing and/or, ,

calibrations were performed prior to returning ' components 'or systems to I service; quality control records were maintained; activities performed were

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accomplished by qualified p rsonnel; and parts and materials used were properly certifie Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety-related equipment maintenance which may effect system performanc <

No violations or deviations were identifie . Review of Licensee Nonroutine Event Reports (Unit 1) (92700)

The below listed Licensee Event Reports (LER) were reviewed to determine if the information provided met NRC requirements. The determination included:

adequacy of description, verification of compliance with TSs and regulatory requirements, corrective action taken, existence of potential generic problems, reporting requirements satisfied, and the relative safety signi-ficance of each event. Additional inplant reviews and discussion with plant personnel, as appropriate, were conducted for those reports indicated by an (*). The following LERs are close *LER 413/85-55 Failure To Maintain A Backup Fire Hose Station

LER 413/85-58 Fire Watches Not Maintained On An Hourly Basis

LER 413/85-64 Required Fire Watches Not Performed Due to Miscommunication

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LER 413/85-69 Availability Of Offsite Power Sources Not Verified Due to Personnel Error

LER 413/85-70 Missed Firewatch Due To Malfunction Of Security Computer i

LER 413/85-71 Reactor Trip Due To Malfunction Of Feedwater Control Valve Failure Of Security -Computer System Mdliipl'e'xer

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LER 413/85-72 Causes Two Missed Fire Watches

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No violations or deviations were identifie . Review of TMI Action Items (Units 1 and 2) (25401)

This inspection was conducted to verify the adequacy of implementation of licensee commitments made-to the NRC. The commitments were made in response to the requirements of NUREG-0660, NRC Action Dlan Developed as a Result of the TMI-2 Accident, published May 1980, Revised August 1980; NUREG-0737, Clarification of TMI Action Plan Requirements, published November 1980; and NUREG-0694, TMI-Related Requirements for New Operating Licenses, published June 198 .

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The verification adequacy was based upon personal observations in the plant and review of licensee drawings, procedures, and documents. The specifics are contained in each paragrap I.A.2. Upgrading of R0 and SRO Training and Qualifications. The remaining licensee action relative to this item was to change Operations Management Procedure 3-1 to reflect the required 1 year as an RO for SRO degreed candidates. The inspector verified completion of this action.

l I.D.2 Plant Safety Parameter Display Console. SER No. 5, section 18.2

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documents NRC review of this system. The inspector verified that the system is operable for Unit 2. NRC has requested that additional parameters be added. License Condition (9) (b) has been established and further followup will be performed under the License Condition. .This item was previously closed for Unit I.G.1 Training During Low Power Testin This item was not required for Unit 2 and is therefore closed for Unit II.F.1.2.D.,E., and F Accident Monitorin The licensee committed to t installation of instrumentation for monitoring containment pressure, l containment water level and containment hydroge Two channels with vital j power supply have been provided. The inspector verified these instruments

! are installed and operable for both Unit II.F.2 Instrumentation for Detection of Inadequate Core Coolin The licensee has installed the subcooling meter, thermocouples and RVLIS instrumentation. Final calibration and operability checks have not been completed, however, .these are scheduled to be completed and are controlled by TS requirement Therefore, this item is closed for Unit II.K. PORV PID Controlle The inspector . verified that the PID controller derivative time constant has been set to zero which was the requirement for this ite III.D.1.1.1 Primary Coolant Outside Containment Leak Reductio The inspector verified that periodic tests have been developed and implemented for those systems which could develop leakage outside containment. This item is closed for Unit No violations or deviations were identifie . Operational Staffing (Unit 2) (36301)

The inspector reviewed the area of- operational staffing to assure that all staff positions are filled and that the personnel designated for these positions are trained and meet the prescribed . experience specified in TS Specifically reviewed during this inspection were <

quality assurance..and quality control staff personnel that perform non-destructive examination (NDE). The licensees program for these l

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l personnel are detailed in procedures QA-140 Quality Assurance Inspector Training, Revision II and NDE-8, Training, Qualification and Certification of NDE Personnel, Revision 10. The inspector reviewed ' records of five NDE

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inspectors. Minor discrepancies in various records were identified to supervision for clarificatio No violations of deviations were identifie . Preoperational Test Program Implementation (Unit 2) (70302) (71302) The inspector conducted tours to verify that turned-over equipment was adequately protected and controlled. This review included observation of construction activities, observation for fire hazards and observation of security boundarie The inspector reviewed design modifications associated _with testing to veri fy these changes were adequately controlled and appropriate 1 retesting had been accomplishe Specifically reviewed were modifications associated with the Component Cooling System, Procedure TP/2/A/1200/01. Associated documentation involved is NSM-20014, DCM KC-55 and Station Problem Report CNPR0136 The inspector reviewed status of the preoperational program and specifically verified final approvals for Procedure No . TP/2/A/1100/02A and 028, TP/2/A/1200/03A, TP/2/A/1350/098, TP/2/A/1400/01, TP/2/A/1450/05, PT/2/A/4200/01C, PT/0/A/4200/48,

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IP/2/A/3230/05, IP/0/A/3231/01 and MP/0/A/7150/0 The inspector verified that the licensee had replaced operators for valve Nos. 2VX1A and 2VX2B in the Containment Air Return and Hydrogen Skimmer System. These modifications were made in _ response to concerns previously expressed by NRC:RII relative to' enyironmentab,. qual.ificatio of the operators. This work was documented on Work Request" No. 1588 NSM.

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The inspectors reviewed documentation and held discussions with licensee personnel relative to Diesel Generator failures subsequent to the test program to determine test frequency requirements as defined by Regulatory Guide 1.108 and the TSs. The licensee determined that the 2B engine should be considered as having two failures which requires testing of each engine every 14 day The licensee documented this decision in a Memo to File dated February 24, 1986. The inspectors agreed with the licensees evaluatio The inspector also reviewed Construction Nonconforming Item Reports (NCI's) to verify that- appropriate documentation and evaluation was accomplished for nonconforming conditions on systems being turned-over to operation Specifically reviewed were NCI Nos. 18,400 through 18,420. Special attention was given to NCI No.18,409 which involved

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welding insert material which had been specially ordered for Upper Head Injection System seal welds. . This material had been inadvertently i

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shipped offsite without traceability. The inspector verified that the licensee had ordered new traceable material and that this material had been used for the seal weld No violations or deviations were identifie . Inspector Witnessing of Initial _ Fuel Loading (Unit 2) (72524)

The inspector reviewed the licensee's TSs and license conditions applicable to initial fuel loading. A review of outstanding work items, modifications and surveillances was also _ performe In addition, an independent inspec-tion of approximately 50% of the applicable TSs was reviewed. A verifica-tion was performed to . assure the controlling procedures were approved and issued, that instrumentation was in calibration, and personnel training had been conducte No violations or deviations were identifie . Previously Identified Inspector Findings (Units 1 and 2) (92701) (Closed) Inspector Followup Item 413/85-20-05: Correction of FSAR Tables 7.4.7-1, 7.4.7-2, and 7.4.7-3. This item was. upgraded to a deviation in inspection report 50-413/85-5 This item is-closed for record purpose (Closed) Inspector Followup Item 414/85-63-01 Reactor Internals Quality Releas The inspector reviewed the quality release N QR-P-25622 which appears acceptabl No violations or deviations were identifie t-l

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IR 05000413/1986011

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