IR 05000413/1985031

Insp Repts 50-413/85-31 & 50-414/85-25 on 850626-0726.No Violation or Deviation Noted.Major Areas Inspected:Site Tours,Followup of Licensee Identified Items,Review of Proposed Tech Specs & Fuel Receipt & Storage

ML20133N436
Person / Time
Site:	Catawba
Issue date:	08/01/1985
From:	Dance H, Skinner P, Van Doorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20133N430	List: IR 05000413/1985031 ML20133N426
References
50-413-85-31, 50-414-85-25, NUDOCS 8508130488
Download: ML20133N436 (8)

Text

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[p arcg bo NUCLEAR REGULATORY COMMISSION

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Report Nos.: 50-413/85-31 and 50-414/85-25 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 License Nos.: NPF-35 and CPPR-117 Docket Nos.: 50-413 and 50-414 Facility Name: Catawba Inspection Conducted: June 26 - July 26, 1985 Inspectors: -(

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11. C. Dance,45ection Chief Date Signed Division of Reactor Projects SUMMARY Scope: This routine, unannounced inspection entailed 152 inspector-hours on site in the areas of site tours (Units 1 and 2); followup of licensee identified items (Units 1 and 2); review of proposed Technical Specifications (Unit 2); fuel receipt and storage (Unit 2); instrumentation (cables and terminations) - obser-vation of work (Unit 2); comparison of as-built plant to FSAR description (Unit 2); review of liVAC sealants (Units 1 and 2); maintenance observations (Unit 1);

surveillance observations (Unit 1); review of nonroutine events (Unit 1); alant operations review (Unit 1); and followup of previous identified inspect"on findings (Unit 1).

Results: Of the twelve areas inspected, no violations or deviations were identifie PDR ADOCK 05000413 0 pga

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REPORT DETAILS Persons Contacted Licensee Employees

• J. W. Hampton, Station Manager

• E. M. Couch, Project Manager W. Allgood, Completion Engineer Electrical H. L. Atkins, QA Engineering Supervisor H. B. Barron, Operations Superintendent S. G. Benesole, QA Engineer Hangers B. F. Caldwell, Station Services Superintendent

• J. W. Cox, Superintendent Technical Services T. E. Crawford, Operations Engineer L. R. Davison, Project QA Manager J. R. Ferguson, Assistant Operating Engineer

• L. Hartzell, Licensing and Projects Engineer G. D. Houser, QA Hangers Supervisor

• R. A. Jones, Test Engineer C. S. Kelly, Instrumentation / Electrical Technical Support J. A. Kinard, Technical Support Hangers

• P. G. LeRoy, Licensing Engineer C. E. Muse, Operating Engineer

• T. D. Miles, Construction Engineer, Electrical G. T. Smith, Maintenance Superintendent D. Tower, Operating Engineer J. E. Whichard, Supervisor Electrical Technical Support P. M. White, HVAC Design Engineer E. G. Williams, Project QA Technician Other licensee employees contacted included construction craftsmen, technicians, operators, mechanics, security force members, and office personne * Attended exit intervie . Exit Interview The inspection scope and findings were summarized on July 26, 1985, with those persons indicated in paragraph 1 above. The unresolved item described in paragraph 8 was discussed in detail. The The licensee acknowledged the findings and had no dissenting comment licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio A copy of "Results of Regional Survey of Plant-Specific Information Relating to the Potential For Uncontrolled Radiation Exposures in PWR < Reactor Cavities", was given to the licensee at an exit interview on July 19, 198 This is an information document which has been forwarded to the Public Document Room.

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2 Licensee Action on Previous Enforcement Matters (Closed) Violation 413/85-14-02: Failure to Adequately Review the Result of Data Obtained on Instrument Procedure IP/0/A/3710/08. The response to this item was submitted on June 28, 1985. The inspector reviewed this response and verified implementation of corrective actions and considers licensee action to be acceptabl (Closed) Violation 413/85-14-03: Failure to Meet Technical Specification 3.0.4 Requirements For RHR While In Mode 5. The response to this item was submitted on June 28, 1985. The inspector reviewed this response and verified implementation of corrective actions and considers licensee action to be acceptabl (Closed) Unresolved Item 414/85-21-01: Verification of Adequate Control of Hanger Installation. The licensee has evaluated each of the previously identified discrepancies and has shown each case to be technically insignifican The inspector previously reviewed these evaluations and considered them to be adequate. However, the inspector questioned whether the licensee had an adequate program to identify and correct hanger discrepancies caused after final QC inspection is complete. This damage can and does occasionally occur when personnel use these hangers to gain access to various component The inspector reviewed the licensee walkdown program described by Construction Procedure No. 864 and considers this program generally acceptable. The inspector questioned whether painters had received any special training to prevent damage as much as possible to hangers and to report damage if it does occur since painters do much of their work after final walkdowns are completed. The licensee indicated that previous training had been done but an additional training session would be conducted -

to reinforce this training. This training was accomplished on July 12, 1985 and was witnessed by the inspecto . Unresolved Items *

New unresolve~d items are identified in paragraph . Independent Inspection Effort (92706) (Units 1 and 2)

The inspectors conducted tours of various plant areas. During these tours, various plant conditions and activities were observed to determine that they were being performed in accordance with applicable requirements and procedures. No significant problems were identified during these tours and the various evolutions observed were being performed in accordance with applicable procedure "An Unresolved Item is a matter about which more information is required to determine whether it.is acceptable or may involve a violation or deviatio _. .

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l Technical Specification Review (71301) (Unit 2)

The inspector reviewed the licensee proposed Technical Specifications to determine if connents needed to be forwarded to the NRC:NRR reviewer Verbal comments were forwarde The NRC reviewers met with licensee and Region II representatives at the site to acquire additional information relative to proposed change No violations or deviations were identifie . Fuel Recepit and Storage (605018) (Unit 2)

The inspector observed receipt in progress for the first three fuel shipments to verify that the licensee was meeting requirements of approved procedures and Materials License SNM-1949. Attributes considered in this review included personnel training, housekeeping / cleanliness control, health physics controls, security, receiving inspection (assemblies N23, N26, N27 and N56) and documentatio During this inspection the licensee informed the inspector that radiation monitors required by licensee submittal of June 20, 1984, page 7 were not operable. The licensee took compensatory action of placing two portable monitors in the fuel receipt are This was documented in licensee memorandum Cox/Canady dated July 12, 198 The inspector discussed this compensatory measure with the NRC safeguard representative who indicated this was technically acceptable actio No violations or deviations were identifie . Instrumentation (Cables and Terminations) - Observation of Work (52063C)

(Unit 2)

The inspector observed selected cables to determine if installation was in accordance with appropriate and approved procedures and specification This review included observation of routing, supports, protection, separation, identification of cables and raceways, raceway loading, and terminations. Cables observed were 2CA 845 (Auxiliary Feedwater Discharge Pressure), 2FW564 (RWST Level), 2NS 580 (Containment Pressure), 2CF513 (Steam Generator Narrow Range Level), 2NS551 (Containment Pressure) and 2NS604 (Containment Isolation).

The inspector questioned the licensee relative to separation of Cable N FW564 from heat tracing cable inside the instrument electrical box. The licensee indicated that an apparent discrepancy from specifications existed and wrote Nonconforming Item Report No. 19773. The licensee was requested to evaluate this item for significance and generic implications. This is Unresolved Item 414/85-25-01: Evaluation of Instrumentation Cable Separation Proble No violations or deviations were identifie ..

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4 Comparison of As-built Plant to FSAR Description (37301) (Unit 2)

The inspector performed a walkdown inspection of the Auxiliary Feedwater System to determine if piping, valves, and instrumentation (including electrical control and logic) installation was in accordance with current flow diagrams and FSAR descriptions. System portions shown on Drawing Hos. CN 2592-1.0, CN 2592-1.1, CNEE 0215-01.33, CNEE 0247-02.01, 02, 03, 04,05, and CNEE 0247-04.17, 18, 19, 20, and 21 were observe The inspector reviewed electrical control and instrumentation logic only for the Chemical and Volume Control System to verify that this system met the FSAR descriptio No violations or deviations were identifie . Review of HVAC Duct Sealants (50100) (Units 1 and 2)

The inspector requested the licensee to provide assurance that sealant materials used in HVAC duct joints is environmentally qualified. The licensee informed the inspector that three types of sealants are use These are Tremco Type 440, Epichlorohydrin Gaskets Stock No. R473E and R475E by Rubatex Corp. , and Dow Corning Silastic 732 RTV. The inspector reviewed licensee documentation of environmental evaluation of these materials and considers licensee evaluation of these materials to be adequat No violations or deviations were identifie . Maintenance Observation (62703) (Unit 1)

Station maintenance activities of selected systems and components were observed / reviewed to ascertain that they were conducted in accordance with the requirements. The inspector verified licensee conformance to the requirements in the following areas of inspection: (1) that the activities were accomplished using approved procedures, and functional testing and/or calibrations were performed prior to returning components or systems to service; (2) quality control records were maintained; (3) that the activities performed were accomplished by qualified personnel; and (4) parts and materials used were properly certified. Work requests were reviewed to determined 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 . Surveillance Observation (61726) (Unit 1)

During the inspection period, the inspector verified plant operations were in compliance with various Technical Specifications requirements. Typical of these requirements were confirmation of compliance with the Technical Specifications for reactor coolant chemistry, refueling water tank, emergency power systems, safety injection, emergency safeguards systems, control room

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ventilation, and direct current (DC) 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 surveillance items that were witnessed in part or in full were various calibrations of portions of the nuclear instrumentation and radiation monitoring system No violations or deviations were identifie . Review Of Licensee Nonroutine Event Reports (92700) (Unit 1)

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 Technical Specifi-cations and regulatory requirements, corrective action taken, existence of potential generic problems, reporting requirements satisfied, and the relative safety significance of each event. Additional inplant reviews and discussion with plant personnel, as appropriate, were conducted for those reports indicated by an asterisk (*). The following LERs are close *LER 85-01 Auto Start CA Motor Driven Pumps

• LER 85-08 Reactor Trip Due to Low-Low Steam Generator Level LER 85-13 R1 Firestop Seals on Conduit Not Installed LER 85-14 Stainless Steel Valves Installed with Carbon Steel Filler Material

• LER 85-17 Turbine Driven CA Pump Auto Start

• LER 85-27 R1 Auto Start of 1B D/G Due To Light Socket Failure

• LER 85-30 Swapover of RN Suction to Standby Service Water Pond Due to Breaker Trip

• LER 85-31 Spurious Swapower of RN Suction to Standby Service Water Pond

• LER 85-32 Swapover of RN Suction to Standby Service Water Pond Due to Personnel Error

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• LER 85-33 Reversed Operation of Steam Generator Level Circuitry Caused ESF Actuation

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i LER 85-34 Diesel Generators Startup Due to Distribution System Disturbance

• LER 85-36 Incorrect Calibration of UHI Level Instrumentation 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, Technical Specifications, Control room logs, danger tag logs, Technical and administrative control Specification Action Item Log, and the removal and restoration log were routinely reviewed. Shif t turnovers were observed to verify that they were conducted in accordance with approved procedure The inspectors also verified by observation and interviews, that measures taken to assure physical protection of the facility met current require-ments. Areas inspected included the security organization, the establish-ment and maintenance of gates, doors, and isolation zones in the proper condition, that access control and badging were proper, and procedures followe In addition to the areas discussed above, the areas toured were observed for These included such things as fire prevention and protection activities. control, fire protection systems and materials, a combustible material fire protection associated with maintenance and construction activitie No violations or deviations were identifie . Previously Identified Inspector Findings (92701) (Unit 2)

(Closed) Inspector Followup Item 414/85-19-01: Volume Control Tank Radiographs Sensitivit This item involved a request for further review to be conducted by the licensee Level III inspector relative to the subject radiographs. The licensee conducted this review including utilization of The an image enhance The licensee concluded that the films were acceptabl , 152, 154, 165, NRC inspector reviewed selected films for welds Nos.The inspector also reviewed 169, 170, 195 and 19 Nos. 151, 152, 154, 165 and 170 on the Image Enhance Two penetrations were used for these radiographsThese and adequate sensitivity film, however, meet only exists for one penetrameter in some case codes requirenents since only one penetrameter is required as long as density variation requirements are met. Density variation was me Although sensitivity is borderlina acceptable in some cases, these films are considered adequate and this item is therefore close ..

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l 16. Licensee Identified Items 50.55(e) (99020) (Unit 2)

(Closed) CDR 414/85-01: Control Rod Drive Mechanism Breach Screw Manufacturing Error. A report for this item was submitted on February 20, 198 The inspector reviewed this report and verified implementation of corrective actions identified in the report and considers licensee actions to be acceptabl ,

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