IR 05000414/1985052

Insp Rept 50-414/85-52 on 851021-25.No Violation or Deviation Noted.Major Areas Inspected:Electrical & Instrument Components,Observation of Work Activities & Review of Quality Records

ML20138C327
Person / Time
Site:	Catawba
Issue date:	11/26/1985
From:	Conlon T, Ruff A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20138C324	List: IR 05000414/1985052 ML20138C319
References
50-414-85-52, NUDOCS 8512120548
Download: ML20138C327 (5)

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UNITED STATES '

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NUCLEAR REGULATORY COMMISSION I

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J Report No.: 50-414/85-52 Licensee: Duke Power Company 422 South Church Street Charlotte NC 28242 i

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Docket No.: 50-414 License No.: CPPR-117

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Facility Name: Catawba Inspection Conducted: October 21-25,.1985 Inspector: fj//// $ ob/ //26 W A. B. RufT M ff Eate signed

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Approved me #

T. E. Conlon Section Chief

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Eate Tigned Engineering Branch Division of Reactor Safety l

j SUMMARY

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Scope: This routine, unannounced inspection entailed 35 inspector-hours on site in the areas of electrical components and instrument components. The observation of work and work activities and review of quality records were examined for the above areas. In addition, the licensee's action on a previous enforcement matter and an inspector followup item were examined.

j Results: No violations or deviations were identified, i .

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8512120548 B51129 PDR ADOCK 05000414 G PDR m

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REPORT DETAILS Persons Contacted Licensee Employees

• T. Robertson, Construction Technical Support

• H. Barron, Superintendent of Operations T. Bright, Engineering Manager

• T. Gill, Electrical / Instrument Technical Support

• E. G. Williams, Project QA Technician

• D. B. O'Brien, Construction Technical Support M. Jones, Construction Technical Support W. Reynold, Engineer, Electrical Technical Support R. Burton, Quality Control, Instrumentation T. Harrell, Supervisor, Design Engineer B. Smith, Design Engineer J. Thomas, Senior Engineer J. Harrington, Design Engineer Other licensee employees contacted included construction craftsmen, technicians, security force members, and office personne NRC Resident Inspectors

• P. K. VanDoorn, Senior Resident Inspector

• P. H. Skinner, Resident Inspector

• Attended exit interview Exit Interview The inspection scope and findings were sunnarized on October 25, 1985, with those persons indicated in paragraph I above. The inspector described the areas inspected. The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio . Licensee Action on Previous Enforcement Matters (0 pen) Violation 50-414/85-28-02, Missing or Nonexistent CP-438, Instrument Record The purpose of this procedure was to assure that each installed instruments would be reviwed for any special protection and/or maintenance requirements. The licensee has reviewed and installed protection devices in instruments in the auxiliary building. This was observed during other inspections in the area. Corrective action in the containment building was scheduled after Hot Functional Testing and is to be completed the latter part of November.1985, as indicated in the licensee response. This item will remain open for a more complete inspection after the licensee has completed his resolutio j

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4. Unresolved Items Unresolved items were not identified during the inspectio . Inspector Followup Item (IFI)

(Closed) IFI 50-414/85-28-01, Review of Receiving, Seismic, and Environ-mental Qualification Record for Instruments. The licensee indicated that gages 2SMP5080 and 2NCP5860 are standard stock items and were procured in accordance with their Procurement QA Manual, Procedure 302. These items are located in a mild environment. The seismic qualifications for these gages were reviewed and found to be satisfactor The environmental records for 2NCLT5150, 2NCPT5150, and 2NCRD5860 were reviewed and found to be satisfactory. Instrument 2NCFT5000 (RCS flow signal) is not required for accidents that cause a change in the normal containment operating environ-ment and failure of this instrument as result of exposure to harsh environment will not preclude the safety function of other equipmen Instrument 2SMPT5080 is located in a mild environment and doesn't fall under requirements of 10 CFR 50.4 . Electrical (Components and Systems II) - Review of Quality Records The pertinent records relative to the 4160 volt Essential Auxiliary Power Switchgear Relay Setting were reviewed. This study is applicable to Units 1 and 2 and is covered by Catawba Nuclear Station Design Calculation Number CN-1381-05-1 The study was conducted in accordance with established procedures and were evaluated by qualified personne Within the area examined, no violations or deviations were identifie . Instrument Components and Systems - Work Observation and Record Review (52053 and 52055)

The inspector examined work in process, completed work and records for various selected safety-related components and mechanical / electrical equipment. Ir Jections were made in the areas of storage, in-process and completed work, as-built verification and calibration to verify conformance with applicable codes and standards required by the licensee's Safety Evaluation Report (SAR), licensee commitments, NRC requirements and licensee's procedures. The Catawba procedures and drawing used in the inspection are listed below: QA Procedure M-61, Instrumentation Process Control and Inspections Supplemental inspection instruction designated by various M61D Serial Number Drawing ICS-A-20, Instrument Standards CP-623, Origination and Routing of Instrumentation Process Control Procedure P-3, General and Special Storage Maintenance Requirements Procedure P-1, Receiving Inspection m

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The selected components, as-built plans and records are listed in the discussion sections below, Storage There are not many safety-related components in the instrument storage area at Catawba 2 due to the near completion of construction. Solenoid valves for Design Change Authorization (DCA) M1527, and a level transmitter were examined in the warehouse storage area. Storage conditions were as specified in P-1A inspection records and the items were properly identifie The items inspected consisted of solenoid valves 2SVSV0014, 0015, 0074, 0075, 0134, 0135, 0194, 0195, 2CASV 1490, 1491, 1500, 1501, 1510, 1511, 1520, and Barton Model 764 level transmitter, Serial Number 86 The above items are identified on receiving inspection report, P-1A form, File Number IV 121, dated 10-10-85 and SR-S-2 dated 7-10-85, respectivel In-process and completed work The below listed instruments and their associated components were examined by physical sighting of work, completed work, and review of records for compliance to fore mentioned requirements. The records were properly signed and processed. The areas of inspection included instrument location, orientation, mounting and anchoring, identifi-cation, cleanliness, physical protection, redundancy, separation, tubing runs and slopes.

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Instruments Description 2NSPT5040 Containment Pressure Transmitter 2NSPT5240 Containment Pressure Transmitter 2SMPT5090 SG-A Steam Line Pressure Transmitter 2SMPT5190 SG-D Steam Line Pressure Transmitter 2NILT5260 Containment Sump Level Transmitter 2NILT5270 Containment Sump Level Transmitter 2NCRD5850 RC Loop 1 Hot Leg Wide Range Temperature 2NCRD5900 RC Loop 3 Hot Leg Wide Range Temperature 2CASV0560 Auxiliary.Feedwater System Flow Control Solenoid Valve to SG-B During the inspection of the above items, it was noted that the reactor vessel level indicating system instrument tubing in the annulus at azimuth 75 degrees, 573 foot elevation is subject to damage by construction personnel-stepping on the tubing. The area where tubing damage could occur is in close quarters where it is difficult to walk without stepping on the tubing. It is possible however, if care is taken, to move in this area and not step on the tubin The licensees's representative stated that this area would be looked at during the evaluation of equipment protection as discussed in paragraph 3. This area will see no traffic during plant operation ,

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o 4 Calibration The licensee's representative stated that calibration in the instrumention area is not performed by the construction departmen This activity is performed by the startup group in the power production department. The calibration records for the following instruments were examined:

Instrument Description 2NSPT5370 Containment Spray Pressure Transmitter 2NSP5370 Containment Spray Pressure gage 2NCPT5160 Reactor Coolant Pressure Transmitter 2NCFT5000 Reactor Coolant Flow Transmitter 2NSP5040 Containment Spray Pressure gage 2NSCR5040 Containment Spray Recorder The records showed that the calibrated instruments met the degree of accuracy and/or tolerance specifie Calibrated measuring and test equipment was properly identified, traceable and in calibration. The above instruments were calibrated as part of Work Request Nos. 2576 IAE and 3664 IA As-Built Verification and Change Control Records As-built verification was performed by comparing the actual installa-tion location with as-built location drawing used in the installation of components inspected and listed in paragraph 7.b. In addition, change control records associated with Variation Notices (VNs) were reviewed to insure that their review and evaluation were performed by qualified personnel and that the VN was incorporated into the as-built drawing in a timely manner. The following instruments, drawing and VNs were examine Instrument or VN Drawing 2NCRD5850 CN 2680-1 2NCRD5900 CN 2680-1 2NSPT5040 CN 2499-0 VN 48872 CN-2499-NW2 and NW3 VN 45227 CN-2499-0 VN 49999 CN-2499-CF5 Within the areas examined, no violations or deviations were identifie i