IR 05000413/1985023

Insp Repts 50-413/85-23 & 50-414/85-18 on 850520-24.No Violation or Deviation Noted.Major Areas Inspected: Preoperational Test Procedure Review,Preoperational Test Witnessing & Review of SER Open Item

ML20129C014
Person / Time
Site:	Catawba
Issue date:	06/04/1985
From:	Jape F, Matt Thomas NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20129B974	List: IR 05000413/1985023 ML20129B969
References
50-413-85-23, 50-414-85-18, NUDOCS 8507290323
Download: ML20129C014 (4)

Text

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j Report Nos.: 50-413/85-23 and 50-414/85-18 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-413 and 50-414 License Nos.: NPF-35 and CPPR-117 Facility Name: Catawba 1 and 2 . Inspection Conducted: May 20 - 24, 1985 Inspector: M. Thomas M * /dt S /4/8f 6 Date Signed Approved by: M ' .//t 4//[[[ F. Jape, Section Chief Engineering Branch g Date Signed Division of Reactor Safety SUMMARY Scope: This routine, unannounced inspection entailed 36 inspector-hours on site in the areas of preoperational test procedure review, preoperational test witnessing, and review of a Safety Evaluation Report (SER) open ite Results: No violations or deviations were identified.-

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,e REPORT DETAILS Persons Contacted Licensee Employees

*B. F. Caldwell, Station Services
*J. W. Cox, Technical Services Superintendent
*C. W. Graves, Jr. , Operations Superintendent
*C. L. Hartzell, Compliance Engineer
*R. A. Jones, Test Engineer
*C. S. Kelly, Construction Instrumentation / Electrical P. G. LeRoy, Licensing Engineer
*E. B. Miller, Senior Quality Assurance (QA) Engineer
*T. D. Mills, Construction Engineer - Electrical
*G. Smith, Maintenance Superintendent
*R. A. Throneburg, Construction Status and Control
*E. G. Williams, Project QA Technician Other licensee employees contacted included test coordinators, engineers, technicians, operators, and office personne NRC Resident Inspectors
*P. H. Skinner, Senior Resident Inspector, Operations
*P. K. VanDoorn, Senior Resident Inspector, Construction
* Attended exit interview Exit Interview The inspection scope and findings were summarized on May 24, 1985, with those persons indicated in paragraph I above. The inspector described the areas inspected and discussed the inspection finding No dissenting comments were received from the licensee. 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 This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during the inspectio >

? , : 2 Independent Inspection Effort (92706) - Units 1 and 2 The inspector conducted a general inspection of the Unit 2 auxiliary building, turbine building, reactor building, and the control room to observe ongoing construction and testing activities for compliance with NRC requirements and licensee commitments. In addition, the inspector reviewed the status of SER Open Item 9 concerning upgrading the pressurizer and steam generator power operated relief valves (PORVs) to safety related valve The licensee has committed to upgrade the PORVs prior to startup following the first refueling outage for Unit 1 (License Condition 18) and prior to fuel load for Unit 2. In discussing this matter, licensee personnel stated that the modifications for Unit 1 are scheduled to be completed during the Unit I refueling outage. The pressurizer PORV modification for Unit I will . be done under nuclear station modifications (NSMs) CN-10264 and CN-1043 The Unit 2 modifications will be performed under design change authoriza-tions (DCAs) CN-2-M154 for the pressurizer PORVs and CN-2-M1527 for the steam generator PORVs. The Unit 2 pressurizer PORV modifications have been performe Final QA acceptance and preoperational testing have not been completed yet. The steam generator modifications have not been complete The inspector will continue to follow the progress of these modifications during subsequent inspection . Preoperational Test Procedure Review (70304, 70311, and 70343) - Unit 2 The inspector reviewed the preoperational (preop) test procedures listed below to verify that they were consistent with applicable sections of the Final Safety Analysis Report (FSAR) Chapters 5, 6, 7, 9, 14, and 15, and Regulatory Guides 1.68 and 1.7 The following procedures were reviewed:

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TP/2/A/1200/02A, Residual Heat Removal System Functional Test

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TP/2/A/1200/03C, Safety Injection Pumps and Flow Adjustment Functional Test

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TP/2/A/1200/04, Containment Spray System Functional Test

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TP/2/A/1400/01, Nuclear Service Water System Functional Test The procedures were reviewed to verify that the required reviews were performed, management approval was indicated, and acceptance criteria specifie No violations or deviations were identified in the areas inspecte . Preoperational Test Witnessing (70315) - Unit 2 The inspector witnessed portions of preop tests TP/2/A/1200/02A (Sections 12.1, 12.3, 12.4, and 12.5) and TP/2/A/1200/03C (Section 12.14) which verified that interlocks for various system valves functioned properly. The tests were witnessed to verify the following:

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. Latest revision of the test procedure was available and in use by test personne Test prerequisites were me Proper plant systems were in servic The test was performed as required by the procedur Test discrepancies were documented for review and resolutio Adequate coordination existed among personnel involved in the tes Temporary modifications such as jumpers were installed and tracked in accordance with administrative control Section 12.3 of test TP/2/A/1200/02A was not completed successfully. Test discrepancies were written and the licensee is evaluating the proble Additional sections of the above tests (which demonstrated pump performance criteria could be met for various conditions) were witnessed by the Resident Inspector and are documented in NRC Inspection Reports 50-414/85-05 and 50-414/85-0 No violations or deviations were identified in the areas inspected.

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