IR 05000414/1986021

Insp Rept 50-414/86-21 on 860429-0502.No Violations or Deviations Noted.Major Areas Inspected:Maint Activities, Preoperational Test Results,Precritical Testing & Previously Identified Inspector Followup Item

ML20197J798
Person / Time
Site:	Catawba
Issue date:	05/13/1986
From:	Jape F, Larry Nicholson, Matt Thomas NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20197J786	List: IR 05000414/1986021 ML20197J784
References
50-414-86-21, NUDOCS 8605200174
Download: ML20197J798 (4)

Text

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A UNITED STATES

[9 trugjo NUCLEAR REGULATORY COMMISSION

.[ n REGION 11 g,

j 101 MARIETTA STREET. t ATLANTA. GEORGIA 30323

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Report No.: 50-414/86-21-Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket No.: 50-414 License No.: NPF-48 Facility Name: Catawba Unit 2 Inspection Conducted: April 29 - May 2, 1986 Inspectors: C *

w,,_ ne4_, 8-/8-[d M. Thoma's Date Signed fCfw{k L. NicholsoW n S-/3-ff Date Signed Approved by: /

F. Jape, Section Chief (/ / Date Signed

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, Test Programs Section, Engineering Branch Division of Reactor Safety

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SUMMARY Scope: This routine, unannounced inspection - involved reviewing the areas of-maintenance activities, preoperational test results, precritical testing and a previously identified inspector-followup, ite Results: No violations or deviations were identifie . %

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REPORT DETAILS Persons Contacted Licensee Employees

• J. W. Cox, Technical Services Superintendent t *C. L. Hartzell, Ccmpliance/ Compliance Engineer

• J. A. Kammer, Performance / Unit 2 Test Engineer P. G. LeRoy, Compliance / Licensing Engineer

• F. P. Schiffley, II, Compliance / Licensing Engineer

• G. Smith, Maintenance Superintendent

• W. L. Turbyfill, IAE/ Coordinator i

Other licensee employees contacted included test coordinators, engineers, l technicians, operators, security office members and office personne '

NRC Resident Inspectors *P. H. Skinner, Senior Resident Inspector

• P. K. VanDoorn, Senior Resident Inspector

• Lesser, Resident Inspector I

• Attended exit interview Exit Interview The inspection scope and findings were summarized on May 2, 1986, with those persons indicated in paragraph 1 above. The inspectors described the areas inspected and discussed the inspection findings. No dissenting comments were received from the . licensee. The licensee did not identi fy as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items l

Unresolved items were not identified during the inspectio ,

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2 Independent Inspection - Maintenance (62702)

Maintenance activities associated with the #2 Turbine Driven Auxiliary Feedwater Pump were observed during the inspection period. Inadequate pump discharge flow detected while performing PT/2/A/4250/03C, Auxiliary Feedwater Pump #2 Performance Test, resulted in the disassembly and inspection of valves 2CA-20 and 2CA-181 per Work Requests 4971 PRF and 4980 PRF, respectively. The low flow condition required this maintenance to be performed in accordance with action item a. of Catawba Technical'

Specification 3.7.1.2 as discussed in the resident inspector report (414/86-22). The inspectors witnessed portions of the valve maintenance to verify that proper administrative, material and cleanliness controls were utilize Appropriate system isolations were obtained and operational personnel were aware of the maintenance activit The licensee stated that acceptable discharge flow was obtained subsequent to cleaning and reassembly of the above valve No violations or deviations were identified in the areas inspecte . 'Preoperational Test Results Verification (70329)

In Attachment 2 of DPC's status letter for fuel loading (dated January 24, 1986), all of the preoperational (preop) tests that were not expected to be complete by fuel load were liste Justifications and the modes of operation where the test would be completed was also listed. The testing to be completed before initial criticality was reviewed and discussed with licensee personne Preop test TP/2/A/1600/068, Steam Generator Steam Line Pressure Control Functional Test, was in progress during this inspectio Preop tests TP/2/B/1200/09, Boron Thermal Regeneration; and TP/2/B/1350/17E, 6.9 KV Auxiliary Power Fast / Delay Transfer, will not be completed prior to initial criticality as stated in the lette The licensee stated that justification for not completing these two tests will be addressed in a revision letter to the NRC. The inspectors verified that other tests listed in Attachment 2 which were to be completed by initial criticality had been complete No violations or deviations were identified in the areas inspecte . Precritical Test Procedure Review / Witness (72564, 72302)

The inspectors reviewed precritical test TP/2/A/2600/07, Rod Cluster Control Assembly Drop Time Tes The procedure was reviewed to veri' that:

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FSAR commitments have been included,

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Rod drop time acceptance criteria is as specified in the Technical Specification,

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Correct prerequisites were identified, -

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Drop testing of each rod is performed with no flow and full flow in both the cold and hot plant condition The inspectors witnessed portions of both TP/2/A/2600/07 and TP/2/B/2600/06, Full Length Control Rod Drive Mechanism Timing Test to verify that:

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- Appropriate revisions of the procedures were available and in use by test personnel,

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Test prerequisites were met,

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Personnel involved in the tests were briefed prior to beginning the tests,

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Proper plant systems were in service,

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The tests were performed in accordance with requirements,

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Adequate coordination among personnel involved in the test,

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Test data were collected and recorded in the proper manne No violations or~ deviations were identified in the areas inspecte . Followup on Previously Identified Inspection Findings (92701)

(Closed) Inspector Followup Item 414/86-14-01, concerning guidance for correcting in process procedure documentation error Station Directive 4.2.1, Development, Approval, and Use of . Station Procedures, has been revised (Rev. 21) to provide specific guidance for correcting mistakes after the procedure is in use. This includes prohibiting the use of " white out" to correct mistakes. This item is considered close b I

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