IR 05000327/1987001

Insp Repts 50-327/87-01 & 50-328/87-01 on 870106-08.No Violation or Deviation Noted.Major Areas Inspected:Employee Concerns

ML20207T411
Person / Time
Site:	Sequoyah
Issue date:	02/19/1987
From:	Belisle G, Michael Scott NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20207T405	List: IR 05000327/1987001 ML20207T404
References
50-327-87-01, 50-327-87-1, 50-328-87-01, 50-328-87-1, NUDOCS 8703230545
Download: ML20207T411 (5)

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, . j,y fq) , NUCLEAR RE2ULATORY Cf.MMISSION 1* o REGION il 7 .g 101 MARIETTA STREET, N.W., SUITE 2900

• 2 o ATLANTA, GEORGIA 30323

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Report Nos.: '50-327/87-01 and 50-328/87-01 Licensee: Tennessee Valley Authority 6N38 A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Docket Nos.: 50-327 and 50-328 License Nos.: DPR-77 and DPR-79 Facility Name: Sequoyah 1 and 2 Inspection Conducted: January 6-8, 1987 Inspector:

M. A. Scott Mb A~

Date Signed Approved by: h, h e 7. / 9- W 7 G.'Ti-telisle, 5 ct'on Chief Date Aigned'

Division of Reac o Safety SUMMARY Scope: This routine, announced inspection was conducted in the area of employee concern Results: No violations or deviations were identifie %p2SDO$ 5 f

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REPORT DETAILS Persons Contacted

' Licensee Employees-W. Andrews, Site Quality Manager G. Boles, Maintenance Supervisor L. Bryant, Maintenance Supervisor D. Cowart, Quality Assurance (QA) Supervisor P. Hitchcock, Maintenance Engineer

• J. Kelly, Division of Nuclear Engineering (DNE) Engineer S. Long, Design Basis Reverification Group Engineer M. Martin, Employee Concerns Task Group (ECTG)

• F. Mashburn, Regulatory Compliance

• L. Nobles, Plant Superintendent R. Olson, Modification Manager D. Owens, ECTG Investigator B. Patterson, Maintenance Superintendent

• J. Robinson, Assistant Modification Manager T. Sanders, Maintenance Engineer P. Wallace, Plant Manager Other licensee employees contacted included engineers, technicians, and office personne NRC Resident Inspectors K. Jenison P. Harmon D. Lovelance

• Attended exit interview Exit Interview The inspection scope and findings were summarized on January 8,1987, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail 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 inspectors during this inspectio . Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio .

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2- Unresolved Items s

Unresolved items were not identified during this inspectio . Employee Concerns f

The inspector - examined employee . concern issues during this inspection l perio The 1 specific employee concern element report . identification numbers / titles are MC-40301-SQN, Valve Substitution as Related to Material, Control and MC-40307-SQN, Scrapped Material as Related to Material Contro The inspector discussed these concern specifics and concern evaluation techniques with ECTG and site personnel. The inspector also interviewed the

' investigator who generated ~ these. element. report Additionally, the inspector attended a meeting between the ECTG and NRC, Region II,- personnel regarding ECTG evaluation methodolog The inspector examined the following employee concern site specifics to gain additional clarification: MC-40301-SQN,-Revision 2 This element report concerns a perceived generic . problem of valves being substituted without documentation and drawing changes. The element report concluded that the perceived problem could not be validated / substantiated at Sequoyah. The concern was found to be valid at Watts Bar but was made generic to Sequoya The inspector reviewed the following site procedures and documents:

SQA-134 Critical Structures, Systems, and Components (CSSC) List, Revision 8 SQA-175 Equipment Information System (EQIS), Revision 2 SQM-58 Maintenance History and Trending, Revision 4 i AI-25 Drawing Deviations (Part II), Revision 2 SQEP-30 Control of As Constructed Drawings, Revision 1 SQEP-43 Control of Drawing Deviations, Revision 0 Report No. 2614 Gilbert / Commonwealth, Final Report Technical Review of Sequoyah Nuclear Plant Modifications for Tennessee Valley Authority

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Correspondence Checklist Number 21-86-S-001, Survey Title -

S08-860514-825 Residual Heat Removal System Review, dated-January 30, 1986 Correspondenc Memorandum of February 11, 1986, Subject: . Review-LO4-860218-943 of Auxiliary Control Air (ACA).

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Correspondence Survey Title: Review of Auxiliary Control Air LO4-860224-945 System; survey dates: November 27 - December 20, 1985 The inspector interviewed the ECTG investigator regarding the valve substitution concern finding The inspector also reviewed - the historical package collected by ECTG during the course.of the investi-gation. During the discussion, the . inspector reviewed the investi-gative methodologies and specifics of the result The ' inspector reviewed -the site's available documents which might indicate valve substitution problem In addition to the specific information in the ECTG review, the inspector also reviewed the following documents to determine if they identified improper valve -

substitution:

QA Walkdown Surveys Contractor Reports Various NRC Sources Design Basis Verification (DVB) Walkdown (this was in progress when ECTG performed their review and was not used as part of the ETCG input)

Engineering Change Notice Reverification As Constructed During Deviation Program of AI-25 (Part II)

SQA-134 and 175 These documents did not provide any additional information relative to improper valve substitution since they were not valve specific, consequently, the ECTG review appeared adequat The inspector walked down portions of several piping systems in the plant. A sample of 12 CSSC valves was taken. The information found on the actual valves was compared to drawing requirements without any noticeable problem The sample size was small compared to CSSC valve population, but the valves selected were typical of the CSSC valves not indicated in SQA-13 MC-40307-SQN, Revision 2 This element report concerns a perceived problem with scrap material being issued in safety-related application The element report concluded that the perceived problem could not be validated. The specific concern to Sequoyah (Nuclear Safety Review Staff Report

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SQP-5-004-003) appeared to be adequately investigate The generic issue contained in the element report on the use of scrap material in general during construction up to the present time was evaluated by the inspecto Primary emphasis by the inspector was on construction activities. The ECTG investigator had interviewed ten TVA employees who had been present during plant construction regarding scrap material use. The inspector discussed the element report, the supporting element report investigation package, and the parameters of the concern with the ECTG investigator. The inspector interviewed three additional TVA personnel who had been quality control (QC) inspectors during constructio The inspector's evaluation results were that the concerns could not be substantiate The historical perspective on activities during construction would not support the concerns. The inspector did not followup on corrective actions (ECTG reference CATD 40307-SQN-01) to be carried out by site personnel on aspects of site procedural practice The inspector concluded that the two employee concern element reports were adequate in their investigatio Within these areas no violations or deviations were identified.