IR 05000414/1985061

Insp Rept 50-414/85-61 on 851202-06.No Violations or Deviations Noted.Major Areas Inspected:Licensee Actions on Previous Enforcement Matters & Licensee Mgt of Design Activities

ML20138R547
Person / Time
Site:	Catawba
Issue date:	12/20/1985
From:	Belisle G, Jackson L, Wright R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20138R534	List: IR 05000414/1985061 ML20138R532
References
50-414-85-61, NUDOCS 8512310357
Download: ML20138R547 (7)

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UNITED STATES 1 p pn KEcoq'o, NUCLEAR REGULATORY COMMISSION

.[" ' n REGloN li g ,j 101 MARIETTA STREET, *I ^t ATLANTA. G EORGI A 30323

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Report No.: 50-414/85-61 1 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242

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

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Facility Name: Catawba Unit 2

Inspection Conducted

December 2-6, 1985

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Inspectors: <

L. H./JacksW y 7

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Da'e t-Y [ff Signed l

&W r />l fW R. W? Wri ht',4 / Date/ Signed l Approved by: < v 7" /.A[.4> Td'_

, G. A'.-Belisle, Aning Branch Chief Date Sfgned j Division of Reactor Safety

SUMMARY

Scope

This routine, unannounced inspection involved 74 inspector-hours at corporate headquarters in the areas of licensee actions on previous enforcement matters and licensee management of design activitie Results: No violations or deviations were identified.

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8512310357 851224

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s REPORT DETAILS

' Persons Contacted j Licensee Employees S. Alexander, Supervisor, Design Engineering, Mechanical / Nuclear Divisict(M/ND)

C. Bell, Lead Auditor, Quality Assurance (QA), Audit Division (AD)

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G. Bell, QA Audit Supervisor, AD L. Boyles, Supervisor, Drawing Control, General Services Division (GSD)

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• A. Cobb, Manager, Project Management Division (PMD)

• J. Curtis, QA Manager, Vendors J. Crenshaw, Senior Engineer, Electrical Division (ED)

• L. Davison, QA Manager, Technical _ Services S. Derrick, Supervisor, Central Records, GSD

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R.. Dover, Technical Assistant, ED J. Frye, QA Manager, AD R. Gamberg, Design Engineer, M/ND

• G. Grier, Corporate QA Manager -

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T. Harrall, Supervisor, Design Engineering, ED

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J. Harrington, Design Engineer, ED W. Hogan, Engineering Associate, Civil / Environmental Division (C/ED)

, W. Houston, Senior Engineer, PMD D. Kulla, Supervisor, Design Engineering, C/ED

• T. Mathews, Manager, Duke Projects,- PMD

• Medlin, Design Technical Supervisor

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I. Pearce, Civil Engineering, Principal Engineer, C/ED

! *C. Robinson, Senior QA Supervisor, Vendors, QA i T. Smith, Engineering Associate, C/ED i T. Wyke, Chief Engineer, M/ND Other: licensee employees contacted included engineers, technicians, and  ;

office personne ,

• Attended exit interview

, Exit Interview

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The inspection scope and findings were summarized on December 6, 1985, with- ~-

those persons indicated in paragraph I abov The inspector described the areas inspected and discussed .in detail the inspection' findings. No dis-

! senting comments were received from the licensee. The licensee did not l

' identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.

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_._________________.__________________________.__.-______._________._____._______.____.m________________.__.____.___.m____m____

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3. Licensee Action on Previous Enforcement Matters (92702)

(Closed) Severity Level IV Violation (50-414/85-08-01): Failure to Audit Vendors Trienniall The licensee response dated May 25, 1985, was considered acceptable by Region II. The inspector conducted interviews with Senior Managers in the vendor . inspection and audit groups and determined that the licensee is actively implementing their commitment to audit vendors. The inspector reviewed documents which confirmed that they have audited approximately 65 vendors and only five vendors remain to be audited to meet the January 1, 1986 commitmen The inspector selected two audits at random and verified that adequate essential elements were being audited by the license The inspector concluded that the licensee had determined the full extent of the ' violation, taken action to correct current conditions, and developed corrective actions needed to preclude recurrence of similar problem Corrective actions stated in the licensee response have been implemented.

4. Licensee Management of Design Activities (35060) Design Assurance Duke Power Company (DPC) has assigned overall responsibility for design of the' Catawba Nuclear Station to -its Design Engineering Department (DED) and responsibility for quality assurance of design to its Quality Assurance Department (QAD).

The inspectors discussed the organization of the DED and the QAD with responsible licensee engineers. DPC organizational staffing and responsibility statements are documented in licensee procedure The engineering QA program contains procedures and instructions for implementation and assurance of design control during the various phases of design activities. These procedures assure the design is performed in accordance with approved criteria and that deviations and nonconformances are controlle The OED QA procedures listed below were examined to veri fy the systematic management of the Duke design process and to assure that the QA program met requirements:

Number, Revision Title PR-101, R24 Engineering Calculations PR-130, R18 (

Engineering Drawings PR-170, R4 Design Specifications PR-201, R25 Variation Notices PR-202, R9 Design Nonconformance

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Number, Revision Title (Continued)

PR-301,.R24 Procurement Specifications PR-901, R28 Document Control PR-931, R9 Design QA Recordt Collection, Maintenance, and Storage Personnel Interviews The inspectors interviewed managers from DED and QAD to ascertain the following:

Their understanding of design verification;

. Their interface with design assurance and QA; Their implementation of design verification; Neans of dispositioning design verification findings; and

, Criteria for competency of design verifiers.

i Discussions with managers revealed that each safety-related design

document, such as calculations, specifications, purchase requisitions, 1 or drawings are prepared by qualified individuals in DED. This indi-vidual specifies and includes the appropriate codes, standards, and SAR

. commitments within the design documents. Each design document is then

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checked by another individual qualified in the same discipline and is reviewed for concept and conformity with applicable codes and standard The document is either approved by the chief engineer or his designee j who has overall responsibility for the design function. If the docu-ment involves coordination with other engineering di' visions, then

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it will either be reviewed by the chief engineers or authorized representatives from their respective division Conflicting design verification findings are generally resolved by the next level of supervision. However, individuals assigned to perform the check and review of a nuclear safety-related document have full and independent

, written authority to withhold ' approval of the document until every question concerning the work has been resolved. If required, problem resolution can be escalated to the VP, DED by individuals in design engineering or escalated to the corporate QA manager by individuals in Q The minimum requirements for engineers, designers, and technical

' assistants within DED are delineated in DPC's DED Job Classification ~- -~

-Description Manua The managers interviewed by the inspectors appeared knowledgeable in the areas of design and the design verification process.

4 Design Engineers Interview - Designer Various design engineers and engineering associates from the Catawba

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Projects, Electrical, Civil / Environmental, and Mechanical / Nuclear Design Divisions were interviewed to determine their understanding of implementing procedures for the control of the design proces k

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The following design documents prepared by these individuals were examined by the inspectors and discussed with their authors:

Procurement Specification CNS 1361.00-00-0005, Rev. 6, Electrical Penetrations, Instrumentation, and Control Design Change Authorization DCA-EPSP-011 Effecting Train A of Drawing CN-2702-02.01, Rev. 7, One Line Diagram 4160 Volt Essential Auxiliary Power System (EPC) 4160 Volt Switchgear No. 2 ETA Calculation CNC 1139.14-23-0001, Rev. 34, Waste Evaporator Concentrate Sample Cooler and Heat Exchange Platform Calculation CNC 1139.14-00-0010, Rev. 2, Auxiliary Building -

Radiation Shield Wall at El. 59 Calculation CNC 1223.19-00-0008, Rev. O, Nuclear Water System, Train A & B, Technical Specification Allowable Leak Rates Calculation CNC 1223.03.00-0005, Rev. O, Pressurized Power Operated Relief Valve Set Point Calculation Preparers of the above selected design documents were asked by the inspectors to discuss their specific involvement in the development, handling, and selection of the following design attributes:

Design inputs, received, and established; Design assumptions, received, and established; Design interface; Design documents used to verify design inputs; and Handling design change The inspectors confirmed that the design engineers interviewed were 7ualified, employed approved design procedures, utilized acceptable design criteria and specifications, maintained . satisfactory design interface with other- disciplines / organizations when necessary, implemented design changes appropriately, and had a good understanding of their role in the implementation of the design proces d. Design Verification The inspectors interviewed design verifiers and confirmed that they understood their responsibilities in the design verification process and that they had the required independence to perform their job. The inspectors examined recent designs for which these personnel served as design verifiers, and reviewed qualifications which authorized them to perform design verifications. All verifiers interviewed were qualified and competent to perform their assigned functions, e

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e. Design Interface - Review of New Contract The inspectors selected a contract for the Reactor Building Electrical Penetration Assemblies to confirn. that there was objective evidence of effective interface contro Specification CNS-1361.00.00.0005 had been certified by a Registered Professional Engineer. The specifica-tion was incorporated into the bid package. Conax Corporation was the successful bidder. The contract required the penetrations to be in accordance with ANSI N45.2.2-1972, IEEE 317-1976, IEEE 383-1974, and Duke Power Company's specification CNS 1393-00-0001, Revision 4, for seismic qualification A design pressure of 72 psig at 327 F was specified. The specifications for the penetrations required them to be qualified for a radiation dose level of 1x10' RAD Evidence that similar penetrations had been qualified to a more harsh environment than required for Catawba penetrations were on file at DPC. In fact, the inboard ends of the Test Data Bases One and Two were subjected to a gamma radiation dose rate of 2.04x10' rads / hours for a period of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> yielding an average integrated total dose of 2.238x10' rads in ai Interface documents were transmitted by letters between Conax and DP Review and approval were formally documented.

i f. Design Document Control and QA Records DPC QA Topical Report, Section 17.1.17, specifies the licensee's program commitments for quality record The topical report commits to ANSI N45.2.9-197 Duke Design Engineering Procedures PR-901 and PR-931 provide instructions for document control and design 0A records collection, maintenance, and storage. Supervision from the GSD explained their records responsibilities and duties and how they implement the above mentioned procedures. Particular attention and questions were directed toward the licensee's document control measures concerning the interface of quality documents between DPC corporate design, the Catawba site, and manufacturers / suppliers. Several design documents that were examined and identified in paragraph 4.c were requested and retrieved from the microfiche files without problem g. Audit Reviers The following Design Engineering Department audits performed by the QA Audit Divisiot were examined by the inspectors to verify that the scope- -- -

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and depth of tre subject audits extended to all applicable Appendix B

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' elements, that sudit team members were qualified, that audit findings were reported to upper management and the organizations audited, that corrective actions were being initiated, and that there was followup and reaudit by QA as necessary:

Audit DE-85-1 (CD) Civil / Environmental Division of Design Engineer Department (DED) . _ _ _ _ _ _ _ _ _

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Audit DE-85-2 (ED) Electrical Division, DED Audit DE-85-4 (MD) Mechanical / Nuclear Division /DED Audit DE-85-6 (GS) General Services Division, DED Within these areas, no violations or deviations were identified.