IR 05000382/1986012

Insp Rept 50-382/86-12 on 860512-0822.No Violations or Deviations Noted.Major Areas Inspected:Ae Design Control & Station Mod Programs & Station Mod Implementation Activities

ML20211P950
Person / Time
Site:	Waterford
Issue date:	12/04/1986
From:	Hunnicutt D, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20211P864	List: IR 05000382/1986012 ML20211P860
References
50-382-86-12, NUDOCS 8612190167
Download: ML20211P950 (6)

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APPENDIX U.S. NUCLEAR REGULATORY COMISSION

REGION IV

NRC Inspection Report: 50-382/86-12 License: NPF-26 Docket: 50-382 Licensee: Louisiana Power & Light Company N-80 317 Baronne Street New Orleans, Louisiana 70160 Facility Name: Waterford Steam Electric Station, Unit 3 Inspection At: Taft and Kenner, Louisiana Inspection Conducted: May 12-16, June 30 through July 3, July 14-18, and August 18-22, 1986 Dr Inspector: e M/ d /

R. C. Stewart, Reactor Inspector, Operations Dat6 /

Section, Reactor Safety Branch Approved: ph h2'

D. M. HtTntficutt, Chief, Operations Section

/.2/f/N Dat'e /

Reactor Safety Branch Inspection Summary Inspection Conducted May 12-16, June 30 through July 3, July 14-18, and August 18-22, 1986 (Report 50-382/86-12)

Areas Inspected: Routine, unannounced inspection of licensee's and architect engineers (A/Es) design control programs, station modification program, and the

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review of station modification implementation activitie Results: Within the four areas inspected, no violations or deviations were identifie PDR O ADOCK 05000392 PDR

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DETAILS Persons Contacted Principal Licensee Employees

• R. P. Barkhurst, Plant Manager

• S. Alleman, Assistant Plant Manager, Technical Services

• A. S. Lockhart, Site Quality Manager

• P. V. Prasankumar, Technical Support Supervisor R. V. Seidle, Engineering and Nuclear Safety '

• K. L. Brewster, Onsite Licensing T. F. Gerrets, Corporate QA Manager M. C. Moody, Department Assistant W. J. Baldwin, Operations QA Supervisor P. N. Backes, Operations QA Manager N. S. Carns, Assistant Plant Manager, Operations and Maintenance

• G. E. Wuller, Onsite Licensing Coordinator

• Denotes those attending the exit interview on August 22, 198 The NRC inspector also interviewed other licensee personne . Design Control Program The objectives of the inspection were to ascertain whether the licensee is implementing a QA program relating to the control of design changes and modifications that are in conformance with regulatory requirements, commitments in the application, and industry guides and standard The inspection included the determination that procedures have been established for control of design and modification change requests that include:

Method for initiating a design change reques *

Design Change Request Control Form, with provisions for documenting-completion of required reviews, evaluations, and approvals prior to implementing the chang Method for assuring that proposed change does not involve an unreviewed safety question as described in 10 CFR Part 50.59 or a change in the Technical Specifications.

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Independent design verification.

! Independent auditing of design activitie Design interfaces.

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Trainin Drawing / document contro Installation records and as-built contro Test requirement With regard to the above, the NRC inspector conducted a review of ANSI N45 2.11-1974; Section 17.2.3 of the FSAR; Section 6.5 of the Technical Specifications; and 10 CFR Part 50.59; in comparison with the contents of the following licensees design control program administrative and implementing procedures: Nuclear Operations Management Manual, Chapter VII, Section 3, Revision PE-2-006, Revision 7, Administrative Procedure Plant Engineering Station Modificatio QP-003-001, Design Contro PMP-002, Document Contro PMP-301, Control and Assessment of Station Modification Request PMP-302, Preparation, Control, Processing, and Review of Station Modification Package PMP-303, Performance of Design Verificatio PMP-304, Modification Project Closecu QP-011-001, Test Contro UNT-1-003, Procedure Development, Review, and Approval; Change and Revision; and Deletion, UNT-5-002, Condition Identification and Work Authorization (CIWA). PE-2-005, Plant Engineer CIWA Processin HP-1-101, ALARA Program Implementation, PE-2-014, Equipment Environmental Qualificatio UNT-1-004, Plant Operation Review Committe PMP-307, Performance of Calculation PMP-308, Production and Review of Design Document . . . .

During the review, the NRC inspector observed that the principle design change / modification controlling administrative procedure is PE-2-006,

" Plant Engineering Station Modifications." The responsibilities and requirements for the Nuclear Operations Department to control modifications of Waterford 3, including changes to approved designs, appeared to be well delineated and the program elements indicated conformance with regulatory requirement During the above review, the NRC inspector observed that, although LP&L initiates and has overall control and responsibility for station modifications, most of the design functions are accomplish through the designated A/ In view of the significant A/E involvement in the design functions, the NRC inspector conducted a corresponding review of the design control program being implemented by A/E at the Kenner, Louisiana facility. The review included the following principle A/E program procedures:

E-69-W3, " Protect Preparation of Station Modification Packages."

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E-21-W3, " Preparation of Specification."-

E-30-W3, " Preparation of Calculations."

E-45-W3, " Processing FUSAR Change Requests."

E-74-W3, " Preparation of Retrofit Change Sketches."

• E-76-W3, " Interdisciplinary Design Review and Independent Design Verification."

E-86-W3, " Procurement of Engineered Materials."

E-11-W3, "As-built Documentation."

The overall licensees /A&E programmatic implementing procedure relating to the control of design changes and modifications appeared to be in conformance with regulatory requirements, commitments in the application, and industry guides and standard No violations or deviations were identifie . Design Change Program Implementation During the inspection, the NRC inspector selected station modification package (SMP)84-257, "Radwaste Liquid Storage Capacity Addition," for revie The modification provides an additional radwaste storage tank capacity of

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40,000 gallons located in the north end of the dry cooling tower are .

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It was observed by the inspector that the modification has been the only major modification at the facility since initial startup and is being installed through a series of six design revisions (storage tank installation was scheduled for November 1984 through December 1986).

The system design is based on meeting the regulatory requirements delineated by Regulatory Guide 1.143, " Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants," Revision 1, 197 During the review, the NRC inspector examined the seven design packages (Revision 0-6) in order to identify LP&L program procedural implementation and technical content. LP&L reviews and approvals notably included:

Independent Design Verificatio '

Design Review Guideline Nuclear Safety Review Checklist Safety and Environmental Review ALARA Reviews and Comment Fire Protection Review *

10 CFR Part 50.59 Review CFR Part 50.49 Review PORC Reviews and Approval Acceptance and Test Requirement QA Review The NRC inspector concluded that the SMP 84-257 design packages appear to meet the implementing requirements established by LP&L Procedure PE-2-006, Revision 7. " Plant Engineering Station Modifications."

The NRC inspector also conducted a sampling review of SMP-107,

" Supplemental Fuel Pool Heat Exchanger Modification" package.

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In addition, the NRC inspector conducted system walkdowns of both the l radwaste system modification and the fuel pool supplemental heat exchanger additio During the walkdowns, the NRC inspector reviewed drawings, installation instructions, specifications, and procedures. Although the radwaste system modification is essentially complete, the NRC inspector reviewed the storage tank installation procedure (Chicago Bridge and Iron (C8&I))

including the CB&I manufactures data report, dated January 4,1985, which

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included inspection requirements and inspection and test sequences for

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tank components (ASME Section VIII, Division 1), weld procedure specifications, weld procedure qualification records, and welder qualification record During the walkdown of the supplemental fuel pool heater exchanger installation, the NRC inspector observed that the heat exchanger had been installed and work was proceeding with the installation of the two 12-inch component cooling system (CC) lines and two 10-inch fuel pool cooling and

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purification (FS) lines (inlet and outlet lines for the backup spent fuel pool (BSFP) heat exchanger). The NRC inspector examined QC weld control documentation, FS-SM-107-M3 relative to field welds FW-4 and FW-37A in conjunction with LP&L Procedure MM-1-056, " Weld Test and Inspection and Visual Inspection Requirement Delineated in AWS D1.1." In addition, observations were made of the work activities in progress relative to preparations of installation for the heat exchanger concrete shield wall (seismic Category 1 concrete EBASCO Specification LOV-3988.400.)

During the inspection, the NRC inspector reviewed the most recent station design / modification QA audit conducted by the LP&L QA audit team during the period August 22 through September 16, 1985. (File Folder SA-W3-QA-85-41)

The NRC inspector observed that, although open findings were identified and corrected, audit finding indicated that nuclear operations had in place, an effective program and organization to maintain control of unit design and modifications to that desig No violations or deviations were identifie . Exit Interview The NRC inspector met with the licensee representatives during each of the inspection periods to provide the licensee with inspection updates. A final inspection closeout exit was conducted on August 22, 1986. The NRC senior resident inspector attended the closecut exit. The NRC inspector sumarized the scope and findings of the inspectio __ _ , __ _