IR 05000482/1987002

Insp Rept 50-482/87-02 on 870112-16.No Violations or Deviations Noted.Major Areas Inspected:Document Control Program & Startup Physics Testing

ML20211E441
Person / Time
Site:	Wolf Creek
Issue date:	02/09/1987
From:	Hunnicutt D, Greg Pick, Stewart R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20211E426	List: IR 05000482/1987002 ML20211E420
References
50-482-87-02, 50-482-87-2, NUDOCS 8702240313
Download: ML20211E441 (4)

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report; 50-482/87-02 License: NPF-42 Docket: 50-482 Licensee: Wolf Creek Nuclear Operating Corporation P. O. Box 411 Burlington, Kansas 66839 Facility Name: Wolf Creek Generating Station Inspection At: Burlington Kansas Inspection Conducted: January 12-16, 1987 Inspectors: [N) #

G. A. Pick, Reactor Engineer, Operations

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Section, Reactor Safety Branch bk M R. C. Stewart, Reactor Inspector, Operations

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[)Q Section, Reactor Safety Branch Approved: b jdM# .1/7/77 D. M. Hunnicutt, Chief, Operations Section, Date '

Reactor Safety Branch Inspection Summary Inspection Conducted January 12-16, 1987 (Report 50-4G2/87-02)

Areas Inspected: Routine, unannounced inspection of document control program and startup physics testin Results: Within the areas inspected, no violations or deviations were identifie pg2240313870217 O ADOCK 05000482 PDR

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DETAILS

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. Persons Contacted

~ Wolf Creek Nuclear Operating Corporation

• G. D. Boyer, Plant Manage *G. Rathbun, Manager, Management Systems

• W. J. Rudolph, II, Manager. Quality Assurance (QA)

• C..E. Parry, Superintendent, Quality _ Engineering

• M. G. Williams, Superintendent of Regulatory, Quality, and Administrative Servicos

• W. M. Lindsay, Supervisor, Quality Systems

• C. J. Hoch, QA Technician P. Adam, Reactor Engineering E. McDugall, Document Administration Administrator NRC

• J. E. Cummins, Senior Resident Inspector

• B. L. Bartlett, Resident Inspector

• D. M.- Hunnicutt, Section Chief

• R. C. Stewart, Reactor Inspector

• G. A. Pick, Reactor Engineer-

• Attended exit intervie The NRC inspectors also interviewed other licensee personne . Document Control The objective of this area of inspection was to ascertain whether the licensee had implemented a QA program related to document control that conformed with Technical Specifications (TS), regulatory requirements, commitments in the final safety analysis report (FSAR) and applicable industry guides-and standard During the inspection, the NRC inspector was provided a " walk-through," by the licensee, of the Wolf Creek Nuclear Operating Cooperation (WCNOC)

Configuration Status Accounting Records System (CSARS) which is the project-wide data base controlling system established.for the generation, receipt, release, control, and distribution of document The system maintained current updated master indices for drawings, manuals. Technical Specifications, procedures, and vendor documents. Also included were: the mechanism for issuance, current revisions and the affected documents, distribution, and document control identifie The NRC inspector conducted an independent review of management and administrative procedures verifying assignments and responsibilities for

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administrative controls incorporated within the CSAR syste Procedures included in this review were:

KGP-1150, " Control of WCNOC Documents" KGP-1132, " Configuration Identification" KP-1034, " Drawing Control" KP-1044, "FSAR" KP-1032, " Distribution Control System" ADM-07-100, " Preparation, Revision, Approval and Distribution of WCGS Procedures" ADM-07-407, "WCGS Document Control" ADM-01-001, " Introduction to WCGS Procedures" QAP-6.1, " Maintenance of Controlled Documents" QP-613, "QA Branch Control of Safeguards Information" ADM-01-045, " Document Control, Supervisors Duties and Resposibilities" In addition, the NRC inspector selected ten recently revised documents from CSAR master indices (three procedures, three drawings, and four P& ids) to verify copies at receipt work stations were consistent with the current master indices. Departments visited included operations, document control, plant safety review committee, and the control roo No violations or deviations were identifie . Startup Physics Testing Moderator Temperature Coefficient (MTC) Determination The Wolf Creek Generating Station (WCGS) determined the isothermal temperature coefficient (ITC) and subsequently, obtained the MTC by subtracting the doppler coefficient from the IT The licensee procedure utilized to determine the isothermal temperature coefficient was RXE 01-002, Revision 0, " Reload Low Power Physics Testing." The NRC inspector reviewed the completed procedure data and the associated strip charts. The MTC determination met the frequency prescribed by TS 3.1. Prior to conducting the test, the plant was stabilized with control rod positions, boron concentrations and reactor coolant system (RCS)

temperature and pressure verified to be within established limit The RCS heatup and cooldown rates were such that the RCS remained isothermal for the duration of the measurement. The MTC was calculated correctly and within the limits established by T c

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Control Rod Worth Measurements The NRC inspector reviewed completed Procedure RXE 01-002, Revision 2 and the associated strip charts to determine the adequacy of the licensee's control rod worths and boron endpoint value The licensee ensured before starting the test that: the neutron monitoring system was operational; the reactivity computer was calibrated; chemistry support was available to sample both the RCS and the pressurizer; the reactor was critical at hot zero power; and the control rod banks were in their initial position A maximum band on reactor power was determined and, subsequently, maintained in the allowable range during conduct of the test. Proper overlap and/or no overlap conditions were observed during testin Between each control rod bank worth determination, the RCS was stabilized with control bands observed for RCS temperature and pressure. A limitation on the boron dilution rate was determined by a calculation which limited dilution in the range of 300 to 500 pcm/hr. The control bank worths were in agreement with design as delineated in Section 8 of RXE 01-002, Revision .The NRC inspectors reviewed Procedure RXE-01-002, Revision 0, for adequacy and completeness and determined it met the requirement No violations or deviations were identifie . Exit Interview The NRC inspectors met with the personnel denoted in paragraph 1 on January 16, 1987, and summarized the scope and findings of the inspection.