IR 05000483/2003011

IR 05000483-03-011, on 08/18-22/2003; Union Electric Co., Callaway Plant, Plant Design Pilot, Enclosure 2

ML032400023
Person / Time
Site:	Callaway
Issue date:	08/27/2003
From:	Marschall C NRC/RGN-IV/DRS/EMB
To:	Randolph G Union Electric Co
References
IR-03-011
Download: ML032400023 (10)

Text

ust 27, 2003

SUBJECT:

CALLAWAY PLANT - NRC INSPECTION REPORT 05000483/2003011

Dear Mr. Randolph:

On August 22, 2003, the US Nuclear Regulatory Commission (NRC) completed an inspection at your Callaway Plant. The enclosed inspection report documents the inspection findings, which were discussed on August 22, 2003, with Mr. R. Affolter and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Based on the results of this inspection no findings of significance were identified.

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/ by RLN for Charles S. Marschall, Chief Engineering and Maintenance Branch Division of Reactor Safety Docket: 50-483 License: NPF-30

Union Electric Company -2-

Enclosure:

Inspection Report 05000483/2003011

REGION IV==

Docket: 50-483 License: NPF-30 Report : 05000483/2003-011 Licensee: Union Electric Company Facility: Callaway Plant Location: Junction Highway CC and Highway O Fulton, Missouri Dates: August 18-22, 2003 Lead C. Paulk, Senior Reactor Inspector, Engineering and Maintenance Branch Inspector:

Inspectors: L. Ellershaw, Senior Reactor Inspector, Engineering and Maintenance Branch T. McConnell, Reactor Inspector, Engineering and Maintenance Branch Accompanying B. Henderson, Reactor Inspector, Engineering and Maintenance Branch Persons: G. George, Reactor Inspector Approved By: Charles S. Marschall, Chief Engineering and Maintenance Branch Division of Reactor Safety

-2-SUMMARY OF FINDINGS IR 05000483/2003011; 8/18-22/2003; Callaway Plant; Plant Design Pilot, Enclosure 2 The NRC conducted an inspection with three regional inspectors. No findings of significance were identified. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 3, dated July 2000.

No findings of significance were identified.

Report Details 1. REACTOR SAFETY Introduction The NRC has undertaken a pilot inspection program to determine if efficiencies or resource savings can be gained by consolidating selected baseline inspection procedures. This inspection report documents the performance of Attachment 71111.DS, "Plant Design - Pilot," Enclosure 2. This enclosure is normally performed using Attachment 71111.17, "Permanent Plant Modifications."

The NRC conducted an inspection to verify that the design basis, licensing basis, and performance capability of risk-significant systems, structures, and components have not been degraded and to verify that modifications performed during increased risk-significant configurations did not place the plant in an unsafe condition. Acceptance criteria used by the NRC inspectors included NRC regulations, the technical specifications, applicable sections of the Updated Safety Analysis Report, applicable industry codes and standards, and industry initiatives implemented by the licensees programs.

1RDS Plant Design (71111.DS)

1RDS2 Enclosure 2: Permanent Plant Modifications a. Inspection Scope The inspectors reviewed the eight design changes listed in the attachment. The inspectors reviewed procedures governing design changes to evaluate the effectiveness of the programs for implementing modifications to risk-significant systems, structures, and components to verify that such changes did not adversely affect the design and licensing bases of the facility.

The inspectors interviewed the cognizant design and system engineers for the identified modifications as to their understanding of the modification packages. The inspectors evaluated the effectiveness of the Callaway Action Request System to identify and correct problems concerning the performance of design changes.

b. Findings No findings of significance were identified.

ATTACHMENT KEY POINTS OF CONTACT Licensee:

R. Affolter, Vice President, Nuclear T. Antweiler, Coordinator, Maintenance Rule D. Carstens, System Engineer A. Gerling, Construction Supervisor G. Harris, Design Engineer T. Herman, Supervisor, Design Engineering T. Herrmann, Superintendent, Nuclear Engineering Steam Generator Replacement and Accident Analysis R. Lamb, General Superintendent, Work Control J. Nurrenbern, Coordinator, Maintenance Rule S. Petzel, Engineer, Regional Regulatory Affairs M. Reidmeyer, Supervisor, Regional Regulatory Affairs T. Schroer, Supervisor, Administrative Support D. Stepanovic, Superintendent, Nuclear Engineering Trchnical Support W. Witt, Plant Manager LIST OF DOCUMENTS REVIEWED Calculations:

NUMBER TITLE REVISION ARC-197 Review Auxiliary Feedwater For An Operating 0 Temperature of 120EF ARC-205 Evaluate Vent Lines in Auxiliary Feedwater Piping 0 EF-31 ESW Orifice Sizing 01, Addenda 1 & 2 EF-45 Acceptance Criteria for Essential Service Water Flow 5 Balance Procedures EF-75 Orifice Sizing Calculation for Flow Restricting EFFO001 0 and EFFO002 Callaway Action Requests (CARs)

200102697 200103014 200306225 200306229 200102775 200306108 200306228 200306230

-2-Design Changes:

NUMBER SUBJECT REVISION 88-1044 Installation of Four Differential Pressure Indicators in the A Essential Service Water System 98-1020 Modify Valves for Hot Shorts A 99-1034 ESW Back-pressure Orifice Change to Resolve the Low A, System Back-pressure FCNs 1-4 00-1020 Installation of Additional Back-pressure Orifice Plates in the A, FCN 1 ESW Headers at the UHS 00-1035 Replace ESW Carbon Steel Pipe with Stainless Steel A 01-1016 Rewire EGHV132 to Close Against High DP A 02-1008 Aux Feed Water Vents A 02-1018 Replace AFPs Discharge Check Valves with Automatic A Recirculation Valves Drawings:

NUMBER TITLE REVISION E-23EG09A Component Cooling Water Containment Isolation Valve 4 M-143-00003 Outline Drawing Concentric Restricting Orifice Plates 16 M-22EF02 Piping and Instrumentation Diagram Essential Service 47 Water System M-22AL01 Auxiliary Feedwater System 24 M-23AL01 Auxiliary Feedwater Pumps Suction Piping 7 M-23AL02 Motor Driven Auxiliary Feedwater Pump A Discharge Piping 1 M-23AL03 Motor Driven Auxiliary Feedwater Pump B Discharge Piping 1

-3-Miscellaneous Documents Procedure Qualification Records for WPS 01008T01; 9, 23, 24, and 25 Preventive Maintenance Packages 690229 690230 690231 P712484 P712744 P712589 Procedures:

NUMBER TITLE REVISION APA-ZZ-00143 10CFR50.59 Reviews 0 APA-ZZ-00600 Design Change Control 22 EDP-ZZ-04015 Evaluating and Processing Requests for Resolution 35 (RFRS [sic])

EDP-ZZ-04024 Configuration Control 16 MTW-ZZ-WP003 Control of Welding Materials 15 MTW-ZZ-WP505 General Welding Specification 6 OTN-AL-00001 Auxiliary Feedwater System 13 WPS 0108T0 Welding Procedure Specification for SMAW and 6 GTAW welding of P1 to P8 Materials Work Requests A199329A A690757 A690759 W196692 A690534A A690757A A690759A W199228 A690756 A690758 C690534 A690756A A690758A