United States Nuclear Regulatory Commission - Protecting People and the Environment


ACCESSION #: 9712240065



                                             Illinois Power Company

                                             Clinton Power Station

                                             P.O. Box 678

                                             Clinton, IL 61727

                                             Tel 217 935-5623

ILLINOIS                                     Fax 217 935-4632

  POWER

An Illinova Company                          John G. Cook

                                             Senior Vice President



                                             U-602894

                                             4F.140



                                             December 18, 1997



Docket No.  50-461                           10CFR21.21



Document Control Desk

Nuclear Regulatory Commission

Washington, D.  C.  20555



Subject:  10CFR21 Final Report 21-97-042:

          Discrepancies Between General Electric Boiling Water Reactor

          Design Requirements Documents and System Vendor Manuals



Dear Madam or Sir:



     Illinois Power (IP) notified the NRC in 10CFR21 Interim Report 21-

97-042 (IP letter U-602855) dated October 29, 1997, that an evaluation

under 10CFR21 was in progress regarding discrepancies between the General

Electric (GE) Boiling Water Reactor (BWR) design requirements and system

vendor manuals.  The evaluation has been completed and IP has concluded

that this issue is not reportable under the provisions of 10CFR21.



     The interim report stated that on August 21, 1997, IP identified a

discrepancy between the GE BWR design requirements 22A5604, "Turbine-

Generator Control Requirements GE-Nuclear Energy Division," and the field

line-up instructions contained in GE vendor manual K2804-0007C, "GEK-

64903, Volume III, Steam Turbine-Generator (EHC and TSI Section)." The

specific discrepancy identified was a difference between the GE BWR

Design Requirements document and the system vendor manual for the

specified closing rate of the turbine control valves.  Condition Report

(CR) 1-97-08-183 was initiated to track an investigation of this issue.



     On August 27, 1997, during investigation of CR 1-97-08-183, IP

engineers determined that conflicts may exist between other GE BWR design

requirements documents and the system vendor manuals.  Condition Report

(CR) 1-97-08-303 was initiated to track an investigation of this issue.

The design document discrepancy issue was determined to be potentially

reportable under the provisions of 10CFR21 on September 2, 1997.



                                                  U-602894

                                                  Page 2



     The scope of the generic issue involved documents supplied by GE

under specification K2801 which define the requirements for interface

between GE supplied equipment and equipment supplied by others.  The

Architect-Engineer (AE) for Clinton Power Station was responsible for

identifying specific requirement specifications and including them in

purchase specifications for the equipment suppliers.



     IP has concluded that this issue is not reportable under the

provisions of 10CFR21.  The basis for this conclusion is the review of

the AE's program for controlling this process.  Additionally, the AE's

program was previously audited by GE.  To provide further confidence of

program effectiveness, IP reviewed a sample of GE requirements for

safety-related or Technical Specification-related equipment and did not

identify any failures of vendor supplied implementing drawings to meet

the GE design requirements.  The AE's program is considered to have been

effective in identifying specific requirement specifications and

including them in purchase specifications for the equipment suppliers.

Further, the specific discrepancy between the GE BWR Design Requirements

document and the system vendor manual for the specified closing rate of

the turbine control valves would have no impact on a safety function and

therefore would not create a substantial safety hazard if it had gone

uncorrected.



     Additional information about this issue may be obtained by

contacting W. L. Shurlow, Engineering Projects, at (217) 935-8881,

extension 3223.



                                        Sincerely yours,



                                        J. G. Cook

                                        Senior Vice President

RSF/krk



cc:  NRC Clinton Licensing Project Manager

     NRC Resident Office, V-690

     Regional Administrator, Region III, USNRC

     Illinois Department of Nuclear Safety

     INPO Records Center

     General Electric

     Sargent & Lundy



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