View source for RBG-38-078, Forwards Rev 6 to Pump & Valve Inservice Testing Plan for River Bend Station First 10-Yr Insp Interval

{{Adams
| number = ML20128D903
| issue date = 02/01/1993
| title = Forwards Rev 6 to Pump & Valve Inservice Testing Plan for River Bend Station First 10-Yr Insp Interval
| author name = Odell W
| author affiliation = GULF STATES UTILITIES CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000458
| license number = 
| contact person = 
| document report number = RBG-38-078, RBG-38-78, NUDOCS 9302100262
| package number = ML20128D908
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
}}

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L GULF STATES                                 UTELITIES : COMPANY                                         E RIVER Bf hD 61ADON . POSI OFHCE SOX 220               ST FRANCISvtLLE, LOutSIANA 70776 ARE A COM 604               635 6004     346 8061 Febmary 1,1993 RBG-38,078 File Nos. G9.5, 224.6')0 l
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 River Bend Station .- Unit 1 Docket No. 50-458 Please find enclosed Gulf States Utilities Company's (GSU) Revision 6 of the River Bend Station (RBS) Pump and Valve Inservice Testing Program Plan (Plan) for your review _ This revision is submitted as a follow-up to the letter fmm W.
H. Odell to the NRC dated February 11,1992. In that letter GSU requested an                                         ,
extension of certain interim relief approvals. The NRC gmnted relief in the safety evaluation (SE) accompanying a letter from S. C, Black to J. C. Deddens dated July 16, 1992.
Revision 6 of the Plan is structured so as to provih a clear and understandable description of the Pump and Valve Inservice Testing Program (Program) at RBS.
Some of the changes to the structure include: a Basis (Section 1.1) for the exclusion of components to the Prograhi; a summary of pump inservice testing positions including NRC Generic Letter (UL) 89-04, position 8 (Section 2.4);
and a summary of valve inservice test positions including NRC GL 89-04, position 5.
Also, an inspection schedule and description of the non-intrusive testing pmgram for check valves has been added to valve request for relief (VRR)-24.
VRR-44, .which a ddresses the residual heat removal relief valve for steam condensate supply to reactor com isolation cooling has been converted to an administrative item to delineate that the testing of this valve will no longer be performed. This valve is permanently isolated from any high pressure source.
One new request for relief (RR), VRR-65, which addresses the method for testing of the containment sample return check valve is also included for your
   ' consideration. . This valve cannot be exercised in the reverse closure direction during normal plant operation since it would require isolating the line for a period of time beyond that allowed bp the limited condition for operation in the RBS Technical Specifications.                            -9302iN 2 E 30201
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                                                          'PDR ADOCK-05000458'                              .
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1 An interim RR, VRR-I-01, which addresses' the testing of the drywell to containment interface valves (VF013A/B and VF017A/B) is also included for your consideration. A letter fmm W. H. Odell to the NRC dated November 17, 1992, explained that at present, it is not possible to test these check valves during-the drywell bypass leakage test due to system configuration. Radiograph testing of these valves during RF-4 verined closure and provided adequate assurance that the valves will perform their drywell isolation function as designed.               A modification request has' been generated to add three test connections with isolation valves to enable ' leak rate testing of these check valves. Upon completion of this modification the interim RR will be rescinded.
If you have any questions or require additional infonnation, please contact Mr.
L.L. Dietrich of my staff at (504) 381-4866.
Sincerely, W.H. Odell Manager - Oversight -
River Bend Nuclear Group Enclosure cc:     U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011.
NRC_ Resident Inspector P.O. Box 1051 St. Francisville, LA 70775 Mr. E.T. Baker U.S. Nuclear Regulatory Commission :                                         4
           '11555 Rockville Pike-Rockville, MD 20852 Ms. P. Campbell-U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852
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