View source for RBG-25290, Forwards Rev 3 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval, Per 10CFR50.55a(q). Rev Summary Also Encl

{{Adams
| number = ML20209G279
| issue date = 01/30/1987
| title = Forwards Rev 3 to Pump & Valve Inservice Testing Plan,River Bend Station,First 10-Yr Insp Interval, Per 10CFR50.55a(q). Rev Summary Also Encl
| author name = Booker J
| 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-25290, NUDOCS 8702050325
| package number = ML20209G284
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}

=Text=
{{#Wiki_filter:GULF STATES                         UTELETIES COMPANY RIVER SEND STAflON     POST OFFICE Box 220    ST FRANCISVILLE. LOUISIANA 70775 ARE A CODE 504    635 6094     346 8651 January 30, 1987 RBG-        25290 File Nos. G9.5, G12.5 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
River Bond Nuclear Group Docket No. 50-458 Enclosed for your review is Revision 3 (Control Copy #6) of the River Bend Station Pump and Valve Inservice Testing Plan.                                   A summary of the revisions are described in the Attachment.                                    This submittal is provided in accordance with 10CFR50.55a(g).
Sincerely, W
fhe
                                                               .[ J.Manager-River E. Booker Bend Oversight River Bend Nuclear Group JED/ ERG /hhC/ks Attachment Enclosure cc:   U.S. Nuclear Regulatory Commission (Control Copy #7)
Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 U.S. Nuclear Regulatory Commission (Control Copy #8)
Senior Resident Inspector P.O. Box 1051 St. Francisville, LA 70775 0702050325 870130 PDR   ADOCK 05000450 p1

ATTACl9ENT CHANGE                                                           PAGE
: 1. The statanent specifying when testing mst start after         2-2, the plant enters Cold Shutdown was clarified. 'Ihe            3-3 previous wording could have been misinterpreted to indicate all tests nust start within 72 hours when the intent was that testing in general must start within 72 hours.
: 2. In the first paray@ of 3.1, '1981' was inadvertently          3-1 anitted in earlier revisions.
: 3. In 2.2.4.2 and 3.3.6.1, statements were aMari to allow        2-1, pmp design and description information and                    3-3 administratively set valve open time limits to be changed without requiring a revision of the Punp and Valve Plan.
The inclusion of this information is not required and was included only for information.
: 4. Pep Request for Relief (PRR) No. I was changed to             B-1, No. 10. 'Ihis was necessary because of conputer data          B-10, base limitations. A new PRR #1 was aMari. 'Ihe new         A-1 thru 14 PRR #1 was written to allow a pm p to be tested without shutting it down merely to measure the idle suction pressure. 'Ihe Pmp Inservice Testing Plan (Appendix A) was corresponding revised.
: 5. 1CCP*V300, Supply header to RHR Pm p A bearing               C-22, cooling isolation check valve test frequency was changed     D-15 fran Cold Shutdown to Quarterly. A new test method                    >
was developed that allowed this valve to be easily tested on a quarterly basis.
: 6.  'Ihe normal position of valves 1E12*M0WO64A, B, C was        C-46, incorrectly shown as closed.                                 C-50
       'Ihe wirect, position is open.                               C-53
: 7.  'Ihe stroke time limits of valve 1E51*M0WO68 were            C-60 incorrectly shown as 20.8 seconds due to a typographical error. 'Ihe correct time is 70.8 seconds.
: 8. IICS*V21, RCIC mininum flow line check valve test            C-60, frequency was incorrectly shown as Cold Shutdown. 'Ihe       D-18 correct frequency is Quarterly. The frequency had been properly changed during program developnent and the valve tested as such but the ISI Plan was inadvertently not updated prior to issuance.

ATIACHMENT CHANGE                                                          PME
: 9. ICFM*MNIA, B, 2A, B, 3A, B, 4A, and B, primary             C-62, contalment/drywell hydrogen mixing systs inlet and         C-63, outlet isolation valves are required by Technical          D-54 Specification 3.6.6.2 to re ain closed during plant operation except to control drywell pressure. 'Ihe test            i frequency for these valves were changed frm Quamrly                l to Cold Shutdown.                                                  ,
1
: 10. 1HVC*MOV1A, B, Control Building Ventilation isoittion       3-4 danper valves are required to close within 30 sernds       C-72 by 'Ibchnical Specification 4.7.2.e.2.
11.1G33*M0W001, 4, 39, 40, 53, and 54, Reactor Water            C-91, Cleanup Systs isolation valves are required to r main      C-92, open during plant operation to maintain system operation. D-55
     'Ihe test frequency was changed from Quarterly to Cold Shutdown.
: 12. 'Ihe stroke time limits for 1G33*ENF054 were                C-91, incorrectly shown as 5.3 seconds due to a ty m-1.al l iical error. 'Ihe correct limit is 5.5 seconds.
: 13. 'Ihe open time limits for main steam drain line            C-96 isolation valves 1B21*M0WO67A, B, C, D were administratively increased 1.5 seconds to allow for the inherently longer opening times experienced with these particular valves.
: 14. IW paragraph 3412(a) was incorrectly referenced as         D-45 3522}}