View source for 0CAN029612, Forwards Corrected Page 15 of 17 of Attachment to 960213 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Correcting Last Sentence of Last Paragraph as Listed

{{Adams
| number = ML20100G954
| issue date = 02/20/1996
| title = Forwards Corrected Page 15 of 17 of Attachment to 960213 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Correcting Last Sentence of Last Paragraph as Listed
| author name = Mims D
| author affiliation = ENTERGY OPERATIONS, INC.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000313, 05000368
| license number = 
| contact person = 
| document report number = 0CAN029612, CAN29612, GL-95-07, GL-95-7, NUDOCS 9602260335
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 3
}}

=Text=
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                           - February 20,1996                                                                                                     -!
                           ' OCAN02%12 4
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==Subject:==
Arkansas Nuclear One - Units 1 and 2                                                                  ,
Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Generic Letter 95-07,180-Day Response Corrigendum l
j                             Gentlemen:
Arkansas Nuclear One's 180-Day Response to Generic Letter 95-07, " Pressure Locking and e
Thermal Binding of Safety-Related' Power-Operated Gate Valves," was submitted on February 13,1996 (0CAN029605). Page 15 of 17 of the attachment contained an incorrect                                 '
completion date. The last sentence of the first paragraph, " Corrective Actions" should have read... " refueling outage 2R12" not " refueling outage IR13."' Please replace this page with
                             'the enclosed corrected page. A vertical line has been placed in the left margin to indicate a l
revision to the adjacent text.-
Should you have questions or comments, please contact me.
Very rulyyours, E[                                                                                                                 )
                     /t,. Dwight Ch. ms,                b                                                                                           ;
Director, Nuclear Safety f
                             ' DCM/dwb -                                                                                                             i enclosure: (corrected page) 9602260335 960220 -                   .
t PDR. ADOCK 0500
                 .P                                                                                                                                 ,
pi 260'075

i
          ,      U. S. NRC -
U ".
February 20,1996
               - OCAN029612: Page 2 cc:    Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 i                       Arlington, TX 76011-8064                          .
NRC Senior Resident Inspector
:                       Arkansas Nuclear One P.O. Box 310 i                       London, AR 72847 i
i                     Mr. George Kalman NRR Project Manager Region IV/ANO-1 & 2
* U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3
.                       One White Flint North 11555 Rockville Pike Rockville, MD 20852 i
3 1
^
1

        , Attachment to                                                                                                       l OCAN029605 Page 15 of17 6                                                                                                                           .
SW to EFW Pump Isolation Valves      2CV-0711-2,2CV-0716-1                                                          i A. SusceptibletoEnvironmental Boiler Efect Locking Margin:                          0%(both valves)
Corrective Actions:              Night orders have been issued to inform operators of the potential of these valves to bind, and provide methods of dealing with the occurrence should it happen. The valves will be modified by the end of refueling outage 2R12.
EFW 2P7A to A/B Steam Generators 2CV-1026-2,2CV-1076-2 A. Susceptible to ThermalBinding Corrective Action:               To eliminate binding due to back leakage of feedwater through the check valves, procedures were revised to require opening the valves successfully following an event of this type. Engineering is required to be notified if the valve body temperature exceeds 200 'F.
RB Spray Hender Isolation Valves     2CV-5612-1, 2CV-56! t-2 A. Susceptible to Hydraulic Locking Margin:                          0% (both valves)
Corrective Action:               Implemented short term action to stroke the valves prior to entering MODE 3 in order to relieve any trapped bonnet pressure. These valves will be modified by the end of refueling outage 2R12.
B. SusceptibletoProximity Boller Effect Locking Corrective Action:               Same as above a
Sump Recirculation Outside Isolation Valves 2CV-5649-1,2CV-5650-2 A. Susceptible to Environmental Boiler Efect Locking Corrective Action:               Bonnet pressure relief valves were installed on these valves during refueling outage 2R11 in 1995.
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