View source for SVP-99-111, Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions

{{Adams
| number = ML20206T243
| issue date = 05/17/1999
| title = Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
| author name = Dimmette J
| author affiliation = COMMONWEALTH EDISON CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000254
| license number = 
| contact person = 
| document report number = GL-96-06, GL-96-6, SVP-99-111, NUDOCS 9905240101
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
}}

=Text=
{{#Wiki_filter:e (Nimnl(HI% Cidtfl I Ally'n ( A HUpJfly Quad Liors Grocrating Nanon j
22'l0 2Of db A)enur Nortb                                                                              !
Cordou. ll. 612 4W 40
* Tei w ;<,s u n i
{
Comed SVP-99-111 May 17,1999 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D C 20555                                                                               ;
Quad Cities Nuclear Power Station, Unit 1                                     '
Facility Operating License No. DPR-29 NRC Docket No. 50-254

==Subject:==
Change in status of NRC Generic Letter 96-06," Assurance of Equipment Operability and Containment integrity During Design-Basis Accident Conditions" Actions for Unit 1

==References:==
(1) Letter from J.P. Dimmette, Jr. (Comed), SVP-98-234, to USNRC,                        I dated October 30,1998," Change in Status of NRC Generic Letter          1 96-06 Resolution Actions for Unit 1" The purpose of this letter is to inform the NRC of the current status of our actions on Quad Cities Nuclear Power Station Unit 1 response to Generic Letter (GL) 96-06,
              " Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions."
In the letter referenced above, we revised commitments for penetrations, X-12 (Residual Heat Removal Shutdown Cooling); X-14 (Reactor Water Cleanup); and X-41 (Reactor Recirculation Sample Line Piping). That letter informed the NRC of our 9y1 intention to perform an American Society of Mechanical Engineers Boiler and Pressure            j Vessel Section lil Appendix F 1 (ASME Appendix F), " Rules for Evaluation of Service Loadings with Level D Service Limits," analysis for these penetrations in accordance with Supplement of GL 96-06. This task was completed as scheduled.
The results of the analysis allowed for qualification of penetrations X-12 and X-41. As a result of this qualification, no modifications, (i.e. relief valves) were required to be installed.                                                                                    O[
Prior to completion of the ASME Appendix F analysis for penetration X-14,it became I             evident that this penetration could not be qualified. Based on these preliminary results, l             we completed installation of a relief valve for penetration X-14 in our recent 01P02
)             outage. The analysis of penetrations X-12 and X-41 and the installation of the relief valve for penetration X-14 completes our actions in response to GL 96-06 for Quad Cities Nuclear Power Station Unit 1.
9905240101 990517                                              -
PDR P
ADOCK 05000254 pon                          4 y10
                                                           /
A t nu om comp.m3                                                                                /
a

      , -                                                                        e
   >        May 17,1999 U.S. Nuclear Regulatory Commission
          ,.Page 2 Should you have any questions concerning this letter, please contact Mr. Wally Beck,
          . Acting Regulatory Assurance Manager, at (309) 654 2241, extension 3100.
R     ectfully,
                                     ~
Ca Joel P. Dimmette, Jr.
            $ite Vice President Quad Cities Nuclear Power Station cc:     Regional Administrator-NRC Region til NRC Senior Resident inspector - Quad Cities Nuclear Power Station l
l l
l l
I I
l l
                                                      .}}