View source for JSP-799-90, Suppl to 890630 Application for Amend to License NPF-62 to Include Valve 1E12-F011A Control in Tech Spec Table 3.3.7.4-2

{{Adams
| number = ML20062A820
| issue date = 10/09/1990
| title = Suppl to 890630 Application for Amend to License NPF-62 to Include Valve 1E12-F011A Control in Tech Spec Table 3.3.7.4-2
| author name = Perry J
| author affiliation = ILLINOIS POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000461
| license number = 
| contact person = 
| document report number = JSP-0799-90, JSP-799-90, U-601740, NUDOCS 9010230157
| package number = ML20062A825
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 2
| project = 
| stage = Request
}}

=Text=
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10-09 } -LP CLINToN POWER STATION. I'.o. InoX 678. CLINToN. ILUNOIS 61727 J. STEPHEN PERRY. Vin Pwsident (2171935 6220 JSP-0799-90 October 9, 1990 10CFR50.90 Docket No. 50-461 Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

==Subject:==
Clinton Power Station Proposed Amendment of Facility Operatina License No. NPF-62

==Dear Sir:==

By {{letter dated|date=June 30, 1989|text=letter dated June 30, 1989}} (reference U-601460),
Illinois Power (IP) applied for amendment of Facility Operating License No. NPF-62, Appendix A - Technical Specifications, for Clinton Power Station (CPS). That request consisted, in part, of proposed changes to remove the Operability requirements for the controls in the Remote Shutdown system (Technical Specification 3/4.3.7.4) associated with components used only for the                              ',
               " steam condensing mode" of the Residual Heat Removal                                  l (RHR) system (reference package No. LS-89-005).                  That                   I request was based upon IP's commitment not to use the                                   !
steam condensing mode of the RHR system.
This letter is being submitted as a supplement to the {{letter dated|date=June 30, 1989|text=June 30, 1989 letter}} in order to include the control for valve 1E12-F011A within the scope of controls previously identified as not required to be operable or tested based on IP's commitment not to use the steam condensing mode of the RHR system. In the June 30, 1989 submittal, a footnote was proposed for Technical Specification Table 3.3.7.4-2 to identify the applicable                                  '
valve controls. IP now proposes to make the same
,             ' footnote applicable to the 1E12-F011A control by applying the asterisk associated with the footnote to the 1E12-F011A control under the Equipment Number and Minimum Channels Operable headings of Table 3.3.7.4-2 as was proposed for the three previously identified controls associated with the RHR steam condensing mode.                 In addition, IP proposes to change the functional description of the 1E12-F011A control (to "RHR HX 1A Condensate Dump Vlv") to more accurately reflect the intended-function of this control and associated valve 1E12-F011A.
I C d .'il 9                                                                   0l0 9010230157 901009                                                                  b l
PDR   ADOCK 05000461 P                    PNV

As stated in IP's June 30, 1989 request, IP informed the NRC by {{letter dated|date=June 3, 1987|text=letter dated June 3, 1987}} (reference U-600945) that the steam condensing mode of the RHR system would            '
not be tested under the Startup Test Program (or used) at CPS. The {{letter dated|date=June 3, 1987|text=June 3, 1987 letter}} included a safety evaluation (per 10CFR50.59) written for changes to the            '
CPS Final Safety Analysis Report (FSAR) in support of IP's position. The NRC accepted IP's position provided the following actions are taken:
: 1. Administrative controls are instituted and the appropriate valves are locked out to preclude inadvertent operation of the RHR system in the steam condensing mode.
: 2. Plant procedures are revised to reflect that operation of the RHR system in the steam condensing mode is not permitted.
3._  The.NRC is informed prior to performing the deleted startup testing, should IP decide to use the steam
* condensing mode of RHR at a later date.
As identified in IP's {{letter dated|date=June 30, 1989|text=June 30, 1989 letter}}, IP is in compliance with these requirements.
                                                                            }
The justification for this supplement is bounded by the original justification provided in IP's June 30, 1989         ,
request. Further, the Basis for No Significant Hazards Consideration and the basis for meeting the criteria given in 10CFR51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement, as provided in the original request, remain          -f unchanged. A marked-up copy of the affected page (page 3/4 3-83) from the June 30, 1989 request is attached.             l (The requested supplement to the June 30,-1989 request is        c identified by a double change bar.) An additional page from the June 30, 1989 request containing the proposed r
footnote is also attached for your information.
Sincerely yours,
                                        "()
Q. S. P g V ce President
* DAS/alh                                                          :
Attachment s
cc:  Regional Administrator, Region III, USNRC NRC Clinton Licensing Project Manager NRC Resident Office                                          ,
Illinois Department of Nuclear Safety}}