View source for U-600549, Forwards Response to Sser 5 (NUREG-0853),Section 3.10.1.3, Outstanding Item 9 Re Seismic & Dynamic Qualification of equipment.Safety-related Equipment Qualified

{{Adams
| number = ML20205N321
| issue date = 04/30/1986
| title = Forwards Response to Sser 5 (NUREG-0853),Section 3.10.1.3, Outstanding Item 9 Re Seismic & Dynamic Qualification of equipment.Safety-related Equipment Qualified
| author name = Spangenberg F
| author affiliation = ILLINOIS POWER CO.
| addressee name = Butler W
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000461
| license number = 
| contact person = 
| case reference number = RTR-NUREG-0853, RTR-NUREG-853
| document report number = U-600549, NUDOCS 8605020090
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 5
}}

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{{#Wiki_filter:U-600549 o                                                                                 L30-86 (04-30 )-L 1A.120
      /LLINDIS POWER 00MPANY CLINTON POWER STATION P.o. BOX 678. CLINTON, ILLINots 61727 Artil 30, 1986 Docket No. 50-461 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555

==Subject:==
Clinton Power Station SER Outstanding Issue #711 Seismic and Dynamic Qualification of Equipment

==Dear Dr. Butler:==

This letter is in response to an Open Item identified in NUREG-0853 Supplement No. 5 " Safety Evaluation Report Related to the Operation of Clinton Power Station, Unit No. 1." Attached for the Staff's review is the response to Item 9 of SER Section 3.10.1.3.
Please contact us if you have any questions on this matter.
Sincerely yours, E.1                ,ME F. A. Sp genb rg   i Manager - Licelsing and Safety SMK/ckc Attachments (4) cc:  B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Ill tois Department of Nuclear Safety 8605020090 860430                                                                    )
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     .                                                            Attechm:nt 1 to U-600549 SAFETY RELATED EQUIPMENT INSTALLATION AND QUALIFICATION SER Section 3.10.1.3, Item 9      "Upon completion of its program, the applicant must confirm that all safety related equipment pieces are properly qualified and installed."
Response - Equipment which requires seismic qualification has been qualified. All safety related equipment which is required to support Fuel Load has been installed with the exception of five filters in the Standby Gas Treatment System (VG), which will be installed prior to Fuel Load as part of Special Test Procedure XTP-00-12(See Attachment 2). Ten pieces of qualified safety related equipment are not required and will not be installed prior to Fuel Load. This equipment is tabulated on Attachments 3 and 4.
Deferral of the installation of the Control Room HVAC (VC) System filters listed in Attachment 3 until prior to achieving Initial Criticality was requested by Illinois Power via Letter U-600469, dated March 12, 1986, from Mr. D. P. Hall to Mr. H. R. Denton. This deferral does not require a request for exemption to 10CFR50.49 since the equipment is not electrical and is not covered by this section as defined in 10CFR50.49(b)(1).
Deferral of the installation of the portions of the Reactor Core Isolation Cooling (RI) System listed in Attachment 4 until prior to achieving initial heatup does not require a request for exemption to 10CFR50.49. The function performed by this equipment is not required to mitigate the consequences of any design basis event until prior to achieving initial heatup.
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Attachssnt 2 to U-600549 STANDBY CAS TREATMENT SYSTEM EQUIPMENT WHICH WILL BF INSTALLED PRIOR TO INITIAL FUEL LOAD Equipment    Manufacturer /       Installation       Scheduled Number      Model Number           Document         Completion OVG06FA      AAF/ Pre Filter      MWR C07278         Fuel Load OVG06FB      AAF/ Pre Filter      MWR C07279         Fuel Load OVG07FA      AAF/HEPA Filter      MWR C07278         Fuel Load OVGilFA      AAF/HEPA Filter      MWR C07278         Fuel Load
!     OVG11FB      AAF/HEPA Filter      MWR C07279         Fuel Load i
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        -*                                                      Attachmint 3 to U-600549 CONTROL ROOM HVAC EQUIPMENT WHICH WILL NOT BE INSTALLED PRIOR TO FUEL LOAD Equipment  Equipment                       Installation   Scheduled Number     Type                           Document        Completion OVC23FA    Upstream HEPA Filter           MWR B35289      Initial Criticality OVC23FB    Upstream HEPA Filter           MWR B35290      Initial Criticality OVC25FA    Downstream HEPA Filter         MWR B35291      Initial Criticality l

Attschment 4 to U 600549 REACTOR CORE ISOLATION COOLING EQUIPMENT WHICH WILL NOT BE INSTALLED PRIOR TO FUEL LOAD Equipment      Manufacturer /           Installation         Scheduled Number         Model Number             Document             Completion 1E51-F066(LS) Conax/7F20-11005-02       MWR C01042           Heatup IE51-F066(0)   Asco/NP8320(V)           MWR C01042           Heatup 1E51-F066(0S) Conax/7F20-11001-03       MWR C01042           Heatup 1E51-F316(L)   Namco/EA180              MWR C01459           Heatup 1E51-F316(LS) Conax/7F20-11005-02       MWR C01459           Heatup 1E51-F316(0)   Asco/2068323U            MWR C01459           Heatup 1E51-F316(0S) Conax/7F20-11001-03       MWR C01459           Heatup}}