NG-12-0054, Supplement to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program

Supplement to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program

ML12040A016
Person / Time
Site:	Duane Arnold
Issue date:	02/03/2012
From:	Wells P NextEra Energy Duane Arnold
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-12-0054, TSTF-425, Rev 3
Download: ML12040A016 (4)

Text

NEXTera E N ER;Y DARNOL February 3, 2012 NG-12-0054 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No. 50-331 Renewed Op. License No. DPR-49 Supplement to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Proqram

References:

1) License Amendment Request (TSCR-120): Application for Technical Specification Chanqe Reqardinq Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Proqram (TSTF-425, Rev. 3), NG-11-0037, dated February 23, 2011

2) Response to Request for Additional Information Related to an Amendment to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Proqram, NG-11-0299, dated Auqust 15, 2011

3) Supplemental Information to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Proqram, NG-12-0034, January 19, 2012 In the Reference 1 letter, as modified by Reference 2, NextEra Energy Duane Arnold, LLC (hereafter NextEra Energy Duane Arnold) requested a revision to the Technical Specifications (TS) for the Duane Arnold Energy Center (DAEC) pursuant to 10 CFR 50.90. In the referenced correspondence, NextEra Energy Duane Arnold provided marked-up pages from the current DAEC TS indicating the requested changes. It has subsequently been discovered that one TS page was inadvertently omitted from those marked-up pages in the original application.

Attached is the missing marked-up page. The requested change to this TS page was intended to be included in the original application, as noted by the A-ol NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324

Document Control Desk February 3, 2012 Page 2 of 2 corresponding revised Bases page being in Attachment 4 of Reference 1, as well as the requested change being included in the Table in Attachment 5.

The corresponding clean, typed page was included with those submitted by Reference 3.

This letter makes no new commitments or changes to any existing commitments.

If you have any questions or require additional information, please contact Steve Catron at 319-851-7234.

I declare under penalty of perjury that the foregoing is true and correct.

uted on February 3, 2012 Wells Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC

Attachment:

Proposed Technical Specification Change (Marked-up Page) cc: NRC Regional Administrator NRC Resident Inspector NRC Project Manager M. Rasmusson (State of Iowa)

Attachment to NG-12-0054 PROPOSED TECHNICAL SPECIFICATION CHANGE (MARK-UPS) 1 Page to Follow

RHR-High Water Level 3.9.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. No RHR shutdown C.1 Verify reactor coolant 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from cooling subsystem circulation by an discovery of no in operation with alternate method. reactor coolant reactor coolant circulation temperature

_ 150 0F.

AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem is 12-hours-FsT1 operating when reactor coolant temperature is

Ž 150 OF.

DAEC 3.9-12 IýIEI lul .. l IL f--