Similar Documents at Fermi |
---|
Category:- No Document Type Applies
MONTHYEARML24173A0802024-05-0202 May 2024 Retake Exam Form 2.3-1 Outline Quality Checklist ML22081A0732022-03-0202 March 2022 EGLE Wetland Permit No. WRP032246 v.1 ML16270A5672016-12-15015 December 2016 Record of Decision, U.S. Nuclear Regulatory Commission, Docket No. 50-341, License Renewal Application for Fermi, Unit 2 Nuclear Power Plant ML16187A3662016-06-30030 June 2016 Final ASP Program Analysis - Reject - Fermi Unit 2 Reactor Scram Due to Loss of Turbine Building Closed Cooling Water (LER 341/2015-006) ML15014A1532015-01-14014 January 2015 Attachment 1- NEI Comments on NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML15014A1602015-01-14014 January 2015 Attachment 2 - NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML14125A1882014-04-24024 April 2014 Fermi 2 LRA Drawing List NRC-14-0035, Fermi 2 LRA Drawing List2014-04-24024 April 2014 Fermi 2 LRA Drawing List ML13143A3312013-06-0606 June 2013 Operating Boiling-Water Reactor Licensees with Mark 1 and Mark 2 Containments Addresses List - Enclosure 2 ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1126601882011-09-23023 September 2011 NRC 2011 Davis-Besse ML11186A8962011-03-21021 March 2011 NUREG Section 5.3 Recommendation ML11186A7912011-03-21021 March 2011 NUREG Section 4.4.2 Recommendation ML11186A7282011-03-21021 March 2011 NUREG Section 4.2.1 Recommendation ML11186A6402011-03-21021 March 2011 NUREG Section 3.1.1.2 Recommendation ML11186A5832011-03-21021 March 2011 NUREG Section 3.4 Recommendation ML1021608072010-08-0404 August 2010 ISI Request for Information ML0933507512010-01-14014 January 2010 Temporary Instruction 2515/180, Managing Fatigue ML0911306562009-04-23023 April 2009 04/23/09 Request for Information Mod 50.59 Review - Initial Selection Scope ML0905602932009-02-25025 February 2009 RFI for ISFSI Pad Inspection - Docket Number 072-00071 and 050-00341 ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions NRC-07-0051, Submittal of Revised No Significant Hazards Consideration for the Proposed License Amendment to Delete the Note Associated with the Performance of Channel Calibration for Primary Containment High Range Radiation Monitor in Technical.2007-09-21021 September 2007 Submittal of Revised No Significant Hazards Consideration for the Proposed License Amendment to Delete the Note Associated with the Performance of Channel Calibration for Primary Containment High Range Radiation Monitor in Technical. ML0607201462004-12-17017 December 2004 Final Precursor Analysis, LER 341/03-002, Automatic Reactor Trip and Loss of Offsite Power Due to the August 14, 2003, Transmission Grid Blackout ML0505404642004-02-0909 February 2004 Dynamic Web Page Printout Dated 02/09/2004 Regarding Applied Violations for Nuclear Power Plants ML0330904592003-10-24024 October 2003 Detroit Edison Tpept EP-29005, Rev 3, Hospital Support Request Form 2024-05-02
[Table view] |
Text
3.1.1.2 Testing at a Refueling Outage Frequency for Valves Tested During Power Ascension ASME OM Code Subsection ISTC requires that valves tested on a refueling outage frequency be tested prior to returning the plant to operation at power. Several licensees have indicated that certain valves cannot be tested until power ascension begins. This section was included to give guidance for such valves and to indicate that the operability of technical specifications would control the time for testing such valves. It is intended that such valves will be indicated in the IST program as tested on a refueling outage frequency, even though the plant may return to "operation" before the testing is completed. A similar intent applies to valves tested during power ascension from cold shutdowns which are not refueling outages; however, the language in the OM Code is different for valves tested on a cold shutdown frequency.
Before beginning power ascension from a refueling outage, the licensee normally completes the tests of those valves tested at each refueling outage. However, to test any valves that can only be tested during power ascension, the licensee may begin raising the power level and changing modes in accordance with TS requirements and test the applicable valves when plant conditions allow testing. If maintenance has been performed on a valve during the outage, the licensee is required to consider the valve "inoperable" until completing post-maintenance testing in accord with the operability requirements in the TS. This situation could also apply to valves tested during power ascension or at power following a cold shutdown outage.
NRC Recommendation ASME OM Code Subsections ISTC-3521 and ISTC-3522 requires that all valve testing scheduled for performance during a refueling outage shall be completed before returning the plant to operation. For valves which can only be tested during power ascension, technical specification requirements for the valves or the system determine when the valves are required to be operable. The testing for these valves may be scheduled for refueling outages (or cold shutdown outages) but completed during power ascension from the outage. The NRC has determined that testing of such valves during the plant startup period but prior to reaching steady state full power operation is acceptable without relief .
Basis for Recommendation The staff has determined that the guidance of this section is consistent with ASME OM Code Subsection ISTC and the TS requirements and is acceptable for meeting those provisions.