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Prairie Island Unit 2 is currently in Mode … Prairie Island Unit 2 is currently in Mode 3 with RCS (Reactor Coolant System) at Tave 547 degrees and 2235 psig and preparing for reactor startup following steam generator replacement outage 2R28.</br>At 0933 December 31, 2013 it was discovered that multiple upper lateral support shims and bumpers were removed from both 21 and 22 steam generators. This resulted in both loops being declared inoperable and entry into Tech. Spec. (Technical Specification) LCO (Limiting Condition of Operation) 3.4.5 Condition D. It also placed the Unit 2 Reactor Coolant System in an unanalyzed condition for Seismic and LOCA analyses and required this 8 hour report under 10 CFR 50.72(b)(3)(ii)(B). </br>During this condition both reactor coolant loops were in operation, adequately removing decay heat and keeping Prairie Island in a safe condition.</br>Tech Spec (LCO) 3.4.5 Condition D requires 3 immediate actions: 1. Place the rod control system in a condition incapable of rod withdrawal; action is completed. 2. Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet shutdown margin; action is completed. 3. Initiate action to restore one RCS loop to operable status and operation; action was immediately initiated.</br>Actions have been initiated to reinstall all shims and bumpers in both steam generators. Once these actions are completed and verified the unanalyzed condition will be corrected and Technical Specification (LCO) 3.4.5 Condition D will be exited. These actions are expected to be completed by 1600 on December 31, 2013.</br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE AT 1653 EST ON 1/3/2014 FROM TERRY BACON TO MARK ABRAMOVITZ * * *</br>Technical Specification 3.4.5 Condition D was exited on December 31, 2013 at 1728 (CST), when 21 and 22 Steam Generator Upper Lateral Supports were restored to the proper configuration to meet seismic acceptance criteria. Additionally, based on further analysis, it was determined that with both Reactor Coolant Loops inoperable that this condition is a loss of safety function and reportable under 50.72(b)(3)(v)(B).</br>The licensee has notified the NRC Resident Inspector.</br>Notified the R3DO (Kunowski).t Inspector.
Notified the R3DO (Kunowski).
15:33:00, 31 December 2013 +
49,685 +
14:51:00, 31 December 2013 +
15:33:00, 31 December 2013 +
Prairie Island Unit 2 is currently in Mode … Prairie Island Unit 2 is currently in Mode 3 with RCS (Reactor Coolant System) at Tave 547 degrees and 2235 psig and preparing for reactor startup following steam generator replacement outage 2R28.</br>At 0933 December 31, 2013 it was discovered that multiple upper lateral support shims and bumpers were removed from both 21 and 22 steam generators. This resulted in both loops being declared inoperable and entry into Tech. Spec. (Technical Specification) LCO (Limiting Condition of Operation) 3.4.5 Condition D. It also placed the Unit 2 Reactor Coolant System in an unanalyzed condition for Seismic and LOCA analyses and required this 8 hour report under 10 CFR 50.72(b)(3)(ii)(B). </br>During this condition both reactor coolant loops were in operation, adequately removing decay heat and keeping Prairie Island in a safe condition.</br>Tech Spec (LCO) 3.4.5 Condition D requires 3 immediate actions: 1. Place the rod control system in a condition incapable of rod withdrawal; action is completed. 2. Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet shutdown margin; action is completed. 3. Initiate action to restore one RCS loop to operable status and operation; action was immediately initiated.</br>Actions have been initiated to reinstall all shims and bumpers in both steam generators. Once these actions are completed and verified the unanalyzed condition will be corrected and Technical Specification (LCO) 3.4.5 Condition D will be exited. These actions are expected to be completed by 1600 on December 31, 2013.</br>The licensee notified the NRC Resident Inspector.</br>* * * UPDATE AT 1653 EST ON 1/3/2014 FROM TERRY BACON TO MARK ABRAMOVITZ * * *</br>Technical Specification 3.4.5 Condition D was exited on December 31, 2013 at 1728 (CST), when 21 and 22 Steam Generator Upper Lateral Supports were restored to the proper configuration to meet seismic acceptance criteria. Additionally, based on further analysis, it was determined that with both Reactor Coolant Loops inoperable that this condition is a loss of safety function and reportable under 50.72(b)(3)(v)(B).</br>The licensee has notified the NRC Resident Inspector.</br>Notified the R3DO (Kunowski).t Inspector.
Notified the R3DO (Kunowski).
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00:00:00, 3 January 2014 +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
01:52:09, 2 March 2018 +
14:51:00, 31 December 2013 +
false +
false +
-0.0292 d (-0.7 hours, -0.00417 weeks, -9.5886e-4 months) +
15:33:00, 31 December 2013 +
Unanalyzed Condition Due to Removal of Multiple Steam Generator Lateral Support Shims and Bumpers +
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