09-02-2008 | On March 11, 2008 following maintenance on an outside air intake valve, Surveillance Test Procedure STP-454.002 was performed to restore the "A" train of the Control Room Normal and Emergency Air Handling (CR Ventilation) System to service.
The test results were unsatisfactory.
Investigation into the test failure determined that a control room pressure boundary (CRPB) breach occurred during normal preventive maintenance performed February 26, 2008 on Instrument and Control (I&C) Area Air Handling Unit XAH0048. The identified breach was sufficient to allow a quantity of air out-leakage that reduced CRPB pressure below Technical Specifications (TS) minimum and resulted in increased outside air flow that exceeded the maximum allowed by TS. Repairs were made to the air handling unit and the surveillance test was successfully completed on March 14, 2008.
The effect of the leakage at XAH0048 on the "B" Train of CR Ventilation could not be readily determined. Therefore, both trains of CR Ventilation were assumed to be inoperable from February 26 to March 14, 2008. Since this condition affected both trains of CR Ventilation and existed for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, TS Limiting Condition for Operation (LCO) 3.7.6.a.2 was violated.
A root cause analysis determined that the root causes of this event were: 1) adequate maintenance retests were not procedurally addressed, and 2) Air Handling Unit XAH0048 was located within the CRPB, but not purchased to meet the CRPB design requirements. The corrective actions to prevent recurrence include: 1) revise procedures to verify CRPB restoration requirements and to provide additional guidance for CRPB envelope testing, and 2) perform a design change to either relocate or upgrade Air Handling Unit XAH0048. |
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LER-2008-002, Control Room Normal and Emergency Air Handling Systems Inoperable Due to Pressure Boundary BreachDocket Number |
Event date: |
03-11-2008 |
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Report date: |
09-02-2008 |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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3952008002R01 - NRC Website |
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PLANT IDENTIFICATION
Westinghouse - Pressurized Water Reactor
EQUIPMENT IDENTIFICATION
XAH0048 - Instrument and Control Area Air Handling Unit
IDENTIFICATION OF EVENT
On March 11, 2008, following maintenance on an outside air intake valve, Surveillance Test Procedure STP-454.002 was performed to restore the "A" train of the Control Room Normal and Emergency Air Handling (CR Ventilation) System to service.
This test required demonstrating that the CR Ventilation System maintained a positive pressure in the Control Room Pressure Boundary (CRPB) while limiting the outside air (OA) intake flow. This test is required to meet Technical Specifications (TS) Surveillance Requirement (SR) 4.7.6.e.3. The test results were unsatisfactory.
Investigation into this event determined that a boundary breach occurred on February 26, 2008, during normal preventive maintenance performed on Instrument and Control (I&C) Area Air Handling Unit XAH0048. The identified breach was sufficient to reduce CRPB pressure below TS minimum and resulted in increased OA flow that exceeded the maximum allowed by TS. This breach condition was considered to have existed from February 26, 2008 until the breach was identified and repaired with return to service on March 14, 2008. On March 19, 2008 a past operability review concluded that the effect of the leakage at XAH0048 on the "B" train of CR Ventilation could not be readily determined. Therefore, both trains of CR Ventilation were assumed to be inoperable from February 26 to March 14, 2008. Since this condition affected both trains of CR Ventilation and existed for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, TS Limiting Condition for Operation (LCO) 3.7.6.a.2 was violated.
EVENT DATE
March 11, 2008 Condition Reports CR-08-00944 and CR-08-00972 were initiated to address this event.
REPORT DATE
Initial - May 12, 2008 Revision 1 - September 2, 2008
CONDITIONS PRIOR TO EVENT
Mode 1, 100% Power
DESCRIPTION OF EVENT
Following unsatisfactory test results during performance of STP-454.002, the "A" train of the CR Ventilation System was declared inoperable and an investigation was initiated to determine the reason for the test failure. This investigation of the CRPB identified a breach in the suction plenum of Air Handling Unit XAH0048. XAH0048 is physically located within the CRPB and comprises a physical portion of the CRPB, but has no functional interface with the CRPB. This air handling unit cools and recirculates air to the I&C maintenance shop located outside of the CRPB. Repairs were made to XAH0048 and the surveillance test was successfully completed on March 14, 2008. On March 19, 2008 a past operability review concluded that the effect of the leakage at XAH0048 on the "B" train of CR Ventilation could not be readily determined. In addition, the review conservatively determined that the "B" train CR Ventilation would probably have exceeded the TS maximum limit of 1,000 SCFM outside air flow. The "B" train CR ventilation may very well have maintained the control room differential pressure above 0.125 inch w.g., but it would have been reduced from its normally expected value and could have challenged the TS requirement of greater than 0.125 inch w.g.
Therefore, both trains of CR Ventilation were assumed to be inoperable from February 26 to March 14, 2008.
DESCRIPTION OF EVENT (Continued) The root cause team determined that on February 26, 2008 maintenance had been performed on XAH0048. During this maintenance, duct tape had been removed to allow removal of screws which held a panel cover in place. Following maintenance the duct tape was not restored. Although the post-maintenance test verified that the CRPB had been restored, it only required that the differential pressure be determined with the CR Ventilation System operating in the normal mode. The CRPB differential pressure is normally higher with the CR Ventilation System in the normal mode than in the emergency mode. The breach condition was considered to have existed from February 26, 2008 until the breach was identified and repaired with return to service on March 14, 2008. Since this condition affected both trains of CR Ventilation and existed for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, TS Limiting Condition for Operation (LCO) 3.7.6.a.2 was violated.
CAUSE OF EVENT
Investigation into the test failure determined that a control room pressure boundary (CRPB) breach occurred during normal preventive maintenance performed February 26, 2008 on Instrument and Control (I&C) Area Air Handling Unit XAH0048. The identified breach was sufficient to allow a quantity of air out-leakage that reduced CRPB pressure below TS minimum and resulted in increased outside air flow that exceeded the maximum allowed. Since this condition affected both trains of CR Ventilation and existed for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, TS Limiting Condition for Operation (LCO) 3.7.6.a.2 was violated.
A root cause analysis was completed for this event. The root causes include: 1) procedures did not include the requirements to verify outside air intake flow following maintenance, and 2) Air Handling Unit XAH0048 was purchased for location outside of the CRPB, but was located inside the CRPB and did not adequately meet the design requirements for this location.
ANALYSIS OF EVENT
The CRPB is designed and maintained to provide a habitable environment such that occupants within the CRPB can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge.
The VCSNS Control Room Normal and Emergency Air Handling System consists of two independent, redundant trains that recirculate air in the normal and emergency mode and additionally provide filtration of the air in the emergency mode. It also serves to maintain a positive pressure within the CRPB of greater than 0.125 inch w.g. with a maximum of 1000 SCFM per train of outside air during system operation. Pressurization of the CRPB minimizes infiltration of unfiltered air through the CRPB from all the surrounding areas adjacent to the CRPB.
The subject breach in the suction plenum of Air Handling Unit XAH0048, resulted in the following conditions when the Control Room Normal and Emergency Air Handling System is operating in the emergency mode:
- The Control Room differential pressure (dp) decreased below the TS limit of 0.125 in w.g., with a measured dp of -0.1 inch w.g.
for Train "A" and a projected dp of greater than 0.1 inch w.g. for Train "B". This dp loss was attributed to the out-leakage of air due to the breach of XAH0048.
- To compensate for the out-leakage, OA intake flow increased above the TS limit of 1000 SCFM, with a measured value of -1054 SCFM for Train "A" and a projected value of Both conditions are adverse as control room personnel could possibly be exposed to a larger dose during a radiological event or to more hazardous conditions during a chemical release.
Outside Air Intake Flow - An increase in outside air intake flow of -100 SCFM (i.e., to 1100 SCFM) is judged to have a small adverse impact on both radiological and chemical event consequences. The impact on control room doses is small because the outside air is filtered before entering the control room in the emergency mode. Significance can be quantified by examining the limiting event for control room doses which, for VCSNS, is the postulated Loss-of-Coolant Accident (LOCA). Current design basis analyses for this accident are performed in accordance with Regulatory Guide 1.4. Thyroid, as opposed to whole body, doses are ANALYSIS OF EVENT (Continued) limiting. Existing studies indicate that an increase in the outside air flow of -100 SCFM would increase the 30-day thyroid dose by -0.85 Rem. This is equivalent to -4.7 SCFM of unfiltered inleakage into the CRPB. Dose impacts on other non-LOCA events would be significantly less because of the smaller source terms. Hazardous chemical assessments cbnsider a chlorine cylinder release and failure of the Ammonium Hydroxide Tank in accordance with the guidance of Revision 0 and Revision 1 of Regulatory Guide 1.78, respectively. Current analyses are based on the TS limit for outside air flow (1000 SCFM), but have inherent margins to accommodate potential increases in CRPB inleakage in excess of 700 SCFM before the applicable toxicity limit is approached.
Control Room Differential Pressure - A baseline ASTM E741 integrated test was performed in March 2005 to measure leakage into the CRPB. Filtered outside air was found to be within the current TS limits of 1000 SCFM per train and the maximum unfiltered CRPB inleakage recorded was 41 SCFM. This as-found condition was less that the current analysis limit of 55 SCFM, which is based on thyroid doses being less than or equal to 30 Rem during a postulated LOCA. A decrease in the Control Room differential pressure to - 0.1 inch w.g. is adverse since it creates the potential for unfiltered inleakage to increase above the previously measured maximum of 41 SCFM. This is of concern primarily from a LOCA dose standpoint since, based on current methods, margins are small (- 15 SCFM). Increases in unfiltered inleakage (if any) are expected to be small since a positive pressure would have been maintained in the Control Room.
inleakage margins are small because of the conservatisms inherent to the current licensing basis methods. Substantial increases in the margin (i.e., hundreds of SCFM's) could be made available by crediting the higher thyroid dose limits within Regulatory Guide 1.195 or Alternate Source Term methods. Even though the exact impact on unfiltered inleakage cannot be quantified, these inherent conservatisms provide reasonable assurance that the CR Normal and Emergency Air Handling System would have been able to accomplish its safety function.
CORRECTIVE ACTIONS
Repairs were made to the Air Handling Unit XAH0048 and the surveillance test was successfully completed on March 14, 2008.
An engineering evaluation determined that Air Handling Unit XAH0048 is capable of maintaining its portion of the CRPB during all required design basis events and transients.
The corrective actions from the root cause analysis to prevent recurrence include: 1) revise Station Administrative Procedure SAP-603 to provide specific details for restoration of the CRPB, 2) revise General Test Procedure GTP-214 to reference SAP-603 and to provide guidance for CRPB envelope testing after maintenance, and 3) process a design change per Engineering Change Request ECR-70441 to remove Air Handling Unit XAH0048 from the CRPB or to upgrade it.
Engineering Change Request ECR-70441 will make a determination whether to upgrade the documentation for XAH0048 and retain it within the CRPB or simplify the CRPB design by relocating it outside the CRPB.
PRIOR OCCURRENCES
There is no historical evidence of a prior occurrence.
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| | Reporting criterion |
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05000413/LER-2008-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | 05000334/LER-2008-001 | Control Room Envelope Air Intake During Normal Operation Higher Than Assumed In Design Basis Accident Dose Calculations | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000315/LER-2008-001 | Unit 1 Manual Reactor Trip due to Main Turbine Vibrations | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000272/LER-2008-001 | Inadvertent Start of an Emergency Diesel Generator During Testing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000251/LER-2008-001 | Manual Reactor Trip due to High Level in the 4A Steam Generator | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000247/LER-2008-001 | Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Loss of Feedwater Flow as a Result of Feedwater Pump Speed Control Malfunction | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000530/LER-2008-001 | Manual Reactor Trip when Removing a Degraded CEDM MG Set from Service | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000457/LER-2008-001 | 2A Essential Service Water Train Inoperable due to Strainer Fouling from Bryozoa Deposition and Growth | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000454/LER-2008-001 | Technical Specification Non-Compliance of Containment Sump Monitor Due to Improper Installation During Oriainal construction | | 05000440/LER-2008-001 | ' Condition Prohibited by Technical Specifications Due to Unrecognized Reactor Core Isolation Cooling Inoperability | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000483/LER-2008-001 | Containment Cooler Inoperability | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000412/LER-2008-001 | Unplanned Actuation of the Auxiliary Feedwater System During Plant Startup | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000374/LER-2008-001 | High Pressure Core Spray System Declared Inoperable Due to Failed Room Ventilation Supply Fan | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000323/LER-2008-001 | Reactor Trip Due to Main Electrical Transformer Failure | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000305/LER-2008-001 | Pressurizer PORV and Reactor Coolant System Vent Valves Appendix R Spurious Operation Concern | | 05000271/LER-2008-001 | Crane Travel Limit Stops not Installed as Required by Technical Specifications due to an Inadequate Procedure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000269/LER-2008-001 | Gas Void Found in High Pressure Injection System Suction Piping | | 05000263/LER-2008-001 | | | 05000261/LER-2008-001 | Appendix R Pathway Impassable due to Lock Configuration | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | 05000361/LER-2008-001 | Valid actuation of Emergency Feedwater system following Main Feedwater pump trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000335/LER-2008-001 | Unattended Ammunition Discovered Inside Protected Area | | 05000456/LER-2008-001 | Technical Specification Non-Compliance Due to Inadequate Design of Auxiliary Feedwater (AF) Tunnel Access Covers Causing AF Valves Within the Tunnel to be Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000423/LER-2008-001 | Postulated Fire Scenario Results in Unanalyzed Condition - Pressurizer Overfill | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000369/LER-2008-001 | Potential Failure of Containment Isolation Valves (CIV) to Remain Fully Closed and Ino erable loner than allowed bCTechnical S ecification 3.6.3. | | 05000220/LER-2008-002 | Manual Reactor Scram Due to Loss of Reactor Pressure Control | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000261/LER-2008-002 | Manual Reactor Trip due to High Turbine Vibrations | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000270/LER-2008-002 | Main Steam Relief Valves Exceeded Lift Setpoint Acceptance Band 050002 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000305/LER-2008-002 | 5 . Blocked Open Steam Exclusion Door Results in Postulated Inoperability of Safety Systems | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000336/LER-2008-002 | Unplanned LCO Entry - Three Charging Pumps Aligned for Injection With the Reactor Coolant System Temperature Less than 300 Degrees F. | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000354/LER-2008-002 | BLOWN lE INVERTER MAIN FUSE WITH ONE EMERGENCY DIESEL GENERATOR INOPERABLE CAUSES LOSS OF CONTROL ROOM EMERGENCY FILTRATION LOSS OF SAFETY FUNCTION | | 05000395/LER-2008-002 | Control Room Normal and Emergency Air Handling Systems Inoperable Due to Pressure Boundary Breach | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000382/LER-2008-002 | Inoperable Steam Generator Narrow Range Level Channels | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000369/LER-2008-002 | 'Energy® BRUCE H HAMILTON Vice President McGuire Nuclear Station Duke Energy Corporation MGOIVP 112700 Hagers Ferry Road Huntersville, NC 28078 704-875-5333 704-875-4809 fax bhhamilton@duke-energy.corn August 21, 2008
U.S. Nuclear Regulatory Commission
ATTENTION: Document Control Desk
Washington, D.C. 20555
Subject: Duke Energy Carolinas, LLC
McGuire Nuclear Station, Unit 1
Docket No. 50-369
Licensee Event Report 369/2008-02, Revision 0
Problem Investigation Process No.: M-08-03862
Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached
is Licensee Event Report (LER) 369/2008-02, Revision 0,
regarding the Unit 1 Reactor trip on June 26, 2008 due to
the 1B Reactor Coolant Pump Motor trip which was caused by
a failed surge capacitor.
This report is being submitted in accordance with 10 CFR
50.73 (a)(2)(iv)(A). This event is considered to be of no
significance with respect to the health and safety of the
public. There are no regulatory commitments contained in
this LER.
If questions arise regarding this LER, contact Lee A. Hentz
at 704-875-4187.
Very truly yours,
Bruce H. Hamilton
Attachment
www. duke-energy. corn U.S. Nuclear Regulatory Commission
August 21, 2008
Page 2
cc: L. A. Reyes, Regional Administrator
U.S. Nuclear Regulatory Commission, Region II
Sam Nunn Atlanta Federal Center
61 Forsyth Street, SW, Suite 23T85
Atlanta, GA 30303
J. F. Stang, Jr. (Addressee Only)
Senior Project Manager (McGuire)
U.S. Nuclear Regulatory Commission
Mail Stop O-8G9A
Washington, DC 20555
J. B. Brady
Senior Resident Inspector
U.S. Nuclear Regulatory Commission
McGuire Nuclear Station
B. 0. Hall, Section Chief
Radiation Protection Section
1645 Mail Service Center
Raleigh, NC 27699
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVEDBYOMB:NO.3150-0104 EXPIRES: 08/31/2010 (9-2007) Estimated burden per response to comply with this mandatory collection request: 50 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send ' LICENSEE EVENT REPORT (LER) comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a (See reverse for required number of means used to impose an information collection does not display a currently valid OMB control digits/characters for each block) number, the NRC may not conduct or sponsor, and a person is not required to respond to,' the information collection. 1, FACILITY NAME 2. DOCKET NUMBER I 3. PAGE 05000- ' 1 8McGuire Nuclear Station, Unit 1 _ 0369' OF .4, TITLE . . Unit 1 Reactor Trip due to the 1B Reactor Coolant Pump Motor Trip which was caused by a
failed Surge Capacitor | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000440/LER-2008-002 | Inoperable Emergency Closed Cooling System Results In Condition Prohibited By Technical Specifications | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000454/LER-2008-002 | Technical Specification Non-Compliance Due to Inadequate Design of Auxiliary Feedwater (AF) Tunnel Access Covers Causing AF Valves Within the Tunnel to be Inoperable | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000298/LER-2008-002 | Technical Specification Prohibited Condition Due to Safety Relief Valve Test Failure | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000237/LER-2008-002 | Unit 2 High Pressure Coolant Injection System Declared Inoperable | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000272/LER-2008-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000361/LER-2008-002 | Disturbance on the Pacific DC Intertie cause offsite power frequency to dip below operability limits | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000362/LER-2008-003 | Missed TS completion time results in TS Violation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000220/LER-2008-003 | Power Supplies for Drywell Pressure Indication not Qualified for Required Post-Accident Operating Duration | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000529/LER-2008-003 | Technical Specification - Limiting Condition for Operation 3.0.3 for Greater Than 1 Hour | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2008-003 | | | 05000263/LER-2008-003 | | | 05000423/LER-2008-003 | Automatic Reactor Trip During Shutdown for Refueling Outage 3R12 ., | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000251/LER-2008-003 | . Class 1 Weld Leak Due to Fatigue and Completion of Technical Specification Required Shutdown | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000282/LER-2008-003 | Loss of AFW Safety Function and Condition Prohibited by Technical Specifications Due to Mispositioned Isolation Valve | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000286/LER-2008-003 | Automatic Actuation of Emergency Diesel Generator 33 During Surveillance Testing Caused by .Inadvertent Actuation of the Undervoltage Sensing Circuit on 480 Volt AC Safeguards Bus 5A | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000361/LER-2008-003 | Disturbance on the Pacific DC Intertie cause offsite power frequency to dip below operability limits | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000305/LER-2008-003 | Door Bottom Seal Failure Results in Inoperability of Control Room Ventilation System | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat |
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