As part of a cause investigation regarding a late entry into TS LCO 3.8.1 for Unit 2, on April 19, 2006, it was identified that a reportable event had occurred during the 2004 Unit 1 refueling outage. On March 6, 2004, the Unit 1 4.16kV ESS 1A Bus was being tested in accordance with plant procedures. The ESS 1A Bus was de-energized and LCO 3.8.7 was entered for Unit 2. Unit 1 busses supply electrical power to common systems which impact Unit 2 safety systems and require entry into LCO 3.8.1 and 3.8.7. A review of operator logs for March 6, 2004, identified that only LCO 3.8.7 was entered when the bus was de-energized.
Entry into Unit 2 LCO 3.8.1, Conditions A, B and D was missed, resulting in Required Actions A.1 and B.1 not being performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the mandated time for Unit 2 to be in Mode 3 being exceeded.
The apparent cause for this event was attributed to confusing language in TS 3.8.1 which resulted in an inaccurate interpretation by plant personnel regarding which LCOs were required to be entered to support Unit 1 ESS Bus testing.
Because no loss of safety function occurred, there was no impact to the power required to operate safety-related loads necessary to cool the reactor core, maintain containment integrity, and support other vital functions in the event of a postulated accident in one reactor unit, while safely shutting down the unaffected unit.
- Interim compensatory measures were established to clearly state which TS LCOs were required to be entered during the remaining Unit 1 ESS Bus testing that was being performed during the Unit 1 refueling outage. PPL will revise TS 3.8.1 and/or Bases to provide clarity and remove interpretation on LCO applicability during ESS Bus testing.
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LER-2006-002, Missed Technical Specification LCO 3.8.1 Entry for Unit 2 During Unit 1 ESS Bus TestingDocket Number |
Event date: |
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Report date: |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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3882006002R00 - NRC Website |
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CONDITIONS PRIOR TO EVENT
Unit 1, Mode 5, Refueling Outage Unit 2, Model, 100% Power
BACKGROUND
The primary AC distribution system for Susquehanna Units 1 and 2 each consist of four 4.16 kV Engineered Safeguards System (ESS) buses having a primary and alternate offsite source of power as well as an onsite diesel generator (DG) source that supports one 4.16 kV ESS bus in each unit. In addition, some common support systems required by both units receive power through Unit 1 electrical power distribution subsystems.
EVENT DESCRIPTION
On March 11, 2006, with Unit 1 in a refueling outage, activities for testing the Unit 1 4.16kV ESS Bus 1D (1A204) were in progress. The testing required Unit 2 to enter LCO 3.8.7, Condition C. This was required since Unit 1 busses power common loads, and therefore impact Unit 2 SSCs that are required to be operable when Unit 2 is in Mode 1. PPL personnel later discovered that entry into LCO 3.8.1, Conditions A, B and D for Unit 2 were missed and should have been entered when the Unit 1 bus was de-energized. For a de-energized bus, Condition D requires entry into LCO 3.8.7. Because LCO 3.8.7 was initially entered when the bus was de-energized, the Required Actions for Condition D were met.
The Required Actions for Conditions A and B state that with "One offsite circuit inoperable, verify correct breaker alignment and indicated power availability for each offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter." Although the SR was not completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, this event was determined not to be reportable since the surveillance test was satisfactorily completed prior to exceeding the time required for Unit 2 to be in Mode 3.
As part of PPL's cause investigation for the late entry into TS LCO 3.8.1 for Unit 2, an extent of condition evaluation was performed. On April 19, 2006, PPL identified that a similar (yet reportable) event had occurred during the 2004 Unit 1 refueling outage. On March 6, 2004, the Unit 1 4.16kV ESS 1A Bus (1A201) was being tested in accordance with plant procedures. The ESS lA Bus was de energized and LCO 3.8.7 was entered for Unit 2. A review of operator logs for March 6, 2004, showed that only LCO 3.8.7 was entered when the Unit 1 bus was de-energized. Entry into Unit 2 LCO 3.8.1, Conditions A, B and D was missed, resulting in Required Actions A.1 and B.1 not being performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the mandated time for Unit 2 to be in Mode 3 being exceeded. Although Condition D was not entered, LCO 3.8.7 was entered when the bus was de-energized and the appropriate Required Actions were taken.
Because Unit 2 TS LCO 3.8.1, Required Actions A.1 and B.1 were not completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Action F requires Unit 2 to be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Mode 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Since it was
- not recognized in 2004 that entry into these conditions was required, this event is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B), for any operation or condition prohibited by Technical Specifications.
CAUSE OF EVENT
The apparent cause for the 2004 event was attributed to confusing language in TS 3.8.1 which resulted in an inaccurate interpretation by plant personnel regarding which LCOs were required to be entered to support the Unit 1 ESS Bus testing. Based on interviews with PPL personnel, the impact to operability of an offsite source and a DG during ESS Bus testing was recognized. However, the impact was open to interpretation regarding which LCOs were required to be entered.
ANALYSIS / SAFETY SIGNIFICANCE
Actual Consequences:
During the 2004 event, TS LCO 3.8.7 was entered for Unit 2, but entry into TS LCO 3.8.1, Conditions A, B, and D for Unit 2 was missed. Conditions A and B require SR 3.8.1.1 to be performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to verify correct breaker alignment and indicated power availability for each offsite circuit. Although the SR was not performed, a review of operator logs indicated that power was available to both offsite circuits and the 'A', 'B' and 'CY DGs remained operable and therefore, the intent of the SR was met.
Of the three conditions, Condition D imposed the most restrictive completion time (i.e., 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Unit 2 to be in Mode 3) for one onsite and one offsite 4.16kV power source inoperable. However, the Required Actions in Condition D are modified by a note that states that when Condition D is entered for a de-energized bus and not an inoperable bus, entry into the applicable Conditions and Actions for LCO 3.8.7 are required. In 2004, the Unit 1 ESS bus was de-energized. Entry into LCO 3.8.7 requires a safety function determination (SFD) to be performed in accordance with LCO 3.0.6 to ensure that a loss of safety function had not occurred. During the 2004 event, a SFD was performed which concluded that no loss of safety function had occurred. As such, there was no impact to the power required to operate safety-related loads necessary to cool the reactor core, maintain containment integrity, and support other vital functions in the event of a postulated accident in one reactor unit, while safely shutting down the unaffected unit.
Potential Consequences:
During the 2004 event, the worst case scenario would have been if Unit 2 had had an event (such as loss of an offsite power source or a DG) which required safety-related loads powered by the Unit 1 bus to be available to mitigate the event. However, based on plant design, sufficient power sources (i.e., 3 DGs or 1 offsite power source) would have been available to provide power to safety-related loads necessary to mitigate an event.
CORRECTIVE ACTIONS
Immediate Corrective Action
- Interim compensatory measures were established to clearly state which TS LCOs were required to be refueling outage.
Action(s) to Prevent Recurrence
- Revise TS 3.8.1 and/or Bases to provide clarity and remove interpretation on LCO applicability during ESS Bus testing.
PREVIOUS SIMILAR EVENTS
None
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05000305/LER-2006-010 | | | 05000456/LER-2006-001 | Unit 1 Reactor Coolant System Pressure Boundary Leakage Due To Inter-Granular Stress Corrosion Cracking of a Pressurizer Heater Sleeve | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000454/LER-2006-001 | Technical Specification Required Action Completion Time Exceeded for Inoperable Containment Isolation Valves Due to Untimely Operability Determination | | 05000423/LER-2006-001 | Loss Of Safety Function Of The Control Room Emergency Ventilation System | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000369/LER-2006-001 | Ice Condenser and Floor Cooling System Containment Isolation Valve inoperable longer than allowed by Technical Specification 3.6.3. | | 05000353/LER-2006-001 | HPCI Ramp Generator Signal Converter Failure | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000352/LER-2006-001 | Loss Of One Offsite Circuit Due To Invalid Actuation Of Fire Suppression System | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000336/LER-2006-001 | | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | 05000316/LER-2006-001 | Failure to Comply with Technical Specification 3.6.2, Containment Air Locks | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000315/LER-2006-001 | Plant Shutdown Required by Technical Specification Action 3.6.5.B.1 | | 05000293/LER-2006-001 | | 10 CFR 50.73(a)(2)(iv), System Actuation | 05000289/LER-2006-001 | | | 05000287/LER-2006-001 | Actuation of Emergency Generator due to Spurious Transformer Lockout | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000251/LER-2006-001 | Turkey Point Unit 4 05000251 1 OF 6 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000247/LER-2006-001 | Manual Reactor Trip Due to Multiple Dropped Control Rods Caused by Loss of Control Rod Power Due to Personnel Error | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000440/LER-2006-001 | Incorrect Wiring in the Remote Shutdown Panel Results in a Fire Protection Program Violation | | 05000413/LER-2006-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000368/LER-2006-001 | Completion of a Plant Shutdown Required by Technical Specifications Due to Loss of Motive Power to Certain Containment Isolation Valves as a Result of a Phase to Ground Short Circuit in a Motor Control Cubicle | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000306/LER-2006-001 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000298/LER-2006-001 | Cooper Nuclear Station 05000298 1 of 4 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000286/LER-2006-001 | I | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000282/LER-2006-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000266/LER-2006-001 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000261/LER-2006-001 | Manual Reactor Trip Due to Failure of a Turbine Governor Valve Electro-Hydraulic Control Card | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000255/LER-2006-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000461/LER-2006-002 | Turbine Bypass Function Lost Due to Circuit Card Maintenance Frequency | | 05000458/LER-2006-002 | Loss of Safety Function of High Pressure Core Spray Due to Manual Deactivation | | 05000456/LER-2006-002 | Units 1 and 2 Entry into Limiting Condition for Operation 3.0.3 due to Main Control Room Ventilation Envelope Low Pressure | | 05000443/LER-2006-002 | Noncompliance with the Requirements of Technical Specification 6.8.1.2.a | | 05000387/LER-2006-002 | DMissed Technical Specification surveillance requirement | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000362/LER-2006-002 | Unit 3 Shutdown to Inspect Safety Injection Tank Spiral Wound Gaskets | | 05000336/LER-2006-002 | Manual Reactor Trip Due To Trip Of Both Feed Pumps Following A Loss Of Instrument Air | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000316/LER-2006-002 | | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000315/LER-2006-002 | Failure to Comply with Technical Specification Requirement 3.6.13, Divider Barrier Integrity | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000293/LER-2006-002 | | | 05000289/LER-2006-002 | | | 05000251/LER-2006-002 | Intermediate Range High Flux Trip Setpoint Exceeded Technical Specification Allowable Value | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000440/LER-2006-002 | Scaffold Built in the Containment Pool Swell Region | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000413/LER-2006-002 | Safe Shutdown Potentially Challenged by an External Flooding Event and Inadequate Design and Configuration Control | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000388/LER-2006-002 | Missed Technical Specification LCO 3.8.1 Entry for Unit 2 During Unit 1 ESS Bus Testing | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000348/LER-2006-002 | Main Steam Isolation Valve Failure to Close | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000305/LER-2006-002 | | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000301/LER-2006-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000286/LER-2006-002 | 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249Entergy Tel (914) 734-6700 Fred Dacimo Site Vice President Administration September 13, 2006 Indian Point Unit No. 3 Docket No. 50-286 N L-06-084 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001 Subject:L Licensee Event Report # 2006-002-00, "Manual Reactor Trip as a Result of Arcing Under the Main Generator Between Scaffolding and Phase A&B of the Isophase Bus Housing" Dear Sir: The attached Licensee Event Report (LER) 2006-002-00 is the follow-up written report submitted in accordance with 10 CFR 50.73. This event is of the type defined in 10 CFR 50.73(a)(2)(iv)(A) for an event recorded in the Entergy corrective action process as Condition Report CR-IP3-2006-02255. There are no commitments contained in this letter. Should you or your staff have any questions regarding this matter, please contact Mr. Patric W. Conroy, Manager, Licensing, Indian Point Energy Center at (914) 734-6668. Fred R. Dacimo Site Vice President Indian Point Energy Center Docket No. 50-286 NL-06-084 Page 2 of 2 Attachment: LER-2006-002-00 CC: Mr. Samuel J. Collins Regional Administrator — Region I U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspector's Office Resident Inspector Indian Point Unit 3 Mr. Paul Eddy State of New York Public Service Commission INPO Record Center NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES: 06/30/2007
(6-2004)
. Estimated burden per response to comply with this mandatory collection request: 50 hours.DReported lessons learned are incorporated into the licensing process and fed back to industry. Send 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 internetLICENSEE EVENT REPORT (LER) 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 means used to impose an information collection does not display a currently valid OMB control 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
INDIAN POINT 3 05000-286 1 OF 6
4.TITLE: Manual Reactor Trip as a Result of Arcing Under the Main Generator Between
Scaffolding and Phase A&B of the Iso-phase Bus Housing | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000282/LER-2006-002 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000269/LER-2006-002 | High Energy Line Breaks Outside Licensing Basis May Result in Loss of Safety Function | | 05000263/LER-2006-002 | | | 05000255/LER-2006-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000254/LER-2006-002 | Quad Cities Nuclear Power Station Unit 1 05000254 1 of 3 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000483/LER-2006-003 | Unexpected Inoperability of the Emergency Exhaust System due to Inoperable Pressure Boundary | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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