:on 970311,operator Opened Local Sys Auxiliary Transformer Panel.Cause of Sys Auxiliary Transformer Trip Could Not Be Conclusively Determined.Unit 2 Sys Auxiliary Transformer Tested for Damage| ML20137T253 |
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Zion File:ZionSolutions icon.png |
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| Issue date: |
04/10/1997 |
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| From: |
Brennan N COMMONWEALTH EDISON CO. |
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| Shared Package |
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| ML20137T135 |
List: |
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| References |
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| LER-97-007-02, LER-97-7-2, NUDOCS 9704160044 |
| Download: ML20137T253 (4) |
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Similar Documents at Zion |
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LICENSEE EVENT REPORT (LER)
FACILITY RAME DOCKET NUMBER PAGE Zion Nuclear Power Station Unit 1 0l5l0l0l0l2l9l5 1l0Fl0l4 i
TITLE j
System Auxiliary Transformer Trip Caused By Spurious Operation of the Sudden Pressure Relay with Minimal Impact to the j
Plant EVENT DATE LER NUMBER REPORT DATE OTHER FACILITIES INVOLVE 0
}
MONTH DAY YEAR YEAR sEO.
REV.
MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER (s) i i
7 ION UNIT ?
O l 5 l 0 l 0 l 0 l 3 l 0 l4 i
j oi3 ili al7 al7 olol7 olo 014 ilo al7 I I I I I I I THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS DF 10 CFR 5: (CHECK ONE OR MORE OF THE FOLLOWING)
)
OPERATING MODE i
j 5
20.402(b) 20.405(e)
X 50.73(a)(2)(iv) 73.71(b) j POWER 20.405(a)(1)(1) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c) 0l0l0 LEVEL I
20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(v11)
OTHER (Specify in
)
20.405(a)(1)(111) 50.73(a)(2)(1) 50.73(a)(2)(v111)(A)
Abstract below 20.405(a)(1)(iv) 50.73(a)(7)(ii) 50.73(a)(2)(v111)(B) 3
}
20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LICENSEE CONTACT FOR TH]5 LER NAME TELEPHONE NUMPER i
1 N, M. Brennan, Regulatory Assurance Ext. 2380 i
e1417 714181-121 ole 14-
)
COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT
CAUSE
SYSTEM COMPONENT MANUFACTURER
CAUSE
SYSTEM COMPONENT MA1UFACTURER p
p
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N Ela i 1613 clolelo j
l j l l l g j
i I i i I I I I
I I I I I I
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SUPPLEMENTAL REPORT EXPECTED EXPECTED MONTH DAY YEAR l
SUBMISSION l YEs (If yes. complete EXPECTED submiss!ON DATE)
M NO DATE l
l l
I ABSTRACT (Limit to 1400 spaces. i.e., approximately fifteen single-space typewritten lines).
i At 1554 on March 11, 1997, during rounds, an operator opened the local System Auxil13ry Transformer (SAT) panel.
While leaning against the open panel to tap the oil temperature gauge mounted above the panel, he heard a click.
The SAT deluge activated to spray water on the SAT. the SAT tripped, and th! I experienced an undervoltage j
condition on the safeguard buses. The loads on the safeguard buses were str ipped, the Emergency Diesel Generators l
(EDG) started, and essential loads were sequenced onto the safeguard bwss. This event is reportable per 10CFR 50.73(a)(2)(1v). The sudden pressure lockout relay and associated auxiliary relay were found tripped which indicated the SAT sudden pressure relay (SPR) circuitry had energized. Testing confirmed that the SAT had not j
experienced a sudden pressure event and the sudden pressure circuit was operating properly. Operator error was ruled out. The EDG safe shutdown timer was found not to have fully reset automatically and was reset manually.
The safety significance of these events were minimal as safety related equipment actuated as designed and the timer reset failure does not affect EDG operation.
The cause of the SAT trip could not be conclusively determined. The most probable cause is spurious operation of the SAT SPR. Spurious operation of SPRs has been experienced both within Comed and the utility industry.
Corrective actions taken: 1) the SAT was tested for damage, and none was found. 2) the SPR was replaced with a newer. more reliable model and tested satisfactorily after installation.
- 3) the faulty sudden pressure relay was sent to a lab for analysis. 4) the Unit 2 SAT SPRs will be replaced. 5) Operator actions near electrical panels were addressed, and 6) repairs to the safe shutdown timer are scheduled.
9704160044 970410 PDR ADOCK 05000295 S
PDR i
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY RAME DOCKET NUMBER LER NUMBER PAGE l
YEAR SE0.
REV.
l ZION NUCLEAR POWER STATION 0l5l0l0l0l2l9l5 9l7 0l0l7 0l0 0l2 0l4 0F TEXT Energy Industry Identificatioa System (EIIS) codes are identified in the text 85 [XX]
A.
PLANT CONDITIONS PRIOR TO EVENT Unit 1 MODE 5 - Maintenance Outaae Rx Power !)) RCS [AB] Temp./ Pressure Ambient / Atmos Unit 2 MODE 5 - Refuelina Rx Power M RCS [AB] Temp./ Pressure Ambient / Atmos B.
DESCRIPTION OF EVENT
At 1554 on March 11. 1997 an equipment operator was making his rounds.
The operator opened the local SAT 3anel door to observe the status of various equipment in the panel.
In addition tie operator leaned against the open panel in an attempt to tap the oil temperature gauge mounted above the panel. As he tapped or was about to tap the gauge (operator doesn't remember), he heard a click and the SAT deluge activated, water sprayed on the transformer, and the SAT tripped.
The Unit 1 safeguard buses experienced an undervoltage condition the emergency diesel started. and the blackout timers sequenced the essential Unit 1 essential blackout equipment onto their respective buses.
After the SAT was secured. a walkthrough of the operator's actions was performed.
It was observed that the sudden pressure lockout relay (86) and associated auxiliary relay (63FPX) were tripped.
A review of drawing 22E-1-4814B indicated that the SAT sudden pressure relay circuitry had energized.
Based on this observation it was assumed the SAT had experienced a sudden pressure event. Transformer oil samples were taken but the analysis did not show an indication of an internal problem in the SAT which would have resulted in a pressure spike.
Operational Analysis Department performed various electrical tests on the SAT and found no indication of damage to the transformer.
At Zion, the SAT sudden pressure circuit contains a fault 3ressure relay (63FP), an auxiliary relay (63FPX). and a lockout relay (86).
Both t7e 63FPX and the 86 relays are located in a control panel i.ounted on the north side of the SAT.
Both relays have indicator flags which will indicate when they are tripped.
The 63FP relay is mounted about 4 feet off the ground on the transformer tank and approximately 8 feet from the control panel.
This equipment is not safety related and is installed to minimize damage to the SAT in the event of sudden pressure increase resulting from an internal fault. The relay will not actuate by gradual pressure variations due to transformer temperature changes by normal pump surges, vibrations or mechanical shock. The 63FP relay consists of a sealed housing divided into upper and lower chambers.
The upper chamber contains a piston, a cylinder block, and a self resetting snap-action switch.
The lower chamber contains the spring reinforced bellows which is filled with a special silicone oil with definite physical properties. The upper chamber contains a volume of reserve oil.
The piston contains an equalizing hole to allow for slow pressure changes due to temperature changes and pump starts.
The snap-action switch is a single-pole double throw switch with normally open (NO) and normally closed (NC) contacts.
ILER\\971245.ler(2)
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME DOCKET N1JMBER LER NUMBER PAGE YEAR SEO.
REV.
ZION NUCLEAR POWER STAT 10N 0lSl0l0l0l2l9l5 9l7 0l0l7 0l0 0l3 0l4
~
0F l
TEXT Energy Industry Identification System (Ell 5) codes are identified in the text as [XX]
B.
DESCRIPTION OF EVENT (Continued)
The NC contact of the 63FP relay is wired across the coil of the 63FPX relay to suppress misoperation due to a voltage surge in the control or relay wiring. A review of the circuit showed a DC ground will not cause enough current flow in the 63FPX circuit to cause the relay to operate.
Station logs indicated there was not a DC ground prior to this event. The N0 contact of the 63FP relay is wired in series with the 63FPX coil.
When the 63FP relay operates, the NC 63FP conta>ct opens and the N0 contact closes to energize the 63FPX relay.
The 63FPX relay then operates the 86 relay which trips the SAT, actuates the transformer deluge, and gives an alarm in the control room.
The sudden pressure circuit was tested and the circuit was found to be operating properly.
The circuit was reset, the panel with the 63FPX and 86 relays was vigorously shaken, and the temperature gauge was tap)ed to duplicate an operator action which could have caused this event. Because t1ese actions did not result in actuation of these relays, operator action and inadvertent operation of the 63FPX were eliminated as the causes of the event.
The SPk was replaced with a newer. more reliable model, and the circuit tested satisfactorily.
The SAT was returned to service on March 14, 1997 at 0735.
The Main and Unit Auxiliary Transformer SPRs are a different type and supplied by a different manufucturer.
As a result of the SAT trip the Unit 1. Division 17-2 Safe Shutdown Timer was activated. A subsequent walkdown of this timer revealed it did not fully reset automatically. This problem did not impede the o)eration of the safety related equipment associated with the SAT trip.
The pro)lem may have caused non-sequential loading of the Emergency Diesel Generator in a subsequent event. This malfunction has been addressed in a previous evaluation and corrective actions are in place.
C.
CAUSE OF EVENT
The cause of the event could not be conclusively determined.
The most probable cause is a spurious operation of the SAT sudden pressure relay.
This conclusion is based on the elimination of other possible causes and reports of spurious operation of these relays in the past.
l t
l ILER\\971245.ler(3)
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
]
FACILITY NAME DOCKET NUMBER LER NUMBER PAGE YEAR SEO.
REV.
ZION N'JCLEAR POWER STATION j
0l5l0l0l0l2l9l5 9l7 0l0l7 0l0 0l4 0l4 f
~
~
0F TEXT Energy Industry Identification System (E115) codes are identified in the text as [XX]
D.
SAFETY ANALYSlS This event is reportable pursuant to 10CFR50.73(a)(2)(iv). which states that the licensees shall report:
..any event or condition that results in manual or automatic actuation of any Engineered Safety System (ESF)." The event of the Unit 1 System Auxiliary Transformer (SAT) #142 tripping off in Mode 5 produced a loss of Offsite power to Unit 1.
The SAT trip caused an undervoltage condition on Unit 1 which stripped the safeguard buses, started the Emergency Diesels, and caused the blackout timers to sequence the essential blackout equipment onto their respective buses. The safety significance of the event was minimal since all three Unit 1 diesels started and sequenced on blackout loads.
The reserve feed from Unit 2 SAT #242 and the respective switchgear were available to supply power to Unit 1 safeguarri buses if needed. The failure of the safe shutdown timer to reset automatically did not impede the operation of safety related equipment associated with the SAT trip.
E.
CORRECTIVE ACTIONS
1.
The SAT was tested for damage and none was found.
2 The sudden pressure relay was replaced with a new more reliable model which is i
less prone to spurious operation.
The circuit tested satisfactorily after i
l installation.
3.
The existing sudden pressure relay was sent to a lab for analysis to determine i
the cause of the failure.
l i
4.
The Unit 2 SAT sudden pressure relays will be replaced prior to going to mode 4.
1 5.
As an additional management action, the Unit 1 Operations Manager issued a memo regarding work practice improvements which has been discussed at all shift briefs. The memo addressed operator conduct when working in or around electrical 1
panels and stopping the practice of tapping on gauges.
6.
The Division 17-2 Safe Shutdown timer automatic reset function will be repaired.
F.
PREVIOUS EVENTS SEARCH AND ANALYSIS Similar events have been reported involving the inadvertent operation of sudden pressure relays both within Comed and in the industry.
This information is based on discussions with transformer experts (associated with the transformer manufacturers and the relay manufacturer) and Electric Power Research Institute (EPRI).
- However, the failed relays were not documented or analyzed to determine the cause of the inadvertent operation.
4 G.
COMPONENT FAILURE DATA
General Electric Type J Fault Pressure Relay t
2LER\\971245.ler(4)
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| 05000295/LER-1997-001-01, Forwards LER 97-001-01,which Clarifies Info on Root Cause,Safety Analysis & Event Description.Corrective Actions Updated to Show Status of Items | Forwards LER 97-001-01,which Clarifies Info on Root Cause,Safety Analysis & Event Description.Corrective Actions Updated to Show Status of Items | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000295/LER-1997-001, Forwards LER 97-001-00 Which Involved Discovery of Lack of Sump Cover Plate Holes Contrary to Plant Structural Drawing Details,Per 10CFR50.73(a)(2)(ii)(B) | Forwards LER 97-001-00 Which Involved Discovery of Lack of Sump Cover Plate Holes Contrary to Plant Structural Drawing Details,Per 10CFR50.73(a)(2)(ii)(B) | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000295/LER-1997-001-14, :on 970110,recirculation Sump Cover Plate Holes Were Not Installed at Original Construction.Caused by Construction Error.Holes Installed IAW Emergency Exempt Change Prepared Prior to Ramp Down |
- on 970110,recirculation Sump Cover Plate Holes Were Not Installed at Original Construction.Caused by Construction Error.Holes Installed IAW Emergency Exempt Change Prepared Prior to Ramp Down
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(e)(2) | | 05000295/LER-1997-001-03, :on 970110,recirculation Sump Covers Were Not Installed at Original Construction.Cause Is Unknown & Impact on Plant Operation Is Unknown.Sump Cover Was Removed,Holes Were Drilled & Cover Replaced Prior to Expiration of LCO |
- on 970110,recirculation Sump Covers Were Not Installed at Original Construction.Cause Is Unknown & Impact on Plant Operation Is Unknown.Sump Cover Was Removed,Holes Were Drilled & Cover Replaced Prior to Expiration of LCO
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-001-11, :on 970902,Unit 2 Instrument Bus Perturbation Occurred.Caused by Insufficient Policy/Guidelines. Development of Policy for Proper Use of Protective Gear, Equipment & Tools |
- on 970902,Unit 2 Instrument Bus Perturbation Occurred.Caused by Insufficient Policy/Guidelines. Development of Policy for Proper Use of Protective Gear, Equipment & Tools
| 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-001, Forwards LER 97-001-00 Per 10CFR50.73(a)(2)(iv) Which Requires Written Rept Using NRC Form 366, License Event Rept, within 90 Days of Discovery of Event.Attachment a Contains Commitments Associated W/Ltr | Forwards LER 97-001-00 Per 10CFR50.73(a)(2)(iv) Which Requires Written Rept Using NRC Form 366, License Event Rept, within 90 Days of Discovery of Event.Attachment a Contains Commitments Associated W/Ltr | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000295/LER-1997-002, Forwards LER 97-002-00.Commitments Made by Util Listed | Forwards LER 97-002-00.Commitments Made by Util Listed | 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1997-002-01, :on 970117,containment Isolation Valves Were Not Tested Prior to Leaving Cold Shutdown.Caused by Mgt Deficiencies in TS Implementation Process.Containment Isolation Valves Will Be Verified Tested Prior to Mode 4 |
- on 970117,containment Isolation Valves Were Not Tested Prior to Leaving Cold Shutdown.Caused by Mgt Deficiencies in TS Implementation Process.Containment Isolation Valves Will Be Verified Tested Prior to Mode 4
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-002-09, :on 971012,inadvertent Isolation of Svc Water Cooling to 2B DG During Sys Alignment,Occurred.Caused by Shift Mgt Not Ensuring All Operability Requirements Met. Valve 2MOV-SW0023 Opened to Restore Flow to 2B EDG |
- on 971012,inadvertent Isolation of Svc Water Cooling to 2B DG During Sys Alignment,Occurred.Caused by Shift Mgt Not Ensuring All Operability Requirements Met. Valve 2MOV-SW0023 Opened to Restore Flow to 2B EDG
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-002, Forwards LER 97-002-00,per 10CFR50.73(a)(2)(v)(B),which Requires 30 Day Written Rept.Commitments Associated W/Correspondence,Encl | Forwards LER 97-002-00,per 10CFR50.73(a)(2)(v)(B),which Requires 30 Day Written Rept.Commitments Associated W/Correspondence,Encl | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | | 05000295/LER-1997-003, :on 970117,determined That EDG Tests Completed in Previous Refueling Outages Failed to Meet TS Requirement. Caused by Programmatic Deficiencies.Corrected Deficient Procedures & Completed Tests on Operating Unit |
- on 970117,determined That EDG Tests Completed in Previous Refueling Outages Failed to Meet TS Requirement. Caused by Programmatic Deficiencies.Corrected Deficient Procedures & Completed Tests on Operating Unit
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-003, Forwards LER 97-003-00 Re Unit 2 RHR Sys Declared Inoperable,Per 10CFR50.73(a)(2)(v)(B) | Forwards LER 97-003-00 Re Unit 2 RHR Sys Declared Inoperable,Per 10CFR50.73(a)(2)(v)(B) | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) | | 05000304/LER-1997-003-10, :on 971014,unit 2 RHR Sys Declared Inoperable. Caused by Oil Leak from Oil Bulb.Leak Coming from Oil Bulb on Ob CC Pump Stopped by Removing Bulb & Inspected |
- on 971014,unit 2 RHR Sys Declared Inoperable. Caused by Oil Leak from Oil Bulb.Leak Coming from Oil Bulb on Ob CC Pump Stopped by Removing Bulb & Inspected
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) | | 05000304/LER-1997-004-08, :on 971015,small Bore Containment Penetration Line Inadequately Supported Since Plant Construction Was Noted.Cause Cannot Be determined.Non-destructive Exams Performed to Determine Condition & Integrity of Pipe |
- on 971015,small Bore Containment Penetration Line Inadequately Supported Since Plant Construction Was Noted.Cause Cannot Be determined.Non-destructive Exams Performed to Determine Condition & Integrity of Pipe
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2) | | 05000304/LER-1997-004, Forwards LER 97-004-00,per 10CFR50.73(a)(2)(i).Commitments Associated W/Correspondence,Encl | Forwards LER 97-004-00,per 10CFR50.73(a)(2)(i).Commitments Associated W/Correspondence,Encl | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000295/LER-1997-004, Forwards LER 97-004-00 Re Failure to Start Pump in Required Time & Led to Declaring 1C Containment Spray Pump Inoperable | Forwards LER 97-004-00 Re Failure to Start Pump in Required Time & Led to Declaring 1C Containment Spray Pump Inoperable | | | 05000295/LER-1997-004-04, :on 970221,identified Failure to Start Pump in Required Time & Led to Declaring 1C Containment Spray Inoperable.Caused by Clogged Fuel Filter & Defective components.1C Containment Spray Pump Fuel Drained & Flushed |
- on 970221,identified Failure to Start Pump in Required Time & Led to Declaring 1C Containment Spray Inoperable.Caused by Clogged Fuel Filter & Defective components.1C Containment Spray Pump Fuel Drained & Flushed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1997-004-01, :on 970221,reactor Was Shutdown,Per LCO 3.6.1 Due to One Inoperable Containment Spray pump.1C CS Pump Day Tank Was Drained,Flushed,Refilled w/biocide-added Fuel from Different Source |
- on 970221,reactor Was Shutdown,Per LCO 3.6.1 Due to One Inoperable Containment Spray pump.1C CS Pump Day Tank Was Drained,Flushed,Refilled w/biocide-added Fuel from Different Source
| 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | | 05000295/LER-1997-005, Forwards LER 97-005-00 IAW 10CFR50.73(a)(2)(i)(B).Actions Listed | Forwards LER 97-005-00 IAW 10CFR50.73(a)(2)(i)(B).Actions Listed | 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-005, Forwards LER 97-005-00 Which Documents Event That Occurred at Zion Nuclear Power Station,Unit 2.Commitment Made within Ltr,Encl | Forwards LER 97-005-00 Which Documents Event That Occurred at Zion Nuclear Power Station,Unit 2.Commitment Made within Ltr,Encl | 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-005-07, :on 971021,failed to Test 2A SI Pump Suction Valve in Prescribed Periodicity.Caused by Inadequate Program to Ensure That TS IST Requirements for Each Component Are Met.Ist Group Will Include Second Check in Review |
- on 971021,failed to Test 2A SI Pump Suction Valve in Prescribed Periodicity.Caused by Inadequate Program to Ensure That TS IST Requirements for Each Component Are Met.Ist Group Will Include Second Check in Review
| 10 CFR 50.73(a)(1), Submit an LER 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) | | 05000295/LER-1997-005-03, :on 970221,supplement to Unapproved Mode Change W/Ts Required Equipment Inoperable Were Noted.Caused by Inadequate Planning & Briefing.Both Units Have Been Placed in Cold Shutdown W/Rcs at Atmospheric Pressure |
- on 970221,supplement to Unapproved Mode Change W/Ts Required Equipment Inoperable Were Noted.Caused by Inadequate Planning & Briefing.Both Units Have Been Placed in Cold Shutdown W/Rcs at Atmospheric Pressure
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(viii)(B) | | 05000304/LER-1997-006-07, :on 971028,informed of Potential to Exceed 10CFR50.46 ECCS Acceptance Criteria.Caused by Fuel Clad Gap re-opening & 17% Maximum Cladding Oxidation Limit.Performed Conservative Corrosion Calculations |
- on 971028,informed of Potential to Exceed 10CFR50.46 ECCS Acceptance Criteria.Caused by Fuel Clad Gap re-opening & 17% Maximum Cladding Oxidation Limit.Performed Conservative Corrosion Calculations
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000304/LER-1997-006, Forwards LER 97-006-00 Per 10CFR50.73(a)92)(ii)(B) Which Requires 30 Day Written Rept When Any Event or Condition Occurs That Resulted in Condition of Nuclear Power Plant. Regulatory Commitments Encl | Forwards LER 97-006-00 Per 10CFR50.73(a)92)(ii)(B) Which Requires 30 Day Written Rept When Any Event or Condition Occurs That Resulted in Condition of Nuclear Power Plant. Regulatory Commitments Encl | 10 CFR 50.73(a)(2) | | 05000295/LER-1997-006, :on 970222,Zion Station Exceeded Limiting Condition for Operation Due to Inadequate Procedure Controls.Standing Order to Require Review of TS During OOS Procedure Implementation,Was Issued |
- on 970222,Zion Station Exceeded Limiting Condition for Operation Due to Inadequate Procedure Controls.Standing Order to Require Review of TS During OOS Procedure Implementation,Was Issued
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-007-06, :on 971030,failure to Maintain Required Number of Svc Water Pumps Operable Was Identified.Caused by Failure of Mgt Personnel to Adhere to Requirements for Reviewers to Use Applicable Drawings.Procedure Rev to Provide Guidanc |
- on 971030,failure to Maintain Required Number of Svc Water Pumps Operable Was Identified.Caused by Failure of Mgt Personnel to Adhere to Requirements for Reviewers to Use Applicable Drawings.Procedure Rev to Provide Guidance
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1997-007-02, :on 970311,operator Opened Local Sys Auxiliary Transformer Panel.Cause of Sys Auxiliary Transformer Trip Could Not Be Conclusively Determined.Unit 2 Sys Auxiliary Transformer Tested for Damage |
- on 970311,operator Opened Local Sys Auxiliary Transformer Panel.Cause of Sys Auxiliary Transformer Trip Could Not Be Conclusively Determined.Unit 2 Sys Auxiliary Transformer Tested for Damage
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(7)(ii) | | 05000295/LER-1997-007, Forwards LER 97-007-00 Re Automatic Actuation of Esf. Submitted Table Identifies Actions Committed to by Util | Forwards LER 97-007-00 Re Automatic Actuation of Esf. Submitted Table Identifies Actions Committed to by Util | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000304/LER-1997-007, Forwards LER 97-007-00 Per 10CFR50.73(a)(2)(v)(B) Which Requires Written Rept for Any Event or Condition That Could Prevent Fulfillment of Safety Function of Structures or Sys Needed to Remove Residual Heat.W/Commitments Attach | Forwards LER 97-007-00 Per 10CFR50.73(a)(2)(v)(B) Which Requires Written Rept for Any Event or Condition That Could Prevent Fulfillment of Safety Function of Structures or Sys Needed to Remove Residual Heat.W/Commitments Attached | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | | 05000295/LER-1997-008, :on 970321,air Filters Containing Al Were Inadvertently Installed in Containment Due to Faulty Parts Selection Process.Hepa Filters Containing Al Will Be Removed or Replaced w/non-Al Containing Filters |
- on 970321,air Filters Containing Al Were Inadvertently Installed in Containment Due to Faulty Parts Selection Process.Hepa Filters Containing Al Will Be Removed or Replaced w/non-Al Containing Filters
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-008-07, :on 971122,safety Related Snubber Not in Snubber Program & Subsequently Was Not Inspected Per Ts. Cause Unknown.Procedure TSS 15.6.48 Revised to Incorporate Unit 2 Snubber |
- on 971122,safety Related Snubber Not in Snubber Program & Subsequently Was Not Inspected Per Ts. Cause Unknown.Procedure TSS 15.6.48 Revised to Incorporate Unit 2 Snubber
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-008, Forwards LER 97-008-00 Per 10CFR50.73(a)(2)(i)(B),which Requires 30 Day Written Rept.Attachment a Provides Commitments Associated W/Correspondence | Forwards LER 97-008-00 Per 10CFR50.73(a)(2)(i)(B),which Requires 30 Day Written Rept.Attachment a Provides Commitments Associated W/Correspondence | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000295/LER-1997-009-01, :on 970114,1FCV-CS0002 Was Inoperable Between 970115 & 0208.Caused by Failure to Verify That Acceptance Criteria for Return to Service Was Met.Disciplined Unit Supervisor & Will Cover Event in Licensed Operator Training |
- on 970114,1FCV-CS0002 Was Inoperable Between 970115 & 0208.Caused by Failure to Verify That Acceptance Criteria for Return to Service Was Met.Disciplined Unit Supervisor & Will Cover Event in Licensed Operator Training
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1997-009, Forwards LER 97-009-00 IAW 10CFR50.73(A)(2)(i)(B) Which Requires Listed Corrective Actions | Forwards LER 97-009-00 IAW 10CFR50.73(A)(2)(i)(B) Which Requires Listed Corrective Actions | | | 05000304/LER-1997-009-08, :on 971202,test Relay SIX1-AX Did Not Unlatch as Required During Restoration of PT 10-3.Caused by Failure to Follow Procedures.Rewired Test Relay SIX1-AX |
- on 971202,test Relay SIX1-AX Did Not Unlatch as Required During Restoration of PT 10-3.Caused by Failure to Follow Procedures.Rewired Test Relay SIX1-AX
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000304/LER-1997-009, Forwards LER 97-009-00,re Event Which Occurred at Zion Nuclear Power Station,Unit 2.Commitments Made within Ltr Also Encl | Forwards LER 97-009-00,re Event Which Occurred at Zion Nuclear Power Station,Unit 2.Commitments Made within Ltr Also Encl | 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000295/LER-1997-010, :on 960316,reactor Trip Due to Equipment Failure Occurred.Caused by New But Defective Pneumatic Vol Booster on Valve.Pneumatic Vol Booster for 1C Main FW Regulating Valve Replaced |
- on 960316,reactor Trip Due to Equipment Failure Occurred.Caused by New But Defective Pneumatic Vol Booster on Valve.Pneumatic Vol Booster for 1C Main FW Regulating Valve Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000295/LER-1997-010-01, :on 970404,radiation Area Surveys Were Missed. Caused by Inadequate TS Review.Nso,Unit Supervisor & Shift Engineer,Counseled |
- on 970404,radiation Area Surveys Were Missed. Caused by Inadequate TS Review.Nso,Unit Supervisor & Shift Engineer,Counseled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1997-012-02, :on 970423,determined That Test Criteria for H Recombiner Was Inappropriate.Caused by Low Std for for Documentation of Changes to Vendor Recommendations. Will Review Results of 1995 TS Compliance Self Assessment |
- on 970423,determined That Test Criteria for H Recombiner Was Inappropriate.Caused by Low Std for for Documentation of Changes to Vendor Recommendations. Will Review Results of 1995 TS Compliance Self Assessment
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1997-012, Forwards LER 97-012-00,which Documents 970423 Event That Occurred at Zion Generating Station.Commitments Made by Util,Listed | Forwards LER 97-012-00,which Documents 970423 Event That Occurred at Zion Generating Station.Commitments Made by Util,Listed | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000295/LER-1997-013-02, :on 970412,VT-3 Insp Requirements of Relief Request CR-13 for Reactor Head Bolting Were Not Performed. Caused by Failure to Revise ISI Database After SER Received from Nrc.Procedure Revised |
- on 970412,VT-3 Insp Requirements of Relief Request CR-13 for Reactor Head Bolting Were Not Performed. Caused by Failure to Revise ISI Database After SER Received from Nrc.Procedure Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1997-014-02, :on 970502,TS Surveillances on Radiation Monitors Were Missed Because Technical Interpretation That Kept 1(2)RT-PR15 Operable Was Inoperable.Revised Station Procedures |
- on 970502,TS Surveillances on Radiation Monitors Were Missed Because Technical Interpretation That Kept 1(2)RT-PR15 Operable Was Inoperable.Revised Station Procedures
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1997-015-01, :on 970724,Unit 1 EDGs & Unit 2 RHR Sys Was Declared Inoperable Which Resulted in Inadvertent ESF While Performing TS Related Surveillance.Caused by Unclear Expectations.Declared EDG Operable on 970729 |
- on 970724,Unit 1 EDGs & Unit 2 RHR Sys Was Declared Inoperable Which Resulted in Inadvertent ESF While Performing TS Related Surveillance.Caused by Unclear Expectations.Declared EDG Operable on 970729
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000295/LER-1997-015-02, :on 970724,Unit 1 EDGs & Unit 2 RHR Sys Were Declared Inoperable & Inadvertent Esg Actuation Was Noted While Performing TS Related Surveillances.Cause Is Under Investigation.Restored ESF Equipment |
- on 970724,Unit 1 EDGs & Unit 2 RHR Sys Were Declared Inoperable & Inadvertent Esg Actuation Was Noted While Performing TS Related Surveillances.Cause Is Under Investigation.Restored ESF Equipment
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000295/LER-1997-016-01, Forwards LER 97-016-01,which Clarifies Info on Event Description,Root Causes & Safety Analysis.Cas Have Been Updated.Attachment a Provides Commitments Associated W/ Correspondence | Forwards LER 97-016-01,which Clarifies Info on Event Description,Root Causes & Safety Analysis.Cas Have Been Updated.Attachment a Provides Commitments Associated W/ Correspondence | | | 05000295/LER-1997-016, Forwards LER 97-016-00 Re Failure to Recognize That 125 Vdc Buses Were Inoperable During Inter Unit cross-tie.Event Investigation Is Ongoing & Corrective Actions Will Be Provided in Supplemental LER | Forwards LER 97-016-00 Re Failure to Recognize That 125 Vdc Buses Were Inoperable During Inter Unit cross-tie.Event Investigation Is Ongoing & Corrective Actions Will Be Provided in Supplemental LER | | | 05000295/LER-1997-016-02, :on 970905,failed to Recognize That 125 Vdc Buses Were Inoperable During Inter Unit cross-tie.Cause Indeterminate.Corrective Actions Will Provided in Supplemental Response to LER |
- on 970905,failed to Recognize That 125 Vdc Buses Were Inoperable During Inter Unit cross-tie.Cause Indeterminate.Corrective Actions Will Provided in Supplemental Response to LER
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1997-017-02, :on 970806,TS Surveillance on Containment Isolation Valve Operability Was Missed After Maint.Cause Undetermined.Revised & Performed PT-306 for Affected Valves Prior to Units 1 & 2 Reaching Mode 4 |
- on 970806,TS Surveillance on Containment Isolation Valve Operability Was Missed After Maint.Cause Undetermined.Revised & Performed PT-306 for Affected Valves Prior to Units 1 & 2 Reaching Mode 4
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000295/LER-1997-017, Forwards LER 97-017-00,informing That TS Surveillance Containment Isolation Valve Operability Was Missed After Maint.Commitments Made within Ltr,Encl | Forwards LER 97-017-00,informing That TS Surveillance Containment Isolation Valve Operability Was Missed After Maint.Commitments Made within Ltr,Encl | | | 05000295/LER-1997-017-01, :on 970806,TS Surveillance on Containment Isolation Valve Operability After Maint Was Missed.Caused by Personnel Error.Procedure Writer Who Failed to Identify Remaining Procedures by 1993 UFSAR Rev Has Been Counseled |
- on 970806,TS Surveillance on Containment Isolation Valve Operability After Maint Was Missed.Caused by Personnel Error.Procedure Writer Who Failed to Identify Remaining Procedures by 1993 UFSAR Rev Has Been Counseled
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