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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARBVY-99-109, Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 9908311999-08-19019 August 1999 Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831 ML20209J0081999-07-14014 July 1999 Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting BVY-97-171, Special Rept:On 971105,fire Alarm Panel & Suppression Sys Were Out of Svc Greater than 14 Days.Caused by Hardware Problems W/New Zone Modules Developed During Mods.Sys Placed Back in Svc on 9711211997-12-12012 December 1997 Special Rept:On 971105,fire Alarm Panel & Suppression Sys Were Out of Svc Greater than 14 Days.Caused by Hardware Problems W/New Zone Modules Developed During Mods.Sys Placed Back in Svc on 971121 BVY-97-101, Special Rept:On 970717,determined Ongoing or Recent Contamination Event Could Be Source of Detected Environ Radioactivity.Collection,Analysis & Review of Results of Addl Grab Samples from North Storm Drain Outfall1997-08-0808 August 1997 Special Rept:On 970717,determined Ongoing or Recent Contamination Event Could Be Source of Detected Environ Radioactivity.Collection,Analysis & Review of Results of Addl Grab Samples from North Storm Drain Outfall ML20148B8701997-04-22022 April 1997 Special Rept:On 970123,periodic Source Leakage Test of 150 Uci Cs-137 Source Revealed Presence of Greater than 0.005 Uci of Removable Contamination.Source Removed from Svc & Will Be Disposed of IAW Applicable Regulatory Requirements ML20135E0261997-02-27027 February 1997 Special Rept:On 970116,Cable Vault CO2 & Diesel Fire Pump Day Tank Room CO2 Sys Place in Abort.Caused by Installation of New Low Pressure CO2 Sys for Switchgear Rooms.Established Compensatory Measures & Required Manual Initiation for Sys ML20112F8001996-06-0707 June 1996 Special Rept:On 960424,fire Protection Sys Declared Inoperable as Conservative Precaution for Greater than 14 Days.Calculations for Sys May Not Accurately Reflect Pressure Loss.Mods Being Developed ML20108C6711996-05-0202 May 1996 Special Rept:On 960320,switchgear CO2 Sys Declared Inoperable.Suppression Sys Remains Capable of Automatic Initiation & Compensatory Measure Will Remain in Effect Until Confirmatory Testing Completed ML20064C3501994-02-23023 February 1994 Special Rept:On 940127 & 0209,electric Fire Pump Motor Failed to Start Due to Motor Breaker Trip.Redirected Room Heater Discharge to Diesel Fire Pump Engine Area BVY-92-105, Special Rept:On 920810,electric Fire Pump Portion of Vital Fire Suppression Water Sys Equipment Inoperable for 17 Days. Caused by Need to Perform Preventive maint.Diesel-driven Fire Pump Remained Operable & Contingency Plans Developed1992-09-11011 September 1992 Special Rept:On 920810,electric Fire Pump Portion of Vital Fire Suppression Water Sys Equipment Inoperable for 17 Days. Caused by Need to Perform Preventive maint.Diesel-driven Fire Pump Remained Operable & Contingency Plans Developed ML20248B9851989-06-0202 June 1989 Special Rept:On 890421,cable Vault Carbon Dioxide (CO2) Sys & on 890424,diesel Fire Pump Day Tank Room CO2 Sys Declared Inoperable.Fire Protection Sys Out of Svc for More than 14 by 890602.Fire Watches Established ML20236E2751989-03-14014 March 1989 Special Rept:U Slab Source Found to Be Leaking Contamination During Semiannual Radioactive Source Leak Test.Caused by Break Down of Adhesive That Hold Mylar Covering.Source Removed from Svc & Deconned & Resealed W/New Covering ML20112E1821983-10-0707 October 1983 Rev 1 to RO 83-06:accumulative from 840810-23,buildup of Detectable Quantities of plant-related Co-60 in Connecticut River.Caused by Turbine Bldg Roof Vents Failing to Filter Waste.Procedural Changes Implemented ML20086E2201975-03-10010 March 1975 Ro:On 750209 & 10,excessive Level of Heat Rejected to Connecticut River & Filter Paper Sample Whisked from Numbed Technician Hand by Wind,Respectively.Events Caused by Lack of Communication & Wind,Respectively ML20086E4101975-01-0909 January 1975 Ro:On 741126,RHR Svc Water Pump C (P-8-1C) 1,200-amp Circuit Breaker Encountered Significant Damage During Attempted Start.Caused by Migrating Ionized Gases Causing Front Primary Disconnect Device Failure.Breaker Replaced ML20086E6571974-04-25025 April 1974 Ro:On 740414-16,each Operable Control Rod Not Fully Inserted Was Not Exercised One Notch During Surveillance Exercise. Cause Not Stated.Strict Adherence to Surveillance Test Schedule Emphasized ML20086D8711973-03-0606 March 1973 Ro:On 730205,all-purpose Fuel Grapple Became Detached from Jib Crane Hoist Cable When Tension Applied to Cable.Caused by Design Error.Grapple & Cable End Stud Reassembled,End Stud Drilled & Roll Pin Installed & Staked 1999-08-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8831999-10-21021 October 1999 Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 BVY-99-127, Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 BVY-99-112, Monthly Operating Rept for Aug 1999 for Vermont Yankee.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Vermont Yankee.With BVY-99-109, Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 9908311999-08-19019 August 1999 Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831 BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Vermont Yankee. with ML20209J0081999-07-14014 July 1999 Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting BVY-99-090, Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With ML20196G5071999-06-23023 June 1999 Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading BVY-99-077, Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With BVY-99-068, Monthly Operating Rept for Apr 1999 for Vynp.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Vynp.With ML20206E8741999-04-29029 April 1999 SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application ML20206D9301999-04-27027 April 1999 1999 Emergency Preparedness Exercise 990427 Exercise Manual (Plume Portion) ML20205S4211999-04-16016 April 1999 Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion ML20205K7581999-04-0707 April 1999 Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV BVY-99-046, Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With ML20205F6631999-03-0404 March 1999 Jet Pump Riser Weld Leakage Evaluation BVY-99-035, Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With ML20205P8241999-02-28028 February 1999 Rev 2 to Vermont Yankee Cycle 20 Colr ML20203H9881999-02-18018 February 1999 SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl ML20203A6951999-02-0404 February 1999 Revised Rev 2,App B to Vermont Yankee Operational QA Manual (Voqam) ML20199K7151999-01-21021 January 1999 Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification ML20199K6991999-01-20020 January 1999 Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable ML20199L5951999-01-14014 January 1999 Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i) BVY-99-071, Corp 1998 Annual Rept. with1998-12-31031 December 1998 Corp 1998 Annual Rept. with BVY-99-001, Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station ML20198H5481998-12-23023 December 1998 Rev 2 to Vermont Operational QA Manual,Voqam ML20196H8641998-12-0101 December 1998 Cycle 19 Operating Rept BVY-98-163, Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With ML20195C4161998-11-0909 November 1998 SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds BVY-98-154, Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With ML20155B6471998-10-26026 October 1998 Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage ML20154N0891998-10-16016 October 1998 Rev 1 to Vermont Operational QA Program Manual (Voqam) ML20154B6951998-10-0101 October 1998 SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station BVY-98-149, Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With ML20239A1361998-09-0202 September 1998 SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program BVY-98-135, Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With ML20151U0361998-08-28028 August 1998 Non-proprietary Rev 1 to Holtec Rept HI-981932, Vermont Yankee Nuclear Power Station Spent Storage Expansion Project ML20237E9221998-08-20020 August 1998 Vynp 1998 Form NIS-1 Owners Summary Rept for ISI, 961103-980603 BVY-98-122, Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station ML20205F6491998-07-31031 July 1998 Rev 1 to GE-NE-B13-01935-02, Jet Pump Assembly Welds Flaw Evaluation Handbook for Vermont Yankee ML20236G0011998-06-30030 June 1998 Individual Plant Exam External Events BVY-98-098, Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station ML20248C5081998-05-31031 May 1998 Rev 2 to 24A5416, Supplemental Reload Licensing Rept for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20 ML20248C4951998-05-31031 May 1998 Rev 1 to Vermont Yankee Nuclear Power Station Cycle 20 Colr BVY-98-081, Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station ML20247J8341998-05-31031 May 1998 Peak Suppression Pool Temp Analyses for Large Break LOCA Scenarios, for May 1998 ML20247G4001998-05-12012 May 1998 Interview Rept of Ej Massey ML20247E6351998-04-30030 April 1998 Rev 1 to GE-NE-B13-01935-LTR, Jet Pump Riser Welds Allowable Flaw Sizes Ltr Rept for Vermont Yankee 1999-09-30
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VERMONT YANKEE NUCLEAR POWER CORPORATION s
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= - g ,. Ferry Road, Brattleboro, VT 05301-7002 pra , To 1
\ /. / ENGINEERING OFFICE i 560 MAIN STREET
, N ,, DOL 10N, MA 01740 (50867794 ?11 February 23,1994 ,
BVY 94-25 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Reference:
a) License No. DPR-28 (Docket No. 50-271) .
Dear Sir:
Subject:
Inoperability of Both Vital Fire Suppression Water Pumps The attached Special Report is submitted pursuant to the reporting requirements established by Vennont Yankee Technical Specifications as detailed herein.
We trust that the information provided is adequate; however, should you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, Vermont Yankee Nuclear Power Corporation ,
h .
{
Robert J. \ anczyk Plant Manager cc: USNRC Region 1 Administrator USNRC Resident Inspector, VYNPS USNRC Project Manager, VYNPS -
0 0 0 0,'l!':
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-9403090321 940223 /
PDR ADOCK 05000271 1 9 PDR k
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REPORT DATE: February 23, 1994 OCCURRENCE DATES: 1. January 27, 1994 - 2010 Hrs.
- 2. February 9, 1994 - 2105 Hrs.
FACILITY: Vermont Yankee, Vernon, Vermont IDENTIFICATION OF OCCURRENCES:
This report is submitted to satisfy the Vermont Yankee Technical Specification reporting requirements for the following events:
- 1. The 7-day Limiting Condition for Operation (LCO) for an inoperable diesel fire pump (P-40-1A) was exceeded on 1/27/94, requiring a report to the Commission within 30 days.
- 2. The electric fire pump (P-40-1B) motor failed to start on 2/9/94, due to a motor breaker trip, while the diesel fire pump was inoperable. A report to the Commission _within 14 days of this event is required.
CONDITIONS PRIOR TO OCCURRENCES:
1
- 1. The plant was operating at 100% power at the time of the diesel fire pump failure on 1/20/94.
- 2. The plant was increasing power through 66% at the time of the electric fire pump failure on 2/9/94. ,
l DESCRIPTION OF OCCURRENCES: l
- 1. EVENT 1: 7 DAY LCO EXCEEDED FOR INOPERABLE DIESEL FIRE PUMP At 2010 hrs on 1/20/94, with the plant operating at 100% power, the diesel fire pump (P-40-1A) engine failed to start automatic-ally during planned surveillance testing. The pump was started successfully approximately one hour later.
Based upon engine manufacturer representative investigation and evaluation, the failure was attributed to sustained exposure to low ambient temperature. Subsequent assessments and efforts to provide supplemental room heating did not provide reasonable assurance that the diesel fire pump could be declared operable. A decision was made to remain in the LCO and to aggressively pursue.
design change options.
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_ m___ ._. - -_ . . . __ _ .-. . __
t Due to '(1) the inability to implement manufacturer-recommended engine modifications within 7 days, and (2) continuing cold weather, the pump was inoperable beyond the 7 day LCO period.
The diesel fire pump is governed by plant Technical Specification 3.13.B.2, as follows: "From and after the date that less than the '
above required equipment is operable, restore the component to operable status within 7 days or submit a report within the next the 30 days to the Commission as specified in 6.7.C.2 outlining the plans and procedures to be used to provide for the loss of redundancy in this system".
Vermont Yankee procedure OP 2181, " Service Water / Alternate
, Cooling Operating Procedure", establishes the measures for vital fire suppression water supply system back-up through cross-connection with the plant Service Water system. This back-up capability compensates for the loss of fire pump. redundancy and would be implemented through operation of one isolation valve, as specified by the procedure.
- 2. EVENT 2: VITAL FIRE SUPPRESSION WATER SUPPLY SYSTEM INOPERABLE
- At 2105 hrs. on 2/9/94, with the diesel fire pump inoperable, the electric fire pump motor tripped off-line when the pump attempted to start automatically. A fire water system yard hydrant had been opened to fill a local fire department tanker truck, lowering system pressure. The motor breaker immediately tripped open when ;
the electric pump (P-40-1B) responded to the low pressure start signal. The diesel fire pump engine also failed to start.
The breaker was removed, inspected, tested and reinstalled. The breaker over-current trip set-points were reviewed and determined 4 to be appropriate. The electric fire pump subsequently started l successfully in both manual and automatic start modes. The electric fire pump was declared operable at 1642 hrs on 2/10/94.
Plant Technical Specification 3.13.B.3.a requires that, "With the fire suppression water supply system inoperable ... establish a i backup fire. suppression water system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ... . A backup water supply was established at 0025 hrs. on 2/10/94, by 1 opening the the Service Water / vital fire suppression water system ]
cross-connect isolation valve previously discussed. The valve was j closed, isolating the back-up supply, shortly after electric fire pump operability was restored.
Plant Technical Specification 3.13.B.3.b requires that "With the fire suppression water supply system inoperable .... Submit a Special Report as specified in 6.7.C.2;
- 1) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, l
1 1
. . l I
- 2) Confirmed by telegraph, mailgram or facsimile transmission no later than the first working day following the event and
- 3) In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status ... "
Telephone notification to the NRC Operations Center was made on 2/10/94 at 1828 hrs, and confirmed by facsimile transmission on '
2/10/94 at 1900 hrs.
DESIGNATION OF CAUSES OF OCCURRENCES:
- 1. EVENT-1: QJESEL FIRE PUMP INOPERABILITY The root cause of the diesel fire pump start failure has been attributed to engine exposure to sustained low ambient temperatures. At the time of the 1/20/94 event, the outside ambient temperature was approximately -15*F and the fire pump room air temperature was approximately +40 F. The minimum ambient temperature recommended by the manufacturer is +50 F.
Following the failure to start on one battery set, the diesel engine controls switched to the alternate batteries. Failing to start the engine on the second battery set, the controls blocked further start attempts for a pre-set time period, as designed.
Both battery sets were tested and found to be operable. Examina-tion of fuel samples revealed no evidence of fuel gelling.
Investigation determined that the HVAC-system in the Service Water Pump Room (which encloses the diesel fire pump room) had been altered from its original design. Air intake and exhaust
. dampers originally provided were subsequently removed. These dampers regulate Service Water Pump Room ambient' temperature by reducing heat loss / cold air infiltration under cold outside ambient conditions. The investigation failed to identify any work' or design documentation related to damper removal.
On-site evaluation by the manufacturer's representative resulted in recommendations to install water jacket'and lubrication oil heating subsystems introduced since the time of engine purchase.
The diesel fire pump engine (Cummins model #NT-380-IF) was pur-chased in 1969. No auxiliary subsystems to facilitate automatic engine starting under cold ambient temperature conditions were listed by the manufacturer at that time. No evidence has been identified that such systems were recommended by the manufacturer at a later date, prior to this event.
I 1
- 2. EVENT 2: ELECTRIC FIRE PUMP INOPERABLLITY No root.cause for the electric pump breaker trip was identified during subsequent troubleshooting and testing._Following its reinstallation, the pump was successfully started in both manual and automatic start modes.
The apparent cause for breaker trip is attributed to spurious nalfunction. The breaker is equipped with a General Electric RMS-9 digital trip unit for which incidents of inadvertant tripping were reported in NRC Information Notice 93-75. However, no evidence was found indicating that conditions or events similar to those detailed in IN 93-75 occuredHat the time of the electric fire pump breaker trip.
SHORT TERM CORRECTIVE ACTIONS:
Short term corrective actions taken included:
- 1. Establishing a back-up vital fire suppression water supply less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after primary water supply inoperability by cross-connecting the vital fire water loop with the Service Water system.
- 2. Expediting on-site diesel engine inspection and evaluation by the manufacturer's representative.
- 3. Attempting to provide supplemental heating by redirecting a room heater discharge to the diesel fire pump engine area.
- 4. Initiating a Nuclear Network Operating Experience (OE) entry ;
to alert industry members of this event.
LONG TERM CORRECTIVE ACTION: ,
Planned long term corrective actions include the following:
- 1. A design modification has been initiated to install water -
jacket and lubrication oil heating subsystems on the diesel engine. Installation is scheduled for completion by
- 2. As a conservative measure, the feasibility of replacing the.
electric fire pump breaker RMS-9 digital trip unit with a different trip unit type is under investigation.
- 3. A work order request has been initiated to reinstall the missing Service Water Pump Room HVAC system air intake and exhaust dampers.
i ADDITIONAL INFORMATION:
Diesel Fire Pump: Cummins Model# NT-380-IF Serial # 690907 b
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W