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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARJAFP-95-0145, Special Rept 95-003:on 950223,TB HVAC Sys Fire/Carbon Dioxide Dampers Rendered non-functional in Support of Plant Mod M1-95-007.Dampers Not Returned to Functional Condition within Required Restoration Period Due to Duration of Mod1995-03-24024 March 1995 Special Rept 95-003:on 950223,TB HVAC Sys Fire/Carbon Dioxide Dampers Rendered non-functional in Support of Plant Mod M1-95-007.Dampers Not Returned to Functional Condition within Required Restoration Period Due to Duration of Mod JAFP-95-0082, Special Rept:On 950109,inoperability of Fire Suppression Features Associated W/Listed Areas Noted.Low Carbon Dioxide Concentration Deficiency Will Be Corrected by Changing Discharge Timer Setpoint1995-02-22022 February 1995 Special Rept:On 950109,inoperability of Fire Suppression Features Associated W/Listed Areas Noted.Low Carbon Dioxide Concentration Deficiency Will Be Corrected by Changing Discharge Timer Setpoint ML20078L6611995-02-0606 February 1995 Special Rept:On 950104,fire Protection Features Inoperable to Accomodate Certain Activities During Refueling outage.Non-functional Fire Protection Features Will Be Restored Prior to Plant Restart JAFP-94-0252, Special Rept 94-001 Re Fire Barrier Penetration Seals Not Restored within TS Time Frame.Caused by Scope of Work in Steam Tunnel.Roving Fire Watch Posted in Recirculation Motor Generator Set Room & Floor Plugs Removed1994-05-0606 May 1994 Special Rept 94-001 Re Fire Barrier Penetration Seals Not Restored within TS Time Frame.Caused by Scope of Work in Steam Tunnel.Roving Fire Watch Posted in Recirculation Motor Generator Set Room & Floor Plugs Removed JAFP-93-0601, Special Rept 93-005 Re Nonfunctional Fire Door for Greater than 7 Days Due to Planned Evolution During Fall 1993 Maint Outage.Continuous Fire Watch Posted for Duration.Maint Completed & Sys Restored on 9311091993-11-11011 November 1993 Special Rept 93-005 Re Nonfunctional Fire Door for Greater than 7 Days Due to Planned Evolution During Fall 1993 Maint Outage.Continuous Fire Watch Posted for Duration.Maint Completed & Sys Restored on 931109 JAFP-93-0265, Special Rept 93-003 Re Nonfunctional Fire Barrier Penetration Seal Due to Design & Equipment Problems.Drain Piping Installed,Penetration Sealed & Determined to Be Operable on 9304201993-05-0303 May 1993 Special Rept 93-003 Re Nonfunctional Fire Barrier Penetration Seal Due to Design & Equipment Problems.Drain Piping Installed,Penetration Sealed & Determined to Be Operable on 930420 JAFP-93-0031, Special Rept 93-002:on 921228,fire Barrier,Installed in Front of Fire Door 76FDR-A-272-5,determined to Be Nonfunctional Based on Unsealed Opening in Barrier.Fire Watch Posted & Maint Work Request Initiated1993-01-18018 January 1993 Special Rept 93-002:on 921228,fire Barrier,Installed in Front of Fire Door 76FDR-A-272-5,determined to Be Nonfunctional Based on Unsealed Opening in Barrier.Fire Watch Posted & Maint Work Request Initiated JAFP-93-0011, Updated Special Rept Documenting Inability to Restore Fire Door to Functional Status within Required Time Frame.On 921201,door Determined to Be Nonfunctional & Not Restored Until 921211.As of 930104,two Doors Remain Nonfunctional1993-01-0707 January 1993 Updated Special Rept Documenting Inability to Restore Fire Door to Functional Status within Required Time Frame.On 921201,door Determined to Be Nonfunctional & Not Restored Until 921211.As of 930104,two Doors Remain Nonfunctional JAFP-93-0006, Special rept:post-work Testing & Repair of a Feedwater Return Valve 34NRV-111A Could Not Be Completed within 7-day Period.Continuous Fire Watch & Roving Fire Watch Posted & One Floor Plug Removed on 921219 & Replaced on 9212211993-01-0606 January 1993 Special rept:post-work Testing & Repair of a Feedwater Return Valve 34NRV-111A Could Not Be Completed within 7-day Period.Continuous Fire Watch & Roving Fire Watch Posted & One Floor Plug Removed on 921219 & Replaced on 921221 JAFP-92-0854, Special Rept:On 921209,fire Barrier Doors Remain Nonfunctional Based Upon Revised Surveillance Test Acceptance Criteria.Revised Surveillance Test Criteria & Improved Maint Work Procedures Implemented1992-12-17017 December 1992 Special Rept:On 921209,fire Barrier Doors Remain Nonfunctional Based Upon Revised Surveillance Test Acceptance Criteria.Revised Surveillance Test Criteria & Improved Maint Work Procedures Implemented JAFP-92-0782, Special Rept:On 921002,insp of Fire Doors,Using Revised Surveillance Test Procedure Initiated & Fire Barrier Doors Not Restored to Operable Status within 7 Days.As of 921109, 77 Doors Remained Nonfunctional.Fire Watch Posted1992-11-0909 November 1992 Special Rept:On 921002,insp of Fire Doors,Using Revised Surveillance Test Procedure Initiated & Fire Barrier Doors Not Restored to Operable Status within 7 Days.As of 921109, 77 Doors Remained Nonfunctional.Fire Watch Posted JAFP-92-0570, Special Rept:On 920703,CO-2 Fire Door Required to Close on CO-2 Sys Activation Did Not Fully Close When Released.Fire Door Repaired & Tested Satisfactorily1992-07-31031 July 1992 Special Rept:On 920703,CO-2 Fire Door Required to Close on CO-2 Sys Activation Did Not Fully Close When Released.Fire Door Repaired & Tested Satisfactorily JAFP-92-0454, Special Rept:On 911003,discovered pin-hole Leak in Diesel Fire Pump.Caused by Discharge Pressure.Surveillance Test Procedure Was Revised1992-06-10010 June 1992 Special Rept:On 911003,discovered pin-hole Leak in Diesel Fire Pump.Caused by Discharge Pressure.Surveillance Test Procedure Was Revised JAFP-92-0435, Special Rept:On 920504,CO2 Fire Suppression Sys Declared Inoperable When Walkdown Revealed That 4 Instead of 5 Nozzles Installed in Sys.Caused by Absence of Design Calculations.Replacement Nozzle Installed on 9205181992-06-0303 June 1992 Special Rept:On 920504,CO2 Fire Suppression Sys Declared Inoperable When Walkdown Revealed That 4 Instead of 5 Nozzles Installed in Sys.Caused by Absence of Design Calculations.Replacement Nozzle Installed on 920518 JAFP-92-0316, Special Rept:On 920406,electric Driven Pump Was Out of Service for Approx 16 Days & 5 H.Caused by Extended Overhaul Time.Electric Motor Was Removed,Overhauled,Tested,Found Satisfactory & Returned to Plant1992-05-11011 May 1992 Special Rept:On 920406,electric Driven Pump Was Out of Service for Approx 16 Days & 5 H.Caused by Extended Overhaul Time.Electric Motor Was Removed,Overhauled,Tested,Found Satisfactory & Returned to Plant JAFP-91-0835, Special Rept:Relay Room CO2 Sys Declared Inoperable Due to Failed Surveillance Test.Caused by Slow Closure Time of Temp Control Damper 70MOD-103.Continuous Fire Watch Established & Design Basis Reconstitution Planned1991-12-19019 December 1991 Special Rept:Relay Room CO2 Sys Declared Inoperable Due to Failed Surveillance Test.Caused by Slow Closure Time of Temp Control Damper 70MOD-103.Continuous Fire Watch Established & Design Basis Reconstitution Planned ML20079L2971983-02-0303 February 1983 Telecopy ROs 83-029 & 83-008:on 830202,licensee Informed by Telcon That Error Made in Odyn Base Deck for Reload 4 Cycle 5 Analysis.Caused by Personnel Error in Performing Licensing Analysis.Tech Spec Change Initiated JAFP-82-1106, Ro:On 820628,combustion in Offgas Sys Observed.Caused by Improper Valve Lineup Allowing More Gas to Recombiner than Dilution Flow Rate Could Support.Incident Discussed W/Shift Supervisor & Training Will Be Developed1982-10-19019 October 1982 Ro:On 820628,combustion in Offgas Sys Observed.Caused by Improper Valve Lineup Allowing More Gas to Recombiner than Dilution Flow Rate Could Support.Incident Discussed W/Shift Supervisor & Training Will Be Developed ML20125B2801979-09-26026 September 1979 RO-79-158:on 790926,A/E Advised That HPCI & Automatic Depressurization Sys (ADS) Cabling Affecting Control of HPCI Inboard Steam Supply Isolation Valve Did Not Meet NRC Criteria.Caused by HPCI & ADS Cabling in Same Raceway ML20071G3331978-12-18018 December 1978 RO 78-097/01X-0:during Surveillance of Temp Switches,Instru Were Found Set Above Tech Spec Limit Due to Personnel Using Wrong Conversion Table 1995-03-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARJAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data JAFP-99-0261, Monthly Operating Rept for Aug 1999 for Jafnpp.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Jafnpp.With JAFP-99-0236, Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with ML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept JAFP-99-0211, Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with1999-06-0202 June 1999 Annual Summary of Changes,Tests & Experiments for 1997/1998. with JAFP-99-0181, Monthly Operating Rept for May 1999 for Jafnpp.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Jafnpp.With JAFP-99-0166, Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With JAFP-99-0142, Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0092, Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc JAFP-99-0011, Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20198F9991998-12-0404 December 1998 Assessment of Licensing Basis for Use of Containment Overpressure Credit for Net Positive Suction Head Analyses Power Authority of State of New York,James a Fitzpatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves JAFP-98-0396, Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195J7521998-11-18018 November 1998 Rev 7 to Jaf Colr ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20197G6221998-11-0606 November 1998 Non-proprietary Rev 7 to HI-971661, Licensing Rept for Reracking of Ja FitzPatrick Sfp ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI JAFP-98-0360, Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20155C2821998-10-30030 October 1998 Non-proprietary Rev 0 to GENE-187-30-1598 Np, CRD Bolting Flaw Evaluation for Ja FitzPatrick Nuclear Power Plant ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 JAFP-98-0322, Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With ML20153D2591998-09-21021 September 1998 SER Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20153B5611998-09-0101 September 1998 Rev 1 to JAF-SE-98-013, RHR & Core Spray Suppression Pool Suction Strainer Replacement ML20151X6891998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Ja FitzPatrick Nuclear Power Plant ML20237E8361998-08-25025 August 1998 Rev 6 to Colr ML20237E9471998-08-0808 August 1998 Rev 6 to Colr JAFP-98-0264, Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant ML20236X5881998-07-29029 July 1998 Safety Evaluation Supporting Amend 245 to License DPR-59 ML20236V8181998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief from Implementation of Requirements of 10CFR50.55a Related to Containment Repair & Replacement Activities for James a FitzPatrick Nuclear Power Plant ML20153B5781998-07-28028 July 1998 Rev 0 to JAF-SE-98-025, HPCI & RCIC Suppression Pool Suction Strainer Replacement ML20236X3831998-07-14014 July 1998 Rev 2 to JAF-RPT-MULTI-02671, Summary of Detailed Evaluation for NRC Generic Ltr 96-06 ML20154L9201998-07-10010 July 1998 SER Accepting Rev to Reactor Vessel Surveillance Capsule Withdrawal Schedule for James a Fitzpatrick Nuclear Power Plant JAFP-98-0222, Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0193, Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant1998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0128, Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively JAFP-98-0091, Monthly Operating Rept for Feb 1998 for JAFNPP1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for JAFNPP ML20202G9081998-02-0606 February 1998 Safety Evaluation Re Amend to License DPR-59 to Revise TS Tables 3.2-2 & 4.2-2 JAFP-98-0058, Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant 1999-09-30
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- 3 POWER AUTHORITY OF THE STATE OF NEW YORK g,39 JAMES A. FITzPATRICK NUCLEAR POWER PLANT CoRBIN A. McNEILL, JR. P.o. BOX 41 Resident Manager Lycoming, New York 13093 315-342 3840 October 19, 1982 SERIAL: JAFP-82-1106 Ronald C. Haynes, Regional Administrator United States Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Reference:
Docket No. 50-333
Dear Mr. Haynes:
We have enclosed a report concerning hydrogen combustion in the Off-Gas System which may be of special interest to the Nuclear Regulatory Commission but which was determined not to be reportable under current US Nuclear Regulatory Commission guidelines for Licensee Event Reports.
If there are any questions concerning this report, please contact Mr. Radford J. Converse at 315-342-3840, Extension 202.
Very truly yours, CAM: RJC:j jh CORBIN A. McNEILL, JR.
Enclosure CC: Internal Power Authority Distribution NRC Resident Inspector Document Control Center OR File h o g M o6 82Joj9 -
0 0500o454 PDR
c.
h, ..o COMBUSTION IN THE OFF-GAS SYSTEM Monday, June 28, 1982 - approximately 1605 GENERIC APPLICATION:
The following is an explanation of what combustion in the off-gas system consists of, symptoms associated with it and how to extinguish it.
The hydrogen mixture in some portions of a boiling water reactor off-gas system is combustible, all that is needed is a spark to ignite it. When it ignites it either explodes or, as in James A.
FitzPatrick's case, it burns like a propane flame inside the piping (usually the after condenser).
The symptoms are as follows:
- 1. The stack discharge radiation levels decrease because the hydrogen is being consumed prior to reaching the thirty minute holdup volume, without the hydrogen the holdup time increases to approximately five hours. This allows a lot more decay time for the elements with short half lives.
- 2. Off-gas flow rate decreases because the hydrogen is being consumed prior to reaching the flow element.
- 3. The radiation levels around the off-gas piping increase due to heavier concentra-tion of elements with more energetic emissions. The method of putting it out n is to remove the fuel to stop the 4 combustion.
SPECIFIC EVENT DESCRIPTION:
The operators were attempting to place the off-gas recombiner in service. The system had been previously warmed up and all that was necessary was to open the gas inlet and outlet valves. Two or three attempts were made to open the valve but the system tripped on each attempt. This is not unusual because if the temperature out of the recombiner does not reach a certain level after starting the system, it trips. While making the final attempt, the following events occurred:
.~ - . . - --- - . -
COMBUSTION IN THE OFF-GAS SYSTEM PAGE 1. The off-gas filter high differential pressure alarm actuated.
- 2. The off-gas sample Hi/Lo flow alarm actuated.
- 3. The high off-gas radiation alarm actuated.
- 4. The stack radiation levels decreased.
IMMEDIATE CORRECTIVE ACTION:
The Shift Supervisor immediately ordered the recombiner removed from service. A " SNAP" test was completed and the results ' indicated zero hydrogen. The lack of hydrogen indicated the ;
hydrogen was being consumed by combustion within the piping. The SNAP" test generates a spark inside a small vial of off-gas to determine if hydrogen is present.
The Shift Supervisor then ordered power reduced to aproximately forty percent and shut the first stage air ejector suction valves in accordance with an approved plant procedure. The indications previously discussed returned to normal so the Shift Supervisor had another " SNAP" test accomplished.
The results from this test indicated hydrogen was present, proving the combustion was extinguished.
LONG TERM CORRECTIVE ACTION:
The piping was visually inspected and no damage was found.
The incident wassinvestigated and the probable cause was an improper valve lineup which allowed more gas to the recombiner than the dilution flow rate could support. The catalyst over heated and ignited the gas. The flame traveled back to the aftkr condenser and continued to burn there until the fuel was removed.
The corrective action was to discuss the incident with the Shift Supervisor and training will be accomplished on this incident during the annual training cycle. Incorporated in the training will be this report and several General Electric Service Information Letters (SILs) that explain why the valve lineup is so critical on this system.