|
---|
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
[Table view] |
Text
James A.FitrPetrick Nuclear Power Plant P.o. Box 41
, Lymming. New York 1293 1 315 M2-3M0 I
Harry P. Salmon, Jr.
& Ority nesident uanager February 22, 1995 JAFP-95-0082 United States Nuclear Regulatory Commission ,
Document Control Desk l Mail Station P1-137 Washington, D.C. 20555 '
SUBJECT:
DOCKET NO. 50-333 SPECIAL REPORT 95-002: INOPERABILITY OF FIRE SUPPRESSION FEATURES
REFERENCES:
- 1. LETTER FROM H.P. SALMON (NYPA) TO USNRC CONCERNING NON-FUNCTIONAL FIRE PROTECTION FEATURES (SPECIAL REPORT 95-001, DATED FEBRUARY 6, 1995; JAFP 0062)
- 2. TECHNICAL SPECIFICATION AMENDMENT 218, DATED NOVEMBER 3, 1994 l
Dear Sir:
The New York Power Authority (NYPA) submits this Special Report in accordance with the requirements of Administrative Procedure AP-01.04, " Tech Spec Related Requirements, Lists, and Tables". The Report concerns the inoperability of fire ;
suppression features associated with the Cable Spreading j Room, North Cable Run Room, East Electric Bay, West Electric 1 Bay, Standby Gas Treatment (SGT) System A charcoal adsorber ,
and SGT System B charcoal adsorber. '
Carbon Dioxide Fire Suncression System:
On January 9, 1995, NYPA was informed by a contractor that the preliminary results of a study of the integrity (leak tightness) of areas utilizing carbon dioxide as the fire suppression agent indicated the following:
- 1. The carbon dioxide concentration in the cable Spreading )
Room could not be maintained equal to or greater than '
50 percent for the 15 mir.ute retention period due to leakage of carbon dioxide from the area.
- 2. The North Cable Run Room would be pressurized to approximately 21 inches water column during a carbon dioxide discharge due to insufficient venting of air during the carbon dioxide discharge. The maximum acceptable pressure is approximately five inches water column.
L.
2000C5 s !
9502290439 950222 - / s PDR ADOCK 05000333 Q0 1
- -- . S _ PDR !
, ~ .- - - - .- .. . - - - . _ _ _ _ . - _ _ - _
n -
l
[ United Stetc3 NucloOr Regulatory Camaiccion j
.. SPECIAL REPORT 95-002: INOPERABILITY OF FIRE ;
SUPPRESSION FEATURES {
Page 2 3.- The East ~ Electric Bay would be pressurized to approximately 47 inches water column during a carbon diexide discharge into the area due to insufficient venting of air during the carbon dioxide discharge.
The maximum acceptable pressure is approximately 4.5
-inches water column.
- 4. The West Electric Bay would be pressurized to 3 approximately 39 inches water column during a carbon i dioxide discharge into the area due to insufficient i venting of air during carbon dioxide discharge. The I I
maximum acceptable pressure is approximately 4.5 inches water column.
Each of the above areas is provided with an automatic carbon !
dioxide fire suppression system supplied from the ten ton >
carbon dioxide storage tank.
The fire suppression systems for each of the areas was declared inoperable for the reasons stated above. Since the inoperability of the fire suppression systems exceeded 14 days, a special Report is required within the following 30 days. It should.also be noted that-the carbon dioxide fire suppression systems associated with the ten ton' carbon dioxide storage tank had previously been. declared inoperable due to a planned modification of the control panel and was reported in Special Report 95-001 on February 6, 1995 (Reference 1). The compensatory actions taken for that planned impairment remain in effect and will continue until both the modification of the control panel and modifications to correct the deficiencies discussed above are corrected.
The low carbon dioxide concentration deficiency will be corrected by changing:the discharge timer setpoint and the insufficient air venting will be corrected by providing additional vent area. The planned completion date of the modifications is March 1, 1995.
Standby Gas Treatment (SGT) charcoal Admorber Fire suopression On August 31, 1993, spray nozzle air flow testing of the spray nozzles for the fire suppression system for SGT A charcoal adsorbers was being conducted to satisfy Technical Specification Table 4.12.1. (Note that the Fire Protection Technical Specification limiting conditions for operation and surveillance requirements were subsequently. relocated to plant procedures by Technical Specification Amendment 218 on November 2, 1994.) The surveillance test revealed plugging of 11 of the 18 spray nozzles due to debris. The nossles were cleaned,. air flow tasted with satisfactory results, and the fire suppression system was returned to service in an operable status.
United Stat 03 NuclOOr R:gulctory Commiccien SPECIAL REPORT 95-002: INOPERABILITY OF FIRE SUPPRESSION FEATURES Page 3 On September 2, 1993, the same spray nozzle air test was conducted on SGT B charcoal adsorber spray nozzles.
Eighteen of the 18 nozzles were plugged with debris. The nozzles were cleaned, air flow tested with satisfactory results, and the fire suppression system was returned to service in an aperable status. Analysis of the debris removed from spray nozzles in both systems indicated that most of the material was Iron and Zinc. This is consistent with corrosion of the galvanized steel pipe used in the application.
Based on the results of the 1993 spray nozzle air flow testing and analysis of the debris removed from spray nozzles, requests to perform internal inspection of the piping were initiated. On January 8, 1995, during the current refuel outage, SGT B charcoal adsorber fire suppression system was made inoperable to allow internal inspection of the normally dry piping between the flow control valve and the spray nozzles and a fire watch was established as required. The inspection revealed a significant quantity of pipe scale and the presence of a
" trap" for water that might enter the piping due to inadvertent, spurious or other actuation. Spurious actuations did take place in 1981 and 1982.
The piping for SGT B charcoal adsorber water spray was flushed to remove the debris, drained, and the system was returned to service in an operable status on January 18, 1995.
On January 10, 1995, SGT A charcoal adsorber fire suppression was made inoperable to allow a similar inspection. A fire watch was established and the inspection results were also similar. The system was flushed, drained, and returned to service in an operable status on January 16, 1995.
Procedure changes will be initiated to require draining of the " trap" following an initiation of the system. This action will eliminate significant corrosion in the piping and thus eliminate the source of debris which caused plugging of the spray nozzles.
It should also be noted that while the SGT charcoal adsorber fire suppression system inspection and flushing activities discussed above were completed in less than 14 days, and thus do not require submittal of a Special Report, the New York Power Authority considers the systems to have been significantly degraded (due to the presence of the debris similar to that which had plugged the nozzles previously).
As a result of the degradation that was present for the 16 months prior to January, 1995, the conditions and circumstances related to the degradation have been included in this Special Report.
v ,, . . .. . . - -. .- .- -. . -. - .-_.
^
?!<
l United StatOc'Nucionr Regulctsry Conniccien ;
i a..
SPECIAL REPORT 95-002: INOPERABILITY OF FIRE SUPPRESSION FEATURES :
Page 4 ,
i
.sn===rv of corrective Actions:
carbon Dioxide Fire Suppression Systems: f
- 1. The carbon dioxide discharge timer for the cable spreading room will be adjusted, based on calculations, I to provide a concentration of 50 percent or greater for a 15 minute retention period. (Planned completion ;
date: March 1, 1995). ;
- 2. Additional venting capability will be added to the :
three areas in which calculations indicate an '
overpressure condition would exist during a carbon dioxide discharge. (Planned completion date: March 1, 1995). ,
, i SGT Charcoal Adsorber Fire Sunoression: f
- 1. Plant procedures will be revised to require draining of the normally dry SGT A and B charcoal adsorber fire suppression piping after an initiation. (Planned- ,
completion date: May 1, 1995). :
1 If you have any-questions concerning this matter, please !
contact W. Verne Childs at (315) 349-6071. F Very truly yours, !
HARRY P. SAIJION, J RESIDENT MANAGER HPS:WVC: tic l l
cc: USNRC, Region I USNRC Resident Inspector RMS (JAF) l l
._. -