SER Supporting Util Actions to Prevent Failure of Ammonia Tanks Which May Result in Incapacitation of Control Room & Technical Support Ctr PersonnelML20151A277 |
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Rancho Seco |
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Issue date: |
07/13/1988 |
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NRC |
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Shared Package |
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ML20151A274 |
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References |
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NUDOCS 8807190315 |
Download: ML20151A277 (2) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20045B9051993-06-16016 June 1993 Safety Evaluation Re Order Approving Decommissioning Plan & Authorizing Decommissioning of Rsngs,Unit 1,SMUD.Concludes That Reasonable Assurance That Health & Safety of Public Will Not Be Endangered by Decommissioning Option,Provided ML20029B6721991-02-22022 February 1991 Safety Evaluation Supporting Proposed Rev to Emergency Plan & Granting Exemption from 10CFR50-54(q) Requirements ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 ML20247B3611989-07-17017 July 1989 Safety Evaluation Supporting Amend 112 to License DPR-54 ML20245E1161989-06-20020 June 1989 Safety Evaluation Supporting Amend 111 to License DPR-54 ML20245A1991989-06-0909 June 1989 Safety Evaluation Supporting Amend 110 to License DPR-54 ML20248B6321989-06-0505 June 1989 Safety Evaluation Supporting Amend 108 to License DPR-54 ML20248B9361989-06-0505 June 1989 Safety Evaluation Supporting Amend 107 to License DPR-54 ML20248B9621989-06-0505 June 1989 Safety Evaluation Supporting Amend 109 to License DPR-54 ML20247P1761989-05-30030 May 1989 Safety Evaluation Accepting Generic Ltr 83-28,Item 4.5.2 Re on-line Testing of Reactor Trip Sys ML20247K7261989-05-23023 May 1989 Safety Evaluation Supporting Amend 105 to License DPR-54 ML20247M9231989-05-23023 May 1989 Safety Evaluation Supporting Amend 106 to License DPR-54 ML20247K6871989-05-16016 May 1989 Safety Evaluation Supporting Amend 104 to License DPR-54 ML20246F4671989-05-0404 May 1989 Safety Evaluation Re Inservice Testing Program & Requests for Relief Re ASME Class 1,2 & 3 Pumps & Valves.Program Acceptable ML20245F9041989-04-18018 April 1989 Safety Evaluation Supporting Amend 103 to License DPR-54 ML20248E9371989-03-29029 March 1989 Safety Evaluation Supporting Amend 102 to License DPR-54 ML20155D3131988-09-28028 September 1988 Safety Evaluation Supporting Amend 100 to License DPR-54 ML20151L5511988-07-14014 July 1988 Redistributed Safety Evaluation Supporting Amend 99 to License DPR-54 ML20151A2771988-07-13013 July 1988 SER Supporting Util Actions to Prevent Failure of Ammonia Tanks Which May Result in Incapacitation of Control Room & Technical Support Ctr Personnel ML20195C5571988-06-0808 June 1988 SER Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification (Reactor Trip Sys Components) ML20195C9311988-06-0808 June 1988 SER Accepting Util Response to Generic Ltr 83-28,Item 2.1 (Part 2) Re Vendor Interface Programs (Reactor Trip Sys) ML20150F2851988-03-28028 March 1988 Safety Evaluation Supporting Resolution of Tdi Diesel Engine Vibration Problems at Facility ML20148J8611988-03-17017 March 1988 Safety Evaluation Supporting Amend 98 to License DPR-54 ML20153B2911988-03-15015 March 1988 Safety Evaluation Supporting Amend 97 to License DPR-54 ML20055E3041988-02-12012 February 1988 Safety Evaluation Supporting Util 871223 & 880111 Proposed Changes to Tech Specs,Including Reducing Lower Limits of Detection for Liquid Radioactive Effluents ML20149L6961988-02-12012 February 1988 Safety Evaluation Supporting Amend 95 to License DPR-54 ML20149L2761988-02-0909 February 1988 Safety Evaluation Supporting Amend 94 to License DPR-54 ML20148C7321988-01-0505 January 1988 Safety Evaluation Supporting Amend 93 to License DPR-54 ML20237B4141987-12-0707 December 1987 Safety Evaluation Supporting Amend 92 to License DPR-54 ML20236X1771987-12-0303 December 1987 Safety Evaluation Supporting Amend 91 to License DPR-54 ML20236X1111987-11-13013 November 1987 Safety Evaluation Supporting Amend 90 to License DPR-54 ML20236Q2461987-11-10010 November 1987 Safety Evaluation Supporting Util & Related Submittals Re Design Mods to Emergency Electrical Distribution Sys (Ref Tdi Diesel Generators) ML20236J2671987-11-0303 November 1987 Safety Evaluation Supporting Amend 89 to License DPR-54 ML20245C7831987-10-27027 October 1987 Safety Evaluation Supporting Amend 88 to License DPR-54 ML20245C7051987-10-27027 October 1987 Safety Evaluation Supporting Amend 87 to License DPR-54 ML20236G8791987-10-23023 October 1987 Safety Evaluation Supporting Amend 86 to License DPR-54 ML20236D1361987-10-23023 October 1987 Safety Evaluation Supporting Util 870826 Request to Use Repair & Replacement Program Contained in ASME Section XI 1983 Edition Including Addenda Through Summer 1983 ML20238D4151987-09-0303 September 1987 Evaluation of Engineering Rept ERPT-E0220 Re Reactor Regulation of Util Approach to Compliance W/Reg Guide 1.75 for New Diesel Generator Installation at Plant.Licensee Approach to Demonstrating Compliance Acceptable ML20238B1771987-08-27027 August 1987 Safety Evaluation Supporting Amend 85 to License DPR-54 ML20236E3731987-07-24024 July 1987 Safety Evaluation Supporting Existing & Proposed Mods to Meteorological Program & W/Planned Improvements,Facility Will Satisfy Min Meteorological Emergency Preparedness Requirements of 10CFR50.47 & 10CFR50,Apps E & F ML20205T3021987-03-31031 March 1987 Safety Evaluation Supporting Amend 84 to License DPR-54 ML20205R7871987-03-26026 March 1987 Safety Evaluation Concluding Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing Permits on-line Functional Testing of Sys,Including Diverse Trip Features of Reactor Trip Breakers ML20205C3951987-03-13013 March 1987 Safety Evaluation Re Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61).Util 860123 Submittal Re Matl Properties & Fast Neutron Fluence of Reactor Vessel Acceptable ML20206B6561987-03-13013 March 1987 Corrected SER Re Fracture Toughness Requirements for Protection Against PTS Events (10CFR50.61).Util 860123 Submittal Re Matl Properties & Fast Neutron Fluence of Reactor Vessel Acceptable ML20205J0971987-03-11011 March 1987 Safety Evaluation Re Sys Selected for Facility Sys Review & Test Program.Sys Constitutes Adequate Scope for Sys Review & Test Program ML20211P2601987-02-19019 February 1987 Safety Evaluation Accepting Util 860116 Request for Amend to License DPR-54,redefining Fire Area Boundaries Required to Be Operable to Separate safety-related Fire Areas & Reassessing Adequacy of Components in Fire Area Assemblies ML20210D1011987-02-0303 February 1987 Safety Evaluation Supporting Issuance of Amend 83 to License DPR-54 ML20215N6881986-11-0404 November 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 4.4 Re Improvements in Maint & Test Procedures for B&W Plants 1999-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20195D1901999-05-0606 May 1999 Annual Rept ML20195H8571998-12-31031 December 1998 1998 Annual Rept for Smud. with ML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20248C4301998-05-0606 May 1998 Annual Rept, Covering Period 970507-980506 ML20249A7831997-12-31031 December 1997 1997 Smud Annual Rept ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20140A6371997-05-0606 May 1997 Annual Rept, Covering Period 960507-970506 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20141J2711996-12-31031 December 1996 Smud 1996 Annual Rept ML20138L1231996-11-13013 November 1996 Smud Rancho Seco Incremental Decommissioning Action Plan, Rev 0,961113 ML20129E7151996-10-14014 October 1996 Defueled SAR for Rancho Seco ML20029D3561994-03-31031 March 1994 Update of 1991 Decommissioning Cost for Rancho Seco Nuclear Generating Station ML20059H6821994-01-17017 January 1994 Revised Rancho Seco Quality Manual ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20045B9051993-06-16016 June 1993 Safety Evaluation Re Order Approving Decommissioning Plan & Authorizing Decommissioning of Rsngs,Unit 1,SMUD.Concludes That Reasonable Assurance That Health & Safety of Public Will Not Be Endangered by Decommissioning Option,Provided ML20059K1981993-05-0606 May 1993 Annual Rept, Covering Period from 920501- 930506,consisting of Shutdown Statistics,Narrative Summary of Shutdown Experience & Tabulations of Facility Changes, Tests & Experiments,Per 10CFR50.59(b) ML20034F7031993-02-25025 February 1993 Amend 1 to Enterprise Rept 162 Re Defect on Starting Air Distributor Housing Assembly,As Followup to 930115 Final Rept.Addl Listed Part Numbers Discovered Which Are Higher Level Assemblies of Housing ML20128C9641993-02-0202 February 1993 Informs Commission of Status of Open Issues & Progress of Specified Facilities Toward Decommissioning ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20126E6771992-08-0303 August 1992 Rev 7 to Rancho Seco Quality Manual ML20029A7511991-02-28028 February 1991 Suppl to Special Rept 90-13:on 901224,25,29 & 910113,listed Meteorological Instrumentation Inoperable for More than 7 Days.Work Request Initiated & Instrumentation Channels Declared Operable on 910116 ML20029B6721991-02-22022 February 1991 Safety Evaluation Supporting Proposed Rev to Emergency Plan & Granting Exemption from 10CFR50-54(q) Requirements NL-90-451, Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station1990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 NL-90-443, Monthly Operating Rept for Aug 1990 for Rancho Seco1990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Rancho Seco ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage NL-90-439, Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station1990-07-31031 July 1990 Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station 05000312/LER-1990-002, :on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.21990-07-20020 July 1990
- on 900614,Step 6.9.3.1 of Liquid Waste Discharge Permit Checked R-15017A as Inoperable & Two Independent Samples Not Performed.Caused by Personnel Error. Caution Will Be Added to Step 6.9.2
ML20055F8591990-07-16016 July 1990 Special Rept 90-11:on 900613,06,25,18,21 & 28,fire Barriers Breached More than 7 Days & Not Made Operable in 14 Days. Corrective Actions:Operability of Fire Detectors Verified on One Side of Breached Barriers NL-90-423, Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station NL-90-355, Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Rancho Seco Nuclear Plant ML20055C6301990-05-21021 May 1990 Special Rept 90-09:on 900424,25,30,31 & 0502,fire Barriers Inoperable for More than 7 Days,Per Tech Spec 3.14.6.2 Requirement.Hourly Fire Watches Established & Penetrations & Doors Returned to Operable Status ML20055C6291990-05-21021 May 1990 Special Rept 90-08:on 900419,fire Pump Batteries Inoperable When Surveillance Procedure SP.206 Not Performed by Due Date.Caused by Test Frequency Incorrectly Changed from Weekly to Monthly.Surveillance Schedule Revised ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML20033G6011990-03-30030 March 1990 Rev 1 to Defueled Requalification Training Program for NRC Licensed Operators ML20042E6921990-03-30030 March 1990 Special Rept 90-06:on 900301,06 & 14,listed Fire Barrier Penetrations That Failed Surveillance Test Not Restored to Operable Status within 7 Days as Required by Tech Spec 3.14.6.2.Operability of Fire Detectors Verified ML20033G6031990-03-30030 March 1990 Rev 1 to Defueling Training Programs for NRC License Candidates ML20042E6931990-03-30030 March 1990 Special Rept 90-07:on 900228,high Temp Detector Circuit for Zone 53 Not Restored to Operable Status within 14 Days When Circuit Failed Surveillance Test SP.345 & Would Not Alarm. Fire Watch Established.Detector Found Operable on 900316 NL-90-054, Monthly Operating Rept for Feb 1990 for Rancho Seco Nuclear Generating Station1990-02-28028 February 1990 Monthly Operating Rept for Feb 1990 for Rancho Seco Nuclear Generating Station ML20006F4181990-02-0909 February 1990 Special Repts 90-1,90-2,90-3 & 90-4:on 900110,16,18,19,30 & 31,fire Barriers Breached for More than 7 Days.All Fire Barrier Penetrations & Fire Doors Returned to Operable Status NL-90-035, Monthly Operating Rept for Jan 1990 for Rancho Seco Nuclear Generating Station1990-01-31031 January 1990 Monthly Operating Rept for Jan 1990 for Rancho Seco Nuclear Generating Station ML20006A3611990-01-17017 January 1990 Part 21 Rept 152 Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Supplied to Listed Sites by Cooper Industries.Qualified Replacement Valve in Process of Being Specified.Info Will Be Available by 900215 1999-08-13
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l SAFETY EVALUATION REPORT RANCHO SEC0 CONTROL ROOM AND TECHNICAL SUPPORT CENTER HABITABILITY RELATIVE TO POTENTIAL ACCIDENTAL AMMONIA SPILLS
1.0 INTRODUCTION
The Radiation Protection Branch (PRPB) was requested to evaluate the habitability of the Rancho Seco control room / technical support center (CR/TSC) relative to potential ammonia tank rupture accidental releases. The staff reviewed the licensee's submittal of May 19, 1988 and performed independent analyses of the potential consequences in the CR/TSC as a result of accidental amonia releases.
2.0 DISCUSSION The requirements for the protection of the CR/TSC personnel under accidental chemical release conditions are specified in GDC-19.
The guidance for the bases of acceptance of the GDC-19 requirements are provided in SRP Section 6.4 and Regulatory Guides 1.78 and 1.95.
By letter dated May 19, 1988, the licensee proposed to reduce the concentration of aqueous amonia stored onsite from 28% to 20%.
The aqueous amonia, which is stored in a 20,000 gallon tank, has been identified as potentially hazardous to CR/TSC habitability. This amonia tank is approximately 152 meters from the normal operation CR/TSC intake. The CR/TSC habitability in case of accidental amonia release depends upon odor detection of ammonia by the CR/TSC personnel and the donning of self-contained respiratory equipment within 2 minutes of detection.
The licensee presented the analyses of the potential consequences of accidental amonia releases on CR/TSC habitability. The staff evaluated the licensee estimates and made its own independent analyses.
The NRC staff has evaluated the habitability of the CR/TSC with respect to a failure of the 20,000 gallon tank of 20% anhydrous amonia, located 152 meters from the CR/TSC intake, in accordance with SRP 6.4 and Regulatory Guide 1.78.
Since there is no provision for monitoring for amonia with automatic isolation of the normal ventilation system, the t
licensee is depending on the ability of operators to detect the amonia odor and don self-contained breathing apparatus prior to incapacitation.
Regulatory Guide 1.78 suggests that the operator is adequately protected if it can be demonstrated that a chemical in the air can be detected by the operator and that he can don a self-contained breathing appratus in 8807190315 880713 PDR ADOCK 05000312 p
PDC
-2 less than two minutes and not be exposed to an incapacitating concentration of that chemical "protective action limit" in the two minute period.
For amonia, the normal odor threshold is approximately 47 ppm.
The "protective action limit" for amonia, from Regulatory Guide 1.78, is 100 ppm.
Utilizing the conservative assumptions of Regulatory Guide 1.78, the staff has analyzed the consequences of a rupture of the 20,000 gallon tank of 20% anhydrous amonia to the CR/TSC personnel.
Based upon this analysis, the staff finds that there are more than two minutes available between the time when 47 ppm and 100 ppm of amonia would be present in the CR/TSC.
The licensee has provided several analyses of the consequences in the CR/TSC of the amonia tank failure.
Based upon these analyses the licensee also concludes that the "protective action limits" are not exceeded in the CR/TSC within two minutes after initial odor detection by CR/TSC personnel.
Based upon'our own independent analyses and our review of the licensee analyses, the staff concludes that the CR/TSC personnel are adequately protected from the potential effects of a major failure of the amonia tank.
3.0 CONCLUSION
Based upon the foregoing, the NRC staff finds that the licensee has demonstrated that the CR/TSC habitability systems will adequately protect the CR/TSC operators from the consequences of a major ammonia tank failure in accordance with the requirements on GDC-19.
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