Similar Documents at Perry |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20196B8771996-12-16016 December 1996 First Amended & Restated Master Decommissioning Trust Agreement Dtd as of 961231 Between Toledo Edison Co & Mellon Bank ML20196B8951996-12-16016 December 1996 First Amended & Restated Master Decommissioning Trust Agreement Dtd as of 961216 Between Cleveland Electric Illuminating Co & Mellon Bank ML20134H2191996-10-18018 October 1996 Application of Acoustic Methodology for Evaluation of Submerged Structures on Mark III Large Passive ECCS Suction Strainer ML20115J9831996-06-30030 June 1996 Individual Plant Examination of External Events for Severe Accident Vulnerabilities for Pnpp PY-CEI-NRR-2076, Rev 2 to Nonproprietary Version of Controlled Copy of Dose Calculation Data Base for Application of Revised DBA Source Term to CEI Pnpp1996-06-14014 June 1996 Rev 2 to Nonproprietary Version of Controlled Copy of Dose Calculation Data Base for Application of Revised DBA Source Term to CEI Pnpp ML20128L5611996-04-10010 April 1996 Safety Evaluation Summary Per 10CFR50.59(B)(2) 1994-1996 ML20100G0111996-02-0101 February 1996 Rev 0 to Pnpp EALs Bases Document ML20101M9851995-08-0808 August 1995 Analytical Rept ML20113D1691995-07-24024 July 1995 Pyrolysis Gas Chromatography Analysis of 5 Thermo-Lag Fire Barriers Samples ML20083C0301995-04-27027 April 1995 GE Numac Leak Detection Sys Seismic Analysis Summary, for DCP 87-0725 ML20196B7871995-04-21021 April 1995 Pennsylvania Power Co Master Decommissioning Trust Agreement for Beaver Valley Power Station & Perry Nuclear Power Plant ML20083C0191995-03-0303 March 1995 GE Numac Leak Detection Sys Emi/Rfi Analysis Rept, for DCP 87-0725 ML20073E9681994-09-26026 September 1994 Course of Action Progress Rept ML20210J8731994-04-0707 April 1994 Detoxification of Clam-Trol CT-4 & CT-1:Daphnia Magna Bioassays ML20059M6111993-11-15015 November 1993 Rev 0 to Perry Nuclear Power Plant Course of Action ML20196B8501993-07-0101 July 1993 Ohio Edison Co Master Decommissioning Trust Agreement for Perry Nuclear Power Plant Unit One,Perry Nuclear Power Plant Unit Two,Beaver Valley Power Station Unit One & Beaver Valley Power Station Unit Two ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20101J9821992-06-19019 June 1992 Five-Yr Plan ML20096A8921992-05-0808 May 1992 Rev 0 to Evaluation of Flaw Indication(S) in Perry Feedwater Nozzle to Safe-End Welds, Summary Technical Rept PY-CEI-NRR-1463, Rev 0 to Evaluation of Flaw Indications in Perry FW Nozzle to Safe-End Welds Extrapolated Beyond RF0-31992-02-14014 February 1992 Rev 0 to Evaluation of Flaw Indications in Perry FW Nozzle to Safe-End Welds Extrapolated Beyond RF0-3 ML20092A4391992-01-31031 January 1992 Rev 0 to N71 Pipe Rupture Evaluation ML20077G6261991-06-28028 June 1991 Simulation Facility Certification ML20070Q5121991-03-0707 March 1991 Rev 1 to Evaluation of Indications in Perry Feedwater Nozzle-to-Safe-End Welds, Summary Technical Rept ML20246B2031989-06-23023 June 1989 Safety Evaluation for Limitorque Motor Operators Motor W/O T-Drains PY-CEI-NRR-0835, Motor Valve Testing & Evaluatiion at Perry Nuclear Power Plant (IE Bulletin 85-003)1988-03-31031 March 1988 Motor Valve Testing & Evaluatiion at Perry Nuclear Power Plant (IE Bulletin 85-003) ML20149F9931988-01-29029 January 1988 Final Rept,Msiv Solenoid Valve Failure,Analytical Chemistry Results ML20155K1391987-12-30030 December 1987 Final Rept MSIV 3-Way Dual Solenoid Valve Failures ML20205N7091987-03-23023 March 1987 Draft GE Record in Nuclear Safety:Independent Study of GE Nuclear Control & Implementation Dept Based on Records of SA Milam & Nrc. NRC Lists of Documentation Examined & Related Info Encl ML20212G7461987-01-0707 January 1987 Rept of Emergency Evacuation Review Team on Emergency Response Plans for Perry & Davis-Besse Nuclear Power Plants ML20202F3391986-07-31031 July 1986 Control Room Validation Summary Rept ML20203G1171986-07-29029 July 1986 Analysis of Mode of Ignition & Combustion Propagation for Both Charcoal Adsorber Bed Combustion Events ML20203G1221986-07-29029 July 1986 Metallurgical Analysis of Offgas Sys Adsorber Bed Vessels ML20203G1561986-07-29029 July 1986 Description of Testing Methods to Verify Adequacy of Offgas Vault Refrigeration & Processing Sys. W/19 Photographs of Offgas Sys Components & Recovery Activities.Attachment 2 Contains 25 Oversize Graphs of N-64 Offgas Sys Event ML20203G0931986-07-29029 July 1986 Analysis of Physical & Chemical Properties of Original & Replacement Activated Carbon ML20203G0881986-07-29029 July 1986 General Description & Background of Offgas Sys ML20203G1331986-07-29029 July 1986 Description of Charcoal Removal,Sys Drying & Replacement Carbon Installation Activities ML20203G0791986-07-28028 July 1986 Unit 1 Offgas Sys Charcoal Adsorber Combustion Events Final Rept PY-CEI-NRR-0478, Rev 0 to Deep Well Injection at Calhio Wells & Leroy,Oh Earthquake of 8601311986-06-10010 June 1986 Rev 0 to Deep Well Injection at Calhio Wells & Leroy,Oh Earthquake of 860131 ML20204F6641986-05-28028 May 1986 Rev 1 to Environ Qualification Rept of Two Duct Sealants ML20198J3141986-05-20020 May 1986 Suppl 2 to Dcrdr Summary Rept ML20198D5501986-04-30030 April 1986 Cleveland Electric Illuminating Co,Perry Power Plant Confirmatory Program of 860131 Ohio Earthquake Effect, Progress Rept ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20203G5411986-04-24024 April 1986 Emergency Instruction Validation Summary Rept ML20117E8101986-03-31031 March 1986 Results of Atmospheric Tracer Study within Bldg Complex at Pnpp ML20210T5801986-02-25025 February 1986 Spectral Analysis of Perry Nuclear Power Plant Velocity- Time Histories Resulting from Ohio Earthquake ML20151T9521986-02-0303 February 1986 ML 5.0 Earthquake,860131,Strong-Motion Data from Perry Nuclear Power Plant Seismic Instrumentation ML20138A9491985-11-0101 November 1985 Rev 1 to Environ Analysis of Silicone Rubber Boot Seals ML20133K8881985-10-14014 October 1985 Suppl 1 to Dcrdr Summary Rept 1999-06-17
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2329, Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A PY-CEI-NRR-2323, Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER PY-CEI-NRR-2289, Monthly Operating Rept for May 1998 for Perry,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Perry,Unit 1 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 PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
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GENERAL DESCRIPTION AND BACKGROUND OF OFF-GAS PROCESSING SYSTEM System Purpose
'Ihe purpose of the Off-Gas System is to process and control the release of gaseous radioactive effluents from the condenser to the site environs.
The Off-Gas System performs its function by reducing the off-gas volume. This is accomplished by:
recombining hydrogen and oxygen into water, delaying the passage of Krypton and Xenon, and O -
physical adsorption
System Description
The Off-Gas System is non-safety class and is made up of three primary segments. The first segment consists of preheaters, catalytic recombiners, an off-gas condenser and a water separator. These components are used to j recombine the hydrogen and oxygen and to remove moisture from the off-gas process stream. The second segment consists of a hold-up line which allows any short-lived activity in the off-gas process stream to decay. The third segment consists of cooler condensers, moisture separators, prefilters, desiccant-type gas dryers, gas coolers, charcoal adsorber trains and C\
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afterfilters which remove trace moisture and delays the passage of Krypton and Xenon. The Off-Gas System recei'/es discharge steam, air, and noncondensible gases from the main condenser via the steam jet air ejectors (SJAE'st.
Hydrogen is removed in the first segment of the system by a catalytic recombiner which requires an inlet temperature of 350*F to begin recombination. The off-gas is teated from approximately 228'F to 350'F by the preheater to place the gas and recombiner in thermal equilibrium. Once recombination of hydrogen with oxygen to produce water vapor begins, the recombination reaction produces heat and raises the off-gas temperature to approximately 830'F. There are two 100 percent capacity preheaters each with an associated catalytic recombiner. The standby recombiner is kept hot by heaters which cycle on and off to maintain the recombiner at 350'F. After the off-gas passes tMough the recombiner, it passes through the off-gas condenser which cools the process stream to condense and remove the water vapor. The off-gas passes through the condenser shell while condensate flows
- through the tubes to reduce the off-gas temperature from 830'F to approximately 140'F. The off-gas then passes through a water separator in which water droplets in the off-gas impinge on a wire mesh screen in the separator, drain to the bottom of the water separator and then drain back to the off-gas condenser. Level in the off-gas condenser is maintained by two level controllers and two level control valves. The condensate from the off-gas condenser drains to the low pressure condenser via the Main, Reheat, Extraction, and Miscellaneous Drains System.
The second segment of the Off-Gas System allows time for short-lived activity to decay. This is accomp13shed by the holdup line which is a series of loops
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.f in the off-gas piping which requires the off-gas approximately 10 minutes to pass through. Any condensate which collects in the holdup line is drained via a loop seal to the Radwaste System.
n e third segment provides for the decay of long-lived activity, primarily Krypton and Xenon. Krypton and Xenon are each members of the noble gases which vary in their holdup time and level of physical adsorption. 'Ihe charcoal adsorbers are more efficient when operated at low temperatures. For this reason, the adsorbers are located in a vault room kept at a temperature of approximately O'F.
Prior to entering the charcoal adsorbers, the off-gas is dried to prevent formation of ice which would plug the adsorbers. The moisture is removed by cooling the off-gas to 45'F in the cooler condenser which contains 35'F glycol on the secondary side. Additionally, moisture is removed by a moisture separator and the condensate drains via a loop seal to the Radwaste System.
We off-gas passes through the prefilter to remove any particulates before it enters the desiccant dryer. There are two cooler condensers, two moisture A
separators, and two prefilters, each of which has 100 percent capacity.
loop seal drain is located on the prefilter inlet to remove any accumulated moisture. The desiccant dryer is the final stage of moisture removal and it further reduces the moisture content.
O
r i There are four desiccant dryers in this system arranged as two dryers per train. Each train has its own regeneration system to dry the desiccant once it becomes saturated and regeneration is accomplished automatically by timers.
shifting from one dryer to another in the same train is automatic while shifting between trains requires operator action.
After being dried, the off-gas is cooled to O'F by the gas coolers, and then enters the charcoal adsorbers. The gas coolers are cooled by refrigerated air from the Off-Gas Vault Refrigeration System and normal flow for the off-gas is through the A and B gas coolers. If the first charcoal adsorber in the train becomes plugged, it can be bypassed by shifting flow to the C and D gas coolers. Gas coolers C and D are piped to the inlet of the second charcoal adsorber in each train.
O There are two trains of charcoal adsorbers with four adsorbers per train. The pressure envelope of the system is designed to be explosion resistant and the pressure vessels are designed to withstand 350 psig static pressure.
Channeling in the charcoal adsorber is inhibited by using a flow distributor on the inlet and outlet piping in each vessel and by having long columns of charcoal. Both trains of the system are normally in service during plant operations. After passing through the charcoal adsorbers, the off-gas passes through either of two (2) 100% afterfilters which remove any particulates from the process stream. The off-gas is then discharged to the environs via the Off-Gas Building Exhaust System.
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p Initial Charcoal Loading and Previous Testing Initial loading of charcoal into the adsorber bed vessels began April- 5,1985 in accordance with General Electric's procedure GEP-IP-0040, and was performed by General Electric personnel. Upon completion of the initial loading, all adsorber bed vessels were inerted with a nitrogen (N 2
) blanket to inhibit vessel and piping corrosion and to maintain a dry environment for the carbon adsorbent.
Testing of the Off-Gas Vault Refrigeration System began in late May, 1985.
During this testing, portable heaters were installed in the adsorber vessel vaults. The vaults were heated and then stabilized at a temperature of 150*F and held at that temperature for approximately 4-1/2 hours. 'Ihe vault heat-up process took approximately 33-1/2 hours. The Off-Gas Vault Refrigeration System was then started in the pull-down mode and the acceptance criteria of i
O'F was successfully achieved in less than 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />. Adsorber bed charcoal temperature indications were not required to be monitored during the heat-up and cool-down process, although charcoal was installed in the adsorber bed vessels.
Preoperational testing of the Off-Gas Processing System began on July 2, 1985 and was completed in October, 1985, with test exceptions remaining open. One l
of the exceptions identified during testing concerned the ability of the Off-Gas Vault Refrigeration System to maintain vault and charcoal adsorber temperatures at O'F +2'F. Prior to retesting the Off-Gas Processing System to close these test exceptions, it was decided to gather additional information to verify the cool down capability of the Off-Gas Vault Refrigeration System.
i 3
O etest er the ort-ces v e1e errieer tien svste ce-eeced en sene 18.1eee and on June 20, 1986 the first Unusual Event was declared due to combustion
- activity in vessels D014A and D014B. A detailed chronology of both combustion events is contained in the recovery plan included in this report.
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