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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20210P4461997-08-31031 August 1997 Update 2 to TMI-2 Post-Defueling Monitored Storage Sar ML20210T3411997-08-31031 August 1997 Rev 0 to TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20199E5841997-08-18018 August 1997 Limited Liability Company Agreement of Amergen Energy Co, LLC Among PECO Energy Co,British Energy PLC & British Energy,Inc ML20133D8771996-12-23023 December 1996 Rev 2 to TMI-1 Evaluation of Thermo-Lag Fire Barriers ML20137F1301996-08-27027 August 1996 Rev 0 to Auxiliary Bldg Sump Sludge Prevention (Regulatory Required) ML20117H6621996-07-20020 July 1996 Rev 1 to TR 094 TMI-1 Evaluation of Thermo-Lag Fire Barriers ML20129G9291996-06-17017 June 1996 TMI-1 Reload Design & Setpoint Methodology ML20148F0831996-04-0202 April 1996 Rev 0 to EDG 1B Air Start 2 Reservoir Tank ML20148F0611996-04-0202 April 1996 Rev 0 to SQ-TI-EG-T-0001B-1, EDG 1B Air Start 1 Reservior ML20098B1291995-09-19019 September 1995 Rev 1 to Pages 3 & 30 of TMI-1 USI A-46 Seismic Evaluation Rept ML20100L6581995-05-25025 May 1995 Div 1/2 Mod Design Description for New TMI-1 Radwaste Demineralizer Sys Three Mile Island Unit 1,Nuclear Generating Station, Rev 2 ML20087J5281995-05-11011 May 1995 Nonproprietary Page 2 of TMI Unit 1 USI A-46 Seismic Evaluation Rept ML20082G4191995-03-22022 March 1995 Rev 0 to Topical Rept 093, TMI-1 Reactor Bldg Twenty Yr Tendon Surveillance (Insp Period 6) ML20082Q8051995-03-10010 March 1995 TMI-1 Core Thermal-Hydraulic Methodology Using VIPRE-01 Computer Code ML20082G4441995-02-22022 February 1995 Vols I & II 20th Yr Physical Surveillance of TMI-1 Containment Bldg ML20100L6321994-08-0303 August 1994 Shipment of Miscellaneous Waste Evaporator Concentrates ML20059M2181993-11-30030 November 1993 Amend 19 to Pdms Sar ML20148F0931993-10-28028 October 1993 Rev 0 to Air Accumulator for FW-V-16A ML20148F1011993-10-28028 October 1993 Rev 0 to Air Accumulator for FW-V-16B ML20059F0471993-08-31031 August 1993 Amend 18 to Post-Defueling Monitored Storage (Pdms) Sar. W/Rev 2 to List of Pdms Requirements & Commitments ML20056E5921993-07-31031 July 1993 Conservative Design In-Structure Response Spectra for Resolution of USI A-46 for Tmi,Unit 1 ML20059D7351993-02-0707 February 1993 Review of Offsite Response to Site Area Emergency Incident at Three Mile Island Nuclear Station ML20126D2831992-12-18018 December 1992 Criticality SAR for TMI-2 Reactor Vessel ML20114B9631992-08-0808 August 1992 Rev 3 to Criticality Safety Evaluation of TMI Fuel Storage Facilities W/Fuel of 5% Enrichment ML20058F6561992-07-31031 July 1992 Companion Sample Exams ML20058F6481992-01-31031 January 1992 Metallographic & Hardness Exams of TMI-2 Lower Pressure Vessel Head Samples ML20066K3591991-01-31031 January 1991 Rev 0 to Rept on 1990 Eddy Current Exams of TMI-1 OTSG Tubing ML20216K1251990-10-31031 October 1990 Amend 9 to Post-Defueling Monitored Storage Sar ML20217A4251990-09-11011 September 1990 Rev 3 to Licensing Rept for Spent Fuel Pool Mod of Pool a: TMI Unit I ML20058M7251990-08-0101 August 1990 Rev 2 to Div Technical Evaluation Rept for Processed Water Disposal Sys ML20056A0091990-07-26026 July 1990 TMI-1 Trust Agreements ML20043A2341990-05-0202 May 1990 Rev 0 to TMI-1 Reactor Bldg 15-Yr Tendon Surveillance (Insp Period 5). ML20055C9461990-03-31031 March 1990 Final Rept, TMI - Unit 2 Safety Advisory Board, for Mar 1981 - Dec 1989 ML20247R6371989-09-12012 September 1989 Submerged Demineralizer Sys ML20246H9401989-08-25025 August 1989 Corrected Pages 5-10 Through 5-18 & 5-26 to Rev 1 to Defueling Completion Rept,Second Submittal ML20246E1021989-08-18018 August 1989 Portion of Rev 1 to, Defueling Completion Rept ML20246G1161989-08-15015 August 1989 Rev 0 to SER for Removal of Metallurgical Samples from TMI-2 Reactor Vessel, Safety Analysis ML20247J2251989-07-31031 July 1989 Rev 7 to Div Sys Description for Auxiliary Bldg Emergency Liquid Cleanup Sys (Epicor II) ML20246E3481989-07-0505 July 1989 Rev 0 to TMI-2 Defueling Completion Rept ML20245K0151989-06-30030 June 1989 Amend 4 to Post-Defueling Monitored Storage Sar ML20246P8081989-05-31031 May 1989 Rev 12 to Defueling Water Cleanup Sys ML20244E3241989-04-30030 April 1989 Rev 7 to Technical Evaluation Rept 15737-2-G03-107, Waste Handling & Packaging Facility ML20235G5761989-02-0101 February 1989 Rev 0 to Criticality Safety Evaluation for Increasing TMI-2 Safe Fuel Mass Limit ML20155G5581988-10-10010 October 1988 Rev 0 to Technical Evaluation Rept for Processed Water Disposal Sys ML20154F6941988-09-0909 September 1988 Rev 0 to SER for Completion of Upper Core Support Assembly Defueling 1999-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30
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Nu: lear SAFETY ANALYSIS sA , 4350-3256-85-1 Rev. # 5 Page I
of 39 TITLE SAFETY EVALUATION REPORT FOR CANISTER HANDLING AND PREPARATION FOR SHIPMENT Ottinator <
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Muclear 4350-3256-85-1 Title Safety Evaluation Report for Page 2 of 39 Canister Handling and Preparation for Shipment '
Rev. *
SUMMARY
OF CHANGE Approval *Date 0 Issued for use. , 12/85 1 Revised to incorporate site comments: added reference 1/86 to SAR for transportation of core debris, revised canister monitoring and integrity verification section, I noted the FHB crane modifications, and revised section i on seismic design. l 2 Revised commitment pertaining to closing of FHB missile 2/86 ,
shield door, corrected lowering speeds for canister :
from transfer cask. {
3 Revised to incorporate more detail on canister and 5/86 I shield plug lifting systems, provide more~ detail on j canister dewatering, increase discussion on heavy load i drops, add detail on railcar jacking system, and add discussion on truck bay fire hazards. l r
4 Revised to reflect the pressure in a " worst-case" 4/87 canister " ready for shipment" following a one-year j buildup pf radiolytic gases and the canister dewatering ;
criterion for determining the dewatered canister void volume.
5 Revised Section 2.3.1 to delete redundancy regarding 5/87 canister dewatering and weighing. Revised Section 2.3.2 to delete the estimated holding time for canisters and revise Section 3.2 to delete the 5% restriction on the number of canisters weighing greater than 2800 pounds. ,
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4350-3256-85-1 The NuPac 125-8 Shipping. Cask, mounted onia skid which is mounted ~on-an eight axle flat bed.railcar,cis brought onto the site on the existing.
rail lines to.a point outside.the security fence protective area.- The-
. cask protective coverings (tarp, sunshield and overpacks) are removed at-this point. The overpacks weigh approximately.ll,700. pounds each and the sunshield weighs approximately 500 pounds.
Th~e floor support brackets for the skid and the-CUS are installed. With the rall moat. bridge installed, the railcar with the skid / cask assembly is rolled'into the truck bay and aligned with the CUS. To accomplish north-south alignment of the skid lift lugs to the CUS clevises the railcar may be jacked from one side to tilt the lift lugs into align-ment. The jacking will cause tilting by compressing and.relleving railcar springs and will not lift the ralicar wheels off the. tracks.
.The railcar may extend into the exclusion zone, but no part of the ..
skid / cask assembly will extend over the exclusion zone. ;The skid / cask assembly is disconnected from the railcar and connected to the CUS which lifts the assembly from the_raticar. The railcar is removed from'the building and the assembly lowered onto the skid floor support brackets.
When the skid / cask assembly is in place the CUS.is removed and staged on the 305'-1" elevation'of the truck bay. -A saddle is attached to-the cask trunnions. The cask hydraulic lifting assembly is attached to the-skid and saddle and uprights the cask. A Ilmit switch trips the.hydrau -
lic lift assembly'when the cask _is level. Ratchet binders and screw jacks are.used to connect the. saddle to the jib crane support platform.
The hydraulic lifting assembly is then de-energized. The hydraulic lifting assembly may remain in place untilJthe cask is lowered to the horizontal position.
-The 5,200 pound secondary containment vessel lid'and the 3,000 pound-primary containment' vessel lid will be removed and stored in their respcctive truck. bay storage stands using the FHB crane auxiliary-
'holst. The shipping cask loading collar (SCLC) which weighs approxi-mately-36,000 pounds will be lifted from its storage stand and placed on top of the shipping cask.by the FHB 110 ton crane. The system will=then be_ ready to begin the sequence of operations to load defueling canisters.
2' 3
. Preparation of Canisters 2.3.1 Verification of Canister Integrity Canister integrity is initially verified by weighing the canister before and after storage in fuel pool 'A' to detect water inleakage. Each canister is weighed by the FHB canister handling bridge (CHB) after initial canister dewatering.
Prior to shipping, canister integrity is vertfled by two methods. Following the dewatering and filling with cover gas at the dewatering station, the canister relief valves are removed and the canister is capped and observed for bubbles Rev. 5/0135P 4
4350-3256-85-1=
for a minimum of 5 minutes. The acceptance criteria is "No Visible Bubbles." Also, when the-dewatered canister:Is moved to the FHB racks prior to shipping, the weight is recorded.
This weight is compared to the weight when the canister-is moved to the loading station just prior to shipment. These weights must agree within instrument repeatability.
Any canisters whose integrity cannot be verified will be treated as ' damaged' canisters. Procedures to repair.these damaged canisters will be developed and implement _ed on a case by case basis.
2.3.2 Verification of Catalyst Function Prior to shipment each canister will be monitored for. gas control. Canisters may be sampled for the presence of hydro-gen and oxygen to determine gas appearance rates. If it is decided to sample a canister, the sampling will take place after the dewatering and following an adequate holding period. The dewatering will occur either in the vessel or at the dewatering station. Following the dewatering, the canister is brought to the FHB racks where they will remain until they are sampled. The period of time that they are allowed to sit will be determined by sampling each type of canister several times. This will determine optimum holding times and general gas appearance rates.
Following the holding period, the canister may be returned to the dewatering station where the sampling is performed or it may be sampled at its rack location. An evacuated 150 cc to 300 cc sample vessel is connected to a long-handled 1/4" Hansen connection tool. The sample vessel is then connected, via the long handled tool, to the 1/4" purge inlet connection on the canister, the sample is obtained by opening a remote valve connected to the vessel, and the vessel is then retrieved. The volume of the sample will ensure that the Hansen connection on the canister is purged as well as obtaining a part of the top volume of the canister. This will be a conservative sample since, if there is stratification of the gases, released hydrogen will tend to migrate to the top of the canister.
After the sample is taken, the canister may be dewatered again. The argon cover gas pressure is checked and brought to approximately 2 atmospheres, any remaining relief valves are removed, and the canister purge and drain lines are capped.
The canister is then taken back to the racks, after performing the bubble test for canister integrity and weighing the dewatered canister as described in Section 2.3.1.
Rev. 5/0135P t _J
.. 1 p.n 4350-3256-85 <
-The canister istlifted into, and lowered from, the FTC by an integral
. canister lifting system.
~The' lifting system consists of.the following-components:
o' a 3,000 pound rated capacity hoist designed in accordance with ANSI B30.16, (i.e., safety factor of 5 to ultimate strength for. load bearing parts),
- o. reeving box, consisting of load bearing parts designed for 3,500 pounds with safety factors of 6 to yield and 10 to ultimate
- strength,~and I o. grapple assembly,~ consisting of a 3,500. pound rated capacity. center point grapple with. safety factors of 3 to yield and 5 to ultimate strength, a grapple connector designed at 3,500 pounds with safety factors of 6 to yield and 10 to ultimate strength, and a non-load bearing grapple alignment guide. The grapple is the same as the grapple used in the canister transfer shield, and is also discussed in Reference 2.
The FTC canister lifting system is configured with four part reeving and an equalizer such that the hoist will be subjected to only one half of the total load of the grapple assembly and canister. In general, the maximum weight of a defueling canister that will be-lifted by the lifting system is 2,800 pounds. The weight of the grapple assembly .is-less than 200~ pounds. Since.the holst will only-be subjected to one half of the combined weight of the canister and grapple assembly, the holst will be subjected to a load of less than 1,500 pounds. Thus, in general, the hoist can be considered to have a safety factor of 10 to ultimate strength. There is the possibility, however, that canisters may weigh up to 5 percent above 2,800 pounds (i.e., 2,940 pounds). For these canisters, the holst can be considered to have a safety factor of 9.55 to ultimate strength. In addition, the canister lifting system has been tested with loads up to 4,500 pounds by the FTC vendor and will be tested on-site with a load of at least 3000 pounds.
After being fully withdrawn into the FTC, the canister is held by the canister lifting system, and the bottom door is closed. Indication of the door being closed is provided by limit switches and canister
. position is given by a height encoder.
The bottom door is designed to withstand a canister drop from within the FTC and, thereby, provide a redundant line of defense against a canister drop out of the FTC during transport. The bottom door is designed to fall "as-is" and is disconnected from its power source during trans-port. For these reasons the FTC is considered to be
" single-failure-proof" with respect to a canister drop during trans- '
port. The FTC is not single failura proof while canisters are being raised or lowered. The consequences of a canister drop during this period are discussed in sections 5.2.2 and 6.1.
The lifting device for the FTC and its connection points to the FHB crane are designed to safety factors of 6 to yield and 10 to ultimate for a single attachment point based on the approximate design load of 22.8 tons (includes static load plus 15 percent for dynamic load).
Rev. 5/0135P 1