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Category:APPLICATION
MONTHYEARML19350D1611981-03-19019 March 1981 Reapplication by Wa Fraser for Operator License ML19350D1601981-03-19019 March 1981 Reapplication by Re Boyer for Senior Operator License ML19350D1591981-03-19019 March 1981 Reapplication by Nj Monson for Operator License ML20129H1651979-01-31031 January 1979 Partially Withheld Application for M Kending for Reactor Operators License Examination ML20128F5071979-01-31031 January 1979 Partiallt Withheld Application by C Mell for Reactor Operators License Examination ML20128F5331979-01-31031 January 1979 Partially Withheld Application for J Brummer for Senior Operator License Examination ML20128F5561979-01-31031 January 1979 Partially Withheld Application by J Garrison for Senior Operator License Examination ML20129H1461979-01-31031 January 1979 Partially Withheld Application by J Herman for Operator License ML20129H1881979-01-31031 January 1979 Partially Withheld Application for D Smith for Reactor Operator License Examination ML20129H2011979-01-31031 January 1979 Partially Withheld Application by D Mayhue for Reactor Operator License Examination ML20129H1281979-01-24024 January 1979 Partially Withheld Application for Amendment to Senior Operator License for R Hutchinson ML20129G6381978-11-0909 November 1978 Partially Withheld Application for Renewal of Senior Operator Licesne Number SOP-2866-1 by J Seelinger ML20129G4601978-09-14014 September 1978 Partially Withheld Application for Reactor Operator License for E Hemmilia ML20129G4311978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for Hb Shipman ML20129F5161978-09-14014 September 1978 Partially Withheld Application for Senior Operator for R Zechman ML20129F4871978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for C Hartman ML20129F4741978-09-14014 September 1978 Partially Withheld Application for Senior Operator License for J Logan ML20024B7591977-07-0505 July 1977 Application by Wh Zewe for Senior Reactor Operator License ML20024B7581975-07-10010 July 1975 Application by Wh Zewe for Senior Reactor Operator License ML20024B7571974-05-20020 May 1974 Application by Wh Zewe for Hot Reactor Operator License.Prof Qualifications Encl ML19270H5331973-12-19019 December 1973 Amend 2 to Application for SNM License Re Higher Strength Source to 1,300 Ci of Americium ML19270H5311973-10-15015 October 1973 Amend 1 to Application for SNM License ML19270H5291972-06-0808 June 1972 Application for SNM License for Storage Only of Fuel Elements & Byproduct Matl 1981-03-19
[Table view] Category:MATL/BYPRODUCT LICENSE
MONTHYEARML19270H5331973-12-19019 December 1973 Amend 2 to Application for SNM License Re Higher Strength Source to 1,300 Ci of Americium ML19270H5311973-10-15015 October 1973 Amend 1 to Application for SNM License ML19270H5291972-06-0808 June 1972 Application for SNM License for Storage Only of Fuel Elements & Byproduct Matl 1973-12-19
[Table view] Category:AMENDS & RENEWAL
MONTHYEARML19270H5331973-12-19019 December 1973 Amend 2 to Application for SNM License Re Higher Strength Source to 1,300 Ci of Americium ML19270H5311973-10-15015 October 1973 Amend 1 to Application for SNM License ML19270H5291972-06-0808 June 1972 Application for SNM License for Storage Only of Fuel Elements & Byproduct Matl 1973-12-19
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211D1321999-08-20020 August 1999 Application for Amend to License DPR-50 to Revise TS Bases Re Degraded Undervoltage Relay Setpoint Calibration Frequency & Degraded Voltage Relay Tolerance Rev ML20210J0941999-07-29029 July 1999 Suppl TS Change Request 274 to License DPR-50,revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance Tss,As Result of NRC Generic Concerns Re CR Habitability Issues ML20209D6651999-07-0808 July 1999 Corrected TS Pages 3-21,4-5a,4-9,4-38 & 6-3 to Amends 211 & 212 to License DPR-50.Pages Failed to Reflect Previously Approved Changes Granted in Amends 203 & 204 in Case of Amend 211 & 207 in Case of Amend 212 ML20196K5901999-06-29029 June 1999 LAR 285 for License DPR-50,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls Can Continue to Be Moved ML20209C0551999-06-29029 June 1999 LAR 77 for License DPR-73,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matl May Continue to Be Moved ML20195E3341999-06-0404 June 1999 TS Change Request 265 to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20209B5891999-05-26026 May 1999 LAR 281 to License DPR-50,revising TMI-1 UFSAR Chapters 5 & 14 to Permit Use of Conservative Deterministic Failure Margin Methodology for Seismic Analysis of Portions of Auxiliary Steam Line.Rept 240046-R-001 Encl.Rept Withheld ML20206R1111999-05-13013 May 1999 Application for Amend to License DPR-50,requesting That License Sections 2.a.(3) & 2.c.(7) & TS Section 3.1.1 Be Revised to Incorporate Administrative Updating & Changes to Bases Statement ML20205H0691999-04-0101 April 1999 TS Change Request 262 to License DPR-50,revising TS by Adding LCO Action Statements & Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0421999-02-0202 February 1999 TS Change Request 274 to License DPR-50,expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems ML20196H9751998-12-0303 December 1998 LAR 279 to License DPR-50,reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4401998-12-0303 December 1998 LAR 278 to License DPR-50,requesting Consent to Transfer & Authorize Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License.Supporting Documentation,Encl ML20196G7671998-11-25025 November 1998 TS Change Request 277 to License DPR-50,changing Surveillance Specs for OTSG ISIs for TMI-1 Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only ML20195C6811998-11-12012 November 1998 Amend 52 to License DPR-73,relocating Audit Frequency Requirements from TMI-2 to TMI-2 Post Defueling Monitored Storage QA Plan & Extends Max Allowed Interval Between Certain Audits from 12 Months to 24 Months ML20154P8441998-10-19019 October 1998 Application for Amend to License DPR-50,providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage.Proprietary & non- Proprietary Calculation,Encl.Proprietary Info Withheld ML20154Q6201998-10-19019 October 1998 TS Change Request 248 to License DPR-50,adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18, Remote Shutdown Sys ML20154M3691998-10-15015 October 1998 Application for Amend to License Amend Request 276 to License DPR-50 Revising UFSAR Chapter 14 Accident Analysis Atmospheric Dispersion Factors.Ufsar Revised Pages Encl ML20249B2391998-06-11011 June 1998 TS Change Request 273 to License DPR-50,incorporating Alternate High Radiation Area Control Consistent W/Reg Guide 8.38 ML20217E5131998-03-23023 March 1998 Application for Amend to License DPR-50,revising TS Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 Efpy.Request Also Submitted in Response to NRC ML20217G0161997-10-0303 October 1997 Suppl to License Amend Request 268 to License DPR-50, Replacing Pages 4-80 & 4-81 Previously Submitted w/TMI-1 License Amend Request 268 on 970812 ML20211C2221997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re TS Change Request 266.Supplement Provides for Phased Review & Issuance of License Amends & Involves Administrative Correction to TS Decay Heat Removal Sys Leakage Rate ML20211C3211997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re License Amend Request 269 Submitted on 970814.Suppl Includes Addl Change to TS Section 3.1.4 & Proposed Page Rev Clarifying That UFSAR Analysis Is More Conservative ML20210J9951997-08-14014 August 1997 Revised License Amend Request 269 for License DPR-50, Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J3981997-08-12012 August 1997 Tech Spec Change Request 268 for License DPR-50,revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operations ML20198E7871997-07-30030 July 1997 TS Change Request 266 to License DPR-50,incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 ML20141E1311997-05-0808 May 1997 Application for Amend to License DPR-50,consisting of Change Request 264,incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2351997-04-21021 April 1997 Application for Amend to License DPR-50,requesting Rev to TS 3.3 Re Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Systems ML20134M1111997-02-0707 February 1997 Application for Amend to License DPR-50,incorporating Certain Improvements from Revised STS for B&W Plants, NUREG-1430 & Addl Changes as Described in Encl TS ML20133D2651996-12-24024 December 1996 Application for Amend to License DPR-50,requesting Reinstatement of Auxiliary & Fuel Handling Bldg Ventilation Sys TS ML20132F3221996-12-16016 December 1996 Application for Amend to License DPR-50,consisting of Change Request 260,reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135C5201996-12-0202 December 1996 TS Change Request (Tscr) 75 to License DPR-73,relocating Audit Frequency Requirements to Pdms QA Plan ML20134D7761996-10-24024 October 1996 Amend 51 to License DPR-73,revising TS to Extend Surveillance Interval for Demonstrating Operability of Containment Airlock ML20128K1831996-10-0808 October 1996 Amend 50 to License DPR-73,revising TS to Incorporate Improvement from Administrative Controls Section of Revised STS for B&W Plants ML20117H0181996-08-29029 August 1996 Application for Amend to License DPR-50,consisting of TS Change Request 257,incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1901996-06-28028 June 1996 Application for Amend to License DPR-50,consisting of Change Request 259,allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8751996-05-24024 May 1996 Errata to Application for Amend to License DPR-50,consisting of TS Change Request 243,replacing Pages for App a ML20101R1361996-04-10010 April 1996 Application for Amend to License DPR-50,consisting of Change Request 243,revising Addl Group of Surveillances in Which Justification Has Been Completed Following Receipt of 930623 Application ML20100J6831996-02-22022 February 1996 Application for Amend to License DPR-50,consisting of Change Request 254,revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Station Battery Cell Parameters Not Met ML20095J2261995-12-21021 December 1995 Revised TS Change Request 254,raising Low Voltage Action Level to 105 Volts DC ML20091L2831995-08-23023 August 1995 Rev to TS Change Request 223 to License DPR-50,incorporating Ref to 10CFR20.1302 ML20087F4881995-08-11011 August 1995 Rev to TS Change Request 252 to License DPR-50,removing TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements.Certificate of Svc Encl ML20086R3001995-07-24024 July 1995 Rev to LAR 250 to License DPR-50,clarifying Section III, SE Justifying Change for source-range Nuclear Instrumentation SRs ML20085N1551995-06-22022 June 1995 TS Change Request 227 to License DPR-50,replacing Pages for App A.Certificate of Svc Encl ML20084N3461995-06-0101 June 1995 TS Change Request 223 to License DPR-50,deleting Remaining Portions of RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084L4201995-06-0101 June 1995 TS Change Request 251 to DPR-50,revising TS 5.3.1.1 to Describe Use of Advanced Clad Assemblies ML20084B3261995-05-24024 May 1995 Application for Amend to License DPR-50.Amend Would Change Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7771995-05-17017 May 1995 Application for Amend to License DPR-50,consisting of Change Request 252,removing Chemical Addition Sys Requirements from TS to COLR ML20079A7771994-12-23023 December 1994 Rev to TS Change Request 221 to License DPR-50,revising TS Page 3-32a ML20073F9241994-09-26026 September 1994 LAR 246 to License DPR-50,revising License Condition 2.C.9 Re Long Range Planning Program ML20069A6731994-05-20020 May 1994 TS Change Request 244 to License DPR-50,requesting Revised CR Trip Insertion Time Testing Acceptance Criterion for Remainder of Cycle 10 for 12 Specific CRs Which Initially Experienced Slow Rod Drop Times During Testing on 940317 1999-08-20
[Table view] |
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i A}ENDMENT NO.1 TO APPLICATION FOR SPECIAL NUCLEAR MATERIAL LICENSE FOR STORAGE ONLY OF FUEL ELDENTS AND BY-PRODUCT MATERIAL FOR
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Tile THREE MILE ISLAND NUCLEAR STATION UNIT 1
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0779
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s THREE MILE ISLA';D tl NIT 1 FUEL AND BY-PRODUCT STORACE LICENSE APPLICATION This application is filed pursuant to title 10 code of Federal Regulations, Part 70 for authorization to receive, possess, store, inspect, and package for transport nuclear fuel assemblies. Authori-zation is also requested for the storage of other radioactive by-product materials to be used in subsequent operations of the reactor. It is requested that the Special Nuclear Materials License remain in effect until receipt of the Operating License.
The following information is submitted in support of the application:
1.0 APPLICANT Metropolitan Edison Company
- 2800 Pottsvil]e Pike, Muhlenberg Township Berks County, Pa.
Mailing Address: P. O. Box 542, Reading, Pa. 19603 2.0 ADDRESS OF STORAGE SITE The Three Mile Island Nuclear Station is located on Three Mile Island
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3.0 CORPORATE INFORMATION 1he information set forth in the application for Construction Permit and Operating License, Docket 50-289 dated May 3,1967, for the Three Mlle Isl.md Nuclear Station l'ni t 1, is hereby incorporated by re ference .
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s- Findings concerning centrol and ownership of the applicant are set forth ,
s in the Order of the Atomic Safety and Licensing Board dated May 16, 1972.
4.0 RADIOACTIVE MATERIAL 4.1 Fuel Elements The 177 fuel assemblies of the initial core that will be received and stored are described in the following table:
Square cross-section 8.536 inches square -
of fuel assembly Effective fuel length 144 inches Over-all fuel assembly length 165.625 inches Rod array type 15 x 15 - 225 (208 fuel rods 16 control rod channels 1 instrument channel)
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Rod clad thicknesc .0265 inches Rod clad material Zr-4
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Rod outside diameter .430 inches No. of fuel assemblies 177 U-235 enrichments (%) 2.06% 2.72% 3.05%
No. of Assemblics 56 61 60 UO2 Weight Per assembly (pounds) 1,159.5 lbs. UO2
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UO2 Weight per rod 5.5 7 lb s . UO 2 U weight per assembly 1,022.2 lbs. U The maximum amount of special nuclear material, as kilograms of U-235, which may be possessed at any one time is 10,300 kilograms. This represents the initial core and assumes that all additional storage spact-has been utilized.
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, 4.2 Other Raaroactive Materials Up to 50.1 curies of Cosium 137 will be received for subsequent
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use as gamma sources for calibrations in connection with reactor operation.
Up to 800 curies of Americium will be received for subsequent use as neutron sources- for reactor initial startup, operation, and portable instrument calibration.
5.0 TRANSPORTATI ON All fuel assemblics are to be delivered to the site in accordance with shipping procedures and a_ tangements of the Babcock & Wilcox Company.
The fuel assemblies will be shipped in steel shipping containers (B&W Model B Fresh Fuel Shipping Container) supplied by the fuel manufacturers, Babcock &
Wilcox Company as licensed under SNM-1168. The Model B shipping container has been assigned DOT Special Permit No. 6206.
Fuel will be shipped to the site by truck, six containers per truck f.-
and one or two fuel assemblies per container. Upon arrival at the site, the containers and truck trailers will be inspected for damage and monitored for external radioactive contamination.
6.0 STORAGE CONDITIONS The fuel assemblies will be stored in the Fuel Handling Building shown on Figures 1-3, 1-4, 1-5, 1-7 & 1-8 of the Final Safety Analysis Report.
The fuel storage pools are constructed of reinforced concrete and lined with
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stainless steel. It is expected that the fuel will be stored in the fuel storage racks in a wet condition with a boron concentration of 2270 PPM.
However, should circumstances prohibit the flooding of the fuel storage peola, the fuel will be placed in the storage racks in a dry condition. Since the Fuel ifandling nullding is a reinforced concrete structure, it is considered ext ra >1:. unifl el:, t ha t a fi re will occur. llowever, the use of flam.n'.
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4/ s materials in the Fuel Handling Building will be carefully controlled as an added margin of safety.
6.1 Inspection & Handling As soon as practicable af ter arrival at the Fuel Handling Building, the shipping containers will be unloaded from the truck trailers. The new fuel assemblies will be removed one at a time from the shipping containers and placed in a vertical position in the new fuel inspection stand, to check for integrity and numbering. Damaged rods, if any, will be detected by visual inspection and by the performance of radiation surveys by quali-fied personnel as the shipping containers are opened or as the assemblies are unwrapped. All activities of unloading, inspecting, moving and storing of the assemblies will be performed in accordance with written procedures
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which will have been approved by the Three 1 Ele Island Nuclear Station Super-intendent. .
6.2 Safety Evaluation The atorage racks in the Fuel Handling Building are designed to
. provide a center-to-center spacing of twenty-one inches or more between the fuel assemblies. This arrangement provides for up;:ight storage of the fuel
. assemblies in an array in which the effective multiplication factor is less than 1.0 in the flooded condition. This conclusion is based on the calculated K
eff f 0.87 in c la unborated water for 3.5 percent enriched fuel assemblies in a 21-inch square array (1) . Since the highest enrichment for which this applicatica is being made is 3.05 percent, a factor of conservatism is pre-sent in the calculations.
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l The effective multiplication factor of an unmoderated storage 1
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array of uranium fuel elements which are enriched to less than five percent 7-(. -
uranium-235 is always less than 1.0, cegardless of the spacing.
In addition to the fully flooded and unmoderated conditions, con-sideration was also given to the condition of moderation within the assedblies and less than full water reflection between assemblies. The only conceivable means by which this condition could exist are listed below:
(1) The accumulation of water in the fuel assedblies to a greater degree than between assemblies, such as might arise from use of a fire hose in the Fuel Storage Building.
(2) The use of fog, spray, or foam fire fighting equipment.
(3) The presence of packaging material which has moderating properties in the interior of the assemblies.
None of these methods are considered credible for the follcwing g reasons:
l (1) The amount of combustible material present in the Fuel Storage
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Building will be at a minimum. There will be no sprinklers in the building and signs will be posted on the building prohibiting the use of fire hoses, fog, or foam fire fighting equipment within the building. Carbon dioxide extinguishers will be used for fire protection.
(2) Openings will be made in the plastic protective coatings near the bottom of each fuel assembly. In the event that adminis-trative controls should not prevent water from entering the fuel assemblies, these holes would allow the water to drain out immediately.
(3) There will be no packaging material between the fuel rods of the asre 6. lies at any time the assemblies are stored in taa i i
Fuel Storage Building racks. Polyethylene or other plastic I
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materials will be used as protective covers around the fuel assemblies but not within the assemblies. ,
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Therefore, it is concluded that it is not credible that the condition of moderation within assemblies and less than full moderation between assemblies can exist.
It is concluded that the storage methods described in this request are adequate to prevent criticality and protect the health and safety of the public.
6.3 Radiation Monitoring The following RMS instrumentation will be operational and will be utilized to provide continuous radiation monitoring in the Fuel Handling Building:
6.3.1 RM-G9 Fuel Handling Bridge Detector, Victoreen Instrument
(' Corporation Aren Monitor (Ion Chamber) Model 845 Range .1 to 107 mr/hr.
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6.3.2 RM-A13 Fuel Handling Building Air Monitor (particulate, gaseous, iodine). Victoreen Instrument Corporation Model 840.
The radiation monitors listed above will have an external alarm of sufficient intensity to be heard throughout the storage and handling i
area. An assortment of portable and laboratory radiation instrumentation will also be available during receipt, inspection and storing of the fuel as ser.b lies .
The above mentioned radiation monitoring equipment will be in service prior to receipt of fuel and will be used for both routine and emer; c r e:. oltva t icas .
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O 6.3.3 Personnel Monitoring Ne .
i All authorized personnel who enter the fuel inspection 6 storage area shall carry personnel monitoring devices. In addition, routine radiation surveys will be conducted in the inspection and storage area.
6.3.4 Monitoring of New Fuel Assemblies Each new fuel aseembly will be monitored for alpha and beta contamination. A beta-gamma dose rate survey will also be taken of each fuel assembly. All readings will be recorded and identified by fuel assembly number.
6.3.5 Emergency Procedure An emergency procedure will be posted in the Fuel Handling Building. In the unlikely event of a radiological incident, this procedure C'- will provide the following information: the evacuation route to be utilized by personnel when leaving the Fuel Handling Building, and listing of reentry
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procedures to be followed after the accident.
All personnel involved in fuel handling operations will be
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trained in the emergency procedures utilized in the event of a radiological incident.
The .sadiation Protection Supervisor or his designated Radiation Protection technician will be responsible for execution of the emergency procedure.
6.3.6 Request for Exemotion Applicant requests exemption from the monitoring and emergency procedures requirements of Section 70.24, 10 CFR 70. This exemption is i
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- requested because the nature of the special nuclear material, storage arrange-ments, and procedural controls which Applicant proposes to employ preclude any possibility of accidental criticality during receipt, unloading, inspec-tion and storage of the new fuel assemblies.
7.0 INDEMNITY Application will be made by Met-Ed to Nuclear Energy Liability Insurance Associates for insurance in the amount of $1,000,000 for the period from first shipment of fuel assemblies from Babcock & Wilcox's manufacturing facilities in Lynchburg, Virginia, until the first fuel asse=bly is loaded into the reactor. Proof of financial protection will be furnished
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prior to fuel shipment.
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METROPOLITAN EDISON' COMPANY t
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By 2
,, Vice President
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Attest:
ti 7779 m 1.) 7,8
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Secre ta ry Sworn and subscribed to before ne this /5 I' day of McMb 1973.
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