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| II. | | II. |
| By letter dated April 13, 1985, the licensee requested exemptions from 10 CFR 30.51, 40.61, 70.51(d), 70.53, and 70.54 regarding the requirements for record keeping, inventorying, and reporting cf core special nuclear, source and byproduct materials. Specifically, 10 CFR 30.51 and 40.61 specify the requirements for keeping records which show the receipt, transfer and disposal of source and byproduct material. 10 CFR 70.51(d) specifies the requirements for the periodic conduct of a physical inventory of all special nuclear material in possession. 10 CFR 70.53 specifies the' requirements for the periodic submittal of a Material Balance Report and Physical Inventory Listing of special nuclear material possessed by the licensee. 10 CFR 70.54 specifies the requirements for submitting fluclear Material Transaction Reports for the transfer or receipt of special nuclear material. In meetings with the licensee held subsequent to the April 18, 1985 exemption request, staff representatives of the flRC and Department of Energy (D0E) have determined that the licensee will have sufficient information to comply with the requirements of 10 CFR 70.54 and that an exemption from this regulation is not necessary. | | By {{letter dated|date=April 13, 1985|text=letter dated April 13, 1985}}, the licensee requested exemptions from 10 CFR 30.51, 40.61, 70.51(d), 70.53, and 70.54 regarding the requirements for record keeping, inventorying, and reporting cf core special nuclear, source and byproduct materials. Specifically, 10 CFR 30.51 and 40.61 specify the requirements for keeping records which show the receipt, transfer and disposal of source and byproduct material. 10 CFR 70.51(d) specifies the requirements for the periodic conduct of a physical inventory of all special nuclear material in possession. 10 CFR 70.53 specifies the' requirements for the periodic submittal of a Material Balance Report and Physical Inventory Listing of special nuclear material possessed by the licensee. 10 CFR 70.54 specifies the requirements for submitting fluclear Material Transaction Reports for the transfer or receipt of special nuclear material. In meetings with the licensee held subsequent to the April 18, 1985 exemption request, staff representatives of the flRC and Department of Energy (D0E) have determined that the licensee will have sufficient information to comply with the requirements of 10 CFR 70.54 and that an exemption from this regulation is not necessary. |
| III. | | III. |
| The accident at Three Mile Island Unit 2 severely damaged the reactor core. | | The accident at Three Mile Island Unit 2 severely damaged the reactor core. |
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Category:GRANTS OF EXEMPTION FROM & EXTENSION TO NRC REQUIREME
MONTHYEARML20210B8491999-07-21021 July 1999 Exemption from Certain Requirements of 10CFR50.54(w),for Three Mile Island Nuclear Station Unit 2 to Reduce Amount of Insurance for Unit to $50 Million for Onsite Property Damage Coverage ML20206D4141999-04-20020 April 1999 Exemption from Requirements of 10CFR50,App R,Section III.G.2 Re Enclosure of Cable & Equipment & Associated non-safety Related Circuits of One Redundant Train in Fire Barrier Having 1-hour Rating ML20058A5491993-11-17017 November 1993 Exemption from Requirements in 10CFR50.120 to Establish, Implement & Maintain Training Programs,Using Sys Approach to Training,For Catorgories of Personnel Listed in 10CFR50.120 ML20210D7291992-06-15015 June 1992 Exemption from Requirements of 10CFR70.24 Re Criticality Accident Requirements for SNM Storage Areas at Facility Containing U Enriched to Less than 3% in U-235 Isotope ML20155F6621988-10-0606 October 1988 Exemption from Requirements of 10CFR55.45(b)(1), 10CFR55.45(b)(2),10CFR55.45(b)(4),10CFR55.45(b)(5), 10CFR55.45(a)(2),10CFR55.53(e) & 10CFR55.53(f) Re Operators Licenses About Requirements for Plant Simulation Facility ML20153E6771988-08-31031 August 1988 Exemption from Requirements of 10CFR55.59(c)(2), Subsections (IV) & (V), & 10CFR55.59(c)(3)(i) Items a Through AA, Eliminating Requirements for Certain Lecture Subjs & Manipulation Exercises ML20155B6631988-05-27027 May 1988 Exemption from Requirements of 10CFR70.24 Re Criticality Accident Requirements.Exemption Contingent Upon NRC Review of Mode 1 Criticality Analysis ML20210T1521987-02-0909 February 1987 Exemption from 10CFR50,App A,Gdc 17 & 19 Requirements Re Electrical Power Sys & Control Room Habitability ML20141G1251985-12-30030 December 1985 Exemption from 10CFR50.61 Requirements for Protection Against Pressurized Thermal Shock Events ML20138K1631985-10-24024 October 1985 Exemption from 10CFR61.55 Re Waste Classification of Epicor II Resin Liners ML20138D3921985-10-17017 October 1985 Exemption from 10CFR30.51,40.61,70.51(d) & 70.53 Requirements,Per 850418 Request.Exemption from 10CFR70.53 Shall Expire Following Completion of Defueling Effort, Including Assessment of Fuel Fines & Debris within Plant ML20134L9361985-08-28028 August 1985 Exemption from GDC 34 Re Removal of Residual Heat & GDC 37 Re Testing of Eccs,Per Util 850326 Request.Environ Assessment & Notice of Finding of No Significant Environ Impact Encl ML20133P8021985-08-0808 August 1985 Exemption from 10CFR50 App A,Gdc 34 Re RHR Sys & GDC 37 Re Testing of ECCS Sys ML20128H7961985-05-16016 May 1985 Partial Exemption from 10CFR50.54(a) Requirements Re Incorporating QA Program Revs Into FSAR 1999-07-21
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20210B8491999-07-21021 July 1999 Exemption from Certain Requirements of 10CFR50.54(w),for Three Mile Island Nuclear Station Unit 2 to Reduce Amount of Insurance for Unit to $50 Million for Onsite Property Damage Coverage ML20206D4141999-04-20020 April 1999 Exemption from Requirements of 10CFR50,App R,Section III.G.2 Re Enclosure of Cable & Equipment & Associated non-safety Related Circuits of One Redundant Train in Fire Barrier Having 1-hour Rating ML20206T7211999-02-11011 February 1999 Memorandum & Order (CLI-99-02).* Denies C George Request for Intervention & Dismisses Subpart M License Transfer Proceeding.With Certificate of Svc.Served on 990211 ML20198A5111998-12-11011 December 1998 Comment Opposing Proposed Rule 10CFR50.65 Re Requirements for Monitoring Effectiveness of Maintenance at Nuclear Power Plants.Proposed Rulemaking Details Collaborative Efforts in That Rule Interjects Change ML20154G2941998-09-17017 September 1998 Transcript of 980917 Public Meeting in Rockville,Md Re License Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen. Pp 1-41 ML20199J0121997-11-20020 November 1997 Comment on Pr 10CFR50 Re Financial Assurance Requirements for Decommisioning Nuclear Power Reactors.Three Mile Island Alert Invokes Comments of P Bradford,Former NRC Member ML20148R7581997-06-30030 June 1997 Comment on NRC Proposed Bulletin 96-001,suppl 1, Control Rod Insertion Problems. Licensee References Proposed Generic Communication, Control Rod Insertion, & Ltrs & 961022 from B&W Owners Group ML20078H0431995-02-0101 February 1995 Comment Opposing Proposed Rule 10CFR50 Re Shutdown & Lowpower Operations for Nuclear Reactors ML20077E8231994-12-0808 December 1994 Comment Supporting Proposed Rules 10CFR2,51 & 54 Re Rev to NRC NPP License Renewal Rule ML20149E2021994-04-20020 April 1994 R Gary Statement Re 10 Mile Rule Under Director'S Decision DD-94-03,dtd 940331 for Tmi.Urges Commissioners to Engage in Reconsideration of Author Petition ML20065Q0671994-04-0707 April 1994 Principal Deficiencies in Director'S Decision 94-03 Re Pica Request Under 10CFR2.206 ML20058A5491993-11-17017 November 1993 Exemption from Requirements in 10CFR50.120 to Establish, Implement & Maintain Training Programs,Using Sys Approach to Training,For Catorgories of Personnel Listed in 10CFR50.120 ML20059J5171993-09-30030 September 1993 Transcript of 930923 Meeting of Advisory Panel for Decontamination of TMI-2 in Harrisburg,Pa.Pp 1-130.Related Documentation Encl ML20065J3461992-12-30030 December 1992 Responds to Petition of R Gary Alleging Discrepancies in RERP for Dauphin County,Pa ML20065J3731992-12-18018 December 1992 Affidavit of Gj Giangi Responding to of R Gary Requesting Action by NRC Per 10CFR2.206 ML20198E5581992-12-0101 December 1992 Transcript of Briefing by TMI-2 Advisory Panel on 921201 in Rockville,Md ML20210D7291992-06-15015 June 1992 Exemption from Requirements of 10CFR70.24 Re Criticality Accident Requirements for SNM Storage Areas at Facility Containing U Enriched to Less than 3% in U-235 Isotope ML20079E2181991-09-30030 September 1991 Submits Comments on NRC Proposed Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. Informs That Util Endorses Comments Submitted by NUMARC ML20066J3031991-01-28028 January 1991 Comment Supporting SECY-90-347, Regulatory Impact Survey Rept ML20059P0531990-10-15015 October 1990 Comment Opposing Proposed Rules 10CFR2,50 & 54 Re Nuclear Power Plant License Renewal ML20059N5941990-10-0404 October 1990 Transcript of 900928 Public Meeting in Rockville,Md Re Studies of Cancer in Populations Near Nuclear Facilities, Including TMI ML20055F4411990-06-28028 June 1990 Comment Supporting Petition for Rulemaking PRM-50-55 Re Revs to FSAR ML20248J1891989-10-0606 October 1989 Order.* Grants Intervenors 891004 Motion for Permission for Opportunity to Respond to Staff Correspondence.Response Requested No Later That 891020.W/Certificate of Svc.Served on 891006 ML20248J1881989-10-0303 October 1989 Motion for Permission for Opportunity to Respond to Staff Correspondence in Response to Board Order of 890913.* Svc List Encl ML20248J0301989-09-29029 September 1989 NRC Staff Response to Appeal Board Order.* Matters Evaluated in Environ Assessment Involved Subjs Known by Parties During Proceeding & Appear in Hearing Record & Reflect Board Final Initial Decision LBP-89-7.W/Certificate of Svc ML20247E9181989-09-13013 September 1989 Order.* Requests NRC to Explain Purpose of 890911 Fr Notice on Proposed Amend to Applicant License,Revising Tech Specs Re Disposal of Accident Generated Water & Effects on ASLB Findings,By 890929.W/Certificate of Svc.Served on 890913 ML20247G0361989-07-26026 July 1989 Transcript of Oral Argument on 890726 in Bethesda,Md Re Disposal of accident-generated Water.Pp 1-65.Supporting Info Encl ML20247B7781989-07-18018 July 1989 Certificate of Svc.* Certifies Svc of Encl Gpu 890607 & 0628 Ltrs to NRC & Commonwealth of Pa,Respectively.W/Svc List ML20245D3651989-06-20020 June 1989 Notice of Oral Argument.* Oral Argument on Appeal of Susquehanna Valley Alliance & TMI Alert from ASLB 890202 Initial Decision Authorizing OL Amend,Will Be Heard on 890726 in Bethesda,Md.W/Certificate of Svc.Served on 890620 ML20245A5621989-06-14014 June 1989 Order.* Advises That Oral Argument on Appeal of Susquehanna Valley Alliance & TMI Alert from Board 890202 Initial Decision LBP-89-07 Authorizing OL Amend Will Be Heard on 890726 in Bethesda,Md.W/Certificate of Svc.Served on 890614 ML20247F3151989-05-22022 May 1989 NRC Staff Response to Appeal by Joint Intervenors Susquehanna Valley Alliance/Tmi Alert.* Appeal Should Be Denied Based on Failure to Identify Errors in Fact & Law Subj to Appeal.W/Certificate of Svc ML20246Q2971989-05-15015 May 1989 Comment Opposing Proposed Rule 10CFR50 Re Ensuring Effectiveness of Maint Programs for Nuclear Power Plants ML20246J6081989-05-12012 May 1989 Licensee Brief in Reply to Joint Intervenors Appeal from Final Initial Decision.* ASLB 890203 Final Initial Decision LBP-89-07 Re Deleting Prohibition on Disposal of accident- Generated Water Should Be Affirmed.W/Certificate of Svc ML20247D2761989-04-20020 April 1989 Transcript of 890420 Briefing in Rockville,Md on Status of TMI-2 Cleanup Activities.Pp 1-51.Related Info Encl ML20244C0361989-04-13013 April 1989 Order.* Commission Finds That ASLB Decision Resolving All Relevant Matters in Favor of Licensee & Granting Application for OL Amend,Should Become Effective Immediately.Certificate of Svc Encl.Served on 890413 ML20245A8381989-04-13013 April 1989 Transcript of Advisory Panel for Decontamination of TMI-2 890413 Meeting in Harrisburg,Pa.Pp 1-79.Supporting Info Encl ML20245A2961989-04-13013 April 1989 Transcript of 890413 Meeting in Rockville,Md Re Affirmation/Discussion & Vote ML20248H1811989-04-0606 April 1989 Valley Alliance/Tmi Alert Motion for Leave to File Appeal Brief out-of-time.* W/Certificate of Svc.Served on 890411.Granted for Aslab on 890410 ML20248G0151989-04-0606 April 1989 Valley Alliance/Tmi Alert Motion for Leave to File Appeal Brief out-of-time.* Requests to File Appeal Brief 1 Day Late Due to Person Typing Document Having Schedule Problems ML20248G0261989-04-0606 April 1989 Susguehanna Valley Alliance/Tmi Alert Brief in Support of Notification to File Appeal & Request for Oral Argument Re Appeal.* Certificate of Svc Encl ML20248D7211989-04-0404 April 1989 Memorandum & Order.* Intervenors Application for Stay Denied Due to Failure to Lack of Demonstrated Irreparable Injury & Any Showing of Certainty That Intervenors Will Prevail on Merits of Appeal.W/Certificate of Svc.Served on 890404 ML20247A4671989-03-23023 March 1989 Correction Notice.* Advises That Date of 891203 Appearing in Text of Commission 890322 Order Incorrect.Date Should Be 871203.Certificate of Svc Encl.Served on 890323 ML20246M2611989-03-22022 March 1989 Order.* Advises That Commission Currently Considering Question of Effectiveness,Pending Appellate Review of Final Initial Decision in Case Issued by ASLB in LBP-89-07. Certificate of Svc Encl.Served on 890322 ML20236D3821989-03-16016 March 1989 Valley Alliance & TMI Alert Motion for Extension of Time to File Brief in Support of Request for Appeal in Matter of 2.3 Million Gallons Of....* Certificate of Svc Encl.Served on 890316.Granted for Aslab on 890316 ML20236D3121989-03-15015 March 1989 Licensee Answer to Joint Intervenors Motion for Extension of Time to File Brief on Appeal.* Motion Opposed Based on Failure to Demonstrate Good Cause.W/Certificate of Svc ML20236D2901989-03-11011 March 1989 Valley Alliance/Tmi Alert Motion for Extension of Time to File Brief in Support of Request for Appeal in Matter of Disposal of 2.3 Million Gallons of Radioactive Water at Tmi,Unit 2.* Svc List Encl ML20236A3761989-03-0808 March 1989 Licensee Answer Opposing Joint Intervenors Motion for Stay.* Stay of Licensing Board Decision Pending Appeal Unwarranted Under NRC Stds.Stay Could Delay Safe,Expeditious Cleanup of Facility.Certificate of Svc Encl ML20236C2441989-03-0808 March 1989 NRC Staff Response in Opposition to Application for Stay Filed by Joint Intervenors.* Application for Stay of Effectiveness of Final Initial Decision LBP-89-07,dtd 890202 Should Be Denied.W/Certificate of Svc ML20235V2641989-03-0202 March 1989 Notice of Aslab Reconstitution.* TS Moore,Chairman,Cn Kohl & Ha Wilber,Members.Served on 890303.W/Certificate of Svc ML20235V2161989-02-25025 February 1989 Changes & Corrections to Susquehanna Valley Alliance/Three Mile Island Alert Documents Submitted on 890221.* Certificate of Svc Encl 1999-07-21
[Table view] |
Text
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, Enclosure 1 I
UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of )
)
GENERAL PUBLIC UTILITIES NUCLEAR ) Docket No. 50-320 CORPORATION )
(Three Mile Island Nuclear Statior, Unit 2) )
EXEMPTION 1.
GPU Nuclear Corporation, Metropolitan Edison Company, Jersey Central Power and Light Company and Pennsylvania Electric Company (collectively, the licensee) are the holders of Facility Operating License No. DPR-73, which has authorized operation of the Three Mile Island Nuclear Station, Unit 2 (THI-2) at power levels up to 2772 megawatts thermal. The facility, whica is located in Londonderry Township, Dauphin County, Pennsylvania, is a f pressurized water reactor previously used for the commercial generation of electricity.
By Order for Modificatior, of License, dated July 20, 1979, the licensee's authority to operate the facility was suspended and the licensee's authority was limited to nairitenance of the facility in the present shut-down cooling mode (44 Fed. Reg. 45271). .By further Order of the Director, Office of Nuclear Reactor Regulation, dated February 11, 1980, a new set of license requirements was imposed to reflect the post-accident condition of the facility and to assure the continued maintenance of the current safe, stable, long-tem cooling condition of the facility (45 Fed. Reg.11292).
The license provides, among other things, that it is subject to all rules, regulations and Orders of the Comission now or hereaf ter in effect.
! o
II.
By letter dated April 13, 1985, the licensee requested exemptions from 10 CFR 30.51, 40.61, 70.51(d), 70.53, and 70.54 regarding the requirements for record keeping, inventorying, and reporting cf core special nuclear, source and byproduct materials. Specifically, 10 CFR 30.51 and 40.61 specify the requirements for keeping records which show the receipt, transfer and disposal of source and byproduct material. 10 CFR 70.51(d) specifies the requirements for the periodic conduct of a physical inventory of all special nuclear material in possession. 10 CFR 70.53 specifies the' requirements for the periodic submittal of a Material Balance Report and Physical Inventory Listing of special nuclear material possessed by the licensee. 10 CFR 70.54 specifies the requirements for submitting fluclear Material Transaction Reports for the transfer or receipt of special nuclear material. In meetings with the licensee held subsequent to the April 18, 1985 exemption request, staff representatives of the flRC and Department of Energy (D0E) have determined that the licensee will have sufficient information to comply with the requirements of 10 CFR 70.54 and that an exemption from this regulation is not necessary.
III.
The accident at Three Mile Island Unit 2 severely damaged the reactor core.
Video inspections and topography measurements indicate a cavity in the upper core region which represents approximately 26% of the tocal original core volume. fio more than 2 of the original 177 core fuel assemblies
w remain intact and only 42 assemblies have any full length fuel rods. The core damage extenas radially all the way out to the core former walls. As a result of the accident induced embrittlement of virtually all fuel rods, no fuel assemblies are expected to be withdrawn intact. There is a significant amount of core debris in ex-core region locations (e.g., an estimated 10 to 20 tons in the lower reactor vessel head) and much of the
- core byproduct material has been released from the fuel. For' example, analyses of core debris bed samples indicate that, on the average, only about 13% of the original Cs-137 inventory remains in the fuel although the percentage retained can vary considerably from sample to sample.
During the defueling of the damaged core, the fuel debris will be collected in canisters by vacuuming or " pick and place" techniques. However, as a result of the damaged condition of the core, the licensee will have no means of accurately characterizing (e.g., U-235 enrichment and total uranium content, fission product radionuclide content and distribution, plutonium content) the fuel debris during the defueling sequence. The capability for characterizing the collected fuel debris in each canister would require sophisticated hot cell and laboratory facilities with the means to homogenize, sample, weigh, and analyze the contents of each canister. Such facilities do not exist at Three Mile Island. Given the damaged condition of the core and lack of sophisticated hot cell and laboratory facilities, there is no practical means for the licensee to perform the measurements or precise calculations necessary to comply with the Commission's regulations related to accountability of special nuclear,
7-source and byproduct materials. The staff therefore concludes that exemptions from the requirements of 10 CFR 30.51, 40.61, 70.51(d), and 70.53 are appropriate. As previously sta.ted in Section II of this evaluation, staff representatives of the NRC and DOE have determined that the licensee will have sufficient .information to comply with the transfer requirements of 10 CFR 70.54 and that exemption from this regulation is not necessary.
The granting of these exemptions does not mean that the licensee will not provide any record keeping or reporting of the canister core debris which is intended to be transferred to the custody of the DOE for research and/cr storage at DOE facilities in Idaho. In lieu of the reporting requirements of 10 CFR 70.53, the licensee will provide to the DOE all available information describing the physical contents of each canister including:
the canister identification number, canister type (i.e., knockout, fuel, or filter), date of shipment, the shipment number, the empty weight of the canister, the loaded weight of the canister, the dewatered weighi.~of the canister, maximum total curies, the canister pressure, general physical descriptionofthecanistercontentsincludingvideotapedata(if available), and any additional information based on mutual agreement between the. licensee and the D0E. Further, following the completion of defueling and the offsite shipment of the packaged fuel debris, the licensee will be in a position to comply with the requirements of 10 CFR i l ,
70.53 and the licensee will be required to submit a Material Balance Report {
1 and Physical Inventory Listing at that time. ;
i 4
- - , - - - . - . - - - -- . - - - p
In lieu of the requirement in 10 CFR 70.51(d) for the periodic conduct of a physical inventory of all special nuclear material, the licensee will conduct such an inventory upon the completion and analysis of a post-defueling survey.
~
In lieu of the record keeping requirements of 10 CFR 30.51 and 40.61, the licensee will maintain records of each fuel shipment in accordance with the requirements of 10 CFR 71.91. Such records will include an identification i
of the shipment packaging, the maximum total curies, the total quantity of each shipment, and the date of shipment.
IV.
Accordingly, the Commission has determined that, pursuant to 10 CFR 30.11, ;
40.14, and 70.14, these exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. The Commission hereby grants exemptions j from the requirements of 10 CFR 30.51, 40.61, 70.51(d), and 70.53. Tho exemption from 10 CFR 70.53 shall expire following the completion of the ,
defueling effort, including an assessment of any fuel fines and debris which remain within the plant, and the subsequent offsite shipment of all ,
packaged fuel debris, i
It is further determined that the exemptions do not authorize a change in f effluent types or total amounts nor an increase in power level and will not !
result in any significant environmental impact. In light of this v ~ n , a, , - - ,
w determination and as reflected in the Environmental Assessment and Notice of Finding of No Significant Environmental Impact prepared pursuant to 10 CFR 51.21 and 51.30 through 51.32, issued September 20, 1985, it was concluded that the instant action is insignificant from the standpoint of environmental impact and an environmental impact statement need not be prepared.
FOR THE NUCLEAR REGULATORY C0ftMISSION l k Harold R. Denton, Director Office of Nuclear Reactor Regulation Effective Date: October 17, 1985 Dated at Bethesda, Maryland Issuance Date: October l', 1985