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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 ML20149D2521997-07-11011 July 1997 Exemption from Requirements of 10CFR50,App R,Section III.G.2.c to Extent That Requires Installation of Automatic Suppression Sys in Certain Fire Areas.Exemption Approved for Listed Fire Areas.Exemption for Fire Zone FH-FZ-5 Denied ML20148U6671997-07-0303 July 1997 Exemption from Requirements of 10CFR70.24 Re Criticality Monitors as Pertaining to Unirradiated Fuel & Other Forms of Special Nuclear Matls.Exemption Granted ML20093E8041995-10-11011 October 1995 Exemption from Requirements 10CFR50.44,10CFR50.46 & 10CFR50,App K,Enabling Use of Demonstration Fuel Assemblies Using Advanced Clad Matls During Cycles 11,12 & 13 at Plant 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 ML20086F6411991-11-14014 November 1991 Grants Exemption from Requirements of 10CFR50.46(a)(1)(i), 10CFR50.44(a) & App K to 10CFR50 Re Use of Zirlo Clad Fuel Instead of Zircaloy Clad Fuel as Specified in Rules ML20070D7191991-02-25025 February 1991 Exemption from Requirements of 10CFR50,App J Which Requires That Certain Surveillance Tests Be Conducted During Same Refueling Outage as Inservice Insps ML20012A2971990-02-26026 February 1990 Exemption from Reactor Coolant Pump Lube Oil Collection Requirements of Section Iii.O of App R to 10CFR50 ML20205P3821988-11-0202 November 1988 Exemption from 10CFR50,App R,Based on Analysis of Valves MU-V-2B & 2B & MU-V-3,4, & 5,indicating That at Least One Set of Valves Will Be Capable of Performing post-fire Shutdown Role W/O Addl Fire Protection Enhancements 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 ML20205C7701987-03-19019 March 1987 Exemption from Requirements of Section III.G.2 to 10CFR50, App R,Re Fire Protection for Equipment Important to Safe Shutdown ML20210T1521987-02-0909 February 1987 Exemption from 10CFR50,App A,Gdc 17 & 19 Requirements Re Electrical Power Sys & Control Room Habitability ML20207K0841986-12-30030 December 1986 Exemption from Requirements of 10CFR50,App R,Section Iii.G Re Installation of Automatic Fire Detection in Area FH-FZ-2 & Use of fire-rated Cable in Lieu of Fire Barrier Around Certain shutdown-related Circuits 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 ML20092B6161984-06-0404 June 1984 Exemption from Requirements of App R to 10CFR50,Section III.G.2 Re Fire Protection Requirements for Equipment Important to Safe Shutdown ML20053B2181982-05-10010 May 1982 Exemption Granting Extension from 810319 to 821001 for Submitting Plans & Schedules,For Filing Addl Exemptions & Submitting Design Descriptions of Alternative or Dedicated Shutdown Sys Per 10CFR50.48(c) 1999-07-21
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20210Q2491999-08-11011 August 1999 Confirmatory Order Modifying License Effective Immediately. Order Confirms Gpu Nuclear,Inc Commitment as Stated in 990602,to Complete Implementation of Thermo-Lag 330-1 Fire Barriers Corrective Actions by 000630 ML20210B8491999-07-21021 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 ML20137L9401999-04-12012 April 1999 Order Approving Transfer of License for TMI-1 from Gpu Nuclear,Inc to Amergen Energy Co,Llc & Conforming Amend,Per 10CFR50.80 & 90 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 ML20248A6181998-05-22022 May 1998 Confirmatory Order,Modifying License Effective Immediately Gpun Shall Complete Final Implementation of Thermo-Lag 330-1 Fire Barrier C/A at Plant,Unit 1 Described in Gpun Submittals to NRC 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 ML20149D2521997-07-11011 July 1997 Exemption from Requirements of 10CFR50,App R,Section III.G.2.c to Extent That Requires Installation of Automatic Suppression Sys in Certain Fire Areas.Exemption Approved for Listed Fire Areas.Exemption for Fire Zone FH-FZ-5 Denied ML20148U6671997-07-0303 July 1997 Exemption from Requirements of 10CFR70.24 Re Criticality Monitors as Pertaining to Unirradiated Fuel & Other Forms of Special Nuclear Matls.Exemption Granted 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 ML20093E8041995-10-11011 October 1995 Exemption from Requirements 10CFR50.44,10CFR50.46 & 10CFR50,App K,Enabling Use of Demonstration Fuel Assemblies Using Advanced Clad Matls During Cycles 11,12 & 13 at Plant 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 Directors 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 Directors 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 ML20035G8431993-04-23023 April 1993 Comment Concurring W/Numarc Comments Re Proposed GL, Availability & Adequacy of Design Bases Info 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 ML20034H8091992-12-0909 December 1992 Petition for Rulemaking PRM-50-58,requesting Change to 10CFR50,appendix E,To Change Requirement That Each Site Excerise Emergency Plan from Annually to Biennially 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 ML20086F6411991-11-14014 November 1991 Grants Exemption from Requirements of 10CFR50.46(a)(1)(i), 10CFR50.44(a) & App K to 10CFR50 Re Use of Zirlo Clad Fuel Instead of Zircaloy Clad Fuel as Specified in Rules 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 ML20070D7191991-02-25025 February 1991 Exemption from Requirements of 10CFR50,App J Which Requires That Certain Surveillance Tests Be Conducted During Same Refueling Outage as Inservice Insps 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 ML20042E5571990-03-14014 March 1990 Transcript of 900314 Meeting of Advisory Panel for Decontamination of TMI-2 in Harrisburg,Pa.Pp 1-84 ML20012A2971990-02-26026 February 1990 Exemption from Reactor Coolant Pump Lube Oil Collection Requirements of Section Iii.O of App R to 10CFR50 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 ML19351A3731989-09-21021 September 1989 Transcript of 890921 Advisory Panel for Decontamination of TMI Unit 2 Meeting in Harrisburg,Pa.Pp 1-131.Viewgraphs Encl 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 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 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 1999-08-11
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7590-01 i
UNITED STATES NUCLEAR REGULATORY COMMISSION 1
I In the Matter of
'l GPU NUCLEAR CORPORATION, ET AL.
Docket No. 50-289
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(Three Mile Island Nuclear Station,UnitNo.1)
EXEMPTION l
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GPU Nuclear Corporation (GPUN/ licensee) and three co-owners hold Facility Operating License No. DRP-50, which authorizes operation of the Three Mile IslandNuclearStation,UnitNo.1(TMI-1)(thefacility)atpowerlevelsnot in excess of 2568 megawatts thermal. This license provides, among other things, that the facility is subject to all rules, regulations, and Orders of the Nuclear' Regulatory Comission (the Comission or the staff) now or hereafter in effect.
The' facility is a pressurized water reactor located at the licensee's site in Dauphin County, Pennsylvania.
1 II.
On November 18, 1980, the Commission published a revised Section 10 CFR 50.48 and a new Appendix R to 10 CFR Part 50 regarding fire protection features of nuclear power plants (45 FR 76602). The revised Section 50.48 and Appendix R became effective on February 17, 1981.Section III of Appendix R contains 15 I
subsections, lettered A through 0, each of which specifies requirements for a particular aspect of the fire protection features at a nuclear power plant.
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One of these 15 subsections,111.0, is the subject of this exemption request.
This subsection specifically states that "the reactor coolant pump shall be equipped with an oil collection system if the containment is not inerted during normal operation... Such collection systems shall be capable of collecting lube oil from all pressurized and unpressurized leakage sites in the reactor coolant pump lube oil systems....
Leakage points to be protected shall include lift pump and piping, overflow lines, lube oil cooler, oil fill and drain lines and plugs, flanged connections on oil lir.es, and lube oil reservoirs where such features exist on the reactor coolant pumps."
TMI-1 has, in the past, been considered to be in full compliance with Section 111.0 of Appendix R.
However, a plant modification to reduce radiation exposure to workers during normal operation and to improve the occupational safety aspects of adding oil to the RCP lube oil system has been undertaken by the licensee. The modification relocates the lube oil fill station to a remote location outside of the secondary radiation shield with a corresponding addition of significant lengths of fill piping and tubing. Existing drip pans are retained as part of the oil collection system and new drip pans are added beneath reservoirs, drains and overflows. However, collection trays / pipes are not provided for the entire length of each pipe and beneath each fitting. By letter dated October 20, 1989, the licensee requested an exemption from the Appendix requirement to provide collection systems from all potential leakage sites and listed a number of compensatory considerations regarding design and operation of the modified system which would reduce the likelihood of fire.
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3 IV.
The purpose of Appendix R is to accomplish safe shutdown in the event of a single fire and maintain the plant in a safe condition.Section III.0 requires j
collection of oil leakage from RCP lube oil system fill lines. At THI-1, the intent of this section will be satisfied by both the design of the modification and procedurally controlled activities involved in adding oil to the RCPs.
Concerns related to fire caused by carelessness or material failure and resultant lube oil leakage during a seismic event are mitigated although highly unlikely. The additional considerations listed below will reduce the likelihood of fire even further during oil additions without concurrent seismic events.
In the absence of drip pans located below the entire portion of added fill piping / tubing, the licensee proposed minimizing the potential for and controlling leakage and spillage by:
1.
using welded joints at fill piping / tubing connections as much as C
possible; 2.
preventing oil from standing in piping outside the drip collection system by sloping the piping / tubing to drain completely into the RCP t
lube oil reservoirs; 3.
locating fill line connections to oil reservoirs above the reservoir's high level alarm set point and overflow line; j
4 extending existing or installing additional drip pans to collect j
possible leakage from the sight glasses; 5.
confirming after installation that added oil reaches the sump and is not trapped in the piping;
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based on startup and test' data, identifying sight glass level change 4
.versus volume of oil added and incorporate that information in oil-addition procedures; and e
7; revising operating procedures to require wipe-up of any spillage at the remote fill station local drip pans.
V.
Based upon its evaluation, the staff concludes that the licensee's proposed design achieves a level of safety equivalent to that which would be achieved by literal conformance with the requirements of Section III.0 of Appendix R to 10 CFR Part 50.
Accordingly, the Commission has determined pursuant to 10 CFR 50.12(a)
(2)(11) that (1) this exemption as described in Section IV is authorized by law, will not present an undue risk to the public health ano safety, and is consistent with the common defense and security, and (2) special circumstances are present for this exemption in that application of the regulation in this particular circumstance is not necessary to achieve the underlying purposes of Appendix R to 10 CFR Part 50. Therefore, the Commission hereby grants the exemption request identified in Section IV above.
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- I Pursuant to 10 CFR 51.32, the Counission has o'etermined that the granting of this exemption will have no significant impact on the environment I
( 55 FR 6717).
This exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY COM ISSION i
i Bruce A. Boger Acting Director Division of Rea,ctor Projects - I/II
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r Office of Nuclear Reactor Regulation Dated at Rockville, Maryland this February 26, 1990 t
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