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Category:FEDERAL REGISTER NOTICES
MONTHYEARML20216H0321999-09-28028 September 1999 Notice of Issuance of DD 99-12 Under 10CFR2.206 Re Petitions Requesting NRC Immediately Suspend Util Licenses to Operate Units Until Reasonable Assurances That Adequate Protective Measures Will Be Taken ML20212A9101999-09-10010 September 1999 Environ Assessment & Finding of No Significant Impact. Proposed Action Would Exempt Licensee from Requirements of 10CFR50 ML20210C0951999-07-21021 July 1999 Notice of Public Meeting on 990825 in Waterford,Connecticut to Provide Opportunity for Members of Public to Raise Issues & Concerns Re Millstone,Unit 1 Post-Shutdown Decommissioning Activities Rept ML20196J1501999-06-29029 June 1999 Notice of Receipt & Availability for Comment of post-shutdown Decommissioning Activities Rept for Millstone Nuclear Power Station,Unit 1.Comments Should Be Submitted within 30 Days of Notice Date ML20212J0821999-06-15015 June 1999 Notice of Withdrawal of Application for Amend to License DPR-65.Proposed Amends Would Have Revised Facility TSs to Allow Outage Time Extensions for EDGs & Low Safety Injection Sys ML20206U8961999-05-14014 May 1999 Notice of Receipt of Petition for Director'S Decision Under 10CFR2.206.Notice Hereby Given That Petition Dtd 990414, Takes Action with Regard to Millstone Nuclear Generating Station,Units 2 & 3 ML20206G5371999-04-26026 April 1999 Notice of Partial Withdrawal of Application for Amend to FOL DPR-65 Submitted on 980717.Withdrawn Portion of Proposed Amend Would Have Revised Facility TS SR 4.8.1.1.2.C by Deleting Words During Shutdown from First Sentence ML20154N5581998-09-16016 September 1998 Notice of Withdrawal of Amend Request for License DPR-65. Proposed Amend Would Have Revised Requirements for Control Room Air Conditioning System & Support Bases ML20237D5191998-08-20020 August 1998 Notice of Withdrawal of Application for Amend to License DPR-21.Proposed Amend Would Have Revised TSs to Add Limiting Conditions for Operations & Surveillance Requirements for Safety/Relief Valve Electrical Lift Design Mod ML20236V4151998-07-30030 July 1998 Notice of Withdrawal of 951121 Application for FOL NPF-49. Proposed Change Would Have Modified Facility TSs Pertaining to Section 1.33 & Bases Sections 3/4.3.3.9,3/4.3.3.10 & 3/4.11.2.1 ML20217L8921998-04-27027 April 1998 Notice of Withdrawal of Application for Amend to License NPF-49.Proposed Amend Would Have Revised TS 3/4.4.3 to Replace Pressurizer Max Water Inventory Requirement W/Pressurizer Max Indicated Level Requirement ML20217D2791998-04-20020 April 1998 Notice of Consideration of Issuance of Order Re Restructuring of Central Maine Power Co.Nrc Considering Issuance of Order Approving Application Re Proposed Corporate Restructuring ML20203E3421998-02-11011 February 1998 Notice of Issuance of Director'S Decision,Per 10CFR2.206 Wrt 970303 Petition Filed by AA Cizek Re Millstone & Haddam Neck Plants.Petitioner Requests Listed ML20198J2751997-12-16016 December 1997 Notice of Withdrawal of Application for Amend to License DPR-65.Amend Would Have Revised Accuracy Requirements of Meteorological Instrumentation & Supporting Bases ML20202E8001997-11-14014 November 1997 Notice of Withdrawal of Application for Amend to FOL NPF-49. Proposed Amend Would Have Allowed Crediting of Soluble Boron for Maintaining k-effective at Less than or Equal to .95 within Sf Pool Rack Matrix Following Seismic Event ML20198R2091997-10-23023 October 1997 Notice of Withdrawal of 970428 Application for Amend to License NPF-49 Re TS Surveillances 4.1.2.3.1,4.1.2.4.1, 4.5.2.f & 4.5.2.h ML20198R2171997-10-23023 October 1997 Notice of Withdrawal of 970530 Application for Amend to License NPF-49 Re TS Surveillances 4.5.2.f & 4.6.2.2.b ML20212A2621997-10-15015 October 1997 Notice of Withdrawal of Application for Amend to License NPF-49.Amend Would Have Modified List of Valves That Can Be Opened in Modes 1-4 ML20217B9091997-09-12012 September 1997 Notice of Issuance of Partial Director'S Decision Under 10CFR2.206 W/Regard to Petitons & 961223 ML20140F3351997-04-29029 April 1997 Notice of Issuance of Director'S Decision Under 10CFR2.206. Director of NRR Taken Action Wrt 941028 Petition Re Plant, Units 1,2 & 3 ML20137Q8861997-04-0808 April 1997 Notice of Receipt of 970303 Petition Submitted by a Cizek, Per 10CFR2.206 Requesting That Licenses of Three Millstone Nuclear Reactors & Haddam Neck Nuclear Reactor Be Modified by Placing Certain Conditions on OLs ML20147E7661997-03-17017 March 1997 Notice of Withdrawal of Applications for Amend to License DPR-21 ML20147E7531997-03-17017 March 1997 Notice of Withdrawal of Application for Amend to Facility OL DPR-65,to Clarify Design Basis for EDG Fuel Oil Supply ML20134P0931997-02-19019 February 1997 Notice of Withdrawal of Application for Amend to Facility Operating License.Nrc Granted Request of Utility to Withdrawal 951024 Application for Proposed Amend to Facility Operating License DPR-65,Millstone Nuclear Power Unit 2 ML20134B4251997-01-23023 January 1997 Notice of Receipt of Petition for Director'S Decision Under 10CFR2.206.Petition Requesting Certain Actions Associated W/Haddam Neck Plant Operated by Nu ML20138H6551996-12-26026 December 1996 Notice of Issuance of Partial Director'S Decision Under 10CFR2.206 Re Mentioned Plant Unit ML20134H6351996-11-0707 November 1996 Notice of Withdrawal of Application for Amends to Licenses DPR-61,DPR-21,DPR-65,NPF-49 & NPF-86 ML20129H5221996-10-31031 October 1996 Notice of Issuance of Director'S Decision 96-16 Under 10CFR2.206 Re Aj Ross 950102 Petition ML20128P0371996-10-10010 October 1996 Notice of Consideration of Issuance of Amend to License DPR-21 & Proposed NSHC Determination & Opportunity for Hearing.Amend Would Modify Applicability Requirements for Certain Radiation Monitors ML20059C4101993-12-28028 December 1993 Notice of Withdrawal of Application for Amend to License Re Degraded Grid Voltage at Plant ML20058C0341993-11-23023 November 1993 Notice of Receipt of Co Reynolds 930822 Petition for Director'S Decision Under 10CFR2.206 ML20057B3571993-09-15015 September 1993 Notice of Withdrawal of 930427 Application for Proposed Amend to License NPF-49,allowing one-time Extension of Containment Integrated Leak Rate Test for Plant ML20058P7341993-09-10010 September 1993 Notice of Receipt of Petition for Director'S Decision Under 10CFR2.206 Re Request That Immediate Investigation & Accelerated Enforcement Action Against Util for Willful Violation of Employee Protection Be Expedited ML20056G5981993-09-0101 September 1993 Fr Notice Re Aj Ross 930807 Petition,Requesting That EDO Take Escalated Enforcement Action W/Regard to Alleged Violations at Millstone Nuclear Power Plant,Unit 1,per 10CFR2.206 ML20056H4511993-08-23023 August 1993 Notice of Receipt of 930802 Petition for Directors Decision Requesting That EDO Take EA for Violations of 10CFR50.7 ML20127J3941993-01-15015 January 1993 Notice of Consideration of Issuance of Amend to License DPR-21 & Proposed NSHC Determination & Opportunity for Hearing.Proposed Amend Would Allow for Temporarily Bypassing MSL RM Trip Function While Placing Demineralizer Into Svc ML20244C1881989-06-0707 June 1989 Notice of Issuance of Environ Assessment & Finding of No Significant Impact Re Authorization to Store 3,229 Spent Fuel Assemblies in Spent Fuel Pool ML20247C1871989-05-15015 May 1989 Notice of Denial of Amend to License DPR-21 to Revise Tech Specs to Allow Single Loop Operation at Reduced Power ML20245D9971989-04-10010 April 1989 Corrected Notice of Denial of 870601 Application for Amend to License DPR-21 ML20247E6261989-03-27027 March 1989 Notice of Consideration of Issuance of Amend to License DPR-21 & Proposed NSHC Determination & Opportunity for Hearing.Amend Will Change Tech Spec 3.5.F.7(e) to Clarify ECCS Availability & Power Requirements ML20151X0791988-08-11011 August 1988 Notice of Consideration of Issuance of Amend to License DPR-21 & Opportunity for Hearing Re 880624 Application.Amend Revises Tech Spec Section 5.5 to Reflect Max Number of Spent Fuel Assemblies Authorized in Spent Fuel Pool ML20151L9871988-07-27027 July 1988 Notice of Issuance of Environ Assessment & Finding of No Significant Impact Re Proposed Amend to License DPR-21. Amend Would Extend License Expiration Date ML20151A1131988-03-28028 March 1988 Notice of Consideration of Issuance of Amend to License DPR-21 & Opportunity for Hearing on 870817 Request Re Operational Flexibility by Allowing Single Loop Operation at Reduced Power in Event Maint of Recirculation Pump ML20148K7181988-03-24024 March 1988 Notice of Consideration of Issuance of Amend to License DPR-21 & Opportunity for Hearing on Util Request to Delete Ref to Electrical Power & Change Scram Bypass Setpoints to 50% of Rated Thermal Power & Flux Scram Trip Setting ML20234D9991987-12-28028 December 1987 Notice of Consideration of Issuance of Amend to License DPR-65 & Opportunity for Hearing.Amend Deletes Footnote to Tech Spec 3.2.20, Spent Fuel Pool, Removing Limitation Restricting Storage of Consolidated Spent Fuel Boxes to 5 ML20234C3691987-06-30030 June 1987 Notice of Consideration of Issuance of Amend to License DPR-21 & Proposed NSHC Determination & Opportunity for Hearing.Amend Changes Tech Specs to Reflect Reload 11/Cycle 12 Per 870521 Application for Amend,As Modified on 870630 ML20234C3811987-06-30030 June 1987 Notice of Consideration of Issuance of Amend to License DPR-21 & Proposed NSHC Determination & Opportunity for Hearing.Amend Revises Tech Specs 3.4,4.4 & Associated Bases to Comply W/Atws Rule Per 870522 Application for Amend ML20215N5761986-10-31031 October 1986 Notice of Issuance of Facility License DPR-21,authorizing Operation at steady-state Reactor Core Power Levels Not in Excess of 2,011 Mwt & Superseding Provisional OL in Entirety ML20210C6731986-09-16016 September 1986 Notice of Withdrawal of 830902 Application for Amend to License DPR-65,revising Tech Specs Re Steam Generator Tube Insp ML20137B4321985-12-16016 December 1985 Notice of Environ Assessment & Finding of No Significant Impact Re Issuance of Amend to License DPR-65,changing Tech Specs to Increase Storage Capacity of Spent Fuel Pool 1999-09-28
[Table view] Category:TEXT-CODE OF FEDERAL REGULATIONS
MONTHYEARML20216H0321999-09-28028 September 1999 Notice of Issuance of DD 99-12 Under 10CFR2.206 Re Petitions Requesting NRC Immediately Suspend Util Licenses to Operate Units Until Reasonable Assurances That Adequate Protective Measures Will Be Taken ML20212A9101999-09-10010 September 1999 Environ Assessment & Finding of No Significant Impact. Proposed Action Would Exempt Licensee from Requirements of 10CFR50 ML20210C0951999-07-21021 July 1999 Notice of Public Meeting on 990825 in Waterford,Connecticut to Provide Opportunity for Members of Public to Raise Issues & Concerns Re Millstone,Unit 1 Post-Shutdown Decommissioning Activities Rept ML20196J1501999-06-29029 June 1999 Notice of Receipt & Availability for Comment of post-shutdown Decommissioning Activities Rept for Millstone Nuclear Power Station,Unit 1.Comments Should Be Submitted within 30 Days of Notice Date ML20212J0821999-06-15015 June 1999 Notice of Withdrawal of Application for Amend to License DPR-65.Proposed Amends Would Have Revised Facility TSs to Allow Outage Time Extensions for EDGs & Low Safety Injection Sys ML20206U8961999-05-14014 May 1999 Notice of Receipt of Petition for Director'S Decision Under 10CFR2.206.Notice Hereby Given That Petition Dtd 990414, Takes Action with Regard to Millstone Nuclear Generating Station,Units 2 & 3 ML20206G5371999-04-26026 April 1999 Notice of Partial Withdrawal of Application for Amend to FOL DPR-65 Submitted on 980717.Withdrawn Portion of Proposed Amend Would Have Revised Facility TS SR 4.8.1.1.2.C by Deleting Words During Shutdown from First Sentence ML20154N5581998-09-16016 September 1998 Notice of Withdrawal of Amend Request for License DPR-65. Proposed Amend Would Have Revised Requirements for Control Room Air Conditioning System & Support Bases ML20237D5191998-08-20020 August 1998 Notice of Withdrawal of Application for Amend to License DPR-21.Proposed Amend Would Have Revised TSs to Add Limiting Conditions for Operations & Surveillance Requirements for Safety/Relief Valve Electrical Lift Design Mod ML20236V4151998-07-30030 July 1998 Notice of Withdrawal of 951121 Application for FOL NPF-49. Proposed Change Would Have Modified Facility TSs Pertaining to Section 1.33 & Bases Sections 3/4.3.3.9,3/4.3.3.10 & 3/4.11.2.1 ML20217L8921998-04-27027 April 1998 Notice of Withdrawal of Application for Amend to License NPF-49.Proposed Amend Would Have Revised TS 3/4.4.3 to Replace Pressurizer Max Water Inventory Requirement W/Pressurizer Max Indicated Level Requirement ML20217D2791998-04-20020 April 1998 Notice of Consideration of Issuance of Order Re Restructuring of Central Maine Power Co.Nrc Considering Issuance of Order Approving Application Re Proposed Corporate Restructuring ML20203E3421998-02-11011 February 1998 Notice of Issuance of Director'S Decision,Per 10CFR2.206 Wrt 970303 Petition Filed by AA Cizek Re Millstone & Haddam Neck Plants.Petitioner Requests Listed ML20198J2751997-12-16016 December 1997 Notice of Withdrawal of Application for Amend to License DPR-65.Amend Would Have Revised Accuracy Requirements of Meteorological Instrumentation & Supporting Bases ML20202E8001997-11-14014 November 1997 Notice of Withdrawal of Application for Amend to FOL NPF-49. Proposed Amend Would Have Allowed Crediting of Soluble Boron for Maintaining k-effective at Less than or Equal to .95 within Sf Pool Rack Matrix Following Seismic Event ML20198R2091997-10-23023 October 1997 Notice of Withdrawal of 970428 Application for Amend to License NPF-49 Re TS Surveillances 4.1.2.3.1,4.1.2.4.1, 4.5.2.f & 4.5.2.h ML20198R2171997-10-23023 October 1997 Notice of Withdrawal of 970530 Application for Amend to License NPF-49 Re TS Surveillances 4.5.2.f & 4.6.2.2.b ML20212A2621997-10-15015 October 1997 Notice of Withdrawal of Application for Amend to License NPF-49.Amend Would Have Modified List of Valves That Can Be Opened in Modes 1-4 ML20217B9091997-09-12012 September 1997 Notice of Issuance of Partial Director'S Decision Under 10CFR2.206 W/Regard to Petitons & 961223 ML20140F3351997-04-29029 April 1997 Notice of Issuance of Director'S Decision Under 10CFR2.206. Director of NRR Taken Action Wrt 941028 Petition Re Plant, Units 1,2 & 3 ML20137Q8861997-04-0808 April 1997 Notice of Receipt of 970303 Petition Submitted by a Cizek, Per 10CFR2.206 Requesting That Licenses of Three Millstone Nuclear Reactors & Haddam Neck Nuclear Reactor Be Modified by Placing Certain Conditions on OLs ML20147E7661997-03-17017 March 1997 Notice of Withdrawal of Applications for Amend to License DPR-21 ML20147E7531997-03-17017 March 1997 Notice of Withdrawal of Application for Amend to Facility OL DPR-65,to Clarify Design Basis for EDG Fuel Oil Supply ML20134P0931997-02-19019 February 1997 Notice of Withdrawal of Application for Amend to Facility Operating License.Nrc Granted Request of Utility to Withdrawal 951024 Application for Proposed Amend to Facility Operating License DPR-65,Millstone Nuclear Power Unit 2 ML20134B4251997-01-23023 January 1997 Notice of Receipt of Petition for Director'S Decision Under 10CFR2.206.Petition Requesting Certain Actions Associated W/Haddam Neck Plant Operated by Nu ML20138H6551996-12-26026 December 1996 Notice of Issuance of Partial Director'S Decision Under 10CFR2.206 Re Mentioned Plant Unit ML20134H6351996-11-0707 November 1996 Notice of Withdrawal of Application for Amends to Licenses DPR-61,DPR-21,DPR-65,NPF-49 & NPF-86 ML20129H5221996-10-31031 October 1996 Notice of Issuance of Director'S Decision 96-16 Under 10CFR2.206 Re Aj Ross 950102 Petition ML20128P0371996-10-10010 October 1996 Notice of Consideration of Issuance of Amend to License DPR-21 & Proposed NSHC Determination & Opportunity for Hearing.Amend Would Modify Applicability Requirements for Certain Radiation Monitors ML20059C4101993-12-28028 December 1993 Notice of Withdrawal of Application for Amend to License Re Degraded Grid Voltage at Plant ML20058C0341993-11-23023 November 1993 Notice of Receipt of Co Reynolds 930822 Petition for Director'S Decision Under 10CFR2.206 ML20057B3571993-09-15015 September 1993 Notice of Withdrawal of 930427 Application for Proposed Amend to License NPF-49,allowing one-time Extension of Containment Integrated Leak Rate Test for Plant ML20058P7341993-09-10010 September 1993 Notice of Receipt of Petition for Director'S Decision Under 10CFR2.206 Re Request That Immediate Investigation & Accelerated Enforcement Action Against Util for Willful Violation of Employee Protection Be Expedited ML20056G5981993-09-0101 September 1993 Fr Notice Re Aj Ross 930807 Petition,Requesting That EDO Take Escalated Enforcement Action W/Regard to Alleged Violations at Millstone Nuclear Power Plant,Unit 1,per 10CFR2.206 ML20056H4511993-08-23023 August 1993 Notice of Receipt of 930802 Petition for Directors Decision Requesting That EDO Take EA for Violations of 10CFR50.7 ML20127J3941993-01-15015 January 1993 Notice of Consideration of Issuance of Amend to License DPR-21 & Proposed NSHC Determination & Opportunity for Hearing.Proposed Amend Would Allow for Temporarily Bypassing MSL RM Trip Function While Placing Demineralizer Into Svc ML20244C1881989-06-0707 June 1989 Notice of Issuance of Environ Assessment & Finding of No Significant Impact Re Authorization to Store 3,229 Spent Fuel Assemblies in Spent Fuel Pool ML20247C1871989-05-15015 May 1989 Notice of Denial of Amend to License DPR-21 to Revise Tech Specs to Allow Single Loop Operation at Reduced Power ML20245D9971989-04-10010 April 1989 Corrected Notice of Denial of 870601 Application for Amend to License DPR-21 ML20247E6261989-03-27027 March 1989 Notice of Consideration of Issuance of Amend to License DPR-21 & Proposed NSHC Determination & Opportunity for Hearing.Amend Will Change Tech Spec 3.5.F.7(e) to Clarify ECCS Availability & Power Requirements ML20151X0791988-08-11011 August 1988 Notice of Consideration of Issuance of Amend to License DPR-21 & Opportunity for Hearing Re 880624 Application.Amend Revises Tech Spec Section 5.5 to Reflect Max Number of Spent Fuel Assemblies Authorized in Spent Fuel Pool ML20151L9871988-07-27027 July 1988 Notice of Issuance of Environ Assessment & Finding of No Significant Impact Re Proposed Amend to License DPR-21. Amend Would Extend License Expiration Date ML20151A1131988-03-28028 March 1988 Notice of Consideration of Issuance of Amend to License DPR-21 & Opportunity for Hearing on 870817 Request Re Operational Flexibility by Allowing Single Loop Operation at Reduced Power in Event Maint of Recirculation Pump ML20148K7181988-03-24024 March 1988 Notice of Consideration of Issuance of Amend to License DPR-21 & Opportunity for Hearing on Util Request to Delete Ref to Electrical Power & Change Scram Bypass Setpoints to 50% of Rated Thermal Power & Flux Scram Trip Setting ML20234D9991987-12-28028 December 1987 Notice of Consideration of Issuance of Amend to License DPR-65 & Opportunity for Hearing.Amend Deletes Footnote to Tech Spec 3.2.20, Spent Fuel Pool, Removing Limitation Restricting Storage of Consolidated Spent Fuel Boxes to 5 ML20234C3691987-06-30030 June 1987 Notice of Consideration of Issuance of Amend to License DPR-21 & Proposed NSHC Determination & Opportunity for Hearing.Amend Changes Tech Specs to Reflect Reload 11/Cycle 12 Per 870521 Application for Amend,As Modified on 870630 ML20234C3811987-06-30030 June 1987 Notice of Consideration of Issuance of Amend to License DPR-21 & Proposed NSHC Determination & Opportunity for Hearing.Amend Revises Tech Specs 3.4,4.4 & Associated Bases to Comply W/Atws Rule Per 870522 Application for Amend ML20215N5761986-10-31031 October 1986 Notice of Issuance of Facility License DPR-21,authorizing Operation at steady-state Reactor Core Power Levels Not in Excess of 2,011 Mwt & Superseding Provisional OL in Entirety ML20210C6731986-09-16016 September 1986 Notice of Withdrawal of 830902 Application for Amend to License DPR-65,revising Tech Specs Re Steam Generator Tube Insp ML20137B4321985-12-16016 December 1985 Notice of Environ Assessment & Finding of No Significant Impact Re Issuance of Amend to License DPR-65,changing Tech Specs to Increase Storage Capacity of Spent Fuel Pool 1999-09-28
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHEAST NUCLEAR ENERGY COMPANY ,
DOCKET NO. 50-245 NOTICE OF CONSIDfl@lLQ!(_Of_lji10ANCE OF AMENDMENT TO fEl(ITY OPERATING LICEHSE. PROPOSED t(LSIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPOPTUNITY FOR HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. DPR-21 issued to Northeast Nuclear Energy Company (the licensee /NNECO) for operation of Millstone Nuclear Power Station, Unit 1, located in New London County, Connecticut.
The proposed amendment to the Technical Specifications would allow for
- temporarily bypassing the Main Steam Line Radiation Monitor (MSLRM) trip function in order to allow condensate demineralizers to be returned to service, thereby eliminating the possibility of an inadvertent initiation of the MSLRM trip function. A time limit of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per occurrence has been set to minimize the overall time that the MSLRM trip function may be bypassed.
The licensee requested expeditious review of this request because continued plant operation -dictates that the current typical-ultrasonic-resin cleaning cycle of two condensate demineralizers per week be resumed promptly.
A clean demineralizer has not beer, rotated into' service since December 29, 1992, because the licensee believes the evolution may result in a spurious and unnecessary main steam line high radiation monitor trip setpoint being exceeded.-
9301250125 930115 PDR ADOCK 0500 P.
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e Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
In accordance with 10 CFR 50.92, NNEC0 has reviewed the attached proposed change and has concluded that the change does not involve an SHC [Significant Hazards Consideration). The basis for this conclusion is that the three criteria of 10 CFR 50.92(c) are not compromised. The proposed change does not involve an SHC because the change would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously analyzed.
The trip function of the MSLRMs is a postaccident function and hence changes to this function can not increase the probability of occurrence of previously evaluated ar.cidents. The Millstone Unit No. I design casis accident analysis does not take credit for this
.;
- unction and hence there are no effects on the consequences of previously evaluated accidents. in the control rod drop accident, all activity from failed fuel rods is assumed to be immediately transported to the turbine / condenser and is available for leakage from the condenser.
Additionally, the main steam activity detected by the MSLRMs will be removed by the steam jet air ejectors, be monitored by the redundant off-gas monitors and be directed to the off-gas treatment system.
The sensitivity of the off-gas monitors is much greater than the MSLRMs. The noble gas activity required to cause the MSLRMs m
- - . . ~ _---- - - -. - - - . - - - - - .._-
3 to exceed their alarm setpoint will be well above the trip setpoint for the off-gas monitors. The off-gas monitors will automatically initiate closure of the off-gas system discharge valve after a 15 minute time delay and hence, trap all activity within the off-gas system. No significant activity is expected to be released to the public, since it would be contained within the off-gas system, j Furthermore, not closing the MSIVs will reduce the potential dose, as the steam jet air ejector will remain available to direct activity to the off-gas system. If the HSIVs were closed, the activity would remain in the condenser. More activity would be expected to leak out of the condenser than the off-gas system.
- 2. Create the possibility of a new or different kind of accident from any previously evaluated.
The proposed changes allow the HSLRM trip function to be by)assed for a s1 ort period of time (conservatively selected as two lours per occurrence) while condensate demineralizers are placed into service.
The direct impact on the plant is that this particular trip function (i.e., MSIV closure and reactor scram) will not actuate while it is bypassed. Since the design basis accident analysis does not credit this trip function to demonstrate acceptable radiological consequences, the proposed changes have effectively been evaluated previously and are enveloped by the existing analysis. As stated above, in the control rod drop accident, all activity from failed fuel rods is assumed to be immediately transported to the turbine / condenser and is available for leakage from the condenser.
- 3. Involve a significant reduction in a margin of safety.
The proposed changes do not impact the physical protective
-boundaries, nor do they affect the calculated off-site dose consequences, Therefore, there is no impact on the margin of safety. Furthermore, the changes will improve the overall reliability of the plant when compared to the as-found system, since the proposed changes will reduce the chances of an unnecessary plant I
transient occurring as a result of an inadvertent MSIV closure at i 100 percent power.
The NRC staff has reviewed the licensee's analysis and, based on this l
review, it appears that the three standards of 10 CFR 50.92(c) ai r satisfied.
Therefore, the NRC staff proposes to determine that the-amendment request involves no significant hazards consideration.
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4-The Commission is seeking public comments on this proposed determination. Any connents received within 15 days after the date of publication of this notice will be considered in making any final determination.
Written comments may be submitted by mail to the Rules and Directives Review Branch, Division of Freedom of Information and Publications Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written comments may also be delivered to Room P-223, Phillips Building, 7920 Norfolk Avenue, Bethesda, Maryland, from 7:20 a.m. to 4:15 p.m. Copies of written comments received may be examined at the NRC Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555. The filing of requests for hearing and petitions for leave to intervene is discussed below.
By February 24 , 1993, the licensee may file a request for a hearing j with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's " Rules of Fractice for Domestic Licensing Proceedings" in 10 CFR Part 2. Interested persons should consult a current copy of 10 CFR 1
2.714 which is available at the Commission's Public Document Roem, the Gelman Building, 2120 L Street, NW., Washington, DC 20555, and at the local public
1 5-J document room located at the Learning Resources Center, Thames Valley State Technical College, 574 New London Turnpike, Norwich, Connecticut 06360.
If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in-the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors: (1) the nature
- of the petitioner's right under the Act to be made party to the proceeding; ,
(2) the nature and extent of the petitioner's property, financf *l, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest. The petition should also identify the specific aspect (s) of the subject matter of the
- proceeding as to which petitioner wishes to intervene. Any person who has i flied a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to fifteen 1
- (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than 15 days prior to the first prehearing conference ,
scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are '
sought to be litigated in the matter. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted, in addition, the petitioner shall provide a brief explanation of the bases-of the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or.
expert opinion. Petitioner must provide sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact.
Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will not be permitted to participate as a party. .
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.. (
If the amendment is issued before the expiration of_30 days, the i Commission will make a final determination on the issue of no significant c
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i hazards consideration. If a hearing is requested, the final determination will serve to decide when the hearing is held.
If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place af ter issuance of the amendment.
If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before -
the issuance of any amendment.
Normally, the Commission will not issue the amendment until the expiration of the 15-day notice period. However, should circumstances change during the notice period, such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 15-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider all public and State comments received. Should the Commission take this action, it will publish in the FEDERAL REGISTER a notice of issuance. The Commission expects that the need to take this action will occur very infrequently.
A request for a hearing or a petition for leave to intervene must be flied with the _ Secretary of the Commission, 'd.S. fiadaar Regulatory Commission, Washington, DC 20555, Attention: Docketing and Services Branch, ,
or may be delivered to the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555, by the above date. Where
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4
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1 petitions are filed during the last 10 days of the notice period, it is requested that the petitioner promptly so inform the Commission 'oy a toll-free !
telephone call to Western Union at 1-(800) 248-5100 (in Missouri 1-(800) 342-6700). The Western Union operator should be given Datagram Identification Number N1023 and the following message addressed to John F. Stolzt petitioner's name and telephone number; date petition was mailed; plant name; and publication date and page number of this FEDERAL REGISTER notice. A copy of the petition should also be sent to the Office of the General Counsel, U.S.
Nuclear Regulatory Commission Washington, DC 20555, and to Gerald Garfield, Esquire, Day, Berry & Howard, Counselors at Law, City Place, Hartford, Connecticut 06103-3499, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer or the presiding Atomic Safety and Licensing Board that the petition and/or request should be granted based upon a balancing of the-factors specified in 10 CFR 2,714(a)(1)(1)-(v) and 2.714(d).
for further details with respect to this action, see the application for amendment dated January 12, 1993, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555, and at the Local Public Document Room located at t
I f.
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the Learning Resources Center, Thames Valley State Technical College 574 New London Turnpike, Norwich, :onnecticut 06360. !
Dated at Rockville, Maryland, this 15th day of January 1993.
FOR THE NUCLEAR REGULATORY COMMISSION i
i
- # ames J W. ndersen, Acting Project Manager Project Directorate 1-4 Olvision of Reactor Projects - I/II Office of Nuclear Reactor Regulation d
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