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Category:FEDERAL REGISTER NOTICES
MONTHYEARDD-99-01, Notice of Issuance of Director'S Decision DD-99-01,denying CAN Request to Revoke or Suspend HNP Operating License & to Hold Informal Public Hearing in Vicinity of Site & Granting Request to Consider Application of Requirements of 10CFR721999-01-12012 January 1999 Notice of Issuance of Director'S Decision DD-99-01,denying CAN Request to Revoke or Suspend HNP Operating License & to Hold Informal Public Hearing in Vicinity of Site & Granting Request to Consider Application of Requirements of 10CFR72 ML20154J9761998-10-0707 October 1998 Notice Hereby Given That by Petition Dtd 980911,Citizens Awareness Network (Petitioner) Requested That NRC Take Action with Regard to Haddam Neck Plant to Immediately Revoke or Suspend Util Operating License ML20195J4881998-09-16016 September 1998 Notice of EA & Fonsi Re Licensee Request for Reduction in Amount of Insurance Required for Facility ML20217E8981998-04-22022 April 1998 Notice of Receipt of Petition for Director'S Decision from Citizens Awareness Network,Inc Which Requests That NRC Immediately Suspend Operating License for Haddam Neck Plant 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 ML20217B9091997-09-12012 September 1997 Notice of Issuance of Partial Director'S Decision Under 10CFR2.206 W/Regard to Petitons & 961223 ML20217B2751997-09-0303 September 1997 Notice of Director'S Decision Re 970311 Petition Filed by R Bassilakis Re Actions Against CYAPC ML20198G9281997-08-27027 August 1997 Notice of Receipt of & Availability for Comment of post-shutdown Decommission Activities Rept 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 ML20137P5241997-04-0303 April 1997 Notice of Receipt of 970311 Petition for Director'S Decision Under 10CFR2.206.Petition Requests Mod of License for Plant That Would Prohibit Decommissioning Activity for 6 Months W/O Any Contamination Events Occurring ML20137H4131997-03-31031 March 1997 Correction to Notice of Withdrawal of 970313 Application for Facility Operating License DPR-61,modifying TSs Pertaining to Manipulator Crane ML20147E9221997-03-17017 March 1997 Notice of Withdrawal of Application for Amend to License DPR-61.License Amend No Longer Required Due to Licensee Certifying Permanent Cessation of Operation & Permanent Offload of Fuel from Reactor Vessel ML20147E8071997-03-13013 March 1997 Notice of Withdrawal of Application for Amend to License DPR-61,Haddam Neck Plant 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 ML20134H6351996-11-0707 November 1996 Notice of Withdrawal of Application for Amends to Licenses DPR-61,DPR-21,DPR-65,NPF-49 & NPF-86 ML20058G5031993-11-23023 November 1993 Notice of Consideration of Issuance of Amend to Facility OL DPR-61 & Opportunity for Hearing ML20056A5691990-08-0606 August 1990 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing.Amend Would Add Exception from Requirements of Tech Spec 4.0.4 to Surveillance Requirements 4.7.1.2.2a,b & C ML20056A7861990-08-0303 August 1990 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing.Amend Rewords Tech Specs Section 3.4.6.2.f to Better Define Which Sections of Piping Needed ML20055G5571990-07-19019 July 1990 Notice of Issuance of Amend 129 to License DPR-61.Amend Will Add Footnote to Tech Spec Section 5.3.1, Fuel Assemblies & Correct Table 3.3-1a, Reactor Trip Sys Instrumentation Response Time ML20055G5461990-07-19019 July 1990 Notice of Issuance of Amend to License DPR-61,removing Tech Spec Table 4.4-5, Reactor Vessel Matl Surveillance Program- Withdrawal Schedule ML20055F7271990-07-12012 July 1990 Notice of Consideration of Issuance of Amend to License DPR-61 & Opportunity for Hearing.Amend Would Establish Limit of 160 Failed Fuel Rods During Operation ML20247A1661989-08-31031 August 1989 Notice of Consideration of Issuance of Amend to License DPR-61 & Opportunity for Hearing Re 881026 Application, Upgrading Current Custom Tech Spec Format to Westinghouse STS Format ML20246P5541989-08-31031 August 1989 Notice of Consideration of Issuance of Amend to License DPR-61 & Opportunity for Hearing.Amend Will Change Tech Specs to Reflect Changes Associated W/Plant Fire Detection/ Suppression Sys Upgrades in Support of New Switchgear Bldg ML20246P5601989-08-29029 August 1989 Notice of Consideration of Issuance of Amend to License DPR-61 & Opportunity for Hearing.Amend Will Change Tech Specs to Reflect Mods to Upgrade Reactor Protection Sys & Nuclear Instrumentation Sys ML20246M5501989-05-0808 May 1989 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing.Amend Allows Four Containment Air Recirculation Fan Motor HXs to Be Cleaned or Replaced While at Power ML20246F8441989-05-0404 May 1989 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing.Amend Changes Tech Specs Re Various Operation Conditions & Survelliance Requirements as Discussed ML20195C7131988-10-24024 October 1988 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing.Amend Revises Tech Specs Re RCS vents,post-accident Sampling & long-term Auxiliary Feedwater Sys ML20196B3831988-01-15015 January 1988 Notice of Consideration of Issuance of Amend to License DPR-61 & Opportunity for Prior Hearing.Amend Would Revise Tech Specs Provisions Re Degraded Grid Voltage Protection Sys (Dgvps) to Be Consistent W/Util Dgvps Procedures ML20237E1151987-11-23023 November 1987 Notice of Issuance of Environ Assessment & Finding of No Significant Impact Re Amend to License DPR-61,changing Expiration Date from 040526 to 070629 ML20235S3511987-10-0505 October 1987 Notice of Environ Assessment & Finding of No Significant Impact Re Util 870710 Request for Exemption from Certain Requirements of 10CFR50,App J ML20141A9181986-03-27027 March 1986 Notice of Environ Assessment & Finding of No Significant Impact Re Issuance of Amend to License DPR-61.Amend Revises Tech Specs to Permit Repair of Degraded Steam Generator Tubes by Installing Metal Sleeves in Tubes ML20126M5111985-06-14014 June 1985 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing Re 850611 Application to Update Pressure/Temp Limit Curves ML20054K9961982-06-25025 June 1982 Notice of Issuance & Availability of Amends 85,50 & 78 to Licenses DPR-21,DPR-61 & DPR-65,respectively ML20062C2601978-10-24024 October 1978 Notice of Issuance of Amend 29 to Facil Oper Lic DPR-61, Deleting Lic Condition C(3) of Amend 26 & Rev Tech Spec Re Main Steam Line Break Reanalysis ML20062B0761978-07-20020 July 1978 Notice of Issuance of Amend 27 to License DPR-61.Amend Incorporates New Requirements Re Operability of Water Level Alarms in Primary Auxiliary Bldg & Screenwell Bldg 1999-01-12
[Table view] Category:TEXT-CODE OF FEDERAL REGULATIONS
MONTHYEARDD-99-01, Notice of Issuance of Director'S Decision DD-99-01,denying CAN Request to Revoke or Suspend HNP Operating License & to Hold Informal Public Hearing in Vicinity of Site & Granting Request to Consider Application of Requirements of 10CFR721999-01-12012 January 1999 Notice of Issuance of Director'S Decision DD-99-01,denying CAN Request to Revoke or Suspend HNP Operating License & to Hold Informal Public Hearing in Vicinity of Site & Granting Request to Consider Application of Requirements of 10CFR72 ML20154J9761998-10-0707 October 1998 Notice Hereby Given That by Petition Dtd 980911,Citizens Awareness Network (Petitioner) Requested That NRC Take Action with Regard to Haddam Neck Plant to Immediately Revoke or Suspend Util Operating License ML20195J4881998-09-16016 September 1998 Notice of EA & Fonsi Re Licensee Request for Reduction in Amount of Insurance Required for Facility ML20217E8981998-04-22022 April 1998 Notice of Receipt of Petition for Director'S Decision from Citizens Awareness Network,Inc Which Requests That NRC Immediately Suspend Operating License for Haddam Neck Plant 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 ML20217B9091997-09-12012 September 1997 Notice of Issuance of Partial Director'S Decision Under 10CFR2.206 W/Regard to Petitons & 961223 ML20217B2751997-09-0303 September 1997 Notice of Director'S Decision Re 970311 Petition Filed by R Bassilakis Re Actions Against CYAPC ML20198G9281997-08-27027 August 1997 Notice of Receipt of & Availability for Comment of post-shutdown Decommission Activities Rept 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 ML20137P5241997-04-0303 April 1997 Notice of Receipt of 970311 Petition for Director'S Decision Under 10CFR2.206.Petition Requests Mod of License for Plant That Would Prohibit Decommissioning Activity for 6 Months W/O Any Contamination Events Occurring ML20137H4131997-03-31031 March 1997 Correction to Notice of Withdrawal of 970313 Application for Facility Operating License DPR-61,modifying TSs Pertaining to Manipulator Crane ML20147E9221997-03-17017 March 1997 Notice of Withdrawal of Application for Amend to License DPR-61.License Amend No Longer Required Due to Licensee Certifying Permanent Cessation of Operation & Permanent Offload of Fuel from Reactor Vessel ML20147E8071997-03-13013 March 1997 Notice of Withdrawal of Application for Amend to License DPR-61,Haddam Neck Plant 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 ML20134H6351996-11-0707 November 1996 Notice of Withdrawal of Application for Amends to Licenses DPR-61,DPR-21,DPR-65,NPF-49 & NPF-86 ML20058G5031993-11-23023 November 1993 Notice of Consideration of Issuance of Amend to Facility OL DPR-61 & Opportunity for Hearing ML20056A5691990-08-0606 August 1990 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing.Amend Would Add Exception from Requirements of Tech Spec 4.0.4 to Surveillance Requirements 4.7.1.2.2a,b & C ML20056A7861990-08-0303 August 1990 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing.Amend Rewords Tech Specs Section 3.4.6.2.f to Better Define Which Sections of Piping Needed ML20055G5571990-07-19019 July 1990 Notice of Issuance of Amend 129 to License DPR-61.Amend Will Add Footnote to Tech Spec Section 5.3.1, Fuel Assemblies & Correct Table 3.3-1a, Reactor Trip Sys Instrumentation Response Time ML20055G5461990-07-19019 July 1990 Notice of Issuance of Amend to License DPR-61,removing Tech Spec Table 4.4-5, Reactor Vessel Matl Surveillance Program- Withdrawal Schedule ML20055F7271990-07-12012 July 1990 Notice of Consideration of Issuance of Amend to License DPR-61 & Opportunity for Hearing.Amend Would Establish Limit of 160 Failed Fuel Rods During Operation ML20247A1661989-08-31031 August 1989 Notice of Consideration of Issuance of Amend to License DPR-61 & Opportunity for Hearing Re 881026 Application, Upgrading Current Custom Tech Spec Format to Westinghouse STS Format ML20246P5541989-08-31031 August 1989 Notice of Consideration of Issuance of Amend to License DPR-61 & Opportunity for Hearing.Amend Will Change Tech Specs to Reflect Changes Associated W/Plant Fire Detection/ Suppression Sys Upgrades in Support of New Switchgear Bldg ML20246P5601989-08-29029 August 1989 Notice of Consideration of Issuance of Amend to License DPR-61 & Opportunity for Hearing.Amend Will Change Tech Specs to Reflect Mods to Upgrade Reactor Protection Sys & Nuclear Instrumentation Sys ML20246M5501989-05-0808 May 1989 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing.Amend Allows Four Containment Air Recirculation Fan Motor HXs to Be Cleaned or Replaced While at Power ML20246F8441989-05-0404 May 1989 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing.Amend Changes Tech Specs Re Various Operation Conditions & Survelliance Requirements as Discussed ML20195C7131988-10-24024 October 1988 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing.Amend Revises Tech Specs Re RCS vents,post-accident Sampling & long-term Auxiliary Feedwater Sys ML20196B3831988-01-15015 January 1988 Notice of Consideration of Issuance of Amend to License DPR-61 & Opportunity for Prior Hearing.Amend Would Revise Tech Specs Provisions Re Degraded Grid Voltage Protection Sys (Dgvps) to Be Consistent W/Util Dgvps Procedures ML20237E1151987-11-23023 November 1987 Notice of Issuance of Environ Assessment & Finding of No Significant Impact Re Amend to License DPR-61,changing Expiration Date from 040526 to 070629 ML20235S3511987-10-0505 October 1987 Notice of Environ Assessment & Finding of No Significant Impact Re Util 870710 Request for Exemption from Certain Requirements of 10CFR50,App J ML20141A9181986-03-27027 March 1986 Notice of Environ Assessment & Finding of No Significant Impact Re Issuance of Amend to License DPR-61.Amend Revises Tech Specs to Permit Repair of Degraded Steam Generator Tubes by Installing Metal Sleeves in Tubes ML20126M5111985-06-14014 June 1985 Notice of Consideration of Issuance of Amend to License DPR-61 & Proposed NSHC Determination & Opportunity for Hearing Re 850611 Application to Update Pressure/Temp Limit Curves ML20054K9961982-06-25025 June 1982 Notice of Issuance & Availability of Amends 85,50 & 78 to Licenses DPR-21,DPR-61 & DPR-65,respectively ML20062C2601978-10-24024 October 1978 Notice of Issuance of Amend 29 to Facil Oper Lic DPR-61, Deleting Lic Condition C(3) of Amend 26 & Rev Tech Spec Re Main Steam Line Break Reanalysis ML20062B0761978-07-20020 July 1978 Notice of Issuance of Amend 27 to License DPR-61.Amend Incorporates New Requirements Re Operability of Water Level Alarms in Primary Auxiliary Bldg & Screenwell Bldg 1999-01-12
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213 N0_TICE OF ENVIRONMENTAL ASSESSMENT AND FINDING 0F NO SIGNIFICANT IMPACT The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of an exemption from the requirements of Appendix J to 10 CFR Part 50 to Connecticut Yankee Atomic Power Company (the licensee) for the Haddam Neck Plant located at the licensee's site in Middlesex County, Connecticut.
ENVIRONMENTAL ASSESSMENT Identification of Proposed Action:
The licensee is requesting an exemption from Paragraph III.A,3 of 10 CFR Part 50 Appendix J, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors." In 1973, Appendix J was issued to establish
. requirements for primary containment leakage testing and inenrporated by reference, ANSI N45.4-1972, " Leakage Rate Testing of Containment Structures for Nuclear Reactors." This Standard requires that containment leakage calculations be performed by using either the point-to-point method or the total time method. The total time method was used the most by the nuclear industry until about 1976.
At this time, licensees who wish to use mass-point must submit an application for exemption from the Appendix J requirement that containment integrated leak rate tests will conform to ANSI N45.4. The exemption proposed g0080454072005 p ADOCK 05000213 PDR
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( 7590-01 by the licensee would be granted until pending changes to Appendix J become effective. The exemption applies only to the method of calculating containment leakage. In the mass-point method, the mass of air in containment is calculated and plotted as a function of time. Leakage is calculated from the slope of the Linear Least Squares.
With the present developments in technology, the mass-point method has gained increasing recognition. In the total time method, a series of leakage rates are calculated on the basis of air mass differences between an initial data point and each individual data point thereafter. If for any reason (such as instrument error, lack of temperature equilibrium, ingassing or outgassing) the initial data point is not accurate, the results of the test will be affected. In the point-to-point method, the leak rates are based on the mass difference between each pair of consecutive points which are then averaged to yield a single leakage rate estimate. Mathematically, this can be shown to be the difference between the air mass at the beginning of the test and the air mass at the end of the test expressed as a percentage of the containment air mass. It follows from the above that the point-to-point method ignores any mass readings during the test and thus the leakage rate is calculated on the basis of the difference in mass between two measurements taken at the beginning and at the end of the test, which are 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> apart.
The licensee's request for exemption and the bases therefore are contained in a letter dated July 10, 1987.
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.( '7590-01 The Need for the Proposed Action: !
The exemption is needed to allow continued use of the mass-point analysis method at the Haddam Neck Plant.
Environmental Impact of'the Proposed Action: The-proposed exemption will have no incremental' environmental impact relative to current practice because the exemption will allow testing to be conducted in the same manner as it is currently performed.
The error in the total time method creates a higher probability of
-unnecessarily failing a containment integrated leakage rate test (note that the. calculational procedure is'. independent of containment tightness) possibly resulting in increased test frequency, critical path outage time, and exposure to test personnel.
The radiological releases will not be greater than previously determined, nor does the proposed exemption otherwise affect radiological plant effluents, and has no other environmental impact. Therefore, the Comission concludes that there are no significant radiological or non-radiological environmental I
impacts associated with the proposed exemption.
Alternatives to the Proposed Action: It has been concluded that there is no .
measurable impact associated with the proposed exemption; any alternatives to the exemption will have either no environmental impact or greater environmental I
impact.
Alternative Use of Resources: This action does not involve the use of resources beyond the scope of resources used during normal plant operation. .
Agencies and Persons Consulted;_ The Commission's staff reviewed the licensee's request that supports the proposed exemption. The staff did not consult other agencies or persons.
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FINDING 0F NO SIGNIFICANT IMPACT:
Based upon the foregoing environmental assessment, the Commission concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the Commission has determined not to prepare an environmental impact statement.for the proposed exemption.
For further details with respect to this action, see the request for exemption submittal dated July 10, 1987 which is available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C. 205S5, and at the local public document room located at the Russell' Library, 123 Broad Street, Middletown, Connecticut 06457.
Dated at Bethesda, Maryland, this 5th day of October,1987.
FOR THE NUCLEAR REGULATORY COMMISSION Y0 WW "
Cecil 0. Thomas, Director Integrated Safety Assessment Project Directorate Division of Reactor Projects III/IV/V and Special Projects l
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