|
---|
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
[Table view] |
Text
_ _ _ - _ _ _ _ _ _ . _ _ . _ _ _ _ . _ _ _ _ _ - - - _ - _ , . _ _ _ _ _ _ _ , _ _ - . _ _ _ - _ _ _ _ - _ ,
.,l' .
s.
- c. 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS
~
CONSIDERATION DETERMINATION
'AND OPPORTUNITY FOR HEARING The U.S. Nuclear Regulatory Comission (the Comission) is ~considering issuance of an amendment to Facility Operating License No. DPR-61 issued to Connecticut Yankee Atomic Power Company (the licensee) for operation of the Haddam Neck Plant located in Middlesex County, Connecticut.
The proposed amencment provides an extension of the one-time relaxation of the containment integrity specifications issued as License Amendment No.112, to allow the four containment air recirculation (CAR) fan motor heat l
exchangers to be cleaned or replaced while at power.
s Before issuance of the proposed license amenoment, the Comission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations.
The Comission has made a proposed determination that the request for amendment involves no significant hazards consideration. Under the Comission'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 j accident previously evaluated; or (3) involve a significant reduction in a i
margin of safety. ;
i 8905190176 890500 PDR ADOCK 050 g 3 P
_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ - - _ _ - _ _ - _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - - _ _ _ _ _ _ _ - _ _ _ - - - - - - - - - - - - - - - - - - - _ - - - - _ _ - --------------------------------------------N
1 1
(.
,, f
- 1. Involve a significant increase in the probability or consequences of an accident 3reviously evaluated. This Technical Specification change is bounded by t1e evaluation submitted in CYAPCO's letter dated February 10, 1989, and approved by the HRC staff in Arendment No.112. The total time restriction of 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> for having the service water system open envelopes this proposed change as well. CYAPC0 is not requesting an additional 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br />, but proposes to perform the worl. allowed by this license amendment under the original 64-hour restriction approved in Anendnent No.112. Therefore, the 10 CFR'50.92 evaluation described in CYAPCO's February 10, 1989, license amendment request bounds this proposed change as well.
The purpose of the proposed change is to clean / replace the CAR fan motor heat exchangers. In so doing, service water flow through the heat exchanger will increase. This increase in heat removal capacity is necessary to restore the CAR unit performance to that assured in the Updated Final Safety Analysis Report for the design service water temperature. The net effect of the change will be to improve CAR unit cooling system performance, specifically by ensuring proper fan notor cooling.
- 2. Create the possibility of a new or different kind of accident from any previously evaluated. The possiblity for en accioent or malfunction of a different type than any evaluated previously in the Final Safety Analysis Report is not created since the change and/or failure modes associated with the change do not modify the plant response tc the point where it can be considered a eew design basis accident.
The compensatory ceasures, combined with the short duration of containment integrity relaxation, result in an increase in probabilityoffailureofcuntainmentinsolationof7x10~ghewhen averaged over a year. This low probability, coupled with the low probability of accidents resulting in a release of significant radioactivity into the containment, is judged to be negligible and need not be considered for this maintenance evolution. The basis for this determination is that contaiorent isolation failure in the current configuration has some finite probability, and the incremental increase resulting from the proposed change would be insignificant 1y small.
The proposed change does not create a new unanalyzed event based on l compensatory measures which will be in effect. As described above, the proposed change does not increase the probability of an accident to the point where it should be considered within the design basis of the plant.
- 3. Involve a significant reduction in a margin of safety. The proposed change does not impbct the consequences of an accident on the fuel or reactor coolant system protective boundaries. The proposed change will allow the opening of the service water piping inside containment for relatively short periods of time. This piping serves as the containment boundary. The relaxation of containment integrity does not represent a significant reduction in tne margin of safety. As noted above, the i
L____________ _ _ _ _ _
4 compensatory measures which will be implemented provide reasonable assurance that the containment boundary will be maintained and that the allowable off-site dose limit will not be exceeded.
Based on the above discussion, the proposed change will not decrease the margin of safety because of:
- a. The compensatory measures to maintain the containment boundary.
- b. The relatively short duration wben the service water piping inside containment is open.
- c. The unavailability of the CAR fan units is bounded by that
, allowed by both the Technical Specifications and existing administrative controls.
Therefore, based on the above considerations, the Comission has made a proposed determination that the amendment request involves no significant hazards considerations.
' The Ccmission is seeking public coments on this proposed determination.
Any comnents received within 30 days after the date of publication of this notice will be considered in making any final determination. The Comission will not nornelly make a final determination unless it receives a request for a hearing.
Written coments may be submitted by sail to the Regulatory Publications Branch, Division of Freedcm of Information and Publications Services, Office of Administration and Resources Management, U.S. Nuclear Regulatory Comission, Washington, D.C. 20555, and should cite the publication date and page nunber of this FEDERAL REGISTER notice. Written coments may also be deliva. red to Room P-216, Phillips Building, 7920 Norfolk /, venue, Bethesfa, Maryland from 7:30 a.m. to 4:15 p.m. Copies of written coments received may be examined at the NRC Public Document Room, the Gelman Building, 2120 L Street, N.W.,
Washington, D.C. The filing of requests for hearing and petitions for leave to intervene are discussed below.
Ma-i
i .
4-By June 12, 1989 , the licensee may file a request for a hearing IF 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 petition for leave to intervene. Request for a hearing and petitions for leave to intervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. 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 Connission 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 52.714, a petition for leave to intervene shall set forth with particularity the inte.est 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, financial, 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 filed a petition for leave to intervene or who has been admitted as a party
a l
l may amend the petition without requesting leave of the Board up to fifteen (15) days prior to the first prehearing conference scheduled in the pruceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than fifteen (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, and the bases' for each contention set forth with reasonable specificity. Contentions shall be limited to matters
- l within the scope of the aundments under consideration. 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.
Thos,e permitted to intervene becom 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 a hearing is requested, the Comission will make a final determination on the issue of no significant hazards considerations. The final determination will serve to decide when the hearing is held.
If the final determination is that the request for amendment involves no significant hazards considerations, the Comission may issue the amendment and make it effective, notwithstanding the regaest for a hearing. Any hearing held would take place after issuance of the amendment.
1
l If a final determination is that the amendment involves significant hazards considerations, any hearing held would take place before the issuance of cny amendment.
Normally, the Comission.will not issue the amendment until the expiration of the 30-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
.- Comission may issue the license amendment'before the expirhtion of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards considerations. The final determination will consider all public and State comments received. Should the Comission take this action, it will publish a notice of issuance and provide for opportunity for a ^aearing after issuance. The Comission 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
. filed with the Secretary of the Comission, U.S. Nuclear Regulatory Comission, Washington, DC 20555, Attention: Docketing and Service Branch, or may be delivered to the Comission's Public Document Room, the Gelman Building, 2120 L Street, N.W., Washington, DC, by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is requested that the petitioner progtly so inform the Comission by a toll-free telephone call to Western Union at 1-(800) 325 6000 (in Missouri 1-(800) 342-6700). The Western Union operator should be given Datagram Identification Nurrber 3737 and the following message addressed to John F. Stolz: (petitioner's name and telephone number), (date petition was mailed), (plant name), and (publication I
' ,, s -e I
,, 1
)
date and page number of this FEDERAL REGISTEh 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 06103-3494.
Ncntimely 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 Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the petiticner has made a substantial showing of good cause for the granting of a late petition and/or request. That determination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
For further details wich respect to this action, see the application for amendment dated March 31, 1989, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, N.W. , Washington, D.C. and at the Local Pilolic Document Room located at Russell Library,123 Broad Street, Middletown, Connecticut 06457.
Dated at Rockville, Maryland, this 8th day of May, 1989.
FOR THE NUCLEAR REGULATORY COMMISSION W
Alan B. Wang, Proj ect Manager Project Directorate 1-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
_ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - -