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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20206N2621999-05-11011 May 1999 Application for Amend to License DPR-6 to Delete from Defueled Ts,Subsection 1.16,change Definition of Site & Other Associated Editorial Changes ML20217F5191998-03-28028 March 1998 Application for Amend to License DPR-6,per 10CFR50.90 Re Security Plan.Encl Withheld ML20138G1961997-04-30030 April 1997 Application for Amend to License DPR-6,requesting Name Change from Consumers Power Company to Consumers Energy Company, to Reflect Broader Scope of Energy Resources Available Through Company ML20138A9061997-04-22022 April 1997 Application for Amend to License DPR-6,requesting Change to TS to Withdraw Petition to Implement Option B Performance Based Requirements to App J of 10CFR50 ML20134H6281996-11-0707 November 1996 Application for Amend to License DPR-6,adding New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys ML20129C4611996-10-15015 October 1996 Application for Amend to License DPR-3,implementing Option B to Allow Use of Type a Test (Containment) Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining Boundaries) & Type C Test ML20056G3811993-08-24024 August 1993 Application for Amend to License DPR-6,revising 930719 Original Change,Reflects Revision to 10CFR50.36(a)(2) Re Changing Reporting Requirement for Effluent Releases from Semiannual to Annual ML20128D7081993-01-29029 January 1993 Application for Amend to License DPR-6,revising TS to Reflect Administrative Changes in Engineering,Offsite Review & QA Organization ML20059A2091990-08-14014 August 1990 Application for Amend to License DPR-6,reflecting Administrative & Organizational Changes ML20247L0891989-05-25025 May 1989 Application for Amend to License DPR-6,to Align Specs to 10CFR50,App J Requirements That Permit Removal of 24 H Duration Restriction on Integrated Leak Rate Test ML20205P6231988-10-24024 October 1988 Application for Amend to License DPR-6,deleting Tech Spec Requirements to Calibr Portable Gamma & Neutron dose-rate Measuring Instruments at Least Once Every 3 Months & Instead Follow ANSI N323-1978 ML20154S6371988-09-22022 September 1988 Application for Amend to License DPR-6,allowing Independent Review & Audit Functions by Independent Organizational Unit Rather than Standing Committee.Changes Consistent W/Bwr STS, ANSI N18.7-1976 & ANS 3.1-1987.Fee Paid ML20154P2111988-09-21021 September 1988 Application for Amend to License DPR-6,revising Tech Specs to Provide Clarification & Consistency by Reflecting Administrative & Editorial Corrections.Fee Paid ML20154D4761988-09-0808 September 1988 Application for Amend to License DPR-6,proposing Removal of Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes.Fee Paid ML20150C7831988-07-0505 July 1988 Application for Amend to License DPR-6,changing Tech Specs Re Reactor Depressurization Sys (Rds) Surveillance Testing, Eliminating Quarterly Partial Stroke Exercising of Rds Depressurizing Valves ML20148H6271988-03-22022 March 1988 Application for Amend to License DPR-6,changing Tech Specs Re Frequency of Reactor Depressurization Sys Depressurizing Valve Testing ML20237B9661987-12-14014 December 1987 Application for Amend to License DPR-6,removing Numerical Designator from I-type Fuel for Fuel Operating Cycle.Fee Paid ML20236N5021987-11-0909 November 1987 Application for Amend to License DPR-6,changing Tech Specs Administratively to Reflect Features & Terminology Used W/ New out-of-core Power Range Nuclear Instrumentation ML20236B3221987-07-23023 July 1987 Application for Amend to License DPR-6,consisting of Accumulated Administrative Changes ML20210C5961987-02-0404 February 1987 Application for Amend to License DPR-6,changing Tech Spec Section 5.2.1.b by Adding Table of Uncertainty Factors Associated W/Analysis of Core thermal-hydraulic Parameters Heat Flux,Maplhgr & Max Bundle Power ML20212F0301986-12-30030 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Include Second Scram Dump Tank Vent & Drain Valve ML20207C9541986-12-22022 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reduce Station Battery Design Time Interval from 8 to 2 H. Fee Paid ML20215F9941986-12-17017 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Add Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R & Generic Ltr 81-12.Request Supersedes 860421 Application ML20210E5141986-12-17017 December 1986 Application for Amend to License DPR-6,adding Operability & Surveillance Requirements for Alternate Shutdown Sys & Revising Tech Specs for Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg ML20215C7211986-12-0505 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reflect Use of New Hybrid Control Rods Mfg by Nucom,Inc & to Include Reload I-2 Fuel.Fee Paid ML20206M5081986-08-15015 August 1986 Application for Amend to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used W/New out-of-core source-range Nuclear Instrumentation ML20203P8021986-05-0101 May 1986 Application for Amend to License DPR-6,revising Tech Specs to Ensure Consistency w/831230 Exemption from Requirement to Have Two Senior Reactor Operators on Shift ML20203F6461986-04-21021 April 1986 Application for Amend to License DPR-6,changing Tech Specs Re Alternate Shutdown Battery Sys Operability & Surveillance Requirements ML20154K0181986-03-0404 March 1986 Application for Amend to License DPR-6,changing Tech Specs by Adding Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R ML20137V9621985-09-30030 September 1985 Application for Amend to License DPR-6,adding Operability & Surveillance Requirements for Components of Alternate Shutdown Sys Installed in Accordance w/10CFR50,App R ML20132F4561985-09-24024 September 1985 Revised Application for Amend to License DPR-6,changing I1 Fuel MAPLHGR Limits,Per 850816 Request,In Order to Implement Operating Limits for Reload Il Fuel ML20135B7971985-09-0303 September 1985 Application for Amend to License DPR-6,supplementing 741101 Proposed Tech Spec Change to Eliminate Min Control Rod Withdrawal Rate Limit ML20134E3011985-08-16016 August 1985 Application for Amend to License DPR-6,changing Tech Specs to Implement Reactor Operating Limits for Reload I1 Fuel ML20133M1131985-08-0505 August 1985 Application for Amend to License DPR-6,changing Tech Specs to Implement Staff Reorganization ML20132B7311985-07-19019 July 1985 Revised Application for Amend to License DPR-6,providing Tech Specs for Containment Pressure Monitor & Containment Water Level Monitor,Per NUREG-0737,Item II.F.1 ML20128B9131985-06-27027 June 1985 Application for Amend to License DPR-6,changing Tech Specs to Allow Operation of Plant Between Refueling Shutdowns W/O Potential of Requiring Surveillance Test to Be Performed.Fee Paid ML20126A0521985-06-0707 June 1985 Application for Amend to License DPR-6,incorporating Requirement to Adhere to Encl Plan for Big Rock Point Integrated Assessment. Fee Paid ML20128E4931985-05-24024 May 1985 Revised Application for Amend to License DPR-6,revising 840730 Tech Spec Change Request by Renumbering Definition Section 1.2.8 to 1.2.14 Re Administrative Controls ML20058E4011982-07-20020 July 1982 Application to Amend License DPR-6,changing Tech Specs Re Safety Mgt Function ML20058E3881982-07-20020 July 1982 Application to Amend License DPR-20,revising Tech Specs Re Safety Mgt Function ML20054J7321982-06-25025 June 1982 Application to Amend License DPR-6,changing Tech Specs to Change Technical Advisor from Shift to 24-h on-call Schedule 1999-05-11
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20206N2621999-05-11011 May 1999 Application for Amend to License DPR-6 to Delete from Defueled Ts,Subsection 1.16,change Definition of Site & Other Associated Editorial Changes ML20198K6581998-12-24024 December 1998 Amend 120 to License DPR-6,changing License DPR-6 & App a, TS to Reflect Permanetly Shutdown & Defueled Status of Plant ML20217F5191998-03-28028 March 1998 Application for Amend to License DPR-6,per 10CFR50.90 Re Security Plan.Encl Withheld ML20141J8651997-08-14014 August 1997 Amend 119 to License DPR-6,revising Plant License & TS to Reflect Company Name Change from CPC to Consumers Energy Co ML20138G1961997-04-30030 April 1997 Application for Amend to License DPR-6,requesting Name Change from Consumers Power Company to Consumers Energy Company, to Reflect Broader Scope of Energy Resources Available Through Company ML20138A9061997-04-22022 April 1997 Application for Amend to License DPR-6,requesting Change to TS to Withdraw Petition to Implement Option B Performance Based Requirements to App J of 10CFR50 ML20137J9321997-04-0202 April 1997 Amend 118 to License DPR-6,revising TS 4.2.9,to Add Additional Air Compressor ML20134H6281996-11-0707 November 1996 Application for Amend to License DPR-6,adding New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys ML20129C4611996-10-15015 October 1996 Application for Amend to License DPR-3,implementing Option B to Allow Use of Type a Test (Containment) Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining Boundaries) & Type C Test ML20058A1511993-11-15015 November 1993 Amend 112 to License DPR-6,changing TS to Implement Reorganization of Plant Staff ML20057E1951993-10-0505 October 1993 Amend 111 to License DPR-6,changing Reporting Requirements for Effluent Releases from Semiannual to Annual ML20056G3811993-08-24024 August 1993 Application for Amend to License DPR-6,revising 930719 Original Change,Reflects Revision to 10CFR50.36(a)(2) Re Changing Reporting Requirement for Effluent Releases from Semiannual to Annual ML20056E1651993-08-16016 August 1993 Amend 110 to License DPR-6,clarifying TS Re Undervoltage Breakers in RPS ML20128D7081993-01-29029 January 1993 Application for Amend to License DPR-6,revising TS to Reflect Administrative Changes in Engineering,Offsite Review & QA Organization ML20059A2091990-08-14014 August 1990 Application for Amend to License DPR-6,reflecting Administrative & Organizational Changes ML20246D2351989-08-16016 August 1989 Amend 100 to License DPR-6,revising Tech Specs to Provide for New Organizational Unit Entitled Nuclear Safety Svcs Dept to Discharge Offsite Safety Review Functions Instead of Nuclear Safety Board ML20245H8341989-07-28028 July 1989 Amend 98 to License DPR-6,requiring Compliance W/Amended Physical Security Plan ML20248C0571989-05-31031 May 1989 Amend 97 to License DPR-6,adding Operability & Surveillance Requirements for Alternate Shutdown Sys to Tech Spec Sections 11 & 12 & Including Tech Specs for Active Fire Barriers & Fire Detection Instrumentation ML20247L0891989-05-25025 May 1989 Application for Amend to License DPR-6,to Align Specs to 10CFR50,App J Requirements That Permit Removal of 24 H Duration Restriction on Integrated Leak Rate Test ML20246L8191989-05-0202 May 1989 Amend 96 to License DPR-6,revising OL to Allow for Increase in Amount of Byproduct Matl Plant May Possess & Use from 10.5 to 45 Ci Cs-137,as Sealed Sources ML20245F8251989-04-14014 April 1989 Amend 95 to License DPR-6,changing Tech Specs to Include Second Vent & Second Drain Valve to Scram Dump Tank ML20235J0231989-02-15015 February 1989 Amend 94 to License DPR-6,revising Station Battery Surveillance Test Time from 8 to 2 H ML20205S1241988-11-0404 November 1988 Amend 93 to License DPR-6,modifying Tech Specs by Replacing Requirements to partial-stroke Test Reactor Depressurization Sys Depressurizing Valves Quarterly W/Requirement to full- Stroke Test for Depressurizing Valves Each Outage ML20205P6231988-10-24024 October 1988 Application for Amend to License DPR-6,deleting Tech Spec Requirements to Calibr Portable Gamma & Neutron dose-rate Measuring Instruments at Least Once Every 3 Months & Instead Follow ANSI N323-1978 ML20154S6371988-09-22022 September 1988 Application for Amend to License DPR-6,allowing Independent Review & Audit Functions by Independent Organizational Unit Rather than Standing Committee.Changes Consistent W/Bwr STS, ANSI N18.7-1976 & ANS 3.1-1987.Fee Paid ML20154P2111988-09-21021 September 1988 Application for Amend to License DPR-6,revising Tech Specs to Provide Clarification & Consistency by Reflecting Administrative & Editorial Corrections.Fee Paid ML20154G1081988-09-14014 September 1988 Amend 92 to License DPR-6,modifying Paragraph 2.C.(5) of License Re Physical Security ML20154D4761988-09-0808 September 1988 Application for Amend to License DPR-6,proposing Removal of Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes.Fee Paid ML20150C7831988-07-0505 July 1988 Application for Amend to License DPR-6,changing Tech Specs Re Reactor Depressurization Sys (Rds) Surveillance Testing, Eliminating Quarterly Partial Stroke Exercising of Rds Depressurizing Valves ML20154J1871988-05-17017 May 1988 Amend 91 to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used W/New out-of-core Power Range Instrumentation ML20154H5251988-05-17017 May 1988 Amend 90 to License DPR-6,allowing Inclusion of All Reloads of I Fuel Design in Tech Specs ML20148H6271988-03-22022 March 1988 Application for Amend to License DPR-6,changing Tech Specs Re Frequency of Reactor Depressurization Sys Depressurizing Valve Testing ML20237B9661987-12-14014 December 1987 Application for Amend to License DPR-6,removing Numerical Designator from I-type Fuel for Fuel Operating Cycle.Fee Paid ML20236N5021987-11-0909 November 1987 Application for Amend to License DPR-6,changing Tech Specs Administratively to Reflect Features & Terminology Used W/ New out-of-core Power Range Nuclear Instrumentation ML20236B3221987-07-23023 July 1987 Application for Amend to License DPR-6,consisting of Accumulated Administrative Changes ML20211P1321987-02-19019 February 1987 Amend 89 to License DPR-6,revising Tech Spec Section 5.2.1.b to Add Table of Uncertainty Factors Re Analysis of Core Thermal Hydraulic Parameters for Reload I-2 Fuel & to Provide Footnotes Delineating Use of Values ML20211N5181987-02-17017 February 1987 Amend 88 to License DPR-6,revising Tech Spec Section 5.1 to Reflect Use of New Nucom,Inc Hybrid Control Rods in Cycle 22 Core ML20210C5961987-02-0404 February 1987 Application for Amend to License DPR-6,changing Tech Spec Section 5.2.1.b by Adding Table of Uncertainty Factors Associated W/Analysis of Core thermal-hydraulic Parameters Heat Flux,Maplhgr & Max Bundle Power ML20209H0481987-01-28028 January 1987 Amend 87 to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used in Conjunction W/Installation of New source-range Monitoring Instrumentation ML20212F0301986-12-30030 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Include Second Scram Dump Tank Vent & Drain Valve ML20207C9541986-12-22022 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reduce Station Battery Design Time Interval from 8 to 2 H. Fee Paid ML20215F9941986-12-17017 December 1986 Application for Amend to License DPR-6,changing Tech Specs to Add Operability & Surveillance Requirements for Alternate Shutdown Sys Installed Per 10CFR50,App R & Generic Ltr 81-12.Request Supersedes 860421 Application ML20210E5141986-12-17017 December 1986 Application for Amend to License DPR-6,adding Operability & Surveillance Requirements for Alternate Shutdown Sys & Revising Tech Specs for Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg ML20215C7211986-12-0505 December 1986 Application to Amend License DPR-6,revising Tech Specs to Reflect Use of New Hybrid Control Rods Mfg by Nucom,Inc & to Include Reload I-2 Fuel.Fee Paid ML20206M5081986-08-15015 August 1986 Application for Amend to License DPR-6,changing Tech Specs to Reflect Features & Terminology Used W/New out-of-core source-range Nuclear Instrumentation ML20211P3751986-07-11011 July 1986 Amend 86 to License DPR-6,adding Tech Spec Table Sentence Establishing Min Requirements for Shift Crew Composition During Various Operating Conditions ML20198A3801986-05-12012 May 1986 Amend 85 to License DPR-6,adding Definition for Reportable Event & Deleting Reporting Requirements Included in 10CFR50.72 & 50.73 ML20210P1651986-05-0606 May 1986 Amend 84 to License DPR-6,adding Condition to CRD Surveillance Testing Requiring Testing Prior to Startup Following Outages of More than 120 Days ML20203P8021986-05-0101 May 1986 Application for Amend to License DPR-6,revising Tech Specs to Ensure Consistency w/831230 Exemption from Requirement to Have Two Senior Reactor Operators on Shift ML20203F6461986-04-21021 April 1986 Application for Amend to License DPR-6,changing Tech Specs Re Alternate Shutdown Battery Sys Operability & Surveillance Requirements 1999-05-11
[Table view] |
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A CMS Energy Cornpany Big Rock Point Nuclear Plant Kenne P. hnners 10269 US-31 North Site General Manager Charlevoix. MI 49/20 May 11,1999 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 - 0001 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - DEFUELED TECHNICAL SPECIFICATION REQUEST TO DELETE DEFINITION OF SITE BOUNDARY AND REMOVE SITE MAP A request for amendment of the Big Rock Point Defueled Technical Specifications in accordance with 10 CFR 50.90 is enclosed. In order to be consistent with other decommissioning facilities and current NRC guidance, Consumers Energy Company proposes to delete from the Defueled Technical Specifications subsection 1.16, SITE BOUNDARY, which is already defined in 10 CFR Part 20; Figure 5.1-1 BRP Site Map, which is already provided in the Updated Final Hazards Summary Report (UFHSR); change the definition of the Big Rock Point site; and other associated editorial changes. Any future changes made to the UFHSR will be performed under 10 CFR 50.59.
This request is also consistent with guidance issued by the NRC for proposed standard technical specifications for permanently defueled plants.
In accordance with 10 CFR 50.91, Consumers Energy Company has made a determination that the proposed amendment change request involves no significant hazards considerations.
I i
, f \'
enneth P Powers Site General Manager i cc: Administrator, Region III NRC Reactor Decommissioning Inspector - BRP NRR Project Manager - OWFN, USNRC Attaclunent(s) 9905170109 990511 DR ADOCK 0 Q5
-- _ _ - - _ _ - - - . . 1
CONSUMERS ENERGY COMPANY 2 LICENSE DPR-6 DOCKET 50-155 Request for amendment to the Defueled Technical Specifications (DTS)
For the reasons hereinafter set forth, it is requested that the Defueled Technical Specifications contained in the Facility Operating License DPR-6, Docket 50-155 for the Big Rock Point Plant be amended as proposed in Section I below. Revised Defueled Technical Specification pages are provided in Attachment 1. The proposed changes are shown utilizing the " strikeout" and
" redline" method. The proposed new pages of the Defueled Technical Specifications are provided in Attachment 2 to this letter.
I. CllANGES
- 1. Delete subsection 1.16 SITE BOUNDARY. Delete 1.16 SITE BOUNDARY from the Table of Contents. Eliminate the capitalization of this term where necessary as it appears throughout the following subsection (s) of the Defueled Technical Specifications and Bases:
Defueled Technical Bases #
Specifications 6.6.2.5.h 3.3.1.d 6.6.2.6.b
- 2. Delete Figure 5.1-1, BRP Site Map from Defueled Technical Specification ,
Section 5.0, DESIGN FEATURES. Delete "(reference Figure 5.1-1)" from Defueled Technical Specifications subsections 5.1.1.
Delete "(see Figure 5.1-1)" from Defueled Technical Specifications subsections 6.6.2.5.g, and 6.6.2.5.j.
- 3. Delete the following from subsection 5.1.1 of the DESIGN FEATURES section of the Defueled Technical Specificationsi
- a. 5.1.1 LOCATION AND BOUNDRIES j
- b. ... site, consisting of approximately 600 acres,... l
- c. ...The nearest landside property line is about 2680 feet and the ]
nearest shoreline property line is about 200 feet from the ,
containment sphere... l I
- 4. Delete 5.1.1 Location and Boundaries, and FIGURE 5.1-1, BRP Site Map, from the Table of Contents.
)
I l
CONSUMERS ENERGY COMPANY 3 LICENSE DPR-6 DOCKET 50-155 Request for amendment to the Defueled Technical Specifications (DTS)
II. DISCUSSION
- 1. Delete subsection 1.16, SITE BOUNDARY. Eliminate the capitalization of this term as it appears throughout the Defueled Technical Specifications and Bases. Remove this subsection from the Table of Contents.
Including the definition of SITE BOUNDARY in the Big Rock Point Defueled Technical Specifications is unnecessary and redundant because the definition and application of this term already exists in 10 CFR Part 20. Furthermore, it appears that the duplication of temis already defined in the regulations in facility's technical specifications is not necessary since this l requirement is not part of the format prescribed in proposed Standard Technical Specification guidance for decommissioned plants.
As a matter of Use and Application, the defined terms of Section 1.0 of the Technical Specifications appear in capitalized type and are applicable throughout. The use of the term " site boundary" remains appropriate in the Defueled Technical Specifications and Bases, however since it is not a defined tenn, it will noi be capitalized. ;
- 2. Delete Figure 5.1-1 BRP Site Map and its reference from the Defueled Technical Specifications. Delete from the Table of Contents.
- 3. Replace Subsection 5.1 of the DESIGN FEATURES section of the Defueled Technical Specifications in its entirety with the following:
5.1 SITE The plant site is located in Charlevoix County, Alichigan, about 4 miles northeast ofCharlevoix, Afichigan, and about 11 miles west ofPetoskey, Alichigan.
The applicable section of the NRC's regulations dealing with the required content of Technical Specifications, Section 10 CFR 50.36(c)(4), states:
" Design features to be included are those features of the facility such as material of construction, and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (1), (2), and (3) of this section."
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CONSUMERS ENERGY COMPANY 4 LICENSE DPR-6 DOCKET 50-155 Request for amendment to the Defueled Technical Specifications (DTS)
The referenced paragraph (c)(1) deals with safety limits, limiting safety system settings, and limiting control settings; paragraph (c)(2) deals with limiting conditions for operation; and paragraph (c)(3) deals with surveillance requirements. None of the above cited criteria for content of Technical Specifications applies to the site map, figure 5.1-1, in the current Big Rock Point Defueled Technical Specifications.
Two NRC guidance documents also support the proposed changes. NUREG-1625, " Proposed Standard Technical Specifications for Permanently Defueled Westinghouse Plants", which recommends a textual site location description and Regulatory Guide 1.70," Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants", which directs applicants and licensees to provide the site map for their facility in their Safety Analysis Report.
Therefore, removal of the site map and its reference from the Big Rock Point Defueled Technical Specifications and replacement with a textual site location description is appropriate and follows current NRC guidance.
- 4. Delete 5.1.1 Location and Boundaries from the Table of Contents.
it logically follows that these be removed from the table of contents.
III. ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION In accordance with 10 CFR 50.91, Consumers Energy Company has made a determination that the proposed amendment does not involve significant hazards considerations. Consumers Energy Company has concluded that the proposed amendment will 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.
The proposed change is administrative in nature and has no affect on the health and safety of the public. There is no reduction or elimination of federal regulatory requirements associated with the proposed amendment. The information being removed from the Defueled Technical Specifications is unnecessary since SITE BOUNDARY is already defm' ed in 10 CFR Part 20, and the site map is already provided in the Updated Final Hazards Safety Report. Furthermore, the proposed changes are consistent with the guidance provided in NUREG -1625.
CONSUMERS ENERGY COMPANY 5 ,
LICENSE DPR-6 DOCKET 50-155 Request for amendment to the Defueled Technical Specifications (DTS)
The proposed change does not:
- 1) Involve a significant increase in the probability or consequence of an accident previously evaluated.
The proposed amendment does not change the site boundary as it currently exists.
Deleting the SITE BOUNDARY definition and changing the upper case characters to lower case throughout the DTS and the Bases where it appears, and deleting the site figure from the DTS and related references will not increase the probability or consequences of a new or different kind of accident previously evaluated. This proposed change is administrative in nature and does not involve fuel handling or affect or modify any system, structure or cornponent.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed amendment does not change the site boundary as it currently exists.
Deleting the SITE BOUNDARY definition and changing the upper case characters to lower case throughout the DTS and the Bases where it appears, and deleting the site figure from the DTS and related references will not create the possibility of a new or different kind of accident from any accident previously evaluated. This proposed change is administrative in nature and does not involve fuel handling or affect or modify any system, structure or component.
- 3) Involve a significant reduction in the margin of safety.
The proposed changes do not involve any physical changes to the plant or plant procedures. There will be no reduction in a margin of safety.
i CONSUMERS ENERGY COMPANY 6 ;
LICENSE DPR-6 DOCKET 50-155 ;
4 Pequest for amendment to the Defueled Technical Specifications (DTS) j IV. CONCLUSION The Big Rock Point Safety Review Committee has reviewed this Defueled Technical Specification Change request and has determined this proposed change does not involve significant hazards consideration. This proposed change has also been reviewed and J
approved by the Nuclear Performance Assessment Department. A copy of this proposed change request has been sent to the State of Michigan official designated to receive such proposed Amendments to Appendix A of the Big Rock Point Facility Operating License.
CONSUMERS ENERGY COMPANY - 7 LICENSE DPR-6 '
DOCKET 50-155 Request for amendment to the Defueled Technical Specifications (DTS)
CONSUMERS ENERGY COMPANY To the best of my knowledge, information and belief, the contents of this submittal are truthful and complete.
By W
se'nneth P Powers Site General Manager Sworn and subscribed to before me this day May 11,1999.
hattO, bnw bhn '
Jyp'nifer Lyfn Helms, Notary Public L>harlevoix County, Michigan My commission expires August 29,1999 SEAL
ATTACHMENT l' CONSUMERS ENERGY COMPANY BIG ROCK POINT PLANT DOCKET 50-155 Revised Defueled Technical Specification Presenting Proposed Revisions.
Submitted May 11,1999
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