|
---|
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] |
Text
. _ _ __ _ _ __ _. _. .. . . ..
I g, CONSUMERS ENERGY COMPANY D0CKET 50-155 Request for Change to the Technical Specifications ,
License DPR-6 l r
for the reasons hereinafter set forth, it is requested that the Technical l Specifications contained in the Facility Operating License DPR-6, Docket 50- ;
155, issued to Consumers Energy Company on May,1, 1964, for the Big Rock Point Plant be changed as described in Section I below: ,
Revised Technical Specification pages are attached. Proposed changes are shown i by a back-slash (/) in the right-hand margin. -
I. CHANGES
- 1) Technical Specification section 4.1.2(b); Chloride Ion (Ppm) and Boron l (Ppm) need to be revised to read Chloride Ion (ppm) and Boron (ppm). !
- 2) Technical Specification section 6.1.3 Reactor Safety System Bypass; trip ,
function bypassed when the mode relector switch is in the shutdown position, requires revision. Delete ".None", and insert the following:
Low Steam Drum Level" Steam Line Backup Isolation Valve Closed High Condenser Pressure Recirculation Line Valves Closed In the same section, note (c) also requires revision. Delete the last sentence of the note "None of the reactor safety system signals are bypassed since there is no need to withdraw control rods."
- 3) Technical Specification section 6.9.2.2.A 4, Radiological Impact on Man, needs revision to be consistent with Technical Specification section 6.9.2.2.A. Delete "to be submitted within 60 days after January 1 of each year shall", so that the paragraph reads "The Radiological Effluent Release Report shall include potential doses to individuals and populations calculated using measured effluent and averaged meteorological data in accordance with the methodologies in the Offsite Dose Calculation Manual."
i
- 4) Technical Specification section 6.12.1.c. has a reference to the l Chemistry and Radiation Protection Supervisor. Delete " Chemistry and" so l that the section reads "...specified by the Radiation Protection Supervisor in the RWP."
- 5) Technical Specification 6.12.2 needs correction. " Service" needs to be deleted and replaced with " surface", so that the sentence will read.."from the radiation source or from any surface from which the radiation penetrates..."
- 6) Technical Specification 11.3.5.3.7, Action 3 should read " Action a."
- 7) Bases for 13.1.3.1 - Gaseous Effluent Dose Rate requires a correction to the units described to measure skin dose. 3000 mr/hr should read 3000 4
mr/yr.
9704290282 970422 PDR ADOCK 05000155 p PDR
's 1. BIG ROCK POINT Pl. ANT 2
, . TECH SPEC CHANGE REQUEST II. DISCUSSION Changes 1),5),6),and7)
These changes correct typographical errors.
Change 2)
This change is requested to make the Technical Specifications consistent with plant procedures and current design. As evidenced by the proposed change, four trip functions have always been bypassed when the reactor mode switch is in the shutdown position:
LOW STEAM DRUM WATER LEVEL A trip signal from this condition anticipates a loss of water which could lead ;
to a low reactor water level. Four level switches LS-RE06A and LS-RE20A connected to Protection Channel 1 and LS-RE06B and LS-RE20B connected to protection Channel 2, detect this condition. When the steam drum water level drops to 8.0 inches below steam drum center line, a control rod scram is initiated. These switches are located on the steam drum wall, across from the C-30 panel.
The steam drum water level trip signals are bypassed by contacts of auxiliary relays K11 and K12 in the annunciator control units. K11 and K12 are energized by contacts 2-2C (Channel 1) and 9-9C (Channel 2) on the reactor mode switch, S4, in the shutdown, refuel and bypass dump tank positions.
MAIN STEAM ISOLATION VALVE Closure of main steam isolation valve M0-7050 to 50%, whether by remote manual control RMC-5500, malfunction or penetration closure switch SS, initiates a control rod scram. This is accomplished by opening limit switch contacts LS-9 and LS-10 connected to Protection Channel 1 and LS-15 and LS-16 connected to Protection Channel 2, on the valve drive unit.
These trip signals are bypassed by contacts of auxiliary relays K11 and K13 in the annunciator control units. K11 and K13 are energized by contacts 2-2C (Channel 1) and 9-9C (Channel 2) on the reactor mode switch, S4, in the shutdown, refuel and bypass dump tank positions.
HIGH CONDENSER PRESSURE High condenser pressure is used as an indication that the main condenser is no longer available as a heat sink for the reactor output, thereby making a control rod scram necessary.
Pressure switches PS-654 and PS-655 connected to Protection Channel 1 and PS-652 and PS-653 connected to Protection Channel 2, detect this condition when condenser pressure reaches 8.0 inches Hg absolute.
The high condenser pressure trip signal is automatically bypassed any time steam drum pressure is below 500 psig (the definition of shutdown is all or all but one of the control rods fully inserted in the reactor core; and Primary System Coolant water temperature less than 212*F). This automatic bypass is accomplished by PS-REISA and PS-RE15B connected to Protection
[* ; *i,, BIG ROCK POINT PLANT 3 1., TECH SPEC CHANGE REQUEST 4
5 Channel 1 and PS-RE15C and PS-RE150 connected to Protection Channel 2. These pressure switches are set to operate at 450 psig. They are located on the steam drum wall across from the C-30 panel. .
RECIRCULATION LINE VALVE CLOSED 5
, The closure of these valves would prevent coolant circulation to the reactor core and a control rod scram is initiated to prevent development of excessive fuel temperatures.
A trip signal is received at approximately 10% of full simultaneous closure of both discharge valves M0-N001A and M0-N001B, or both suction valves M0-N003A '
and M0-N003B, or 50% of full simultaneous closure of both Butterfly Valves M0-N006A and M0-N0068, or any combination of these valves, one in each loop. That is, if recirculation is restricted in both loops, a trip signal will be inserted. The sensors are limit switch / position switch contacts on each of the drive units of the valves.
1 These trip signals are bypassed by contacts of auxiliary relays K12 and K13 in the annunciator control units. K12'and K13 are energized by contacts 2-2C (Channel 1) and 9-9C (Channel 2) on the reactor mode switch, S4, in the !
shutdown, refuel, and bypass dump tank positions.
J Change 3) l This change is requested to make the Technical Specifications consistent.
Technical Specification section 6.9.2.2.A.4, Radiological Impact on Man, needs revision to be consistent with Technical Specification section 6.9.2.2. A.
Change 4)
This change is required to reflect a recent organizational change that created separate supervisory positions for Chemistry and Radiation Protection.
III. ANALYSIS OF NO SIGNIFICANT HAZARDS CONSIDERATION l l
In accordance with 10 CFR 50.92, Consumers Energy Company has made a determination that the proposed amendment involves no significant hazards considerations. To make this determination, Consumers Energy Company has i
established that operation in accordance with 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.
t The proposed Technical Specification Change does not present an undue risk to the public, and does not impact common defense and security.
The proposed change does not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated.
4
=
. - . . - - - - - . - - - . - . - . - _ - . - . - . ~ _ _ - - . . _ . -
.J BIG ROCK POINT PLANT 4
! --(:- TECH SPEC CHANGE REQUEST The proposed changes are clarifications within the Technical Specifications, and do not alter the technical content of the technical specifications. Plant
, o)eration or configuration-is not affected. The postulated doses received by tie general public and plant personnel as a direct result of accidents '
4 previously described, are not affected. Plant operation or configuration is not affected. Therefore the proposed changes do not. involve a significant increase in the probability or consequences of an accident previously r evaluated. i l
j 2) Create the possibility of a new or different kind of accident from any !
accident previously evaluated. !
l The proposed changes are. either clarifications to correct. inconsistencies )
1 _w ithin the Technical Specifications, or corrections of typographical errors. ;
The proposed changes do not alter the facility in any way,' therefore the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. ;
3)ilnvolve a significant reduction in a margin of safety
' The proposed change does not affect any margin of safety as defined by the ,
Plant Technical Specifications. .
IV. CONCLUSION ;
The Big Rock Point Plant Review Committee has reviewed this Technical Specification Change Request and has determined this change does not involve
, an unreviewed safety question and, therefore, involves no significant hazards consideration. This change has been reviewed by the Nuclear Performance Assessment Department. A copy of this change request has been sent to the State of Michigan official designated to receive such Amendments to the 1
Operating License.
CONSUMERS ENERGY COMPANY
] To the best of my knowledge, information and belief, the contents of this submittal are truthful and complete.
By ~ -
w Rot,ert J Addy \ i
. Plant Manger Sworn and subscribed to before me this 22nd day of April- 1997. t' i
havM, *n OhSM nniff. r Lynn Kelms, Notary Public Ch4rlevoix County, Michigan
-My commission expires August.29, 1999.
2 (SEAL).
__ _ _ ._ - -. .. _ . .-. _ . . _ - . - . ._!