ML20206N275
| ML20206N275 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/11/1999 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20206N268 | List: |
| References | |
| NUDOCS 9905170191 | |
| Download: ML20206N275 (19) | |
Text
(
TABLE OF CONTENTS DEFUELED TECHNICAL SPECIFICATIONS.
FOR BIG ROCK POINT PLANT SECTION DESCRIPTION PAGE 1.0 DEFINITIONS...
1-1 1.1 Action......
1....................................
1.2 Certified Fuel Handler................................. 1-1 1.3 Channel Calibration 1-1 1.4 Channel Check 1-1 1.5 Channel Functional Test 1-1 1.6 Containment Closure.................................. 1-1 1.7 D i rect Path........................................ 1-2 1.8 Fu el H a nd l i ng...................................... 1-2 1.9 Immediately 1-2 1.10 Monitoring Station..................
1-2 1.11 Offsite Dose Calculation Manual (ODCM).................... 1-2 Q
1.12 Operable - Operability 1-3 1.13 Process Control Program (PCP)........................... 1-3 1.14 Reportable Event 1-3 1.15 Shift 1-3 1 9 1 1/
f9 h _ 71_ _ _ _ J _ _ _
4s
- 1. 2 u
- mmuvuuum, 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEMS SETTINGS...
2-1 3/4 LIMITING CONDITIONS FOR OPERATION & SURVEILLANCE REQ UIREM ENTS.....................................
3/4-1 3/4.0 APPLICABILITY....................................
3/4-1 3/4.1 FUEL STORAGE.................................
3/4-2 3/4.1.1 Spent Fuel Pool Parameters...................... 3/4 4 3/4.1.2 Spent Fuel Pool Support System Requirements........
3/4-5 & 6 3/4.1.3 Fuel Storage General Requirements...................
3/4-7 3/4.2 FUEL H AN DLING................................
3/4-8 3/4.2.1 Fuel Handling Support System Requirements.............
3/4-8 3/4.2.2 Fuel Handling General Requirements..............
3/4-9 & 10 3/4'3 CONTROL OF HEAVY LOADS................... 3/4-11 & 12 3/4.4 SEALED SOURCE CONTAMINATION.................
3/4-13 9905170191 990511 PDR ADOCK 05000155 W
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TABLE OF CONTENTS DEFUELED TECHNICAL SPECIFICATIONS BIG ROCK POINT PLANT SECTION DESCRIPTION EAGE 5.0 I)ESIGN FEATURES
.............................5-1 5.1 S ITE...........................................
5 - 1 s..f.9 5,1 f
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STOlk GE A bI SPECT N h SPbNbFUEL...
. 5-1 5.2 5.2.1 Criticality....................................
5-1 5.2.2 Water Le vel...................................
5-1 5.2.3 Cool i ng......................................
5-1 5.2.4 Capacity...........
5-3 5.3 REA CTO R.......................................
5 -3 5.3.1 S ta t u s........................................ 5.3-6.0 ADMINISTRATIVE CONTROLS...........................
6-1 6.1 RESPONSIBILITY AND AUTHORITY....................
6-1 6.1.1 Senior Nuclear Officer............................
6-1 6.1.2 Site General Manager.............................. 6-1 6.1.3 Shift Supervisor................................
6-1 6.2 ORGANIZATION........
6-1 6.2.1 Reporting Relationships 6-1 6.2.2 Facility Organization.............................. 6-2 TABLE 6.2-1 Minimum Shift Crew Composition..........
6-3 6.3 STAFF QUALIFICATIONS............................
6-4 6.4 TRAINING...........
6-4 6.5 REVIEW AND AUDIT.................
6-4 6.5.1 CPC-2A Quality Program Description................... 6-4 6.6 PROCEDURES AND PROGRAMS........
6-5 6.6.1 Procedures..............
6-5 6.6.1.1 Scope 6-5 6.6.1.2 Review and Approval.........................
6-5 6.6.1.3 Temporary Changes...
6-5 6-6 6.6.2 P rograms......................................
'6.6.2.1 Radiation Protection Program....................
6-6 6.6.2.2 High Radiation Area..........................
6-6 6.6.2.3 Process Control Program (PCP) 6-7 6.6.2.4 Offsite Dose Calculation Manual (ODCM).
6-8
q
-j BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS-d 1.0
. DEFINITIONS -
l 1,12 OPERABLE - OPERABII ITY ~
1 A system, subsystem, train, component or device shall be OPERABLE or havei OPERABILITY when it is capable of performing its specified function (s) and when -
all necessary attendant instrumentation, controls, electrical power, cooiing or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its safety function (s) are also capable of performing their related support function (s).
1.13 PROCESS CONTROL PROGRAM (PCP)
The PROCESS CONTROL PROGRAM contains the methods and determinations which ensure that the processing and packaging of wet solid radioactive wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61 and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
1.14 REPORTABI E EVENT A REPORTABLE EVENT is any of those conditions specified as reportable in Specification 6.9.
1.15 SHIFT A SHIFT shall be the duration of the normal work period, which will be either 8 or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in length L determined by the Site General Manager. For purposes of determining the maximum allowable time between surveillances, when the specified surveillance interval is "once per SHIFT," the maximum allowable extension not to exceed 25 percent of the specified surveillance interval described in Surveillance Requirement 4.0.2 shall be based upon the SHIFT duration approved by the Site
- General Manager at that time.-
1.16 SITE I;OUNDA"Y Thc L;C "OUNDA"Y 15 C ; T..e t~yurd whlch de 1..d 15 i.v; v..ed, Ic.Kd, er vC.wix cum.ullcd by de l L. ~c.
. 1-3 3
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BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 5.0 DESIGN FEATURES 5.1 SITE 5.1.1 LOCATION AND DOUNDARIES The plant site si;c, consisting of epproxinieicly 500 acics, is located in Charlevoix County, Michigan, about 4 miles northeast of Charlevoix, Michigan, and about 11 miles west of Petoskey, Michigan. Thc ncerc51lendsidc prof ~rty lirm is abent 2580 fcci snd the ncerc5; 5herclinc prof ~dy linc is shout 200 fcci fieni the contehuiicn; sphcic (refcicncc Figurc 5.1-1).
5.2 STORAGE AND INSPECTION OF SPENT FUEL 5.2.1 CRITICALITY Spent fuel is stored in spent fuel storage racks which are designed and shall be maintained with sufficient center-to-center distance between stored fuel assemblies to ensure a k rr less than or equal to 0.95 when the racks are flooded with unborated e
water.
The fuel loading per axial centimeter of any assembly placed in the Spent Fuel Pool shall be less than or equal to a maximum of 28.3 grams of U " or equivalent.
2 Fuel inspection stations, if installed, shall be designed and maintained with sufficient center-to-center distance between fuel assemblies placed in the inspection stations to ensure a k rr less than or equal to 0.95 when flooded with unborated e
water.
5.2.2 WATER LEVEL The Spent Fuel Pool is designed to maintain a normal water level between 630' and 632' 6".
5.2.3 COOLING The configuration of storage racks placed in the Spent Fuel Pool allows for adequate circulation of water to prevent localized pool boiling.
5-1
BIG ROCK POINT DEFUEI FD TECHNICAL SPECIFICATIONS - 5.0 DESIGN FEATURES 4$.
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BIG ROCK POINT DEFUEI En TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS e.
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year -
in accordance with the methodology and parameters in the ODCM at least every 31 days; f.
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50.
g.
The dose rate due to radioactive materials released in gaseous effluents from.
the site to areas at or beyond the site boundary (5cc Tigsrc 5.1-1)'shall be' limited to the following:
(a)
For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and (b) For tritium and for all radionuclides in particulate form with halflives greater than 8 da,vs: Less than or equal to 1500 mrems/yr to any organ.
h.
Limitations conformin'; to Appendix I to 10 CFR Part 50 on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the facility to areas beyond the SITE 00UNDARY, site boundary; and i.
Limitations conforming to 40 CFR Part 190 on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources.
j.
The dose to a member of the public from tritium and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to areas at or beyond the site boundary (5cc rignic 5.1-1) shall be limited to the following:
(a)
During any calender quarter: Less than or equal to 7.5 mrems to any organ, and (b) During any calender year: Less than or equal to 15 mrems to any organ.
6-9 s
i BIG ROCK POINT DEFUEMD TECHNICAL SPECIFICATIONS i
6.0 ADMINISTRATIVE CONTROLS 6.6.2.6 Radiological Environmental Monitoring Program
'A program shall be provided to monitor the radiation and radionuclides in the environs of the facility. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the q
ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3)
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include the following:
a.
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM; i
b.
A Land Use Census to ensure that changes in the use of areas at and beyond.
the SITE DOUNDARY site boundary are identified and that modifications to the monitoring program are made if required by the results of this census, or 4
alternatively, that critical receptors are assumed to exist at the SITE j
DOUNDARY site boundary or offsite location of highest dose consequence;
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and j
l i
c.
Part.icipation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part 3
of the quality assurance program for environmental monitoring.
6.6.2.7 Fire Protection Program A fire protection program meeting the requirements of 10 CFR 50.48(f) shall be established, implemented, and maintained.
6,6.2.8 Cold Weather Protection Program This program provides administrative controls to ensure that appropriate measures are implemented and maintained during cold weather to protect the facility against cold temperatures which could impact the safe storage of irradiated fuel or result in -
unplanned or unmonitored radioactive material release.-
)
I 6-10
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ATTACHMENT 2 -
- CONSUMERS ENERGY COMPANY BIG ROCK POINT PLANT-DOCKET 50-155 Revised Defueled Technical Specification Presenting Proposed Pages :
Submitted May 11,1999 i
i 1
TABLE OF CONTENTS DEFUELED TECHNICAL SPECIFICATIONS FOR BIG ROCK POINT PLANT SECTION DESCRIPTION PAGE 1.0 DEFINITIONS.......................
1-1 1.1 Ac t io n..........................
1-1 1.2 Certified Fuel Handler................................. 1-1 1.3 Channel Calibration................
1-1 1.4 Channel Check 1-1 1-1 1.5 Channel Functional Test...............................
1.6 Containment Closure.................................. 1-1 1-2 1.7 Direct Path.......................................
1-2 1.8 Fuelliandling.
1-2 1.9 Immediately 1.10 Monitoring Station................................... 1-2 1.11 Offsite Dose Calculation Manual (ODCM).................... 1-2 1-3 1.12 Operable - Operability 1.13 Process Control Program (PCP)........................... 1-3 1.14 Reportable Event 1-3 1.15 Shift 1-3 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEMS SETTINGS...... 2-1 3/4 LIMITING CONDITIONS FOR OPERATION & SURVEILLANCE REQ U IREM ENTS.....................................
3 /4-1 3/4.0 APPLICABILITY....................................
3/4-1 3/4.1 FUEL STORAGE.................................
3/4-2 3/4.1.1 Spent Fuel Pool Parameters...................... 3/4 4 3/4.1.2 Spent Fuel Pool Support System Requirements........
3/4-5 & 6 3/4.1.3 Fuel Storage General Requirements...................
3/4-7 i
3/4.2 FUEL H AN DLING.................................
3/4-8
)
3/4.2.1 Fuel Handling Support System Requirements.............
3/4-8
{
3/4.2.2 Fuel Handling General Requirements.............
3/4-9 & 10 3/4.3 CONTROL OF HEAVY LOADS........
3/4-11 & 12 3/4.4 SEALED SOURCE CONTAMINATION.................
3/4-13 i
l As Proposed i
TABLE OF CONTENTS DEFUELED TECHNICAL SPECIFICATIONS BIG ROCK POINT PLANT SECTION DESCRIPTION PAGE 5.0 DESIGN FEATURES 5-1 5.1 S ITE..........................................
5-1 5.2 STORAGE AND INSPECTION OF SPENT FUEL.............
5-1 5.2.1 Criticality....................................
5-1 5.2.2 Wate r Level...................................
5 - 1 5.2.3 Cooling......................................
5-1 5.2.4 Capacity.........
5-3 5.3 REACTOR.......................................
5 -3 5.3.1 S ta tu s........................................ 5.3 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 RESPONSIBILITY AND AUTHORITY....................
6-1 6.1.1 Senior Nuclear Officer............................. 6-1 6.1.2 Site General Manager.............................. 6-1 6.1.3 Shift Supervisor................................. 6-1 6.2 ORG A NIZATION..................................
6-1 6.2.1 Reporting Relationships 6-1 6.2.2 Facility Organization.............................
6-2 TABLE 6.2-1, Minimum Shift Crew Composition..........
6-3 6.3 STAFF QUALIFICATIONS.....
.................6-4 6.4 TRAINING........................
6-4 6.5 REVIEW AND AUDIT...............................
6-4 6.5.1 CPC-2A Quality Program Description.................
6-4 6.6 PROCEDURES AND PROGRAMS.......................
6-5 6.6.1 Proced ures....................................
6-5 6-5 6.6.1.1 Scope 6.6.1.2 Review and Approval.......,.................
6-5 6.6.1.3 Temporary Changes.....................
6-5 6.6.2 Programs....................................
6-6 6.6.2.1 Radiation Protection Program....................
6-6 6.6.2.2 IIigh Radiation Area........................... 6-6 6.6.2.3 Process Control Program (PCP)
..................6-7 6.6.2.4 Offsite Dose Calculation Manual (ODCM)............. 6-8 As Proposed
BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 1.0
- DEFINITIONS 1.0 DEFINITIONS ;
1.12 OPERABIF -- OPERABII ITY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and when.
all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its safety function (s) are also-capable of performing their related support function (s).
1.13
- PROCESS CONTROL PROGRAM (PCP)
The PROCESS CONTROL PROGRAM contains the methods and determinations which ensure that the processing and packaging of wet solid radioactive wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,.61 and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
1 1.14 REPORTABI E EVENT 1
A REPORTABLE EVENT is any of those conditions specified as reportable in Specification 6.9.
1 1.15 SHIFT A SHIFT shall be the duration of the normal work period, which will be either 8 or 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in length as determined by the Site General Manager. For purposes of determining the maximum allowable time between surveillances, when the specified surveillance interval is "once per SHIFT," the maximum allowable extension not to exceed 25 percent of the specified surveillance interval described in Surveillance Requirement 4.0.2 shall be based upon the SHIFT duration approved by the Site 1
General Manager at that time.
1-3 As Proposed -
I BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS
{
l 5.0 DESIGN FEATURES 5.1 SLTE The plant site is located in Charlevoix County, Michigan, about 4 miles northeast of Charlevoix, Michigan, and about 11 miles west of Petoskey, Michigan.
5.2 STORAGE AND INSPECTION OF SPENT FUEL 5.2.1 CRITICALITY Spent fuel is stored in spent fuel storage racks which are designed and shall be maintained with sufficient center-to-center distance between stored fuel assemblies to ensure a k,y less than or equal to 0.95 when the racks are flooded with unborated water.
The fuel loading per axial centimeter of any assembly placed in the Spent Fuel Pool shall be less than or equal to a maximum of 28.3 grams of U " or equivalent.
2 Fuel inspection stations, if installed, shall be designed and maintained with sufficient center-to-center distance between fuel assemblies placed in the inspection stations to ensure a k,y less than or equal to 0.95 when flooded with unborated water.
5.2.2 WATER LEVEL The Spent Fuel Pool is designed to maintain a normal water level between 630' and 632' 6".
5.2.3 COOLING The configuration of storage racks placed in the Spent Fuel Pool allows for adequate circulation of water to prevent localized pool boiling.
5-1 As Proposed a
~
BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS i
i 5.0 DESIGN FEATURES I
FIGURE DELETED 5-2 As Proposed,
BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS e.
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year -
in accordance with the methodology and parameters in the ODCM at least every 31 days; f.
Limitations on the operability and use of the liquid and gaseous effluent -
treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50.
g.
The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the site boundary shall be limited to the following:
(a)
For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and 1
(b) For tritium and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
h.
Limitations conforming to Appendix I to 10 CFR Part 50 on the annual and l
quarterly air doses resulting from noble gases released in gaseous effluents from the facility to areas beyond the site boundary; and i.
Limitations conforming to 40 CFR Part 190 on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources.
j.
The dose to a member of the public from tritium and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released to areas at or beyond the site boundary shall be limited to the following:
(a)
During any. calender quarter: Less than or equal to 7.5 mrems to any organ, and (b) During any calender year: Less than or equal to 15 mrems'to any organ.
6-9 As Proposed
/
BIG ROCK POINT DEFUELED TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS 6.6.2.6.
Radiological Environmental Monitoring Program
~
A program shall be provided to monitor the radiation and radionuclides in the -
environs of the facility. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of -
environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
Monitoring, sampling, analysis, and reporting of radiation and radionuclides, a.
in the environment in accordance with the methodology and parameters in the ODCM; b.
A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoririg program are made if required by the results of this census, or alternatively, that critical receptors are assumed to exist at the site boundary or offsite location of highest dose consequence; and c.
Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part -
of the quality assurance program for environmental monitoring.
6.6.2.7 Fire Protection Program A fire protection program meeting the requirements of 10 CFR 50.48(f) shall be established, implemented, and maintained.
6.6.2.8 Cold Weather Protection Program This program provides ' administrative controls to ensure that appropriate measures are implemented and maintained during cold weather to protect the facility against cold temperatures which could impact the safe storage of irradiated fuel or result in unplanned or unmonitored radioactive material release.
6-10
. As Proposed
5
/
' ATTACilMENT 3' CONSUMERS ENERGY COMPANY BIG ROCK POINT PLANT DOCKET 50-155 Revised Defueled Technical Specification Bases Presenting Proposed Revisions -
Submitted May 11,1999 1
BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS 3/4.3 CONTROL OF HEAVY LOADS BASES The ACTION associated with this specification is required to place the crane load in a safe '
condition and prohibit resumption of load handling activities until approved by the Site General Manager.
4.3.1.c This surveillance provides assurance that the trip mechanism is OPERABLE.
-3.3.1.d This specification assures that releases to the SITE COUNDARY site boundary resulting from heavy loads events will be reduced by the containment shell.
CONTAINMENT CLOSURE, as opposed to leak-tightness, is specified, since there is no propelling force r.ssociated with analyzed heavy loads accidents.
4.3.1.d The surveillance required by this specification provides assurance that CONTAINMENT CLOSURE exists.
1
- B3/4-12
)
i
j/
i 1
- dTTACHMENT 4 CONSUMERS ENERGY COMPANY BIG ROCK POINT PLANT-DOCKET 50-155 Revised Defueled Technical Specification Bases Presenting Proposed Pages.,
Submitted May 11,1999 q
J t
t
BIG ROCK POINT PERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS.
3/4'.3 CONTROL OF HEAVY LOADS BASES-i The ACTION associated with this specification is required 'to place the crane load in a safe condition and prohibit resumption of load handling activities until approved by the Site -
General Manager.
4.3.1.c This surveillance provides assurance that the trip mechanism is' OPERABLE.
~
3.3.1.d This specification assures that releases.to the site boundary resulting from_ heavy loads events will be reduced by the containment shell. CONTAINMENT :
CLOSURE, as opposed to leak-tightness, is specified, since there is no propelling force associated with anal zed heavy loads accidents.
4.3.1.d The surveillance required by this specification provides assurance that CONTAINMENT CLOSURE exists.
3/4-12 As Proposed