ML20195D045

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs,Revised to Agree with Current Facility Defueled TS Format
ML20195D045
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 06/03/1999
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20195D042 List:
References
NUDOCS 9906090073
Download: ML20195D045 (16)
v • d • e


Text

1

.. . i l

ATTACIIMENT 1 CONSUMERS ENERGY COMPANY l BIG ROCK POINT PLANT DOCKET 50-155 LICENSE DPR-6 i

Supplement Revised Defueled Technical Specification Presenting Proposed Revisions Submitted June 3,1999 l I

l l

l 1

l I

9906090073 990603 PDR ADOCK 05000155 P PDQ

r 1

TABLE OF CONTENTS DEFUELED TECIINICAL SPECIFICATIONS FOR BIG ROCK POINT PLANT l SECTION DESCRIPTION PAGE j 1.0 D E FINITION S . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............ 1-1 1.1 Action...................................... .... 1-1 1.2 Certified Fuel Handler . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.3 Channel Calibration .................................. 1-1 1.4 Channel Check .................................... 1-1 l 1.5 Channel Functional Test .......... ................... 1-1 1.6 Containment Closure . . . . . . . ........................ . 1-1 1.7 Di rect Path . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.8 Fuel H andling . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.9 Im med iately . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.10 Monitoring Station . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.11 Offsite Dose Calculation Manual (ODCM) . . . . . . . . . . . ........ 1-2 l 1.12 Operable - Operability ................................ 1-3 1.13 Process Control Program (PCP) . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 l 1.14 Reportable Event ................ ................... 1-3 1.15 Shift ................... ..... .................. 1-3 ;

,u m _ m _,__. , , ,

1.1 u um uvuuum,y ..... .......... .................... 1s 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEMS SETTINGS , . . . 2-1 l

3/4 LIMITING CONDITIONS FOR OPERATION & SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . ............... 3/4-1 3/4.0 APPLICABILITY . . . . . . . . . . . . . . . . . . . . . . .............. 3/4-1 l 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 ANDLING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 AMENDMENT NO. 120

l

  • TABLE OF CONTENTS DEFUELED TECHNICAL SPECIFICATIONS BIG ROCK POINT PLANT SECTION DESCRIPTION PAGE 5.0 DESIG N FEATURES ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1 E t S IT E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 T
  • s...,t umouvumm

__.____.1 uummm,'w ..............

n _ _ _ _ _1_

. . . .. . . . . . ..s, E 1 r ,u u n u s. , ,e , nu,u Y*1#'* T Yn T* f f n n f* *

  • _

o m. m oy 1E__

. . . . . . . . . . . . . ..........s't E d 5.2 STORAGE AND INSPECTION OF SPENT FUEL . . . . . . . . . . . . . 5-1 5.2.1 Criticality . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 5-1 5.2.2 Water I2 vel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 5-1 5.2.3 Cool i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2.4 Capac ity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-3 5.3 REACTOR ....................................... 5-3 5.3.1 Statu s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.3 6.0 ADMINISTRATIVE CONTROLS . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 6.1 RESPONSIBILITY AND AUTIIORITY . . . . . . . . . . . . . . . . . . . . 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 ANIZATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 6.2.1 Reporting Relationships . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 l 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 TRAI NI N G . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 u re s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 ,

6.6.1.1 Scope . . . ................................. 6-5 l

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 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 ii AMENDMENT NO. 120

\

BIG ROCK POINT DEFUFI Fn TECHNICAL SPECIFICATIONS 1.0 DEFINITIONS .

1.12 OPERABIF - OPERABILITY 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. i

'1.14 REPORTABLE EVENT l l

1 A REPORTABLE EVENT is any of those conditions specified as reportable in i Specification 6.9. j 1.15 SHIFT A SHIFT shall be the duration of the normal work period, which viill be either 8 or i 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 l determining the maximum allowable time between surveillances, when the specified i 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, i

1.10 SITI' "OUNDA"Y j Tre :;;T:: "OUNnA"Y is ;:.a; ;;re wyora w:get. ;te : ara is oot owred. :caud, or oik s.x cu m,v;;cd t,y its ;;cc..a c.

1-3 AMENDMENT NO. 120

i EIG ROCK POINT DEFUEISD TECIINICAL SPECIFICATIONS 5.0 DESIGN FEATURES

  • 5.1 ' SITE 5.1.1 LOCATION AND COUNDARIES i

The plant site sitc, censisting of er,i,sexinietely 500 ecrcs, is located m '

Charlevoix County, Michigan, about 4 miles northeast of Charlevoix, Michigan, and about 11 miles west of Petoskey, Michigan. The reercsi leraisidc i,iogity l lirs is ebout 2680 fcci ermi the iserc5i showlirs progriy lire is eboei 200 fcci freniihc conteinns.it sidsrc (reference Figuic 5.1-It-5.2 STORAGE AND INSPECTION OF SPENT FUEL 1

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. ,

1

- The fuel loading per axial centimeter of any assembly placed in the Spent Fuel I Pool shall be less than or equal to a maximum of 28.3 grams of U2 " or equivalent.

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 AMENDMENT NO. 120

BIG ROCK POINT DEFUEI FD TECIINICAL SPECIFICATIONS 5.0 DESIGN FEATURES Fignic 5.1-1, DRP Sitc Map v 2 c .

bA A< n "p

/ .

'r' ey g

~

'ig

, l s.

f x r<l 1i .

NiN e \ a 5l)g v) _

e 5

a

, N f tf f \

2

.. SUN M?.r\

1 9\ . m ,

I

?

\.

44 2

\$ _

.8 5  ; ;qw E '%?

t

.~.

zz

/l' L

i

/ 5-2 AMENDMENT NO. 120 1

1 l

BIG ROCK POINT DEFUEIID TECHNICAL SPECIFICATIONS 6.0 ' ADMINISTRATIVE CONTROIS

e. Determination of cumulative and projected dose contributions from J 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 j treatment systems to ensure that the appropriate portions of these l 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 l from the site to areas at or beyond the site boundary (5cc Figsrc 5.1-1) {

shall be limited to the following: j (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 l l

(b) For tritium and for all radionuclides in particulate form with l halflives 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 quarterly air doses resulting from noble gases released in gaseous i effluents from the facility to areas beyond the SITE DOUNDARY; 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 l in particulate form with half lives greater than 8 days in gaseous J effluents released to areas at or beyond the site boundary (scc Figsrc 5-M) shall be limited to the following: l (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 6-9 AMENDMENT NO. 120

BIG ROCK POINT DEFUEIED TECHNICAL SPFCIFICATIONS 6.0 ADMINISTRATIVE CONTROLS any organ.

6.6.2.6 Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the j environs of the facility. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and i (2) verification of the accuracy of the effluent monitoring program and I 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:

)

a. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology l

and parameters in the ODCM;  !

b. A Land Use Census to ensure that changes in the use of areas at and beyond the SITI: DOUNDARY site boundary are identified and that modifications to the monitoring program are made if required by the results of this census, or alternatively, that critical receptors are assumed to exist at the SITE DOUNDARY 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.

I 6.6.2.7 Fire Protection Procram 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 Procram 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 l irradiated fuel or result in unplanned or unmonitored radioactive material release.

6-10 AMENDMENT NO. 120 i

ATTACliMENT 2 CONSUMERS ENERGY COMPANY BIG ROCK POINT PLANT DOCKET 50-155 LICENSE DPR-6 Supplement Revised Defueled Technical Specification Presenting Proposed Pages Submitted June 3,1999

~

l TABLE OF CONTENTS i DEFUELED TECIINICAL SPECIFICATIONS FOR BIG ROCK POINT PLANT l

SECTION DESCRIPTION PAGE 1.0 DEFINITIONS . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .......... 1-1 1.1 Action . . . . . . . . . . . . . . . . . . ............. ........ 1-1 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 Contaimnent Closure . . . . . . . . . . . . . . . . . ................ 1-1 1.7 Direct Path . . . . . . . . . . . .......................... 1-2 1.8 Fuel Ha ndling . . . . . . . . . . . . . . . . . . . . . . . . . . ........... 1-2 1.9 Immed iately . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... ... 1-2 1.10 Monitoring Station . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 l 1.11 Offsite Dose Calculation Manual (ODCM) . . . .............. 1-2 1.12 Operable - Operability ............................... 1-3 1.13 Process Control Program (PCP) . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 l 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 REQUIREMENTS . . . . . . . . . . . . . . . . . . ........ ........ . 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 ANDLING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 l l

1 l

As Proposed '

i AMENDMENT NO. 120 l

l i

\

TABLE OF CONTENTS l DEFUELED TECHNICAL SPECIFICATIONS BIG ROCK POINT PLANT SECTION DESCRIPTION PAGE 5.0 DESIGN FEATURES .................................... 5-1 5.1 S IT E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2 STORAGE AND INSPECTION OF SPENT FUEL . . . . . . . . . . . . . 5-1 l 5.2.1 Criticality . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2.2 Water Level . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2.3 Coo l i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2.4 Capac ity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -3 5.3 REACTO R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -3 5.3.1 S tatu 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 TRAI N I N G . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 6.6.2 Programs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... 6-6 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 As Proposed ii AMENDMENT NO. 120

1 l

' BIG ROCK POINT DEFURI.Rn TECHNICAL SPECIFICATIONS 1.0 ' DEFINITIONS OPERABLE - OPERABII ITY

l. *1.12 I

A system, subsystem, train,' component or device shall be OPERABLE or have l OPERABILITY when it is capable of;>erforming 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.

l 1.14 REPORTABI.R EVENT A REPORTABLE EVENT is any of those conditions specified as reportable in Specification 6.9.

. 1.15 SHIFT l l 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 i

- detcrmining the maximum allowable time between surveillances, when the specified i 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 l General Manager at that time.

l i

i l

i l

l-As Proposed 1-3 AMENDMENT NO. 120

1 BIG.. ROCK POINT DEFUEIED TECHNICAL SPECIFICATIONS

'5.0 DESIGN FEATURES

' 5.1 SIIE The plant site is located in Charlevoix County, Michigan, about 4 miles northeast of Charlevoix, Michigan, and about 11 miles west of Petoskey, i Michigan.

5.2 STORAGE AND INSPECTION OF SPENT FUEL 5.2.1 CRITICALITY Spent fuel is stored in spent fuel storage racks which are Osigned and shall be maintained with sufficient center-to-center distance between stored fuel assemblies to ensure a k,n 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 j Pool shall be less than or equal to a maximum of 28.3 grams of U235 or '

equivalent.

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 i unborated water. f

)

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 rack.s placed in the Spent Fuel Pool allows for j adequate circulation of water to prevent localized pool boiling. j l

As Proposed 5-1 AMENDMENT NO. 120

l BIG ROCK POINT DEFUEISD TECHNICAL SPECIFICATIONS l

5.0 DFSIGN FEATURES I l

1 I

FIGURE DELETED I

I i

i i

l l

As Proposed 5-2 AMENDMENT NO. 120

BIG ROCK POINT DEFUELFn TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS .

e.- Determination of cumulative and projected dose contributions'from radioactive ef0uents for the current calendar quarter and current

alendar 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 ensum 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 (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 j and quarterly air doses resulting from noble gases released in gaseous I 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 halflives 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 I

As Proposed 6-9 AMENDMENT NO. 120 i

BIG ROCK POINT DEFURI RD TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS any organ.

6.6.2.6 Radiological Envirormental 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:

a. Monitoring, sampling, analysis, and reporting of radiation and radionuclides 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 monitoring 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 i

A fire protection program meeting the requirements of 10 CFR 50.48(f) shall i be established, implemented, and maintained.

6.'6.2.8 Cold Wenther 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.

l l

As Proposed l 6-10 AMENDMENT NO. 120

Retrieved from "https://kanterella.com/w/index.php?title=ML20195D045&oldid=3041571"