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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20199H2771999-01-20020 January 1999 Proposed Tech Specs Changing Table 3.3.8.1-1 to Revise Allowable Values for Degraded Voltage Relay Reset & Dropout Setpoints as Specified Per Items 1.c,1.d,2.c & 2.d ML20196A0941998-11-20020 November 1998 Proposed Tech Specs Re Div 3 Diesel Generator Droop Issue ML20196A1501998-11-20020 November 1998 Revised Pages Constituting Rev 3 to CPS TS Bases,Consisting of Pages Annotated with Rev Numbers 3-1,3-2,3-3,3-4 & 3-5. Changes to Text Identified with Rev Bars.No Rev Bars Included for Changes to Format ML20155A5631998-10-23023 October 1998 Proposed Tech Specs LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)1998-10-0505 October 1998 Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7) ML20153F4201998-09-23023 September 1998 Corrected Proposed Tech Specs Bases Page B 3.8-94 Re SVC Protection Sys ML20237E4191998-08-24024 August 1998 Proposed Tech Specs SR 3.8.1.17,revising Acceptance Criteria for Meeting ready-to-load Requirement for Division 3 DG ML20237C3501998-08-17017 August 1998 Proposed Tech Specs Partially Reducing Load at Which DGs Are Required to Be Tested Per Affected SRs in Order to Reduce Stress & Wear on Machines While Still Sufficiently Challenging Machines to Confirm Operability ML20236X0071998-07-31031 July 1998 Proposed Tech Specs,Revising Acceptance Criteria of SRs 3.8.1.7,3.8.1.12,3.8.1.15 & 3.8.1.20 ML20216B1511998-05-0404 May 1998 Proposed Tech Specs Pages,Incorporating Requirements for Static Var Compensator (SVC) Protection Sys Under New TS ML20217M3351998-04-27027 April 1998 Proposed Tech Specs Re Mgt Changes Occurring in Operations Organization at Plant ML20212C6951997-10-23023 October 1997 Proposed Tech Specs,Constituting Rev 2 to CPS TS Bases.Rev Consists of Pages Annotated W/Rev Numbers 2-1 Through 2-14 ML20149J1701997-07-22022 July 1997 Proposed Tech Specs Requesting Exemption to 10CFR50,App a, General Design Criteria to Allow Operation W/Identified Offsite Circuit Condition U-602714, Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation1997-04-0101 April 1997 Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation ML20133F2051997-01-0707 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A5951996-12-13013 December 1996 Proposed TSs Re Transfer of Minority Ownership ML20134M3181996-11-19019 November 1996 Proposed Tech Specs Revising Table 3.3.8.1-1, Loss of Power Instrumentation, by Dividing Function, Degraded Voltage - 4.16 Kv Basis & Degraded Voltage Dropout - 4.16 Kv Basis, re-numbering Items in Table & Revising Associated Notes ML20128K0711996-10-0404 October 1996 Proposed Tech Specs 3.3.8.1,adding Action Statement & Note Requiring Restoration of Inoperable Degraded Voltage Relays, Rev to Table 3.3.8.1-1 ML20134C1631996-09-20020 September 1996 Proposed Tech Specs,Revising TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling1996-08-15015 August 1996 Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling ML20116N1101996-08-15015 August 1996 Proposed Tech Specs 2.0, Safety Limits, Changing TS to Incorporate Revised SLMCPR as Calculated by GE for CPS Cycle 7 U-602619, Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses1996-08-15015 August 1996 Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses ML20113E7261996-06-28028 June 1996 Proposed Tech Specs,Allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable U-602591, Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures1996-06-21021 June 1996 Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures ML20108C9431996-05-0101 May 1996 Proposed Tech Specs,Implementing 10CFR50,App J - Option B ML20107L0011996-04-19019 April 1996 Proposed Tech Specs,Revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met ML20100H7741996-02-22022 February 1996 Proposed Tech Specs,Proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier ML20100H7901996-02-22022 February 1996 Proposed Tech Specs,Deleting SR 3.3.8.1.1 Which Requires Channel Check for Loss of Power Instrumentation & Changing TS Table 3.3.8.1-1 to Change Allowable Value for Degraded Voltage Function from 3762V & 3832V to 3876V ML20100H8171996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv ML20100H8411996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20095G4791995-12-14014 December 1995 Proposed Tech Specs 3.4.2, Flow Control Valves Re Proposed Deletion of Average Rate of Movement Verification Requirement ML20095G5141995-12-14014 December 1995 Proposed Tech Specs 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation to Eliminate Periodic Response Time Testing of Analog Trip Modules ML20095G6401995-12-14014 December 1995 Proposed Tech Specs Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys ML20094D2141995-10-27027 October 1995 Proposed Tech Specs,Consisting of Changes to TS 5.2.2.e to Revise Requirements for Controls on Working Hs of Unit Staff That Perform SR Functions ML20094D2031995-10-27027 October 1995 Proposed Tech Specs,Consiting of Changes to TS 3.1.3 to Include 25% Surveillance Overrun Allowed by LCO 3.0.2 Into Allowances of Surveillance Notes for Control Rod Notch Testing Per SR 3.1.3.2 & SR 3.1.3.3 ML20085N0621995-06-23023 June 1995 Proposed Tech Specs Bases,Per TS 5.5.11, TS Bases Control Program ML20085F5961995-06-0909 June 1995 Proposed Tech Specs,Incorporating Description of Exclusion Area Boundary ML20085J9701995-02-16016 February 1995 Proposed Tech Specs Reflecting Enforcement Discretion Re TS LCO for Div 2 DC Electrical Power Sources ML20078Q2931995-02-14014 February 1995 Proposed Tech Specs 3.8.2, AC Sources-Shutdown, 3.8.5, DC Sources-Shutdown & 3.8.8, Inverters-Shutdown ML20078N2701995-02-10010 February 1995 Proposed TS 3.3.2.1, Control Rod Block Instrumentation ML20078E9701995-01-27027 January 1995 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements U-602372, Proposed Tech Specs Requesting Complete Rev of CPS TS for Conversion to Improved TS Per Guidance Provided by NUREG-1434, Improved BWR-6 TS, Rev 0,dated Sept 19921994-11-18018 November 1994 Proposed Tech Specs Requesting Complete Rev of CPS TS for Conversion to Improved TS Per Guidance Provided by NUREG-1434, Improved BWR-6 TS, Rev 0,dated Sept 1992 ML20076G2721994-10-14014 October 1994 Proposed Tech Specs,Allowing Drywell Bypass Leakage Test to Be Performed at five-yr Interval ML20072E6701994-08-12012 August 1994 Proposed Tech Specs Eliminating Requirement to Perform Manual Testing of solid-state Logic Independently from self-test Sys ML20072E6191994-08-12012 August 1994 Proposed Tech Specs Allowing Drywell Bypass Leakage Rate Tests to Be Performed at Intervals as Long as Ten Years ML20072C1251994-08-0505 August 1994 Proposed Tech Specs Re Requirement for Accelerated Testing of Div 1 DG ML20069Q3851994-06-27027 June 1994 Proposed Tech Specs 3/4.4.3.1, Reactor Coolant Sys Leakage- Leakage Detection Sys ML20069N3201994-06-16016 June 1994 Proposed Tech Specs Adding -89 After ASTM D3803 in Testing Requirements Specified for SGTS & MCR Filter Sys Charcoal & Changing Test Temp for Testing SGTS Charcoal from 80 C to 30 C ML20069K8191994-06-13013 June 1994 Proposed Tech Specs to Allow 36-inch Isolation Valve Leak Measurement Be Performed at Least Once Per 18 Months, Providing Valves Remain Closed During Period ML20070N6951994-04-26026 April 1994 Proposed Tech Specs Adopting Changes Recommended in NRC Re NUREG-1434 1999-01-20
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20209E0551999-07-0606 July 1999 1999 Business Plan ML20206F2231999-04-27027 April 1999 NRC Manual Chapter 0350 Restart Action Plan for Clinton Power Station ML20199H2771999-01-20020 January 1999 Proposed Tech Specs Changing Table 3.3.8.1-1 to Revise Allowable Values for Degraded Voltage Relay Reset & Dropout Setpoints as Specified Per Items 1.c,1.d,2.c & 2.d ML20206E6281998-12-31031 December 1998 Rev 17 to ODCM for Clinton Power Station ML20196A0941998-11-20020 November 1998 Proposed Tech Specs Re Div 3 Diesel Generator Droop Issue ML20196A1501998-11-20020 November 1998 Revised Pages Constituting Rev 3 to CPS TS Bases,Consisting of Pages Annotated with Rev Numbers 3-1,3-2,3-3,3-4 & 3-5. Changes to Text Identified with Rev Bars.No Rev Bars Included for Changes to Format ML20155A5631998-10-23023 October 1998 Proposed Tech Specs LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)1998-10-0505 October 1998 Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7) ML20153F4201998-09-23023 September 1998 Corrected Proposed Tech Specs Bases Page B 3.8-94 Re SVC Protection Sys ML20237E4191998-08-24024 August 1998 Proposed Tech Specs SR 3.8.1.17,revising Acceptance Criteria for Meeting ready-to-load Requirement for Division 3 DG ML20237C3501998-08-17017 August 1998 Proposed Tech Specs Partially Reducing Load at Which DGs Are Required to Be Tested Per Affected SRs in Order to Reduce Stress & Wear on Machines While Still Sufficiently Challenging Machines to Confirm Operability ML20236X0071998-07-31031 July 1998 Proposed Tech Specs,Revising Acceptance Criteria of SRs 3.8.1.7,3.8.1.12,3.8.1.15 & 3.8.1.20 ML20236Q4661998-07-17017 July 1998 Rev 0 to Procedure 2800.93, Emergency Reserve Auxiliary Transformer Integrated Test ML20236Q4651998-07-17017 July 1998 Rev 0 to Procedure 2800.92, Emergency Reserve Auxiliary Transformer Integrated Test ML20236Q4571998-07-17017 July 1998 Rev 0 to Procedure 2800.91, Emergency Reserve Auxiliary Transformer Test ML20216B1511998-05-0404 May 1998 Proposed Tech Specs Pages,Incorporating Requirements for Static Var Compensator (SVC) Protection Sys Under New TS ML20217M3351998-04-27027 April 1998 Proposed Tech Specs Re Mgt Changes Occurring in Operations Organization at Plant ML20203D5651998-02-19019 February 1998 Plan for Excellence ML20212C6951997-10-23023 October 1997 Proposed Tech Specs,Constituting Rev 2 to CPS TS Bases.Rev Consists of Pages Annotated W/Rev Numbers 2-1 Through 2-14 ML20149J1701997-07-22022 July 1997 Proposed Tech Specs Requesting Exemption to 10CFR50,App a, General Design Criteria to Allow Operation W/Identified Offsite Circuit Condition ML20149H8991997-06-30030 June 1997 CPS Long Term Improvement Plan U-602714, Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation1997-04-0101 April 1997 Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation ML20133F2051997-01-0707 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A5951996-12-13013 December 1996 Proposed TSs Re Transfer of Minority Ownership ML20134M3181996-11-19019 November 1996 Proposed Tech Specs Revising Table 3.3.8.1-1, Loss of Power Instrumentation, by Dividing Function, Degraded Voltage - 4.16 Kv Basis & Degraded Voltage Dropout - 4.16 Kv Basis, re-numbering Items in Table & Revising Associated Notes ML20128K0711996-10-0404 October 1996 Proposed Tech Specs 3.3.8.1,adding Action Statement & Note Requiring Restoration of Inoperable Degraded Voltage Relays, Rev to Table 3.3.8.1-1 ML20134C1631996-09-20020 September 1996 Proposed Tech Specs,Revising TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20116N1101996-08-15015 August 1996 Proposed Tech Specs 2.0, Safety Limits, Changing TS to Incorporate Revised SLMCPR as Calculated by GE for CPS Cycle 7 U-602619, Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses1996-08-15015 August 1996 Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling1996-08-15015 August 1996 Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling ML20137A1101996-08-14014 August 1996 Rev 19 to App V Second 10-Yr Interval Pump & Valve Testing Program Plan ML20137A1021996-07-10010 July 1996 Rev 5 to App IV Second 10-Yr Interval Inservice Exam Plan ML20113E7261996-06-28028 June 1996 Proposed Tech Specs,Allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable U-602591, Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures1996-06-21021 June 1996 Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures ML20108C9431996-05-0101 May 1996 Proposed Tech Specs,Implementing 10CFR50,App J - Option B ML20107L0011996-04-19019 April 1996 Proposed Tech Specs,Revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met ML20100H8411996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20100H7901996-02-22022 February 1996 Proposed Tech Specs,Deleting SR 3.3.8.1.1 Which Requires Channel Check for Loss of Power Instrumentation & Changing TS Table 3.3.8.1-1 to Change Allowable Value for Degraded Voltage Function from 3762V & 3832V to 3876V ML20100H8171996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv ML20100H7741996-02-22022 February 1996 Proposed Tech Specs,Proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier ML20095G5141995-12-14014 December 1995 Proposed Tech Specs 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation to Eliminate Periodic Response Time Testing of Analog Trip Modules ML20095G6401995-12-14014 December 1995 Proposed Tech Specs Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys ML20095G4791995-12-14014 December 1995 Proposed Tech Specs 3.4.2, Flow Control Valves Re Proposed Deletion of Average Rate of Movement Verification Requirement ML20117E3001995-11-0606 November 1995 Rev 18 to App V Pump & Valve Testing Program Plan ML20094D2031995-10-27027 October 1995 Proposed Tech Specs,Consiting of Changes to TS 3.1.3 to Include 25% Surveillance Overrun Allowed by LCO 3.0.2 Into Allowances of Surveillance Notes for Control Rod Notch Testing Per SR 3.1.3.2 & SR 3.1.3.3 ML20094D2141995-10-27027 October 1995 Proposed Tech Specs,Consisting of Changes to TS 5.2.2.e to Revise Requirements for Controls on Working Hs of Unit Staff That Perform SR Functions ML20085N0621995-06-23023 June 1995 Proposed Tech Specs Bases,Per TS 5.5.11, TS Bases Control Program ML20085F5961995-06-0909 June 1995 Proposed Tech Specs,Incorporating Description of Exclusion Area Boundary ML20087J5691995-05-17017 May 1995 Rev 17 to App V, Pump & Valve Testing Program Plan of CPS ISI Program Manual ML20085J9701995-02-16016 February 1995 Proposed Tech Specs Reflecting Enforcement Discretion Re TS LCO for Div 2 DC Electrical Power Sources 1999-07-06
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Attachment 3 to U-602591 PS-95-016 Page1of5 !
Attached Marked-Up Pages of the Technical Specifications 9606260063 960621 1 DR ADOCK 0500 C___
. Attachment 3 to U-602591 PS-95-016 Page 2 of 5
- - High Radiation Area
- 5.7 5.0 ADMINISTRATIVE CONTROLS c,g, m'h [qggg 5.7 High Radiation Area l 4
di ursuant to 1.0 C 20, paragrap 1601(c), in lieu the requirements 10 CFR 20.1601 , each high radi on area, as ,
defined in CFR 20, in wh an individual co receive a deep ;
dose equi lent > 100 are ut < 1000 mrem i one hour (at 30 cm), :
shall barricaded and onspicuously pos as a high radiation area nd entrance the to shall be cont led by requiring is ance of a Radi on Work Permit WP). Individuals qual ed ,
radiation pro tion procedures .g., radiation prot ton j technicians) or ersonnel conti sly escorted by suc ,
individuals be exempt fro e RWP issuance requJ ment during the perfo nce of their ass ed duties in high r diation areas in which n individual cou receive a deep dos equivalent :s 3000 mrem one hour (at 30 ), provided they ar otherwise followin pla radiation protec on procedures for ry into such high j r iation. areas.
Any individual o group of individu3 1s permitted to ente - such l areas shall b rovided with, or (companied by, one more of the followl .
- a. A diation monitori device that conti usly indicates e radiation dose ate in the area.
. A radiation m toring device tha continuously integrat the radiati dose rate in the ea and alarms when a fesetJ '
integrat dose is received. ntry into such areas th this itoring device ma e made after the dose ate lev s in the area have een established and pe onnel are re of them.
c An individual qu fied in radiation prot tion procedures with a radiatio dose rate monitoring d ice, who is l
/ responsible f providing positive co rol over the activities ithin the area and shal perform periodic radiatio surveillance at the frej ency specified by t radiati n protection supervisio 5.7.2 In d ition to the requirements of Specification 5. , , areas in \
wp h an individual could r,e(eive a deep dose equJ alent 1000 mrem in one hour (at 30 cm) shall be provided with locked or continuously guarded / doors to prevent unayttiorized entry and the keys shall be majn'tained under the admD(istrative control of the shift supervisof on duty or radiatio Vprotection supervision.
Doors shall remgn locked except duri eriods of access by personnel unpef an approved RWP that all specify the dose rate (continued)
CLINTON 5.0-20 Amendment No. 95
Attachmsnt 3 to U-602591 PS-95-016 Page 3 of 5
. High Radiation Area 5.7 5.7 High Radiation Area i
l 5.7.2 (continued) le s in the immediat ork areas. If an dividual could ceive a de'ep dose quivalent > 3000 mr in one hour (at 30 cm),
the RWP shall al specify the maximu llowable stay times for individuals i ose areas. In liep of the stay time
{
I specificatip TV of thesurveil cameras) continuous RWP, direct ance may bepfmade remote (such by personne as closed ci u qualif) tid in radiation prot on procedures to provide p itive exp sfure control over the,a tivities being performed wi in the
- a. Individuals qualified in radiation protecticri rocedures (e.g., radiation protection technicians) or perse,n n 1 continuously escorted'by such Jn'dividuals may be exempt from Ahe RWP issuance requirement dur 69 the performance of their pifigned duties in high radiati areas in which an individuaVcould receive a deep l dose equi ent s 3000 mrem in one hou (at30cm),providedthe are oth ise following plant radia protection procedures fo1 i entry to such high radiation ar . l l
5.7.3 I addition to the requiremeJ of Specification 5.7.1, ividu al reas in which an individu r could receive a deep dose quivalen ;
2: 1000 mrem in one hour 30 cm), accessible to per annel, that areas such as reactor con inment, wher 1
are located within la no enclosure exists r purposes of locking, or at cannot be continuously gua , and where no enclosure c be reasonably constructed ar the individual area, that ndividual area shal ;
be' barricade d conspicuously posted, an a flashing light shall be activate as a warning device. l l
CLINTON 5.0-21 Amendment No. 95
Attachm2nt 3 to U-602591 PS-95-016 g$g g 7" Page 4 of 5 5,7.1 Pursuant to 10 CFR 20, paragraph 20.1601(c), in lieu of the requirements of 10 CFR 20.1601(a), each high radiation area, as defined in 10 CFR 20, in which an individual could receive a deep dose equivalent > 100 mrem in one hour (at 30 cm), shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP) or equivalent.
Any individual or group ofindividuals permitted to enter such areas shall be provided with, or accompanied by, one or more of the following:
- a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.
l
- b. A radiation monitoring device that continuously integrates the radiation !
dose rate in the area and alarms when a preset integrated dose is received. j Entry into such areas with this monitoring device may be made after the !
dose rates in the area have been determined and personnel have been made l knowledgeable of them. ,
l
- c. An individual qualified in radiation protection procedures (e.g., a radiation l protection technician or supervisor) with a radiation dose rate monitoring device. This individual shall be responsible for providing positive radiation protection control over the activities within the area and shall perform l
periodic radiation surveillance at the frequency specified by radiation protection supervision.
5.7.2 In addition to the requirements of Specificatica 5.7.1, high radiation areas in which an individual could receive a deep dose equivalent 21000 mrem in one hour (at 30 cm) shall be provided with locked or continuously guarded doors to prevent unauthorized entry. The keys to such locked doors shall be administratively controlled by the shift supervisor or radiation protection supervisor (or respective designee). Doors shall remain locked except during periods of access by personnel under an approved RWP or equivalent.
Individual high radiation areas in which an individual could receive a deep dose equivalent 21000 mrem in one hour (at 30 cm), accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists for enabling locking, or that is not continuously guarded, and where no lockable enclosure can be reasonably constructed around the individual area, shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device..
t.
?
. Attachment 3 to U-602591 PS-95-016 Page 5 oE S
. /Afjg R'f" ( Conbh stGd) 5.7.3 In addition to requirements of Specification 5.7.1 and 5.7.2 for high radiation areas, if an individual could receive a deep dose equivalent > 3000 mrem in one hour (at 30 cm), the RWP or equivalent shall also specify the maximum allowable stay time or dose (on an alarming dosimeter) for individuals ia those areas. In lieu of the stay time or dose specification of the RWP or equivalent, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
5.7.4 Individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals may, for the performance of their assigned duties in high radiation areas in which an individual could receive a deep dose equivalent s; 3000 mrem in one hour (at 30 cm), be exempt from the requirements of Specifications 5.7.1 and 5.7.2 for issuance of an RWP or equivalent provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.
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