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 1992ML20078L899 |
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Site: |
Clinton |
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Issue date: |
11/18/1994 |
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From: |
ILLINOIS POWER CO. |
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To: |
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Shared Package |
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ML20078L887 |
List: |
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References |
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RTR-NUREG-1434 U-602372, NUDOCS 9412010198 |
Download: ML20078L899 (11) |
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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
[Table view] |
Text
- - .
i Enclosure 2 to U-602372 sure 2 to U-60' toe
' Page 1 of 5 isectio o 5 of 476 C
fl ASecondary Containment} 3.6.4.1 SURVEILLANCE REQUIREMENTS (continued)
FREQUENCY SURVEILLANCE 3cor in ckd) Qu% &
SR 3.6.4.1.3
& Verif Ot\
secondary containment F 31 days
-- --- " -- is closed, except wher, the g/ dorig normal acce:s and exit cp[eaiag it beir.;
r-thEi. et lee 5L vike:6 fee deer :h entry he ein b3.6.4.1.4 Verify each standby gas treatment (SGT) 118hnthsoI _q j subsystem will draw down the Tsecondary a STAGGERED ,
TEST BASIS containment}#t o 290.25 Finch of vacuum water gaugeG : ON_hs cM9 du f e. 3 qMJ-1,]~ g4
(\dAhip%Rjf %wedMU) 4i k byt Verify each SGT subsystem can maintain 18[monthson SR 3.6.4.1.5 a '0.255] inch of vacuum water gauge in a STAGGERED ainment}Worihourat TEST BASIS hl C . 2 f> teg{ secondary a flow rate 4 006 cfm.
kW 4
__a N.
T %
F 4 0RS 3.lo.?.I-I 3.6-46 Rev. C d 9/28/92-
-BWR/6-STS -
9412cic>i9s 94111a PDR ADOCK 05000461 P PDR
Enclosure 2 to U-602372 -
g, ,
_ y6 Page 2 of 5 3,, , 257 J
DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.4.6 ---
N Es---------------
This Surveil nce shall not b -K g3p performe n MODE 1, 2, o .
- 2. C it may be take or unplanned events that-sati fy this SR.
pn is sero I 4 '2_ f 18 months Vi rify eachdreq]uwe4h supplies a f440 battery charper
- 3) e hoursp @ amps at 2[250 '"N2 "D3 V for ---
~
h f au cael M sooa N O 4 be+k tf charfen sWI 'U q
E 100 orsb5 o +)_ t 2- 5 J fts t.- % *T bovpf, SR 3.8.4.7 -------------------NOTES-------------------
- 1. SR 3.8.4.8 may be perfonned in lieu of SR 3.8.4.7 once per 60 months.
- 2. This Surveillance shall not be C4 performed in MODE 1, 2, or 3./haene,])
it may be taken for unplanned events that satisfy this SR.
g Verify battery capacity is adequate to 18 months P supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.
(continued)
(
-BWR/6-Si9 3.8-28 Rev. 0,-09/28/42-t.
Enclosure 2lto U-602372. .
i c Page 3 of.5 I ure 2 to U4
]
sectio i
4 of 257)
Battery Cell 7araihefes a -
3.8.6 ;
3.8 ELECTRICAL POWER SYSTEMS 3.8.6 ' Battery Cell Parameters LCO 3.8.6 Battery cell parameters for the vision 1, 2, batteries shall be within the-Geiepr.,
@ i Table 3.8.6 1.
.Hrsy APPLICABILITY: When associated .0 Ol::Pical p0uer subsyste=5 2rz required to be OPERABLE.
ACTIONS l
...........................__....-.--NOTE------------------------------------- i Separate Condition entry is allowed for each battery.
CONDITION REQUIRED ACTION COMPLETION TIME l
>S A. One or more battoies A.1- Verify pilot cell I hour with one or more electrolyte level and ,
battery cell float voltage meet 1 parai *ters not within Table 3.8.6-1 limits -
, Category C *aha -.
auft 32.b-1 z, g*
Ccdegor y A o~B Ano .
01 -
A.2 Verify battery cell 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> parameters meet 'Afjp_
Table 3.8.6-1 Category C vehes. O *'CC L.,- s.
fee AR
'7 days er ca//en A.3 Restore battery cell 31 days ;
parameters to Category A and B limits of r Table 3.8.6-1.
(continued)
(,
- BWR&--ST S- 3.8-32 Rev. O, 49/28/92 -
t !
.)
u 9
y,- - - -,
Enclosure 2 to U-602372 Page 4 of 5
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e
,i.' - .2283 d r les y nsene m .__,
, . (Dj(O dokhbr]h I
<askms aM manv4$ .
~
{.0 ADMINISTRATIVF CONTROLS j ,r2 4 to u .
Section 5 of50 i l
A+ttr Qechnical Specifications (TS) Bases Control Prograh
~
5.5.p @na reuiwQ g>
p 5.C'.i h Changes to the Bases of the dqim
- 1) ep i l m e u der appropriate eR
,g* '
~pec,1prgontrols ca n on s . - m an4-ra . ~ ;cned om d-;ng to ,
i.
r5sC.2- h Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:
A change in the TS incor orate in the license; or usAR
- 2. J/. A change to the gpdated-F5fe r Bases that involves an unreviewed safety es o as defined in 10 CFR 50.59.
A 6.6.3 OC. The Bases Control Program shall contain provisions to ensure that the Bases ar maintained consistent" with th AR.
d;&er
% : N :or.Es Q U @ ,p M r ssee cih% 5
- >a ss.n.5.llA . e. 2. l x
p-5.0.'
Proposed changes R approved that by themeet tne criteria of[to impiementatio )
be reviewed and NRC prior %.
Changes to the Bases implemented without prior NRC approval shall )
be provided the NRC on a frequency consistent with-10 CFR 50.7 (c),
1 T
l I This progmm prov:aes a rneans & p<ocesce !
chan (hCdges CM' dab to h Boses of %ese TecAnicol
@@ l 4WRio did 5.0-16 Rev.- 0, 09/20/'"'
Enclosure 2 to U-602372
. Page 5 of 5
-jPrunrfirrac Programsfand Manuals]
7 % , M 5 *U
'8' h meduri% grams [andManuals CS 5.7.Q.'6 c 14 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued) k y,,
methodo6gy iryIBranc Techn' al Pos Tion (BT ETSB -5,
.- "Postfiated 5dioac ve Re1 ase du to Wast Gas Sys em Leak
- Fr' ure"]. The li uid ra .<aste antitie< shall b determi >d in OCzt i a cordan with tandar Revie Plan, P ction1.7.3,"/otulatedj (adioa ive Rel;_ase du to Tan Failur s"] .
The program shall include: g rrMn conde/nser gas tfeo&rrent Gee
- a. The limits for concentrations of hydrogen .and -exygen-i,n thed .
-[Weste Ces ;ioldttp-System} and a surveillance program to' 1 g
ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the s m is designed to withstand a hydrogen explosion);
T. b survei lance program to ensure that the cantity f radioa ivity con ined in [ ch gas stor ge. tank nd fed s stem] is le than t amount e offgas reatment oc ' into Iu tha would res t in a who e body expo ure of n .5 rem s an individua in an unr tricted ar , in the event of 'an i' u controlle release of he tanks' ntents]; and i
A surveillance program to re that the. quantity of vadicac6W b'f. wed tivity contained i el4 outdooriiduid radwastc- tank [
tnatlarenotsurrou1Ledbylinerf, d y dike,orwallsfcapable
^ of holdirLg the tankW contents and - @othavLtank overflo(and surrounding area drains cohrdcted to the [m_ M (l"' ~3 I_gg .g{piquid Radwaste treatment ystemDsAlc ;; thcn9hc 2 cent-than-the~its t.at would rast'1+ i n-eeneentration: le :
0p23 -it cFa, 20. Appendh-s-Teb4c ::, column 2, at-the-neer+et-pet 41e water supply-and--t-he-neercst ;urfdcc nier supply in l
.an unrertri-ctedarca, in the event-cf an snccntre!!ed D w r +.- , , a. . _ u ., , l L fl0 cur;e6 ' - ~ ~ - '" -"- -- ~ " - - " - ~ ' -
l Olchtdy The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the l Explosive Gas and Storage Tank Radioactivity Monitoring Program i 97$m surveinance f requencies.
ome dBsbep of ey&dmd LNMe %d.;
(continued) 4WRN 5.0-28 Rev. 0, 09/20/9' P
L i Enclosure 3 to U-602372 l Page 1 of 6 PCIVs 3.6.1.3
, \
ACTIONS (continued) !
l CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Isolate the affected 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except penetration flow paths penetration flow path for main steam with one PCIV by use of at least line and excess inoperable, except due one closed and de- flow check to leakage not within activated automatic valves (EFCVs) i limit. valve, closed manual '
valve, blind flange, AND or check valve with flow through the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for valve secured. main steam line i i
AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for l EFCVs AND (continued)
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l CLINTON 3.6-10 Amendment No. 95
-Enclosure 3 to U-602372 Page 2 of'6 Secondary Containment, ,
3.6.4.1 !
. SURVEILLANCE-REQUIREMENTS '(continued)
SURVEILLANCE . FREQUENCY-SR 3.6.4.1.3 Verify one door in each access to 31 days secondary containment is closed, except '
during normal entry and exit.
SR 3.6.4.1.4 Verify each standby gas treatment (SGT) 18 months on i subsystem will draw down the secondary a STAGGERED i containment to 2: 0.25 inch of varsum TEST BASIS i water gauge within the time required by Figure 3.6.4.1-1.
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SR 3.6.4.1.5 Verify each SGT subsystem can maintain 18 months on a 2: 0.25 inch of' vacuum water gauge in the STAGGERED TEST secondary containment for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at a BASIS flow rate s 4400 cfm.
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CLINTON 3.6-45 Amendment No. 95
Enclosure 3 to U-602372
. Page 3 of 6 DC Sources-0perating 3.8.4
.SURV51LLANCEREQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is a 129 V 7 days on float charge.
SR 3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors.
0_R Verify battery connection resistance is s 150 E-6 ohm for inter-cell connections, for inter-rack connections, for inter-tier connections, and for terminal connections.
SR 3.8.4.3 Verify battery cells, cell plates, and 18 months racks show no visual indication of physical damage or abnormal deterioration.
SR 3.8.4.4 Remove visible corrosion, and verify 18 months battery cell to cell and terminal connections are coated with anti-corrosion material.
I SR 3.8.4.5 Verify battery connection resistance is 18 months l s 150 E-6 ohm for inter-cell connections, for inter-rack connections, for inter-tier connections, and for terminal connections.
SR 3.8.4.6 Verify each Division 1 and 2 battery 18 months charger supplies a 300 amps at 2 125 V for a 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and each Division 3 and 4 battery charger supplies a 100 amps at 2 125 V for 2 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. l I
(continued)
CLINTON 3.8-25 Amendment No. 95
. Enclosure 3 to U-602372 Page 4 of 6 Battery Cell Partmeters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 Battery cell parameters for the Division 1, 2, 3, and 4 batteries shall be within the limits of Table 3.8.6-1.
APPLICABILITY: When associated battery is required to be OPERABLE.
ACTIONS
__..........__....__________.--------NOTE-------------------------------------
Separate Condition entry is allowed for each battery.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Verify pilot cell's 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with one or more electrolyte level and battery cell float voltage meet parameters not within Table 3.8.6-1 Table 3.8.6-1 Category Category C limits.
A or B limits.
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A.2 Verify battery cell 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l parameters meet !
Table 3.8.6-1 AND Category C limits.
Once per 7 days thereafter AND A.3 Restore battery cell 31 days parameters to Category A and B limits of Table 3.8.6-1.
(continued)
CLINTON 3.8-30 Amendment No. 95
. Enclosure 3 to U-602372 Page 5 of 6 Programs and Manuds i 5.5
.5.5- Programs and Manuals 5.5.8 Explosive Gas and Storace-Tank Radioactivity Monitorina Proaram (continued)
- b. A surveillance program to ensure that the quantity of radioactive material contained in each outdoor tank that is not surrounded by a liner, dike, or walls capable of holding the tank's contents and that does not have a tank overflow and surrounding area drains connected to the liquid radwaste treatment system is s 10 curies, excluding tritium and dissolved or entrained noble gases.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.
5.5.9 Diesel Fuel Oil Testina Proaram A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:
- a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:
- 1. an API gravity or an absolute specific gravity within limits,
- 2. a kinematic viscosity within limits for ASTM 2D fuel oil, and
- 3. a water and sediment content within limits or a clear and bright appearance with proper color;
- b. Other properties of the new fuel oil are within limits for ASTM 20 fuel oil within 31 days of addition to the storage tanks; and
- c. Total particulate concentration of the fuel oil in the stcrage tanks is s 10 mg/l when tested every 31 days in accordance with ASTM D-2276-88.
(continued)
CLINTON 5.0-14 Amendment No. 95
~
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~ Enclosure 3 to U-602372 l' ' -
Page 6 of 6 p g i
-5.5 5.5 1b ograms and Manuals (continued) 5.5.11 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.
- a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
- b. Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:
- 1. A change in the TS incorporated in the license; or
- 2. A change to the USAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.
- c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the USAR.
- d. Proposed changes that meet the criteria of either Specification 5.5.11.b.1 or Specification 5.5.11.b.2 above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
5.5.12 Ultimate Heat Sink (VHS) Erosion. Sediment Monitorina and Dredaina Program A program to provide maintenance on the VHS in the event inspections of the UHS dam, its abutments, or the VHS shoreline indicate erosion or local instability. This program shall ensure that the VHS is maintained in such a way as to achieve the following objectives:
- a. During normal operation, there will be a volume of water in the VHS below elevation 675 sufficient to receive the sediment load from a once-in-25-year flood event; and i
- b. Still be adequate to maintain the plant in a safe-shutdown condition for 30 days under meteorological conditions of the severity suggested by Regulatory Guide 1.27.
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CLINTON 5.0-16 Amendment No. 95 I,