Proposed Tech Specs 3/4.7.4, Snubbers, Consistent W/ Alternate Schedule for Visual Insp for Changes to Surveillance RequirementsML20082C167 |
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Site: |
Clinton |
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Issue date: |
07/12/1991 |
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From: |
ILLINOIS POWER CO. |
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Shared Package |
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ML20082C164 |
List: |
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References |
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NUDOCS 9107180099 |
Download: ML20082C167 (7) |
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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
- _ _ _ _ _ . _ _ . - . _ _ _ . - __ .- _ _ _ . _ _ _ _ . . _ _ . . _ . _ . - _ .- _- - _ - - . - _
Attachment 2 to U f01855 LS-91*003 in9[y Yase 5 of 11 L1HITiNG CONDITIONS FOR OPERATION AND SURVEll. LANCE RE0UIREMENTS
$ECiION PAGE CONTAINMENT SYSTEMS (Continued)
Table 3.6.6.2-1 Secondary Containment. Ventilation Sys 'm Automatic Isolation 0ampers............................... 3/4 6-69 Standby Gas Treatment System..............................
3/4 6-70 3/4.6.7 ATMOSFHERE CONTROL Containment Hydrogen Recombiner Systems................... 3/4 6-73 Centainment/0rywell Hydrogen Hixing System. . . . . . . . . . . . . . . 3/4 6-75 Prd ry Containment /Drywell Hydrogen Ignition System...... 3/4 6-76 i
3/4.7 PLANT SYS _TEMS 3/4.7.1 SERVICE WATER SYSTEMS Shutdown Service Water System (Loops A, B, C). . . . . . . . . . . . . 3/4 7-1 Ultimate Heat Sink........................................ 3/4 7-2 3/4.7.2 CONTROL ROOM VENTILATION SYSTEM........................... 3/4 7-3 3/4.7.3 REACTOR CORE ISOLATION C001.INA SYSTEH. . . . . . . . . . . . . 3/4 . . . .7-7 y/4._7; 4_- f Cmo m . .... ........
......_.. _1/3J o _
b4Mt.3fI.N-I 6flWOef Vi%V4%p%JeCtioti Intc rval.,.. . ...p ..,,...
. . . . . _ .s M b 13 m.
t 19tre'*. 7. W Fimple'F l aTi Tor ~bnUUDe r WnCT.lona l TeC . . . . . . . . .,
.e 3/4.7.5 SEALED SOURCE CONTAHINATI0H............................... 3/4 7-15 3/4.7.6 MAlH TURBINE BYPASS SYSTEM................................ 3/4 7-17 3/4.7.7 LIQUID STORAGE TAHKS...................................... 3/4 7-18 3/4.7.B MAIH CONDENSER OFFGAS MONITORING Offgas - Explosive Gas Mixture............................ 3/4 7-19 Offgas - Hoble Gas Radioactivity Rate..................... 3/4 7-20 3/4.8 ELECTRICAL POWER SYSTEMS 3/4,8.1 AC SOURCES AC S o u rc e s - Op e ra ti ng. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-1 CllHTON - UNIT 1 xii Amendment No. 40 9107180099 910712 F)DR ADOCK 0".000461 l P PDR t
- LS91-003 Page 6 of 11 N ANT sinEMS 2/4.7.4 SNUEElRS LIMITING CONDITION FOR OPERATION 3.7.4 All snubbers shall be OPERABLE. The only snubbers excluded from the requirements are those installed on non-saf ety related systems 'and then only if
- heir f ailure or f ailure of the system on which they are installed would ha, no adverse ef fect on any safety-related system.
AM L ICABILITY: OPERAT10t4AL CONDITIONS 1, 2, and 3. OPERATIONAL CONDITIONS 4 and 5 f or snubbers located on systems required OPERABLE in those OPERATIONAL CONDITIONS.
ACTION:
With one or more snubbers inoperabic, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specifications 4.7.4.f and 4.7.4 9 on the attached component or declare the attached system inoperable and follow the appropriate ACTION statem.i. for that system.
SURVEILLANCE REOUIREMEllTS 4.7.4 Each snubber shall be demonstrated OPERABLE rmance of the following augmented inservice inspection program the re uirements of Specification 4.0.5. Gainen te
- a. inspection Types As used in this specification ype of snubbe hall mean snubbers of
}
the same design and manuf acturer, irrespective of capacity.
- b. Visual Insoections cateqcritta
~
~
Snubbers are categorized as naccessible or accessible during reactor operation. Each of these 0, Q (inaccessible and g)11hlt)_Rgy A gspectedindeengen,Ql,yact r n M i @ dule t h . t 1
niUVTle-v sua -4nspect4cn-of-eech-type-of--Snub e-sh d " ^^ '-- ---
'"r-t:
- e f te e-4-vonths-but-w4 th4 n-lO-months-of-coseeno4ng-SCWG-CMAAMON. and--
k she44- 4nea ude-e44-snubbees. I f-eH-snubbees-erc f cu',d-OPRAME duri ng->
-Hrst-4ns.s v4ce-v4+ve4 4nspectient-the-second-4nserv4te-visuel--4cspee44a-
) -shah-be-perforned-et-the-f 4est-tefuel4ng-outage. Otherwher-subsNgues =
\ -visual-inspections-shal4-be-performed-4n-eecordance-wHb-the-fv44ains -
! *schecult** dele rrn'ened by Table. 4.*/.4-l. %e vl5nd intpec Co rs
'i nierva\ Cor each type of Snubber sbli be deterrn'.ned based U Pon 4 hc U i e r'A p rovided 'i n Table 9 71.4 -3 1 c\ nd me O rst
[ 'in$pcW.on InicevoA dettem'ined u5'ig %'.5 cr'ilerA W\ M 6d c e n w e pre u s ,ns w om .,nserva os e , u s . -
CLINTON - UNIT 1 3/4 7-9
_. j
- Attachment 2 to U 601855
. LS-91-003 l' age 7 of 11 PLANT SYSTEMS
$NUBEERS SURVEILLANCE REOUIREMENTS (Continued) 4.7.4 (Continued) _ _m - - . _
- % . , Inoperable Snubbers SubsequentVijsu,L g%, per Inspection Period InspectiondeM od*,#
> 0
' . # ' 18 months t 25%
1 12 months i 25%
2, # .- 6 months t 25%
"' p # '3, 4 4 days t 25%
5, 6, 7 62 ay + 25%
Nu % _
8 or more -
31 days 2 a
- c. Visual Inspection Acceptance Criteria __
+
Visual inspections shall ver fy (1)M[no+M5nvi'sibie Waecindica-h*D tions of damage or impairsd OPERABIL W 2 attac3ments to the fou [n- **
dation or supporting structure ar d i J m nd (3) fasteners forlattach
=- auttJ the snubber to the componenl. aiWtW1.he snubber anchorage are CNb=ead OP_MABW Snubbers.wh{c ear inoperable as a result of visual inspec-
'tions.LWay-be__e ermined 4 E5__ for the purpose of establishing the next
^ h=@% visual inspectioriinterval, provided that: (1) th,e cause of the rejection is clearly established and remeAtjkint.,_that_.pQ:' r snubber and for other snubberg) irrespective of(ithe type 3:n _th:t_ ty _ ,that mtiy be generi-cally susceptible; and (2) the affectTed snubber ts runctionally tested in . .
hs Js-J.q,und y ndigo11_andAtermined OPIRABt.f_ per Spt '.t catio_n i 4__.7.4f.i MSERT 2.
owever r -when-e44cid-port-of-e-hydredk ;nubEr ie'f;0nd'.; Y; .~;:.t';. ,
the-snubber-shah-be-dec4ered-inoperet>4e-et.d ::nn:t b: d:t:r'n:d ^"E" ELE ty-functionaHesting-for-the prpie-ef 2;t;bihhh; th; n;;t i: :!
ins pection-i nterv al r---AH-snubbero-connec t:d - t: : 'n:;;nbh ::--- . -
-hydreulic41uid-reservoie-shah 4e-count;d ;; 'n;p;r:bh ;n tb;-;.
_ _ - - - - - -~
- d. Transient Event Inspection An inspection shall be performed of all snubbers attached to sections of systems that have_ experienced unexpected, potentially damaging tran-sients, as determined from a review of operational data or a visual inspection of the systems, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for accessible areas. and witnin 6 months for inaccessible areas following this determination, in additien to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the follow-ing: _(1) manually induced snubber movement; or (2) evaluation of in place snuboer piston setting; or (3) stroking the mechanical snubber thrown its full range of travel.
- - - - - e,m-%.
7 f.
' ~
+ '
l b ,
j - Mhe-inspection d nterval-shall-not4e-lengthened-move-then-ene-+teP=a' : ti m
! *The provisions-of-Specification-4rM-er: ::t-:pp!!::M:_
_ _ _ _ _ ~ _ ~ - -
CLINTON - UNIT 1 3/4 7-10
5 Attachment 2 [
to U.601855 +
LS 91 003 l Page 8 of 10 {
ifiSJ.RT 1 to 4.7.4.c l l
4 shall be classified as unacceptable and may be reclassified [
acceptable. t
(
IESERT.2 to 4.7.4.c !
?
J All snubbers found connected to an inoperable common hydraulic {
fluid reseivoir shall be counted as unacceptabic for determining j the next inspection interval. A review and evaluation shall be- E performed and documented *,o justify continued operation with an unacceptable snubber. If continued operation cannot be justified.
the snubber shall be declared inoperable and the ACTION requirements shall be met.
l i
t h
i I
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Attachment. 2 to U-601855 1.S-91-003 l' age 9 of 11 TABLE 4.7.9-1 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS '
Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval (Notes 1 and 2) (Notes 3 and 6) (Nates 4 and 6) (Notes 5 and 6)__
1 0 0 1 00 0 0 2 100 0 1 -4 150 0 3 8 200 2 5 13 300 5 12 25 400 8 18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 -109 ;
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. . _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . _. _.. ._. . . . _ ._ ___..... ._..-.,_ _.~ ,_ _ . _ _ _ .
Attachment 2 T4bt N il.N "l (Conheed) .
Page 10 of 11 Note 1: The next visual inspection interval for a snubber population or cate-gory size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categor-ics may be examined separately or jointly. However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next-inspection interval for that category.
Note 2: Interpolation between population or category sizes and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or C if thLi integer includes a fractional value of unacceptable snubbers as determined by inter-polation.
Note 3: If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.
Note 4: If the number of unacceptable snubbers is equal to or.less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
Note 5: If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval. However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced 3roportionally by interpoldtion; that is, the previous interval shall >e reduced by d factor that is one-third of tie ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B dnd C.
Note 6: The provisions of Specification 4.0.2 are applicable for all inspec-tion intervals up to and including 48 months.
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Attachment 2 to U-6018$$
1.S91-003 PLANT SYSTEM 5 Pace 11 of 11 BASES 3/4 7.3 REACTOR COPE !$0LATION COOLING SYSTEM (Centinued)
The surveillance requirements provide adequate assurance that RCIC will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a complete functional test requires reactor shutdown. The pump discharge piping is main-tained full to prevent water hammer damage.
3/4.7.4 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of !
the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers are classified and grouped by design and manufacturer but not by site.
For example, mechanical snubbers utilizing the same design features of the 2-kip,10-kip, and 100 kip capacity manufactured by Company "A" are of the same type. The same design mechanical snuboers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as-would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information Of snubber location, size and system affected shall be available at the plant. The accessibility of each snubber shall be determined and reviewed by the Facility Review Group and approved by the Manager, Clinton Power Station. The determination shall I
be based upon the accessibility of the snubber during plant operations (e.g.,
radiation level, temperature, atmosphere, location, etc.). The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
When a snubber is found inoperable, an engimering evaluation is performed. in addition to the determination of the snubber mode of f ailure, in order to deter-mine if any safety related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
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(To pyovi_de_ f urthtr asturAqc.gohupgeliabilith p, representative sample of the installed snubbers will be functinnafly tested during plant shutdowns at 18 month intervals. Observed failures of these_sarglsnubbers wilj 3eguire t Qt'on d ,gsi n tk +fge ve n c i e s_g o f a .gjincqa Jea mme :.J.
g Qn,j_tys .rwbi& cmc yisTG%pe.ctcd iU Q QeregegC1 .
~ ^ V-HydraulicsnubbersanFmechan(1Ta'lsnubbersmayeachbetreateYasadifferent entity for the above surveillance programs.
The service life of a snubber is evaluated via manufacturer input and informa-tion through consideration of the snubber service conditions and associated installation and maintenance records, i.e., newly installed snubber, .'ai re-placed, spring replaced, in high radiation area, in high tamperature area, CLINTON - UNIT 1 B 3/4 7-2 Revision 1
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