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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20095F5891995-12-12012 December 1995 Proposed Tech Specs Re Containment Sys ML20094D0611995-10-31031 October 1995 Proposed TS Page 6-18,deleting TS 6.9.2.d, Seismic Event Analysis ML20098C5181995-10-0202 October 1995 Proposed Tech Specs,Revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C4111995-09-29029 September 1995 Proposed TS 3/4.1.2.8 Re Reactivity Control Sys - Borated Water Sources - Shutdown TS 3/4.1.2.8 Re Reactivity Control Sys - Operating & TS 3/4.5.1 Re ECCS - Core Flooding Tanks ML20098C1121995-09-29029 September 1995 Proposed TS 3.4.3 & Associated Bases,Modifying Lift Setting of Pressurizer Code Safety Valves to Greater than or Equal to 2,575 Psig,Corresponding to Lift Setting Tolerance of +3% of Nominal Lift Pressure 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216E6111999-09-0707 September 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210H0731999-07-28028 July 1999 Proposed Tech Specs 3/4.7.5.1, Ultimate Heat Sink, Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4311999-07-27027 July 1999 Proposed Tech Specs,Changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G4801999-07-26026 July 1999 Proposed Tech Specs 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation & Associated Bases ML20210G9161999-07-26026 July 1999 Proposed Tech Specs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5391999-07-26026 July 1999 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B for Type B & C Containment Leakage Rate Testing ML20195F9351999-06-10010 June 1999 Proposed Tech Specs,Revising TS 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.6.5.1, Crevs ML20207E7941999-05-21021 May 1999 Proposed Tech Specs Allowing Use of Expanded Spent Fuel Storage Capability ML20205E5031999-03-19019 March 1999 Proposed Tech Specs Withdrawing Proposed New Action B, Previously Submitted in 981027 Application ML20204F1821999-03-0909 March 1999 Proposed Tech Specs,Adopting Changes in Frequency & Scope of Volumetric & Surface Exams Justified by W TR WCAP-14535A ML20155E4971998-10-28028 October 1998 Proposed Tech Specs 4.0.2 Re Applicability of 25% Surveillance Interval Extension Allowance ML20197G5521998-10-28028 October 1998 Rev 8 to Dbnps,Unit 1 Technical Requirements Manual ML20155E3231998-10-28028 October 1998 Proposed Tech Specs Revising Various Sections of 6.0, Administrative Controls, Including Relocation of 6.11 Contents to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D7791998-10-27027 October 1998 Proposed Tech Specs Relocating TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8521998-10-27027 October 1998 Proposed Tech Specs Revising SRs 4.8.2.3.2.d,4.8.2.3.2.e, 4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155E0721998-10-27027 October 1998 Proposed Tech Specs Revising 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation,To Provide Potential Reduction in Spurious Trip Rate for Potential Cost Savings in Excess of $50,000 ML20151W3071998-09-0808 September 1998 Proposed Tech Specs Permitting Use of Framatome Cogema Fuels M5 Advanced Alloy for Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2991998-09-0808 September 1998 Proposed Tech Specs Revising Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20206D2721998-08-28028 August 1998 Rev 11,change 1 to Odcm ML20217P8351998-04-24024 April 1998 Proposed Tech Specs Clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20217P8811998-04-24024 April 1998 Proposed Tech Specs 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases Relocating Tables of Response Time Limits to Plant USAR Technical Requirements Manual ML20217C4881998-03-20020 March 1998 Proposed Tech Specs SR 4.4.5.3.c.1,providing Greater Specificity as to Location of Addl Insps in Unaffected SG ML20217N4471998-02-27027 February 1998 Proposed Tech Specs Pages Provided to Modify Proposed New Action 3.7.6.1.b to Make More Consistent w/NUREG-1431 ML20203L1111998-02-26026 February 1998 Proposed Tech Specs Pages Re Amend to License NPF-3 Involving Incorporation of New Repair Roll Process for SG Tubes W/Defects in Upper Tube Sheet ML20197J2621997-12-23023 December 1997 Proposed Tech Specs Pages Re Changes to TS Definition 1.2, TS 3/4/9.5 & New TS 3.0.6 & Associated Bases.Ts Index Rev to Reflect Change to TS 3/4.9.5,included ML20197J5971997-12-23023 December 1997 Proposed Tech Specs Pages,Revising TS Surveillance Requirements for ISI Requirements of Internal Auxiliary Feedwater Header,Header to Shroud Attachment Welds & External Header Thermal Sleeves ML20217M5601997-09-0505 September 1997 Rev 11.0 to Davis-Besse Odcm ML20217R2821997-08-26026 August 1997 Proposed Tech Specs,Clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2871997-08-26026 August 1997 Proposed Tech Specs,Modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5981997-07-29029 July 1997 Proposed Tech Specs 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating ML20141F1101997-06-24024 June 1997 Proposed Tech Specs,Deleting Requirements for Safety Features Actuation Sys Containment High Radiation Monitors ML20138C3261997-04-18018 April 1997 Proposed Tech Specs 3/4.7.6 Revising Limiting Condition for Operation to Include New Required Actions in Event That One or Both Channels of Radiation Monitoring Instrumentation Becomes Inoperable ML20138A6891997-04-18018 April 1997 Proposed Tech Specs 3/4.5.3.2.1 & 3/4.5.2 Modifying Presently Specified 18-month Surveillance Frequencies to New Specified Frequencies of Once Each 24-months ML20140D9481997-04-0909 April 1997 ODCM, Rev 10 ML20138M1281997-02-14014 February 1997 Proposed Tech Specs 3.5.2 Re Emergency Core Cooling Systems & 4.5.2.f Re Surveillance Requirements ML20134L0561997-02-13013 February 1997 Proposed Tech Specs Re Changes Made Concerning Decay Heat Removal Sys Valve ML20134F1811997-01-30030 January 1997 Proposed Tech Specs Re Possession & Use of SNM as Reactor Fuel ML20134D7621997-01-30030 January 1997 Proposed Tech Specs Revising SR Intervals from 18 to 24 Months Based on Results of DBNPS Instrument Drift Study & TS 2.2, Limiting Safety Sys Settings, Based on Results of Revised Framatome RPS Instrument String Error ML20134B0591997-01-20020 January 1997 Proposed Tech Specs 3/4.5.3 Re ECCS Subsystems ML20132B7031996-12-11011 December 1996 Proposed Tech Specs Revising TS Definitions,Instrumentation TS & ECCS TS for Conversion to 24 Month Fuel Cycle for License NPF-3 ML20134F1891996-10-28028 October 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Systems ML20117P5311996-09-17017 September 1996 Proposed Tech Specs,Supporting Conversion of DBNPS from 18 Month to 24 Month Fuel Cycle ML20117N8531996-09-12012 September 1996 Proposed Tech Specs Re Reactivity Control Systems & Emergency Core Cooling Systems ML20117M2201996-09-0404 September 1996 Proposed Tech Specs 6.2.3,removing Specific Overtime Limits & Working Hours ML20116K2631996-08-0707 August 1996 Proposed Tech Specs Re Definitions,Applicability Bases, Containment Spray Sys & Containment Isolation Valve for Conversion to 24 Month Fuel Cycle ML20117K1911996-05-28028 May 1996 Proposed Tech Specs 3/4.3.1.1 - RPS Instrumentation & TS 3/4.3.2.3 - Anticipatory RTS Instrumentation Increasing Trip Device Test Interval ML20101M1921996-03-29029 March 1996 Proposed Tech Specs 3/4.6.4.4 - HPS,3/4.6.5.1 - Shield Building Evs & 3.4.7.6.1 - CREVS Re Changing Surveillance Requirements for Charcoal Filter Lab Testing to Revise Methodology Used to Determine Operability in ESF AHUs ML20101C6961996-03-0606 March 1996 Proposed Tech Specs,Allowing Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI Pump 1-2 Until 10th Refueling Outage,Scheduled to Begin 960408 ML20100E0101996-02-0505 February 1996 Proposed TS 3/4.3.2.1,Table 3.3-3,safety Features Actuation Sys Instrumentation,Reflecting Design & Actuation Logic of Plant Sequencers & Essential Bus Undervoltage Relays ML20107C3101995-12-21021 December 1995 Rev 9 to Odcm 1999-09-07
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ - _ _____ _
. Docket No. 50-346 '
Lic:l;nac No. NPF-3 i Sarici No. 1346 -
[
i :
PtANT SYSTEns 1
{ , 3/4.7.7 SNUB 8tR$ , , l i \
j L151IDG_CDFDIIl0M.IOR.DPEMIION ' ;
t 3.7.7 All safety related soubbers shall be OPERAtt.E. ,
,t l APPLICA8tt,17Y: N00E5 1, 2, 3 and 4. (H00ES 5 and 6 for se'ubbers located !
) en systems required Op1RAB!.E is these MODES). '
1 .
j ACTIONt i
) a. With one or more snubbers (noperable 1. withia 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> j replace or restore the inoperable snubber (s) to OPERAtt.E
- status, or 2. verify systee operability with the snubber (s) ,
l inoperable by engineering evaluation withia 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; er -
- 3. declare the supported subsystem inoperable and follow ' l j -
the appropriate ACTIOW statement for that system. ;
l and, for snubbers which have failed either the visual er !
l functional tests t
i i b. Perform an engineering evaluaties within to days te deter-J .
eine it any safety-related systes er composest has bees I adversely affected by the inoperability of the saubber and
- l if the snubber nede of failure has imparted a sigstficant ;
effect er degradaties es the supported composest er systee.1 i
,' The previsions of Technical Specificaties 3.0.4 are not ;
, applicable for the componeet, or system. '
}
125.ll!#RE9EA2 DIS
, 4.7.7 Each snubber 8 shall be demonstrated OPERAli2 by the requirements i
I of the fallowing surveillance prograss and pursuant to require-seats of Specificaties 4.0.5. }
4.7.7.1 Visual fospecties Prearse f
- l i ,
i i
1 Engineering evaluaties is not required when a snubber is renewed for
! surveillance testing provided it is returned to OffRA8!.E status withis I the requirements of action statenest a. l' 1
l 8 Safety related saubbers are listed in the latest revisten of applicable
! surveillance test precedure(s). Saubbers may be added to, or removed l j f roe, safety related systees and their assigned groups without te6ee en f
- i,1ces Amendeest.
4 i P
- DAVIS SESSE, IMIT 1 3/4 7 20 ggg g, g4 4 1
Dock:st No. 50-346 1.icen;3 No. NPF-3 S3rici No. 1346 P!.W SYSTT.95 -
f, 05%'UMMEIlMISC311LUGIM -
- a. General Requirements At least once per inspection interval, each group of soubbers in use in the plant shall be visually inspected in accordance with Spectfication 4.7.7.1.b and 4.7.7.1.c.
Visual inspections may be performed with binoculars, or other visual support devices, for those snubbers that are' difficult to access and where required to keep espesure as low ~as reasonably achievable. Response to fa!!ures shall be in accordance with Specification 4.7.7.1.d.
- b. Taspection Interval and Sample Criteria The inspectton interval and sample criteria say be applied on the basis of snubber groups. The soubber groups may be established based on physical characteristics and accessi-bstity. Isaccessible soubbers are defined as those locat.
ed: (a) inside contairaent, (b) in high radiation exposure zones, or (c) in areas shere accessibility is tietted by physical constralsts such as the need for scaffolding.
Visual inspections for a group shall be performed in accordance with the following schedule:
Saubbers are divided into four (4) groups " Accessible" -
Group I and "!naccessible" Group !! for either hydraulic or sechanical.
No. of !aoperable Soubbers nlithin a Group - Subsequent Group Visual per Inspection laterval faspection Intervat 3 * ,8 0 18 months
.I 12 monthe 2 6 month:
3, 4 124 days
$, 6, 7 62 days 4 or more 31 days the tospections for a group shall teclude 100 percent of soubbers la that group.
I Ihe inspection interval shall not be lengthened more than one step at a tilse, and The provisions of Spectitcation 4.0.2 are not applicable.
'All the time intervals are 12$1, eacept that the inspection of inaccessible saubbers may be deferred to the nest shutdous when plaat conditions allow $ days for inspectica.
DAVIS 8ES$t, W!! ! 3/4 7 21 Anendment No. 94-
\ uvaut.bo. su-> u I
Licenza No. NPF-3 Serial N6.13bv!
P SYSTD'S .
M4MQ!11gVIS (Ntim4)
- c. Acceptance Criteria A snubber shall be considered OPERABLI as a result of a visual inspection ift (1) there are no visible indications
! of damage or inoperability, and (2) attachments to the '
foundation or supporting structure are secure.
- d. Response to Tailures_
for each soubber unit which does oor, meet the visual inspection acceptance criteria of Specification 4.7.7.1.c:
Detensine the snubber OPERABI.E by functionally testing the snubber per Specification 4.7.7.2, unless the (Lydraulic) soubber was determined inoperable because the fluid port was found uncovered; O ,
f 1. Perfora the ACT!0N specified in 3.1.Ta; g
- 2. Perfone an engineering evaluation as specified in j 3.1.7.b.i I
.gd a
- 3. Increase the frequency of group inspection as de-scribed in Specification 4.7.7.1.b unless the cause of the rejection is clearly established and resedied for that particular snubber and for other snubbers that say be generically susceptible.
- e. "Inse.ri W 4.7.7.2 Functional Test Protrae ,
- a. Ceneral Requirements.
At least once per laspection interval a representative saepte of each group of saubber to use in the Plant shall be functionally tested in accordance with Specifications 4.7.7.2.b and 4.7.7.2.c. Ilesponse to the failures shall be in accordance with Specification 4.7.7.2.d.
For all snubbers, functicast testing shall consist of either beach tasting or toplace testing.
- b. lospectico Interval and $4epte Criter a The snubbers say be categorized inte groups based en physical characteristics. Snubbers are divided inte four (4) groups: " Accessible" Croup 1 and "tasccessible" -
Group 11 for either hydraulic or mechanical, tack group say be tested tadependently free the standpotat of per=
forming additional tests if fattures are discovered, i
DAVIS lES$t, WIT 1 3/4 7*22 Amendment No. Q ,94
Docket No. 50-346
, Lican23,No. NPF-3 Satici No. 1346 .
I Insert "A" Transient Event Inspection An inspection shall be performed of all hydraulic and mechanical snubbers ,
attached to sections of systems that have experienced unexpteted, potentially damaging transients as determined from a review of operational data. A i visual inspection of the snubbers on these systems shall be performed within six months following such an event. In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following: (1).
, manually induced snubber movement; or (2) evaluation of in-place snubber
! piston setting; or (3) stroking the mechanical snubber through its full range of travel.
i I
i i
4 1
s i
3 ,
1 k
1 1
I r
o
,n~-- .--r .-,-e-n.--------v,---~ew,-, ------ , , - ,.-- w..m ve-,. +- - - - - - - - --,-,-----,-n--,n- r -m- -e,~-- ~-- ,m--ma-- . -
[Joc au t ,,ho . JU-J40 Licenza No. NPF-3 S2ri5l Nb. 13hy sysitns -
SMTllL$1CEJJay1ReMNTS (continuedi The inspection interval for functional testing shall be 18 months.
Snubbers which are scheduled for removal for seat mainte-nance say be included in the test sample prior to any maintenance on the snubber.
The representative sample shall consist of at least to percent (rounded off to next highest integer) of each group of snubbers in use in the Plant. The selection process shall ensure that all snubbers, regardless+of their accessibili- l ty classification, are functionally tested at least once every ten inspection intervals,
- c. Acceptance Criteria for hydraulic snubbers (either inplace testing or bench testing), the test shall verify that:
- l. Snubber piston will allow the hydraulic fluid to
, " bypass" free one side of the piston to the other to assure unrestrained action is achieved within the specified range of velocity or acceleration in both tension and compression.
- 2. When the snubber is subjected to a movement which creates a load condition that exceeds the specified range of velocity or acceleration, the hydraulic fluid is trapped in one end of the snubber causing suppres-sion of that sovement.
- 3. Snubber release rate or bleed rate, where required, occurs in compression and tension.
For mechanical snubber in place and bench testing, the test shall verify that:
- 1. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.
1
- 2. Activation (restraining action) is achieved in both tensionandcompressioy wA:n Ae spec $cJ roop 8
P:=::::t--et-ethe. m_,,,iens4.e f.eetien;! testing fer iedisids1 -
savhbees-in-these-eetetecie; ;;;y be g;;ated by tt.e 0 issi;; ;;17 i f-a 5 eti m .1: b:ei: fer ::c.p i:: i: ;;;;;;; d.
DAVIS-BESSE, UNIT 1 , 3/4 7-23 Amendment No. H , 94
Dqc ke t .5k) . 50-346 Licsn;3 No. NPF-3 s
- j l S
- rimi N'o. 1346 . - - .'i r; I PLA.YT SYSTEMS -
7' !
. . il d t, . _ . , 1 SilHYEl'.I.L C' JIMIEf.I'ENIS_ffontinue f1, , ; . , ,; '
- 4. Response to Failures For each inoperable snubber per Specification 4.7.7.2.c:
- 1. Perform the ACTIONS specified in 3.7.74 and 3.7.7b; and
- 2. Within the s'pecified inspection interval, functionally test an additional sample of at least to percent of the snubber units from the group that the inoperable snubber unit is in.
The functional testing of an additional sample of at least 10 percent from the inoperable snubber's group is required for each snubber unit determined to be inoperable in subsequent functional tests, or until all snubbers in that group have been tested; and
- 3. The cause of snubber failure vill be evaluated and, if caused by a manufacturing or design deficiency, all snubbers of the same or similar design subject to the same defect shall be functionally tested within
, 90 days from determining snubber inoperability. This testing requirement shall be independent of the requirements,in 4.7.7.2.d(2) above.
+
l 1 DAVIS-BESSE, UNIT 1 3/4 7-24 Amendment No. 1),94 (Tables 3.7-3 and 4.7 4 deleted.
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Docket.N.o. au-ho i Licensa No. NPF-3 Sarial N'o. 1346 PLOT SYSTEMS BASES PLWT SYSTEMS 3/4.7.7 SNUB 8ERS
! BASES A11' safety-related snubbers are required OPERABl.E to ensure that the
- 1. structural related systems integrity of the reactor is maintained duringcoolant and following systesa anglgother 5 safety-
__. event.
e are, those installed on l Snubbers safety-related excluded systems for from loads thisother inspection than progegJMY or on nonsafety-related systems and then only if their failure or failure of the system on g which they are ig" stalled, vould have no adverse effect on any safety-related system during a . . W.S event. l
- Inoperable is defined as
i
- 1. For visual test -
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- a. The fluid no long' er is supplied to the valve block, or
- b. Mounting pins are disengaged from the saubber.
- c. Attachment to foundation or supporting structure is not secure.
- 2. For functional test .
- a. The snubber (excluding end anchors, i.e., pin-to pia) does not
, meet specified test criteria.
f 4
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection i
I interval varies inversely with the observed snubber failures and is '
determined by the number of inoperable saubbers found during an inspec-j tion.
Inspections performed before that interval has elapsed say be used i as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required '
time interval has elapsed (noeinal time less 257) may not be used to lengthen the required inspection interval. Any inspection whose results
! require a shorter inspection interval will override the previous schedule.
\
Wen the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers (Tat say be generi-cally susceptible, and verified by functional testing, that saubber may be exempted free being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the soubber by visual inspection, or are similsely located or exposed to the same environeestal conditions such as temperature, radiation, and vibration.
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j DAVIS-8 ESSE, UNIT 1 B 3/4 7 ,
Amendment No. 94
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1 Oucket .S o . JU-Jau- 1 Licznsa No. NPF-3 .fj f ,. , * .
. . . , , , , ; {l Sarial No. 1346 PLANT SYSTI.MS 5<; - . \
I O 9 '. ' .. ; ..... :,,;c;d I SASES l Uben a snubber is found inoperable through a visual or functional test, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine 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 degrada-tion on the supported- component or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested at 18 month inte rvals . Observed failures of these sample snubbers shall require functional testing of additiocal units. When a snubber is found to be inoperable due to failure to lock up or failure to move (i.e., f rozen in place), the cause will be evaluated for further action or testing.
In cases where the cause of failure bas been identified, additional snubbers that have a high probability for the same type of failure or are being used in the same application that caused the failure shall be tested. This requirement increases the probability of locating inoperable snubbers without testing 100% of the snubbers.
Hydraulic snubbers and mechanical snubbers may each be treated as a dif ferent entity for the ab'ove surveillance programs.
i DAVIS-BESSE, UNIT 1 8 3/4 7-$a Amendment No. 94
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LICENSE AMEN 0 MENT 055293 012887 150.00 150.00 Ord.Cr CATE 40 vtecOs rati'i TOTAL AMOUNT
>S- 540642 020687 873800 UNITED STATES NUCLEAR _ 15_0. 0_0
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YC. F 30 SLO 6L2 EDISON 't?'
540642 TOLEDO TRUSTCORP 70'.tDO u ANSFELD. CP*O VOD AFTER 90 DAv5 NCf VA.c pot MO8t THAN 5:5 000 UP4E55 COUNTER 5GC PAY To rm ci:t- :s _ _ _ DA.TE . AMOUNT-UNITED STATES NUCLE AR _02/.06/87 $********150.00 REGULATORY COMMISSICN OFFICE OF THE CONTRCLLER WASHINGTON OC 20555
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