Letter Sequence Other |
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MONTHYEARML20067C4071982-11-24024 November 1982 Responds to Re Tech Specs for Snubber Surveillance.All Snubbers Defined in Ansi/Asme OM-4 Std Will Be Listed in Tech Spec Tables in Manner Similar to Current Table on Hydraulic Snubbers Project stage: Other ML20105B9341983-06-28028 June 1983 Requests Extension Until 830801 to Submit Revised Tech Specs for Snubbers,Due to Extensive Internal Review Project stage: Other ML20077G8181983-08-0101 August 1983 Extends Submittal Date for Proposed Tech Specs on Snubber Surveillance to 830901,to Allow for Resolution of Util Nuclear Review Board Comments Project stage: Other ML20077M1361983-09-0101 September 1983 Proposed Changes to Tech Specs 3.7.7 & Table 3.7-3 Re Snubber Surveillance to Include Mechanical Snubbers W/ Schedules,Actions & Acceptance Criteria for Sample Testing Project stage: Request ML20077M1341983-09-0101 September 1983 Application for Amend to License NPF-3,revising Tech Specs 3.7.7 & Table 3.7-3 Re Snubber Surveillance to Include Mechanical Snubbers W/Schedules,Actions & Acceptance Criteria for Sample Testing.Safety Evaluation Encl Project stage: Request ML20077M1301983-09-0101 September 1983 Forwards Application for Amend to License NPF-3,revising Tech Specs 3.7.7 & Table 3.7-3 Re Snubber Surveillance to Include Mechanical Snubbers W/Schedules,Actions & Acceptance Criteria for Sample Testing.Class III Fee Encl Project stage: Request ML20101T4441985-01-30030 January 1985 Proposed Tech Specs,Revising Hydraulic & Mechanical Snubber Surveillance Program,Including Changes to Visual & Functional Tests of safety-related Snubbers & Maint of Equipment & Surveillance Records Project stage: Other ML20101T4241985-01-30030 January 1985 Application for Amend to License NPF-3,revising Tech Specs 3.7.7,4.7.7 & 6.10.2.m Re Mechanical & Hydraulic Nuclear safety-related Snubbers Project stage: Request ML20137M8701986-01-22022 January 1986 Notifies That Application to Amend License NPF-3,authorizing post-transient Insp of Hydraulic & Mechanical Snubbers Will Be Submitted by 860228.Understanding That 850130 Application Will Be Approved by 860215 Confirmed Project stage: Request ML20140F9071986-03-26026 March 1986 Informs That Deletion of Footnote 6 & Addition of within Specified Range to Proposed Surveillance Requirements 4.7.7.2b & 4.7.7.2c.2,respectively,will Be Incorporated Into Apr 1986 Amend Application,Per NRC 860324 Request Project stage: Other 1983-09-01
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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
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PLANT SYSTEMS 3/4.7.7 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.7 All safety related snubbers shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
- a. With one or more snubbers inoperable: 1. within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or rentore the inoperable snubber (s) to OPERABLE status, or 2. verify system operability with the snubber (s) inoperable by engineering evaluation within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or
- 3. declare the supported subsystem inoperable and follow the appropriate ACTION statement for that system.
and, for snubbers which have failed either the visual or functional test:
- b. Perform an engineering evaluation within 90 days to deter-mine if any safety-related system or component has been adversely affected by the inoperability of the snubber and if the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.1 The provisions of Technical Specification 3.0.4 are not applicable for the component or system.
SURVEILLANCE REOUTREMENTS 4.7.7 Each snubber 2 shall be demonstrated OPERABLE by the requirements of the following surveillance programs and pursuant to require-ments of Specification 4.0.5.
4.7.7.1 Visual Inspection Program lEngineering evaluation is not required when a snubber is removed for surveillance testing provided it is returned to OPERABLE status within the requirements of action statement a.
2 Safety related snubbers are listed in the latest revision of applicable surveillance test-procedure (s). Snubbers may be added to, or removed from, safety-related systems and their assigned groups without prior Licensing Amendment.
~
8502060169 850130 PDR ADOCK 05000346 -i P PM DAVIS-BESSE, UNIT 1 3/4 7-20
PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
- a. General Reouirements At least once per inspection interval, each group of snubbers in use in the Plant shall be vistally inspected in i
accordance with Specification 4.7.7.1.b and 4.7.7.1.c.
Visual inspections may be performed wita binoculars, or other visual support devices, for thore snubbers that are difficult to access and where requir:d to keep exposure as low as reasonably achievable. Response to failures shall be in accordance with Specification 4.7.7.1.d.
- b. Inspection Interval and Sample Criteria-The inspection interval and sample criteria may be applied on the basis of snubber groups. The snubber groups may be established based on physical characteristics and accessi-bility. Inaccessible snubbers are defined as those locat-ed: (a) inside containment, (b) in high radiation exposure zones, or (c) in areas where accessibility is limited by physical constraints such as the need for scaffolding.
Visual inspections for a group shall be performed in accordance with the following schedule:
. Snubbers are divided into four (4) groups: " Accessible" -
Group 1 and " Inaccessible" - Group II for either hydraulic or mechanical.
No. of Inoperable Snubbers Within a Group Subsequent Group Visual Per Inspection Interval Inspection Interval 3, 4, 5 0 18 months 1 12 months 2 6 months 3, 4 124 days 5,6,7 62 days 8 or more 31 days The inspections for a group shall include 100 percent of snubbers in that group.
3 The inspection interval shall not be lengthened more than one step at a time, and 4 The provisions of Specification 4.0.2 are not applicable.
5A11 the time intervals are +25%, except that the inspection of inaccessible snubbers, may be deferred to the next shutdown when plant conditions allow 5 days for inspection.
DAVIS-BESSE, UNIT 1 3/4 7-21
-PLANT SYSTEMS SURVEILLANCE REOUTREMENTS (Continued)
- c. Acceptance Criteria A snubber shall be considered OPERABLE as a result of a visual inspection if: (1) there are no visible indications of damage or inoperability, and (2) attachments to the foundation or supporting structure are secure,
- d. Response to Failures For each snubber unit which does not meet the visual inspection acceptance criteria of Specification 4.7.7.1.c:
Determine the snubber OPERABLE by functionally testing the snubber per Specification 4.7.7.2, unless the (hydraulic) snubber was determined inoperable because the fluid port was found uncovered; QR
- 1. Perform the ACTION specified in 3.7.7a; and
- 2. Perform an engineering evaluation as specified in 3.7.7.b.;
and
- 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 remedied ~
for that particular snubber and for other snubbers that may be generically susceptible.
4.7.7.2 Functional Test Program
- a. General Requirements At least once per inspection interval a representative sample of each group of snubber in use in the Plant shall
.be functionally tested in accordance with Specifications 4.7.7.2.b and 4.7.7.2.c. Response to the failures shall be in accordance with Specification 4.7.7.2.d.
For all snubbers, _ functional testing shall consist of either bench testing or inplace testing.
- b. Inspection Interval and Sample Criteria The snubbers may be categorized into groups based on physical characteristics. Snubbers are divided into four (4) groups: " Accessible" - Group 1 and " Inaccessible" -
. Group II 'for either hydraulic or mechanical. Each group
. may be tested independently from the standpoint of per-forming additional tests if failures are discovered.
DAVIS-BESSE, UNIT 1 3/4 7-22
PLANT SYSTEMS j SURVEILLANCE REQUIREMENTS (Continued)
The inspection interval for functional testing shall be g 18 months.
Snubbers which are scheduled for removal for seal mainte-nance may be included in the test. sample prior to any i maintenance on the snubber.
The representative sample shall consist of at least 13 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, regardlessa of their accessibili-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:
- 1. Snubber piston will allow the hydraulic fluid to
" bypass" from 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 movement
- 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.
- 2. Activation (restraining action) is achieved in both tension and compression.
t sPermanent or other exemptions from functional testing for' individual-
, snubbers in these categories may be granted by the Commission only if l a justifiable basis for exemption is presented.
i
! DAVIS-BESSE, UNIT 1 3/4 7-23 l
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
', d. Response to Failures
. For each inoperable snubber per Specification 4.7.7.2.c:
- 1. Perform the ACTIONS specified in 3.7.7a and 3.7.7b; and
- 2. Within the specified inspection interval, functionally test an additional sample of at least 10 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 will 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 i 90 days from determining snubber inoperability. This testing requirement shall be independent of the requirements in 4.7.7.2.d(2) above.
DAVIS-BESSE, UNIT 1 3/4 7-24
5 PLANT SYSTEMS RARER PLANT SYSTEMS 3/4/7.7 SNUBBERS BASES All safety-related 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 event.
Snubbers excluded from this inspection program are those installed on safety-related cystema for loads other than seismic or on nonsafety- ,
related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system during a seismic event.
Inoperable is defined as:
- 1. For visual test
- a. The fluid no longer is supplied to the valve block, or
- b. Mounting pins are disengaged from the snubber.
. c. Attachment to foundation or supporting structure is not secure.
- 2. For functional test
- a. The snubber (excluding end anchors, i.e., pin-to pin) does not meet specified test criteria. _
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is c determined by the number of inoperable snubbers found during an inspec-tion. Inspections performed before that interval has elapsed may be used.
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 (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results 1 require a shorter inspection interval will override the previous schedule. .
When'the cause of the' rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generi-
> cally susceptible, and verified by functional testing, that snubber may be
, exempted from 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 snubber by visual
. inspection,,or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
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' PLANT SYSTEMS nAnrn
. When 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 sign.ficant effect or degrada-e tion on the supported component or system.
To provide assurance of en bber functional reliability, a representative sample of the installed snubbers will be functionally tested at 18 month intervals. Observed failures of these sample snubbers shall require functional testing of additional units. When a snubber is found to be inoperable due to failure to lock up or failure to move (i.e., frozen in place), the cause will be evaluated for further action or testing.
In cases where the cause of failure has 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 different entity for the above surveillance programs.
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s DAVIS-BESSE, UNIT 1 B 3/4 7-5b
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, ADMTMISTRATIVE CONTROLS
- e. Records of changes made to Operating Procedures.
- f. Records of radioactive shipments.
3 3 Records of sealed source and fission detector leak tests
- and results. ,
- h. Records of annual physical inventory of all sealed source material of record.
6.10.2 - The following records shall be retained for the duration of the Facility Operating License:
- a. Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.
^ b. Records of new and irradiated fuel inventory, fuel trans-fers and assembly burnup histories.
- c. Records of radiation exposure for all individuals entering radiation control areas.
- d. Records of gaseous and liquid radioactive material released to the environs. -
.- e. Records of transient of operational cycles for those m facility components identified in Table 5.7-1.
- f. -Records of reactor tests and experiments.
3 Records of training and qualification,for current members of the plant staff. )
,~ b. Records of in-service inspections performed pursuant to these Technical Specifications.
- i. Records of Quality Assurance activities required by the QA Manual. . .,.
- j. Records of reviews performed for changes made to procedures
- / .or equipment or reviews of tests and experiments pursuant 1 x to 10 CFR 50.59. ,
- k. Records of meetings of the SRB and the CNRB.
D 1. - acords for Environmental Qualification which are covered under the provisions of paragraph 6.13.
- m. Records of the service lives of all safety.related hydrau-lic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.
'" r DAVIS-RESSE, UNIT 1 6-19 Amendment No. 8, 12 Order dtd. Oct. 24,.1980
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