|
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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
-
l .,
(
PLANT SYSTEMS f
3/4.7.7 SNUBBERS LIMITING CONDITION FOR OPERATION l
S 3.7.7 All snubbers identified in Tables 3.7-3a and 3.7-3b shall be
- OPERABLE.1 APPLICABILITY: MODES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
I
- 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 restore 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 system inoperable and follow the appropriate ACTION statement for that system.
- AND,
- b. Perform an engineering evaluation within 90 days to determine 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.2 The provisions of Technical Specification 3.0.4 are not applicable
~
for the component or system.
SURVETILANCE REOUTREMENTS 4.7.7 Each snubber shall be demonstrated OPERABLE by the requirements i of the following surveillance programs and pursuant to requirements of Specification 4.0.5.
4.7.7.1 Visual Inspection Program
- a. General Requirements At least once per inspection interval, a representative sample of each type of snubber in use in the Plant shall be visually inspected in accordance with Specification 4.7.7.1.b and 4.7.7.1.c. Visual inspections may be performed with binoculars, or other video support devices, for those snubbers that are difficult to access and where required to keep ex-posure ALARA. Response to failures shall be in accordance with Specification 4.7.7.1.d.
~k I
I See plant system-bases for definitions and background information.
.l 2 Engineering 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.
DAVIS-BESSE, UNIT 1 3/4 7-20 8309120217 830901 PDR ADOCK 05000346 P PDR
PLANT SYSTEMS SURVEILLANCE REOUIRMfENTS (Continued)
- b. Inspection Interval and Sample Criteria 1
Tbe 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 accessibility. (See Tables 3.7-3a and 3.7-3b for grouping of snubbers.) Visual inspections for a group shall be performed in accordance with the following schedule:
No. of Inoperable Snubbers Within a Group Subsequent Group Visual i
Per Inspection Interval Inspection Interval 3, 4, s 0 18 months 1 12 months 2 6 months 3, 4 124 days 5,6,7 62 days 8 or more 31 days l
l The first and second inspections shall include 100 percent 1
of all snubbers in Tables 3.7-3a and 3.7-3b. If no snubbers are found unacceptable within a group during two successive inspection intervals, the next sample size may be limited to 50 percent of the snubbers within the eligible group.
For subsequent inspections following inspections in which all snubbers examined are acceptable, the sample size may be further reduced in steps to 25,15, and 10 percent of each eligible g'roup, provided that the total of all
- snubbers subject to inspection at all times is at least 10 percent of the total number of snubbers in Tables 3.7-3a and 3.7-3b.
When an inoperable snubber is revealed during a group ,
inspection, the sample size for that group shall be increased to 100 percent for the next two inspections, except as noted in Specification 4.7.7.1.d(3).
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.
sAll the time intervals are +25%, except that the inspection of inaccessible saubbers, as noted in Tables 3.7-3a and 3.7-3b, may be deferred to the next shutdown when plant conditions allow 5 days for inspection.
DAVIS-BESSE, UNIT 1 3/4 7-21
i .
' 1
'l ' PLANT SYSTEMS i l
SURVETLLANCE REOUIREMENTS (Continued)
, c. Acceptance Criteria i
k 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 3 For each snubber unit which does not meet the visual j inspection acceptance criteria of Specification 4.7.7.1.c:
1, i Determine the snubber OPERABLE by functionally testing the L snubber per Specification 4.7.7.2, unless the (hydraulic) l snubber was determined INOPERABLE because the fluid port
, was found uncovered; l
OR_
- 1. Perform the ACTION specified in 3.7.7a; AND
- 2. Perform an engineering evaluation as specified in
! 3.7. 7.b.;
i L AND
- 3. Increase the frequency of group inspection and the size of the group sample, as described 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 Fractional Test Program I
l General Requirements a.
~
At least once per inspection interval a representative sample of each type 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 hydraulic snubbers, functional testing shall consist of
! either bench testing or inplace testing. Snubbers greater l'
than 50,000 lbs. capacity may be excluded from functional testing requirements.
For mechanical snubbers, functional testing shall consist of either inplace testing or bench testing.
l l.
DAVIS-BESSE, UNIT 1 3/4 7-22 i
_ __. _ . _ , _ _ . . _ . . - , , . - . , . . _._, . _ . . . , _ , . _ = , - . . _ _ _ . , . . . _ _ _ _ , _ _
I ,.
PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
- b. Inspection Interval and Semple Criteria The snubbers may be categorized into groups based on physical characteristics. Each group may be tested independ-ently from the standpoint of performing additional tests if failures are discovered.
The inspection interval for functional testing shall be
.18 months.
Snubbers which are scheduled for removal for seal maintenance may be included in the test sample prior to
- i any maintenance on the snubber.
- l
- i The representative sample shall consist of at least 10 per-cent (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 s of their accessibility classification (per Tables 3.7-3a and 3.7-3b), are function-
, ally tested at least once every ten test intervals.
,i
- c. Acceptance Criteria For hydraulic snubbers (either inplace testing or bench testing), the test shall verify that:
- 1. Gradual movement of snubber piston will allow the hydraulic flui,d to " bypass" from one side of the piston to the other.
- 2. When the snubber is subjected to a sudden movement which creates a load condition that exceeds the allowable normal operating condition, the hydraulic l
fluid is trapped in one end of the snubber causing l .
suppression of that movement.
d For mechanical snubber inplace testing, the test shall verify that:
- 1. The snubber is not locked solid (i.e., frozen);
\
l 6 permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented.
DAVIS-BESSE, UNIT 1 3/4 7-23
PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
For mechanical snubber bench testing, the test shall verify that:
- 1. The force that initiates free movement of the snubbe.r 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.
- 3. Snubber release, where required, occurs in compression and tension.
- 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 test 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.
l l 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 desi;;n subject to the l
same defect shall be functionally tested within l 90 days from determining snubber inoperability. This testing requirement shall be independent of the requirements in 4.7.7.2.d(2) above.
ll lt l
l l
l
! DAVIS-BESSE, UNIT 1 3/4 7-24 l
I
-m---r m--,_..4.--, . , .__.%_ . _ . _ , - , _,y ,,y r,.,y- , , ,.,. , , , - , . - - - _ . _ . , , . , m-.- -.--, ,, , . - - , - , , , 3..,... . ,_-,,._
TABLE 3.7-3a
,2,3 e SAFETY RELATED HYDRAULIC SNUBBER SYSTEMS 1 AUXILIARY FEEDWATER MAIN STEAM -
COMPONENT COOLING MAKEUP & PURIFICATION CONTAINMENT SPRAY PRESSURIZER CORE FLOOD REACTOR COOLANT SYSTEM DECAY HEAT REMOVAL SERVICE WATER DEISEL GENERATOR EXHAUST SPENT FUEL POOL HIGH PRESSURE INJECTION STEAM GENERATOR MAIN FEEDWATER MISCELLANEOUS LIQUID RADWASTE (ECCS DRAIN)
TABLE 3.7-3b 1 ,2,3,4 SAFETY RELATED MECHANICAL SNUBBER SYSTEMS AUXILIARY FEEDWATER MAICUP & PURIFICATION CONTAINMENT VENTILATION REACTOR COOLANT SYSTEM (HYDROGEN RECOMBINER) REACTOR COOLANT SYSTEM DECAY HEAT REMOVAL SAMPLING HIGH PRESSURE INJECTION SERVICE WATER MAIN STEAM STEAM GENERATOR DRAIN F
I Snubbers may be added to, or removed from, safety-related systems and their assigned groups without prior Licensing Amendment to Table 3.7-3a/b provided that a revision to Table 3.7-3a/b is included with the next License Amendment request.
2 Inaccessible snubbers are defined as those located: (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.
3 Snubbers are divided into four (4) groups: " Accessible" --Group 1 and
" Inaccessible" - Group II (see note 2) for either hydraulic or mechanical.
4 Safety related snubbers are those covered by the criteria in 10CFR50 Appendix A and listed in the latest revision of applicable surveillance test procedure (s).
A DAVIS-BESSE, UNIT 1 3/4 7-25
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PLANT SYSTEMS RARRR PLANT SYSTEMS j 3/4/7.7 SNUBBERS BASES l 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 excluded from this inspection program are those installed 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.
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.
- 2. For functional test
- a. The snubber 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 determined by the aumber of inoperable snubbers found during an inspection.
' 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 250 may not be used to lengthen the required inspection interval. Any inspection whose results 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 gener-ically 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.
When a snubber is found inoperable, 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 degradation on the supported component or system.
DAVIS-BESSE, UNIT 1 B 3/4 7-Sa
PLANT SYSTEMS RASES To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested at 18 month intervals. Selection of a representative sample of 10% provides a confi-dence level of approximately 95% that 90% to 100% of the snubbers in the plant will be OPERABLE within acceptance limits. 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 i
for further action or testing.
In cases where the cause of failure ha's 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 u 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.
To minimize personnel exposures, snubbers, installed in high radiation zones or in especially difficult to remove locations, may be exempted ll (e.g., greater than 50,000 lbs. capacity) from these functional testing requirements provided the OPERABILITY of these snubbers was demonstrated during functional testing at either the completion of their fabrication or at a subsequent date.
DAVIS-BESSE, UNIT 1 B 3/4 7-5b
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