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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20056C0781993-03-16016 March 1993 Proposed Tech Specs Changes,Incorporating Editorial Cleanup ML20128E6811993-01-29029 January 1993 Proposed Tech Specs for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases ML20128E5501993-01-29029 January 1993 Proposed Tech Specs Re Steam Generator Repair Criteria B14087, Proposed Tech Specs Re Steam Generator Repair Criteria1992-07-31031 July 1992 Proposed Tech Specs Re Steam Generator Repair Criteria ML20062H4371990-11-27027 November 1990 Proposed Tech Specs,Adding locked-closed Manual Valve & Removing solenoid-operated Containment Isolation Valve ML20059F0011990-08-25025 August 1990 Proposed Tech Specs Re ESFAS Instrumentation B13597, Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability1990-07-26026 July 1990 Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability B13570, Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases1990-07-0505 July 1990 Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases B13555, Proposed Tech Specs Re Establishment of Limit of 160 Failed Fuel Rods for Cycle 16 Operation1990-06-25025 June 1990 Proposed Tech Specs Re Establishment of Limit of 160 Failed Fuel Rods for Cycle 16 Operation B13380, Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal1989-09-29029 September 1989 Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal ML20245J1451989-08-0404 August 1989 Proposed Tech Specs Re Containment Air Recirculation Sys, Water Level - Storage Pool & Fuel Storage Bldg Air Cleanup Sys ML20248D7711989-08-0202 August 1989 Proposed Tech Spec 3/4.5.1 Revising ECCS to Reflect Component Configurations Following 1989 Refueling Outage Mods to ECCS to Resolve Single Failure Concerns Identified on Three Separate Occassions B13327, Proposed Tech Specs Incorporating Proposed Changes Agreed to During 890330 NRC Meeting & Subsequent Conference Calls, Proposed Changes Necessitated by New Switchgear Bldg Mods & Clarification of Level 1 Undervoltage Surveillance Tests1989-08-0101 August 1989 Proposed Tech Specs Incorporating Proposed Changes Agreed to During 890330 NRC Meeting & Subsequent Conference Calls, Proposed Changes Necessitated by New Switchgear Bldg Mods & Clarification of Level 1 Undervoltage Surveillance Tests ML20248B2771989-07-31031 July 1989 Proposed Tech Specs Re Fire Detection & Spray &/Or Sprinkler Sys B13284, Proposed Tech Spec 3.6 Re ECCS1989-07-31031 July 1989 Proposed Tech Spec 3.6 Re ECCS B13314, Proposed Tech Specs 1.37,3/4.3.1,3.3.3.9,3/4 9.2,Bases 2.2.1,3/4.3.3.9 & 3/4.3.4 & Tables 2.2-1,3.3-1,3.3-1a,4.3-1, 3.3-2,4.3-2,3.3-7 & 4.3-6 Re Reactor Protection Sys & Nuclear Instrumentation Sys1989-07-28028 July 1989 Proposed Tech Specs 1.37,3/4.3.1,3.3.3.9,3/4 9.2,Bases 2.2.1,3/4.3.3.9 & 3/4.3.4 & Tables 2.2-1,3.3-1,3.3-1a,4.3-1, 3.3-2,4.3-2,3.3-7 & 4.3-6 Re Reactor Protection Sys & Nuclear Instrumentation Sys B13295, Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage1989-07-28028 July 1989 Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements & RCS Operational Leakage B13292, Proposed Tech Specs,Supporting Cycle 161989-07-28028 July 1989 Proposed Tech Specs,Supporting Cycle 16 B13181, Proposed Tech Spec Sections 3/4.4,3/4.6 & 3/4.7 Re RCS1989-06-30030 June 1989 Proposed Tech Spec Sections 3/4.4,3/4.6 & 3/4.7 Re RCS B13221, Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes1989-06-29029 June 1989 Proposed Tech Specs Re Inservice Insp of Steam Generator Tubes & Acceptance Criteria for Tubes B13269, Proposed Tech Specs Sections 2.0 & 3/4.3 Re Safety Limits & Limiting Safety Sys Settings & Instrumentation1989-06-23023 June 1989 Proposed Tech Specs Sections 2.0 & 3/4.3 Re Safety Limits & Limiting Safety Sys Settings & Instrumentation ML20245D2281989-06-15015 June 1989 Proposed Tech Specs Re Cycle 15 Operation Coastdown Analysis & Operation A07433, Proposed Tech Specs Re Leakage Detection Sys1989-05-30030 May 1989 Proposed Tech Specs Re Leakage Detection Sys B13256, Proposed Tech Specs,Revising Administrative Controls for Radiological Effluent Monitoring Manual1989-05-25025 May 1989 Proposed Tech Specs,Revising Administrative Controls for Radiological Effluent Monitoring Manual B13169, Proposed Tech Specs,Revising Sections 3.6, Core Cooling Sys, 3.7, Min Water Vol & Boron Concentration in Refueling Water Storage Tank & 4.3, Core Cooling Sys-Periodic Testing, to Combine Into New Section 3.6, Eccs1989-04-30030 April 1989 Proposed Tech Specs,Revising Sections 3.6, Core Cooling Sys, 3.7, Min Water Vol & Boron Concentration in Refueling Water Storage Tank & 4.3, Core Cooling Sys-Periodic Testing, to Combine Into New Section 3.6, Eccs B13208, Proposed Tech Specs Supporting Operation of Cycle 151989-04-30030 April 1989 Proposed Tech Specs Supporting Operation of Cycle 15 ML20245F2581989-04-25025 April 1989 Proposed Tech Specs Re Administrative Controls in High Radiation Area B13201, Proposed Tech Specs Re Containment Integrity,Internal Pressure & Air Recirculation Sys to Allow Four Containment Air Recirculation Fan Motor HXs to Be Cleaned or Replaced While at Power1989-03-31031 March 1989 Proposed Tech Specs Re Containment Integrity,Internal Pressure & Air Recirculation Sys to Allow Four Containment Air Recirculation Fan Motor HXs to Be Cleaned or Replaced While at Power B13098, Proposed Tech Specs Re Administrative Controls & Organizational Charts1989-03-13013 March 1989 Proposed Tech Specs Re Administrative Controls & Organizational Charts B13151, Proposed Tech Specs 3/4.1, Reactivity Control Sys1989-03-0606 March 1989 Proposed Tech Specs 3/4.1, Reactivity Control Sys B13127, Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-371989-03-0101 March 1989 Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-37 1999-08-24
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211G1341999-08-24024 August 1999 Proposed Tech Specs Replacement Pages,Incorporating Addl Info for Pending TS Change ML20210D4331999-07-31031 July 1999 Material Recovery Plan, for Haddam Neck Plant ML20210F5121999-07-28028 July 1999 Rev 0 to CY-HP-0031,Haddam Neck Plant Health Physics Dept Technical Support Document, Bounding Dose Assessment for Offsite Radioactive Matls ML20195C8591999-06-0303 June 1999 Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20199K4861999-01-18018 January 1999 Proposed Tech Specs to Relocate Requirements for Seismic Monitoring Instrumentation from Section 3/4.3.3.3 of TSs to TRM ML20155F9851998-10-30030 October 1998 Proposed Tech Specs Re Editorial Changes & Typographical Corrections ML20155G0061998-10-30030 October 1998 Proposed Tech Specs Correcting Amend Number on Pages Not Changed by Amend 193 ML20155G3561998-10-30030 October 1998 Proposed Tech Specs Updating Pages for Amend 194 Re Seismic Monitors ML20154A7401998-09-24024 September 1998 Spent Fuel Pool Cooling & Makeup Monitoring Program ML20237C4561998-08-13013 August 1998 Proposed Tech Specs Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20249B7841998-06-12012 June 1998 Rev 1 to CY-HP-0025,HNP Health Physics Dept Technical Support Document, Background Cs-137 Concentration in Soil ML20248L3291998-06-0202 June 1998 Proposed Tech Specs Incorporating Proposed Changes Re Seismic Monitoring Into HNP TS ML20247Q6491998-05-0707 May 1998 Revised Nuclear Emergency Planning Operating Procedure Index ML20247E9991998-05-0707 May 1998 Proposed Tech Specs,Reflecting Permanently Defueled Condition of HNP ML20217Q9101998-04-30030 April 1998 Matl Recovery Plan ML20212A6681997-09-29029 September 1997 Final Rept Unrestricted Release Confirmatory Survey Program ML20206D1071997-06-30030 June 1997 Rev 10 to ODCM for Hnp ML20206D1031997-05-31031 May 1997 Rev 10 to Radioactive Effluent Monitoring Manual ML20148G9191997-05-30030 May 1997 Rev 0 to Cyap Haddam Neck Plant Radiation Protection Improvement Plan ML20140E1261997-05-30030 May 1997 Proposed Tech Specs Re Certified Fuel Handler ML20140D5471997-05-30030 May 1997 Proposed Ts,Reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20140E1571997-05-21021 May 1997 Rev 1 to NTM-7.084, Cyap Certified Fuel Handler Recertification Training Program Implementing Procedure ML20140E1391997-05-21021 May 1997 Rev 1 to NTM-7.083, Cyap Certified Fuel Handler Initial Certification Training Program Implementing Procedure ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20216B3071997-02-28028 February 1997 Rev 8 to ODCM for Haddam Neck Plant ML20249B7761997-02-19019 February 1997 Rev 4 to Hwm 15.1-7, Spill Prevention Control & Countermeasure Plan ML20134J6511997-01-31031 January 1997 Proposed Tech Specs Section 6, Administrative Controls ML20134L2551997-01-16016 January 1997 Rev 0 to Integrated Plan for Improvement of Mgt Stds at Connecticut Yankee Nuclear Power Station ML20134L2701997-01-0303 January 1997 Rev 0 to Design Control Process ML20134L2511996-12-31031 December 1996 Rev 0 to Integrated Plan for Improving CA Program at Connecticut Yankee ML20138G6871996-12-24024 December 1996 Proposed Tech Specs Incorporating Changes to Revise Section 6, Administrative Controls & Reflect New Organizational Responsibilities & Titles ML20059L0701994-01-25025 January 1994 Proposed Tech Spec 3.7.1.1.2,Action C Re Atmospheric Steam Dump Capability B14619, Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days1993-11-0202 November 1993 Proposed Tech Specs Increasing AOT for Charging Pump from 72 Hours to Seven Days B14627, Reactor Containment Bldg ILRT Rept. W/1993-09-30030 September 1993 Reactor Containment Bldg ILRT Rept. W/ B14542, Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 21993-08-31031 August 1993 Proposed Tech Specs Permanently Removing Ability for Plant to Operate W/Three Loops While in Modes 1 or 2 ML20057A6241993-08-31031 August 1993 Core Xviii Startup Physics Test Rept ML20056E6281993-08-18018 August 1993 Proposed Tech Specs Re Onsite Power Distribution ML20056D0521993-07-26026 July 1993 Proposed Tech Specs Modifying Action Statement a of TS Section 3.5.1 & Moving Surveillance Requirement 4.5.1.b from TS Section 3/4.5.1 to TS Section 3/4.5.2 as Surveillance Requirement 4.5.2.c ML20056C7471993-07-16016 July 1993 Proposed Tech Specs Changing Submittal Frequency of Radioactive Effluent Release Rept from Semiannual to Annual ML20056C0781993-03-16016 March 1993 Proposed Tech Specs Changes,Incorporating Editorial Cleanup ML20128E6811993-01-29029 January 1993 Proposed Tech Specs for RTS Instrumentation,Srs & Bases & ESFAS Instrumentation,Trip Setpoints,Srs & Bases ML20128E5501993-01-29029 January 1993 Proposed Tech Specs Re Steam Generator Repair Criteria ML20127E2901993-01-11011 January 1993 Rev 43 to Corporate Organization for Nuclear Incidents (Coni) Procedure Coni 1.02,page 7.2-2 of 2,Figure 7.2, Cero Staff-Managers Annual On-Call Schedule B14087, Proposed Tech Specs Re Steam Generator Repair Criteria1992-07-31031 July 1992 Proposed Tech Specs Re Steam Generator Repair Criteria ML20062H4371990-11-27027 November 1990 Proposed Tech Specs,Adding locked-closed Manual Valve & Removing solenoid-operated Containment Isolation Valve ML20217A6311990-11-14014 November 1990 Rev 0 to Haddam Neck Plant Reactor Containment Bldg Integrated Leak Rate Test ML20058H0611990-10-31031 October 1990 Core Xvi Startup Physics Test Rept ML20059F0011990-08-25025 August 1990 Proposed Tech Specs Re ESFAS Instrumentation B13597, Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability1990-07-26026 July 1990 Proposed Tech Spec Page 3/4 7-3 Re Auxiliary Feedwater Sys Operability B13570, Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases1990-07-0505 July 1990 Proposed Tech Specs Revising Sections 3.4.6.2.f,4.4.6.2.1.g & 4.4.6.2.1.h Re RCS Leakage & Low Temp Overpressurization Protection Sys Bases 1999-08-24
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Text
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Docket No. 50-213 B12543 f
Attachment 1 Haddam Neck Plant Proposed Revision to Technical Specifications Snubber Testing and Surveillance J -
1 i
t l
1 i
l
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l June,1987 l
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! B706080299 870601'~
PDR f
P ADOCK 05000213 PDR,
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3.19 Snubbers Applicability: This specification applies to snubbers which are attached to the reactor coolant system and all other safety-related systems whose structural integrity is needed to be maintained during and following a seismic or other event initiating dynamic loads.
Objective: To assure reactor coolant system and other safety related system motions are adequately restricted should a design basis earthquake or other transient occur.
Specification: A. During Modes 1, 2, 3, and 4 (Modes 5 and 6 for snubbers located on systems required operable in those Modes) all safety-related snubbers shall be maintained in an operable condition except as noted in 3.19.B and 3.19.C below. Snubbers on nonsafety-related systems shall be operable if their failure or failure of the system on which they are installed would have an adverse effect on any safety-related system.
B. With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to operable status and perform an engineering evaluation per Specification 4.13.c on the supported component or declare the supported system inoperable and follow the appropriate specification for that system.
Bases All snubbers are required to be operable to ensure that the structuralintegrity of the reactor coolant system and all other safety-related systems are 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.
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.
3-38 w- w
4.13 Snubbers Applicability: This specification applies to the snubbers required to be
- operable in accordance with Specification 3.19.
Objective: To provide assurance of snubber operability over the plant ,
service lifetime.
l Specification: Each snubber shall be demonstrated operable by performance of the following augmented inservice inspection program.
A. Visual Inspection Schedule All snubbers shall be visually inspected in accordance with the following schedule:
Number of Snubbers Found Inoperable During Inspection Next Required Or During Inspection Interval Inspection Interval * #
0 18 months + 25 %
1 12 months I 25%
2 6 months ! 25%
, 3, 4 124 days i 25 %
l 5, 6, 7 62 days 1 25 %
- - 8 or more 31 days 1 25 %
4 The snubbers may be categorized into two groups:. those l
accessible, and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
- The inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
B. Visual Inspection Acceptance Criteria Visual inspection shall verify (1) that there are no. visible indications of damage' or impaired operability, and (2) attachments to the foundation or supporting structure are -
secure. The inspection will also identify indications of -
, excessive leakage from hydraulic snubber reservoirs or
- connections. Snubbers which appear inoperable as a result of i visual inspections may be determined operable for the purpose i
of establishing the next visual inspection interval, provided that l (1) the cause of the rejection is clearly established ' and
! remedied for that particular snubber and for other snubbers
^
that may be generically ' susceptible, and (2) the affected snubber is functionally tested in the as-found condition and determined operable per Specifications 4.13.D or 4.13.E, as applicable.
I 4-26
C. Functional Tests At least once per 18 months during shutdown, a representative sample of at least 10% of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test. For each snubber that does not meet.the functional test acceptance criteria of Specification 4.13.D or 4.13.E, an additional 5% of that type of snubber shall be functionally tested unti! no more failures are found or until all snubbers of that type have been functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. At least one (1) snubber shal1 be selected from each piping system containing snubbers. At least one (1) snubber shall be tested from the full range of snubber manufacturers and snubber sizes used. In the selection of the representative sample, consideration shall be given to other effects on snubbers such as vibration in the vicinity of equipment such as pumps, motors, turbines, valves, etc.
or fluid forces from a relief valve discharge.
Functional test samples shall be rotated such that different snubbers are tested at each test interval.
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period. If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results.of these snubbers may not be included for the re-sampling.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency, all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The purpose of this engineering evaluation shall be to determine if the 4-26B
components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service requirement.
D. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
- 1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both i
tension and compression.
j 2. Snubber bleed, or release rate, where required, is j within the specified range in compression or tension.
! For snubbers specifically required not to displace
! under continuous load, the ability of the snubber to R withstand load without displacement shall be-verified.
1 E. Mechanical Snubbers Functional Test Acceptance Criteria i
l The mechanical snubber functional test shall verify that:
- 1. The force that initiates free movement of the
~
j snubber rod in either tension or compression is less j than the specified maximum drag force.
1 4 2. Activation (restraining action) is achieved within the
! specified range of velocity or ace-leration in both j tension and compression.
4
- 3. Snubber release rate, where required, is within the -
specified range in compression or tension. For i
snubbers specifically required not to displace under continuous load, the ability of the snubber .to withstand load without displacement shall be 1 verified.
i F. Snubber Service Life Monitoring i
, A record of the service life of each snubber, the date at
! which the designated service ' life commences -and the installation and maintenance records on' which the designated service life is based shall ~be maintained as
- required by Specification 6.10.2.h.
J ;
Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation l and maintenance records for each safety-related snubber .i j shall be reviewed to verify that the indicated service life o has not been exceeded or will not be exceeded prior to the l next scheduled snubber service life review. - If ' the
- indicated service life will be exceeded prior to the next l 4-26C l
I
,. . e scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This i reevaluation, replacement or reconditioning shall be indicated in the records.
I Bases 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 number 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 less than 25%) 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 generically susceptible and verified by inservice 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.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18-month intervals. These tests will include stroking of snubbers to verify freedom of movement over the full stroke, restraining characteristics, and drag force (if applicable). Ten percent (10%) of the total of each type of snubber represents an adequate sampling for these tests. Observed failures on these samples require testing of additional units.
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance program.
The service life is evaluated via manufacturer input and information with consideration of snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, high temperature areas, location of potential fluid transient loading, etc.) The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of age and operating conditions. (Due to implementation of the snubber service life monitoring program after several years of plant operation, the O Nrical records to date may be incomplete.) Snubber service life records will provide a statistical basis for future consideration of snubber service life.
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