|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211K8411999-09-0202 September 1999 Proposed Tech Specs Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band ML20210J1431999-07-29029 July 1999 Proposed Tech Specs Changes to ITSs ML20209D3651999-07-0808 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising Allowable Value for CTS Table 3.3-4,functional Unit 8.a.,4 Kv Undervoltage - Loss of Voltage & Functional Unit 8.b.,4 Kv Undervoltage - Grid Degraded Voltage ML20209C2081999-06-30030 June 1999 Proposed Tech Specs Re Temporary Change to CTS Without Action to Reduce Power ML20195G0331999-06-11011 June 1999 Proposed Tech Specs Pages,Revising TS 3.7.1.6 & Bases by Modifying LCO to Require Four ARVs to Be Operable, Eliminating Use of Required in Action Statements & Adding New Action for Three or More ARVs Inoperable ML20195F7961999-06-10010 June 1999 Proposed Tech Specs,Revising Z,S & Allowable Value Terms for Current TS Table 3.3-4,functional Unit 7.b,automatic Switchover to Containment Sump (RWST Level - Low-Low) ML20206Q9041999-05-11011 May 1999 Proposed Tech Specs 3/4.7.5, Ultimate Heat Sink, Proposing Addl Required Zcaion for Restoring Ultimate Heat Sink to Operable Status within Completion Time of 8 H ML20196K7321999-03-26026 March 1999 Proposed Tech Specs Converting to Improved Tech Specs ML20205A2111999-03-25025 March 1999 Markups of Current & Improved TS Re TS Conversion Application ML20207J2021999-03-0505 March 1999 Proposed Tech Specs Re Conversion to ITS Section 1,0,3.1, 3.2,3.3,3.4,3.6,3.7,3.8,3.9,4.0 & 5.0 ML20199G7281999-01-15015 January 1999 Proposed Tech Specs SR 4.7.3b Deleting During SD Requirement & Reflect Appropriate Plant Conditions in Associated 3/4.7.3 Bases ML20199F4511999-01-12012 January 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising TS 3/4.7.5 by Adding New Action Statement Requiring Verification of Operability of Two RHR Trains,Or Initiation of Power Reduction with Only One RHR Train Operable ML20198P1211998-12-29029 December 1998 Proposed Tech Specs to Incorporate Revised Heatup & Cooldown Limit Curves & Revised Cold Overpressure Mitigation Sys (COMS) PORV ML20197H6701998-12-0808 December 1998 Proposed Corrected Tech Spec Page 4.0-2 Increasing Spent Fuel Storage Capacity ML20196G6161998-12-0202 December 1998 Proposed Tech Specs Section 3.3, Instrumentation ML20196B4901998-11-24024 November 1998 Proposed Tech Specs Pages & follow-up Items Re Proposed Conversion to TS Section 1.0,3.4,3.5 & 3.6,per 980828 RAI ML20155H6841998-11-0606 November 1998 Proposed Tech Specs Pages,Revising TS Bases Section 3/4.4.4, Relief Valves ML20155H6121998-11-0606 November 1998 Proposed Tech Specs Bases 3/4.7.1.2 Re Afws ML20154S5721998-10-23023 October 1998 Proposed Tech Specs Section 3.5.1,increasing AOT in Action B. to 24 Hours in Lieu of Current AOT of One Hour ML20154S5911998-10-23023 October 1998 Proposed Tech Specs Sections 3.1, Reactivity Control Sys, 3.2, Power Distribution Sys, 3.4, RCS, 3.5, ECCS & 5.0, Administrative Controls ML20154R9321998-10-20020 October 1998 Proposed Tech Specs 3/4.3,changing ESFAS Functional Units 6.f,8.a & 8.b ML20153H0431998-09-24024 September 1998 Proposed Tech Specs Pages Re RAI on Application for Amend to License NPF-42,incorporating Changes to TS Sections 3.4 & 5.0 ML20236Y2771998-08-0505 August 1998 Proposed Tech Specs Sections 3.1,3.2,3.5,3.9 & 4.0 Converting to Improved Std Tech Specs ML20236R4781998-07-17017 July 1998 Proposed Tech Specs 3/4.7.5 Revising UHS by Adding Temporary New Action Statement ML20236G8321998-06-30030 June 1998 Proposed Tech Specs Re Section 3.6, Containment Sys ML20247F8611998-05-0808 May 1998 Proposed Tech Specs 3/4.3.2,Table 3.3-3,revising Functional Unit 7.b.,RWST Level low-low Coincident W/Safety Injection, by Adding New Action Statement ML20216J8291998-03-20020 March 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity & Increasing Max Nominal Fuel Enrichment to 5.0 W/O (Nominal Weight Percent) U-235 ML20202C4561998-02-0404 February 1998 Proposed Tech Specs 3/4.3 Re Changes to ESFAS Functional Units 6.f,8.a & 8.b ML20202D1251998-02-0404 February 1998 Proposed Tech Specs 3/4.2.4 Re Quadrant Power Tilt Ratio ML20199H3551998-01-28028 January 1998 Proposed Tech Specs 6.3 & 6.12,reflecting Position Change within Organization ML20198P5001998-01-15015 January 1998 Proposed Tech Specs Replacement Pages Clarifying Bases in 970-902 LAR Re Auxiliary Feedwater Sys ML20198Q9411997-11-0606 November 1997 Proposed Tech Specs Bases Section 3/4.8.1,3/4.8.2 & 3/4.8.3 for Installation of Spare Battery Chargers ML20217K2181997-10-17017 October 1997 Proposed Tech Specs 4.5.2b,revising Surveillance Requirement to Vent ECCS Pump Casings ML20217B6161997-09-19019 September 1997 Proposed Tech Specs Bases Section B3/4.9.2,adding Info Re Role of Source of Power Supplied to One Source Range Neutron Flux Monitor in Determining Operability of Monitor in Mode 6 ML20216F7311997-09-0606 September 1997 Proposed Tech Specs,Alleviating Need for Enforcement Discretion Granted by NRC on 970905 ML20216F6911997-09-0505 September 1997 Proposed Tech Specs,Requesting NRC Exercise Discretion Re Compliance W/Srs 4.8.1.1.2.g.2)c)2,4.8.1.1.2.g.3)d) & 4.8.1.1.2.g.4)d) ML20216D1551997-09-0202 September 1997 Proposed Tech Specs,Adding Requirements for Essential Svc Water Flowpaths to turbine-driven AFW Pump ML20196J4071997-07-29029 July 1997 Proposed Tech Specs Revising Wording of Action Statement 5a to TS Table 3.3-1, Reactor Trip Sys Instrumentation ML20141G7721997-07-0303 July 1997 Proposed Tech Specs Section 5.3.1 Incorporating Addl Info Into TS 6.9.1.9, Colr ML20154Q2441997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20151T0151997-05-15015 May 1997 Proposed Tech Specs Re Response to Request for Addl Info on Conversion to Improved Tech Specs ML20195J8241997-05-15015 May 1997 Proposed Tech Specs Re Rev to Increase Spent Fuel Pool Storage Capacity ML20198J6551997-05-15015 May 1997 Proposed Tech Specs Re Response to RAI on Proposed Conversion to Ists,Section 3.8, Electrical Power Sys ML20138B9121997-04-23023 April 1997 Proposed Tech Specs,Revising TS 3/4.9.4 Containment Bldg Penetrations & Associated Bases Section to Allow Selected Containment Isolation Valves to Be Opened Under Administrative Controls During Periods of Core Alterations ML20137X3371997-04-15015 April 1997 Proposed Tech Specs 6.8.5.d Re Reactor Coolant Pump Flywheel Insp Program ML20147F8241997-03-21021 March 1997 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insp Program ML20137C2031997-03-19019 March 1997 Proposed Tech Specs Bases Pp Reflecting Corrections to Ref Made on Those Pp ML20137B9371997-03-18018 March 1997 Proposed Tech Specs,Revising TS Section 5.3.1,fuel Assemblies to Allow Use of Alternate Zr-based Fuel Cladding Matl ZIRLO ML20137B9141997-03-18018 March 1997 Proposed Tech Specs,Revising TS SR 4.5.2.c to Clarify When Containment Entry Visual Insp Is Required ML20134Q0811997-02-17017 February 1997 Proposed Tech Specs,Revising TS 1.7, Containment Integrity, TS 3/4.6.1, Containment Integrity & TS 3/4.6.3, Containment Isolation Valves 1999-09-02
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K8411999-09-0202 September 1999 Proposed Tech Specs Deleting Inequality Signs from Trip Setpoints in SR 3.3.5.3 & Reflecting Info on Calibr Tolerance Band ML20210J1431999-07-29029 July 1999 Proposed Tech Specs Changes to ITSs ML20209D3651999-07-0808 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising Allowable Value for CTS Table 3.3-4,functional Unit 8.a.,4 Kv Undervoltage - Loss of Voltage & Functional Unit 8.b.,4 Kv Undervoltage - Grid Degraded Voltage ML20209C2081999-06-30030 June 1999 Proposed Tech Specs Re Temporary Change to CTS Without Action to Reduce Power ML20195G0331999-06-11011 June 1999 Proposed Tech Specs Pages,Revising TS 3.7.1.6 & Bases by Modifying LCO to Require Four ARVs to Be Operable, Eliminating Use of Required in Action Statements & Adding New Action for Three or More ARVs Inoperable ML20195F7961999-06-10010 June 1999 Proposed Tech Specs,Revising Z,S & Allowable Value Terms for Current TS Table 3.3-4,functional Unit 7.b,automatic Switchover to Containment Sump (RWST Level - Low-Low) ML20206Q9041999-05-11011 May 1999 Proposed Tech Specs 3/4.7.5, Ultimate Heat Sink, Proposing Addl Required Zcaion for Restoring Ultimate Heat Sink to Operable Status within Completion Time of 8 H ML20196K7321999-03-26026 March 1999 Proposed Tech Specs Converting to Improved Tech Specs ML20205A2111999-03-25025 March 1999 Markups of Current & Improved TS Re TS Conversion Application ML20207J2021999-03-0505 March 1999 Proposed Tech Specs Re Conversion to ITS Section 1,0,3.1, 3.2,3.3,3.4,3.6,3.7,3.8,3.9,4.0 & 5.0 ML20199G7281999-01-15015 January 1999 Proposed Tech Specs SR 4.7.3b Deleting During SD Requirement & Reflect Appropriate Plant Conditions in Associated 3/4.7.3 Bases ML20199F4511999-01-12012 January 1999 Proposed Tech Specs Pages Re Amend to License NPF-42, Revising TS 3/4.7.5 by Adding New Action Statement Requiring Verification of Operability of Two RHR Trains,Or Initiation of Power Reduction with Only One RHR Train Operable ML20198P1211998-12-29029 December 1998 Proposed Tech Specs to Incorporate Revised Heatup & Cooldown Limit Curves & Revised Cold Overpressure Mitigation Sys (COMS) PORV ML20207J9621998-12-18018 December 1998 Rev 1 to TRM for Wolf Creek Generating Station,Unit 1 ML20197H6701998-12-0808 December 1998 Proposed Corrected Tech Spec Page 4.0-2 Increasing Spent Fuel Storage Capacity ML20196G6161998-12-0202 December 1998 Proposed Tech Specs Section 3.3, Instrumentation ML20196B4901998-11-24024 November 1998 Proposed Tech Specs Pages & follow-up Items Re Proposed Conversion to TS Section 1.0,3.4,3.5 & 3.6,per 980828 RAI ML20195E7671998-11-10010 November 1998 Rev 0 to EPP 01-2.4, Core Damage Assessment Guidance ML20155H6121998-11-0606 November 1998 Proposed Tech Specs Bases 3/4.7.1.2 Re Afws ML20155H6841998-11-0606 November 1998 Proposed Tech Specs Pages,Revising TS Bases Section 3/4.4.4, Relief Valves ML20154S5911998-10-23023 October 1998 Proposed Tech Specs Sections 3.1, Reactivity Control Sys, 3.2, Power Distribution Sys, 3.4, RCS, 3.5, ECCS & 5.0, Administrative Controls ML20154S5721998-10-23023 October 1998 Proposed Tech Specs Section 3.5.1,increasing AOT in Action B. to 24 Hours in Lieu of Current AOT of One Hour ML20154R9321998-10-20020 October 1998 Proposed Tech Specs 3/4.3,changing ESFAS Functional Units 6.f,8.a & 8.b ML20153H0431998-09-24024 September 1998 Proposed Tech Specs Pages Re RAI on Application for Amend to License NPF-42,incorporating Changes to TS Sections 3.4 & 5.0 ML20236Y2771998-08-0505 August 1998 Proposed Tech Specs Sections 3.1,3.2,3.5,3.9 & 4.0 Converting to Improved Std Tech Specs ML20236R4781998-07-17017 July 1998 Proposed Tech Specs 3/4.7.5 Revising UHS by Adding Temporary New Action Statement ML20236G8321998-06-30030 June 1998 Proposed Tech Specs Re Section 3.6, Containment Sys ML20247F8611998-05-0808 May 1998 Proposed Tech Specs 3/4.3.2,Table 3.3-3,revising Functional Unit 7.b.,RWST Level low-low Coincident W/Safety Injection, by Adding New Action Statement ML20216J8291998-03-20020 March 1998 Proposed Tech Specs,Increasing Spent Fuel Storage Capacity & Increasing Max Nominal Fuel Enrichment to 5.0 W/O (Nominal Weight Percent) U-235 ML20202D1251998-02-0404 February 1998 Proposed Tech Specs 3/4.2.4 Re Quadrant Power Tilt Ratio ML20202C4561998-02-0404 February 1998 Proposed Tech Specs 3/4.3 Re Changes to ESFAS Functional Units 6.f,8.a & 8.b ML20199H3551998-01-28028 January 1998 Proposed Tech Specs 6.3 & 6.12,reflecting Position Change within Organization ML20198P5001998-01-15015 January 1998 Proposed Tech Specs Replacement Pages Clarifying Bases in 970-902 LAR Re Auxiliary Feedwater Sys ML20198Q9411997-11-0606 November 1997 Proposed Tech Specs Bases Section 3/4.8.1,3/4.8.2 & 3/4.8.3 for Installation of Spare Battery Chargers ML20217K2181997-10-17017 October 1997 Proposed Tech Specs 4.5.2b,revising Surveillance Requirement to Vent ECCS Pump Casings ML20217B6161997-09-19019 September 1997 Proposed Tech Specs Bases Section B3/4.9.2,adding Info Re Role of Source of Power Supplied to One Source Range Neutron Flux Monitor in Determining Operability of Monitor in Mode 6 ML20216F7311997-09-0606 September 1997 Proposed Tech Specs,Alleviating Need for Enforcement Discretion Granted by NRC on 970905 ML20216F6911997-09-0505 September 1997 Proposed Tech Specs,Requesting NRC Exercise Discretion Re Compliance W/Srs 4.8.1.1.2.g.2)c)2,4.8.1.1.2.g.3)d) & 4.8.1.1.2.g.4)d) ML20216D1551997-09-0202 September 1997 Proposed Tech Specs,Adding Requirements for Essential Svc Water Flowpaths to turbine-driven AFW Pump ML20196J4071997-07-29029 July 1997 Proposed Tech Specs Revising Wording of Action Statement 5a to TS Table 3.3-1, Reactor Trip Sys Instrumentation ML20141G7721997-07-0303 July 1997 Proposed Tech Specs Section 5.3.1 Incorporating Addl Info Into TS 6.9.1.9, Colr ML20151T0151997-05-15015 May 1997 Proposed Tech Specs Re Response to Request for Addl Info on Conversion to Improved Tech Specs ML20198J6551997-05-15015 May 1997 Proposed Tech Specs Re Response to RAI on Proposed Conversion to Ists,Section 3.8, Electrical Power Sys ML20154Q2441997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20195J8241997-05-15015 May 1997 Proposed Tech Specs Re Rev to Increase Spent Fuel Pool Storage Capacity ML20138F3371997-04-30030 April 1997 Rev 0 to Offsite Dose Calculation Manual ML20138B9121997-04-23023 April 1997 Proposed Tech Specs,Revising TS 3/4.9.4 Containment Bldg Penetrations & Associated Bases Section to Allow Selected Containment Isolation Valves to Be Opened Under Administrative Controls During Periods of Core Alterations ML20137X3371997-04-15015 April 1997 Proposed Tech Specs 6.8.5.d Re Reactor Coolant Pump Flywheel Insp Program ML20147F8241997-03-21021 March 1997 Proposed Tech Specs Re Reactor Coolant Pump Flywheel Insp Program ML20137C2031997-03-19019 March 1997 Proposed Tech Specs Bases Pp Reflecting Corrections to Ref Made on Those Pp 1999-09-02
[Table view] |
Text
'
, Attaclunent IV to ET 91-0044 Page 1 of 8 ATTACIMENT IV FROPOSED TECllNICAL SPECIFICATION CIIANGES 9103080346 910305 PDR ADOCK 05000482 P PDR
. , - - . - . ~ . ,
t Attachinent41V. to ET 91-0044 l l
. , .' "Page 2;ot 8:
-}
~
iLIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS.
PAGE
.'SECTION f TABLE 3.7-1 MAXIMUM ALLOWABLE--POWER RANGE-N'EUTRON FLUX-HIGH SETPOINT WITH INOPERABLE:
STEAM LINE-SAFETY VALVES DURING FOUR-LOOP
.0PERATION........-............-..................... 3/4 7-2 4 i
-TABLE _3.7-2 : STEAM LINE-SAFETY VALVES PER-LOOP... ................. 3/4 7-3 Auxiliary Feedwater System............................... -3/4:7-4 .
1
-Condensate-Storage Tank.................................. 3/4 7-6 Specific Activity.......,'...............................,. 3/4 7-7
" TABLE'4.7-1:. SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY
-5 AMPLE'ANDfANALYSIS PR0 GRAM......................... 3/4 7 . Mai n = Steam Li ne ' Isol ation ' Val ves. . ... . . . . . . . . . . . . . . . . . . . . . 3/4 7-9 3/4.- 7. 2 ' STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......... 3/4:.7-10 -
- 3/4. 7.' 3'~ COMPONENT COOLING WATER SYSTEM........................... 3/4 7-11
- 3/4.7.4 = ESSENTIAL SERVICE ~ WATER SYSTEM........................... 3/4 7-12 f 3/4.- 7. 5-- ULTIMATE HEAT SINK..-...................................... 3/4 7-13 3/4;7.6- ' CONTROL, ROOM EMERGENCY VENTILATION. SYSTEM................ 3/4.7 3/4.7.7 EMERGENCY EXHAUST SYSTEM................................. 3/4 7-17 3/4.7.8- SNUBBERS..... ........................................... 3/4 7-19 FIGURE ,4.7-1, SAMPLINGLPLAN 2) FOR SNUBBER FUNCTIONAL- TEST. . . . . . . . . 3/4 7-24 3 3/4.-7. 9 -- SEALED SOURCE CONTAMINATION.............................. 3/4.7-25
- TABLE :4.7-2 L SNUBBER VISUAL NSPECTION INTERVAL 1
WOLF' CREEK - UNIT 1 X
I
- Attachment IV 'to ET 91-0044
. Page 3 of 8 P[ANTSYSTEMS
.jc
- f1 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION
'3.7.8 All snubbers shall be-OPERABLE. The only snubbers excluded from the requirement are those installed on nonsafety-related systems and then only if
.their f ailure or f ailure'of the system on which they are installed would have no adverse effect on any safety related system.-
-APPLICABILITY: MODES 1, 2, 3, and 4; MODES 5 and 6 for snubbers located on systems re'qluTred OPERABLE in those MODES.
ACTION:
=With one=or more snubbers inoperable on any system, 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 4.7.8g on the attached component or declare the attached system inopera-ble and follow-the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS u
4.7.8 .Each snubber shall be' demonstrated OPERABLE by performance of the follow-ing augmented -inservice inspection program and the requirements of Specifica-tion 4c0.5,
- a. Inspection Types As 'used in t'h is specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity, b, Visual Inspections -
snubb= = ategerecc =
(InsertA) ==ib,e 4r ==ib,e -eur ,g eter 4 speratier. Each-Of the:0 group (inacce: ible ind ecces:4b'e) may be 4" p00ted 4 ndependently =wei+g tc th ;chedule belev The rct 4
9:erv1:0 vicu:1i nspec-tien Of :ch type Of snubber :hal' be perfcrmed after ^ menth; but jth'n 10 month; cf cc mencing P0i!EP OPER^710F :nd 0h: 11 i n:4ude all hydrauli and mech:nical nubber . I' :!' cr"bbert cf each type are found OPERABLE dur ng the first 'ncer" ice i:c:1 4
Linspectien, the :econd 4ncervice 'icu ' *ntpectier cf that type 05:l' be perf 0rmed Ot' the first ref-ucling cutage.
Other'ite, cub;0guent
-44s0:1 i nspec-t i on:-- o f - g i v en-typ: thcl' be performed 4^ acc:rdance-
"ith the fcilcu ng schedule:
i w
WOLF CREEK - UNIT 'l 3/4 7-19
+
,Attachm3nt IV to ET 91-0044
, Page 4 of 8 Insert A Snubbers are categorized as inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7-2. The visual inspection interval for each type snubber shall be determined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this criteria shall be based upon the previous inspectiop interval as established by the requirements in effect before amendment ( ).
NRC to include the number of the license amendment that implements this change
ype n ,
7 AffachmentIVtoET 91-0044 Page 5 of 8 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) _
iu _< t_#u e.mm- m< rs e ms , _ ,a m,a M [ ebb on [eb od inspect [orL3ert6 0 18 months 25%
1 12 months 1 25%
2 6 mnnths 25%
5,6,7 6 9 cr mere 31 day; _ 25%
Visual Inspection Acceptance Criteria '
c.
Visual inspections shall verify that: (1) there are no visible indi-cations of damage or impaired OPERABILITY, and (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are functional. Snubbers which appear inoperable as a result of visual inspections fay be dctcr-incd OP[rn:LE for the purpose of establishing the next visual inspection interval, provided that: (1) the cause of the rejection is clearly established and
. remedied for that particular snubber and for other snubbers irrespec-tive of type that may be generically susceptible; or (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.8f. ^1' :nubber: cc mccted to on
%0per:bl^ c0=cn hydraulic 'luid-r+servcir chall be counted at i-operablp_ :- S t c~ c . Gnsert83
~
i_ hall _ be_ class 1fied as unacceptabls and may be reclassified acceptabh
- d. Transient tvent Inspections - - -
An inspection shall be performed of all hydraulic and mechanical snub-bers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of opera-tional data and a visual inspection of the systems within 6 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; (2) evaluation of in place snubber piston setting; or (3) stroking the mechanical sne v r through its full range of travel.
^iiie iu>pecLivu inteival ivi cach tge of snubber shall not bc 1:.r-gthened we Lucu vue alep al o Lime v.il655 6 g 6 D 6 T i C prob 4tflt-het-beeft-4defTt4-f4ed-eftd corrected; in that-event-the-4nspeet4en-4nterval may be lengt-hened-ene-+ttp-the f i r 3 t t4mc ;nd two-tteps-thereef+ee4f-no-4eopereble-enebbees--of-4 hat-type w+
found.
sine pivvisivus vi Secuificetica 4.0.2 crc n t opp-liest4e, I
WOLF CREEK - UNIT 1 3/4 7-20
Attachmsnt IV to ET 91-0044 Page 6 of 8 l
1 Insert B All snubbers found connected to an inoperable common hydraulic fluid ;
reservoir shall be counted as unacceptable for determining the next l inspection interval. A review and evaluation shall be performed and documented to determine system operability with an unacceptable snubber. If ;
operability cannot be justified, the system shall be declared inoperable and the ACTION requirements shall be met.
4 Attschm:nt IV to ET 91-0044 Page 7 of 8 Insert C (Table 4.7-2 should be inserted in front of Figure 4.7-1)
TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population Column A- Column B Column C per Categort- Extend Interval Repeat Interval Reduce Interval (Notes 1 and 2) (Notes 3 and 6) (Notes 4 and 6) (Notes 5 and 6) 1 0 0 1 80 0 0 2 100 0 1 4 150 0 3 8 200 2 5 13 300 5 12 25 400 8 18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1: The next visual inspection interval for a snubber category shall be determined based upon the previous inspection interval and the rumber of unacceptable snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation. as accessible or inaccessible. These categories may be examined separately or jointly. However, categories must De determined and documented before any inspection and that determination shall be the basis upon which to determine the next inspection interval for that category.
Note 2 Interpolation between population per category and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, and C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
, , . - n . - - ~ . . . . . . . . ~ - . . . - --
., . ~ ?,4
< *' ;p
-d-- =
1Attachmsnt IV to ET 91-0044: -
Page 81of.8L [
i
,s Insert C (con't) i Table 4,7-2 (Continued)
SNUBBER VISUAL INSPECTION INTERVAL Note ~3: If the number.of-unacceptable snubbers is equal to or less than the
- number in Column A.. the next inspection interval may be twice the previous interval but'not greater than 48 months.
Note.4:- If the number of unacceptable snubbers is equal to or less than the
.numbe'r in Column B but greater than the-number in Column.A. the-next . inspection: interval shall- be the same as the previore 1 interval ~.
Note St LIf the number of unacceptable. snubbers is equal to or greater than !
the number in Column C, the next- inspection' interval shall be :
.two-thirds of- the previous interval. However, if the number of unacceptable snubbers is less than the number in Column C but greater' than the number in Column B, the-next interval shall1be
. reduced > proportionally by interpolation, that is, the previous !
-interval shall. be reduced by a : factor that is one-third of the.
ratio of the difference.between the number of' unacceptable snubbers ,
found : during the previous interval and the number in Column B to 1 the difference.in the numbers in Column B and C.
Note 6: ;The. provisions of Specification '4.0.2 are . applicable for all inspection intervals up to and including'48 months.
1
%