|
---|
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
_ . _ _
Att:chment III to VH 88-0055 Pg 1 cf 6 February 26,19e8 DELETE .
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FIGURE 3.9-1 WOLF CREEK MINIMUM REQUIRED FUEL ASSEMBLY I
BURNUP AS A FUNCTION OF INITIAL ENRICHMENT j FOR STORAGE IN REGION 2 I
I
h Attechment III to WM 88-0055 Page 3 of 6 February 26, 1988 .
I
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4
, DESIGN FEATURES -
i 5.3 REACTOR CORE
s 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircalo noniinal active fuel length of .144 inches. y-4 Each fuel rod shall have a a maximum nominal. enrichment of 3.10 weight percent U-235.The initial core load Reload fuel shall be similar in physical design to the initial core loading and shall have a max-inum enrich:ient a weight percent U-235.
. CONTROL R00 ASSEH8 LIES 5.3.2 assemolies.The core shall contain 53 full-length and no part-length control reo 142 inches of absorber asterial.The full-length control rod assemelles shall conta stainless steel tuning. All control rods shall be hafnius, clao with
_S . 4 REACTOR C0OLANT _ SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degraia~ tion pursuant to the applicable Surveillance Requirements,
- b. For a pressure of 2485 psig, and c.
For a temperature of 650'F, except for the pressurizer which is 680*F.
10L!5 . . ..
5.4.2 and surge Theline, totalisvolume 12,135of the Reactor Coolant System, incluaing pressurizer 100 cubic feet at a nominal i of 557'F.
i j 5. 5 HETEOR0 LOGICAL 70VER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
l VOLF CRER - u.4ti 1 5-6 e,nnne 3. -
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g Attachment III to WM 88-0055 Page 4 of 6 February 26, 1988
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OESIGN FEATU,1ES s s s ~
5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with: .
- a. Ak ~
df equivalent to 1ess than or equal to 0.95 when flooded with
,. unborated water, which includes a conservative allowance of 2.6*.
ok/k for uncertainties as described in Section 4.~3 of the FSAR.
Th.is is based on new fuel with an enrichment of Sc5Fweight percent -
U-235 in Region 1 and on spent fuel with combination of initial enrichment and discharge exposures, shown in Figure 5.6-1, in Region 2; and
- b. A nominal inch center-to-center distance between fuel assemolles placed in the storage racks.
- 5. 6.1. 2 The k for new fuel for the first core loading stored dry in the
- spent fuel stoke racks shall not exceed 0.98 when aqueous foam moderation is assumed.
ORAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 2040 feet.
CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1344 fuel assemblies.
- 5. 7 COMPONENT CYCLIC OR TRANSIENT LIMIT
- 5. 7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
'- OL F C y [,; . tng i 1 s. ;
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l FIGURE 5.6-1 MirilDUM REQUIRED FUEL ASSEMSLY EXF050RE AS A FUNC 4
OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION t
i WOLF CREEK . U.*[7 1 53
Att:chment III to WM 88-0055 F:ge 6 ef 6 February 26. 1988 -
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ENRICHMENT (w/o)
FIGURE 5.6-1 WOLF CREEK MINIMUM REQUIRED FUEL ASSEMBLY BURNUP AS A FUNCTION OF INITIAL ENRICHMENT l
FOR STORAGE IN REGION 2
/-_
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4 ATTACHMENT IV l
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