Letter Sequence Other |
|---|
TAC:MD4839, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
|
MONTHYEARML0707401372007-03-0909 March 2007
Biennial 50.59 Evaluation Report for Period Covering January 1, 2005 to December 31, 2006
Project stage: Request
ML0708001982007-03-13013 March 2007
9100-00003-NP, Rev. 1, Wolf Creek Generating Station Main Steam and Feedwater Isolation System (Msfis) Controls Summary
Project stage: Request
ET 07-0004, Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement2007-03-14014 March 2007
Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement
Project stage: Request
ML0711603322007-04-18018 April 2007
Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification
Project stage: Request
ML0711501302007-04-19019 April 2007
2006 Annual Radiological Environmental Operating Report for the Period of January 1, 2006 Through December 31, 2006
Project stage: Request
ML0712204892007-05-0303 May 2007
Meeting Notice - LAR to Upgrade the Main Steam and Feedwater Isolation System (Msfis)
Project stage: Meeting
ET 07-0013, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation System Controls2007-05-0909 May 2007
Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation System Controls
Project stage: Response to RAI
ML0713703642007-05-17017 May 2007
Handout for Meeting with Wolf Creek Nuclear Operating Corporation on the Licensees Application for the Main Steam and Feedwater Isolation System (Msfis) Modification
Project stage: Meeting
ML0713805112007-05-29029 May 2007
Acceptance Review of Licensees Application for Main Steam and Feedwater Isolation System Controls Modification
Project stage: Acceptance Review
ML0713805102007-06-0404 June 2007
Summary of Meeting with Representatives of Wolf Creek Nuclear Operating Corporation for Wolf Creek Generating Station on License Application Request to Update Main Steam and Feedwater Isolation System
Project stage: Meeting
ET 07-0022, Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification2007-06-15015 June 2007
Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification
Project stage: Request
ML0717900072007-07-18018 July 2007
Notice of Meeting with Wolf Creek Nuclear Operating Corporation to Discuss the Licensees License Amendment Request Dated March 14, 2006, to Modify the Main Steam and Feedwater Isolation System
Project stage: Meeting
ML0721501532007-08-0202 August 2007
NRC Staff Handout for August 2, 2007, Meeting with Wolf Creek Nuclear Operating Corporation
Project stage: Meeting
ML0717900062007-08-0808 August 2007
Completion of Acceptance Review of Request to Modify the Main Stream and Feedwater Isolation System
Project stage: Acceptance Review
ML0722109412007-08-14014 August 2007
Summary of Meeting with Representatives of Wolf Creek Nuclear Operating Corporation Discussed on Description and Justification of Its Proposed Modification of the Main Steam and Feedwater Isolation System
Project stage: Meeting
ET 07-0039, Response to NRC Letter Dated August 8, 2007, Regarding the Main Steam and Feedwater Isolation System Controls Modification2007-08-31031 August 2007
Response to NRC Letter Dated August 8, 2007, Regarding the Main Steam and Feedwater Isolation System Controls Modification
Project stage: Request
ET 07-0038, License Renewal Application, Amendment 32007-08-31031 August 2007
License Renewal Application, Amendment 3
Project stage: Other
ML0724200172007-09-11011 September 2007
Request for Withholding Information from Public Disclosure in CS Innovations Topical Report 9100-00003-P for the Wolf Creek Generating Station
Project stage: Withholding Request Acceptance
ET 07-0041, Additional Response to NRC Letter Dated August 8, 2007, Regarding the Main Steam and Feedwater Isolation System Controls Modification2007-09-20020 September 2007
Additional Response to NRC Letter Dated August 8, 2007, Regarding the Main Steam and Feedwater Isolation System Controls Modification
Project stage: Request
ML0725503102007-11-0707 November 2007
Request for Withholding Information from Public Disclosure in CS Innovations Report Submitted August 31, 2007
Project stage: Withholding Request Acceptance
ML0725502832007-11-0707 November 2007
Request for Withholding Information from Public Disclosure in CS Innovations Documents Submitted June 15, 2007, for Wolf Creek Generating Station
Project stage: Withholding Request Acceptance
ML0724201352007-11-0707 November 2007
Request for Withholding Information from Public Disclosure in Three CS Innovations Topical Reports Submitted April 18, 2007 for Wolf Creek Generating Station
Project stage: Withholding Request Acceptance
ML0725502682007-11-0808 November 2007
Request for Withholding Information from Public Disclosure in Topical Report Submitted June 15, 2007, for Wolf Creek Generating Station
Project stage: Withholding Request Acceptance
ML0725502012007-11-0808 November 2007
Request for Withholding Information from Public Disclosure in Topical Report Submitted April 18, 2007, for Wolf Creek Generating Station (Tac No. MD4839)
Project stage: Withholding Request Acceptance
ML0732001042007-11-16016 November 2007
Notice of Meeting with Representatives of Wolf Creek Nuclear Operating Corporation to Discuss Main Steam and Feedwater Isolation System (Tac No. MD4839)
Project stage: Meeting
ML0733103642007-11-27027 November 2007
Revised Notice of Meeting with Wolf Creek Nuclear Operating Corp, to Discuss NRC Staffs Request for Information on Licensees Supplemental Letter Dated September 27, 2007, to the Application Dated February 21, 2006, to Revise TS 5.5.9
Project stage: RAI
ML0733101982007-11-27027 November 2007
Notice of Meeting with Wolf Creek Nuclear Operating Corporation, to Discuss NRC Staffs Request for Additional Information on Licensees Proposed Main Steam and Feedwater Isolation System Modification in Its Application Dated March 14, 2007
Project stage: RAI
ML0731000102007-12-0707 December 2007
Request for Additional Information for the Main Stream and Feedwater Isolation System Modification (Tac No. MD4839)
Project stage: RAI
ML0729700242008-03-0303 March 2008
Issuance of License Amendment 175 Regarding Changes to Technical Specification Table 3.3.2-1
Project stage: Approval
ML0729700282008-03-0303 March 2008
Tech Spec Pages for Amendment 175 Regarding Changes to Technical Specification Table 3.3.2-1
Project stage: Other
ET 08-0017, Additional-Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification2008-03-14014 March 2008
Additional-Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
Project stage: Request
ML0809801342008-04-16016 April 2008
Withholding from Public Disclosure, CS Innovations, 6101-00007, Msfis Instruction, Operation, and Maintenance Manual, Revision 1, Submitted March 14, 2008
Project stage: Other
ML0809802612008-06-23023 June 2008
Wolf Creek,Request for Withholding Information from Public Disclosure in Als Architecture Evaluation and Sfis D3 Assessment Submitted February 28, 2008
Project stage: Withholding Request Acceptance
ML0822703012008-07-29029 July 2008
CS Innovations Report 6002-00026, Rev. 1, Als Platform Overview, Non-Proprietary, Enclosure Viii
Project stage: Request
ML0822702982008-07-30030 July 2008
CS Innovations Report 6002-00002, Rev. 2, Als Configuration Management Plan, Non-Proprietary, Enclosure II
Project stage: Request
ML0822702962008-07-31031 July 2008
Transmitted of Resubmittal of Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
Project stage: Request
ML0821802102008-07-31031 July 2008
Safety Evaluation Report Related to the License Renewal of Wolf Creek Generating Station
Project stage: Approval
ML0809802352008-08-18018 August 2008
Request for Withholding Information from Public Disclosure, Three Proprietary Documents, Affidavit Dated July 29, 2008, Executed by S. Sorenson, CS Innovations, LLC
Project stage: Withholding Request Acceptance
ML0902708252009-01-0909 January 2009
Enclosure II to Wm 09-0001, Msfis D3 Assessment, Rev 2
Project stage: Request
ML0902708232009-01-14014 January 2009
Enclosure III to Wm 09-0001, Operation Plan, Rev 2
Project stage: Request
ML0902704262009-01-16016 January 2009
Enclosures Viii & Xxviii to Wm 09-0001 - CS Innovations Report 6002-00026, Als Platform Overview, Rev 2
Project stage: Request
WM 09-0001, Response to NRC Request for Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification2009-01-16016 January 2009
Response to NRC Request for Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
Project stage: Response to RAI
ET 09-0005, Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification2009-01-29029 January 2009
Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
Project stage: Request
ML0903406802009-02-0909 February 2009
Request for Withholding Information from Public Disclosure, Affidavit Executed by Steen Sorenson, CS Innovations LLC
Project stage: Withholding Request Acceptance
ET 09-0008, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification2009-02-17017 February 2009
Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
Project stage: Other
ET 09-0011, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification2009-02-27027 February 2009
Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
Project stage: Other
ML0906500562009-03-0505 March 2009
Msfis Controls - Implementation of Amendment 181
Project stage: Other
ML0906505542009-03-0606 March 2009
Decontrolled Letter, Draft Safety Evaluation for Modifications to the Main Steam and Feedwater Isolation Control System for Review of Proprietary Information
Project stage: Draft Approval
ML0906202032009-03-27027 March 2009
Request for Withholding Information from Public Disclosure, WCGS Letter Dated 2/17/2009
Project stage: Withholding Request Acceptance
ML0906103172009-03-31031 March 2009
Issuance of Amendment No. 181, Revise Licensing Basis, Modification of the Main Steam and Feedwater Isolation System Controls
Project stage: Approval
2007-08-08
[Table View] |
Text
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 175, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Antitrust Conditions Kansas Gas & Electric Company and Kansas City Power & Light Company shall comply with the antitrust conditions delineated in Appendix C to this license.
(4)
Environmental Qualification (Section 3.11. SSER #4. Section 3.11.
SSER #5)*
Deleted per Amendment No. 141.
(5)
Fire Protection (Section 9.5.1, SER, Section 9.5.1.8, SSER #5)
(a)
The Operating Corporation shall maintain in effect all provisions of the approved fire protection program as described in the SNUPPs Final Safety Analysis Report for the facility through Revision 17, the Wolf Creek site addendum through Revision 15, and as approved in the SER through Supplement 5, subject to provisions b and c below.
(b)
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(c)
Deleted.
(6)
Qualification of Personnel (Section 13.1.2. SSER #5, Section 18, SSER
- 1')
Deleted per Amendment No. 141.
- The parenthetical notationfollowing the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
Amendment No. 175
ESFAS Instrumentation 3.3.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H.
Not Used.
One channel inoperable.
NOTE---------
The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
1.1 Place channel in trip.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR 1.2 Be in MODE 3.
78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> (continued)
Wolf Creek - Unit 1 3.3-25 Amendment No. 123, 156, 175 1
ESFAS Instrumentation 3.3.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME J.
One Main Feedwater NOTE --------------------
Pump trip channel The inoperable channel may be inoperable, bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels.
J.1 Place channel in trip.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR J.2 Be in MODE 3.
7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> K.
One channel inoperable.
NOTE..............---
One additional channel may be tripped for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
K.1 Place channel in bypass.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR K.2.1 Be in MODE 3.
78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND K.2.2 Be in MODE 5.
108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> (continued)
I Wolf Creek - Unit 1 3.3-26 Amendment No. 3, 156
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 5)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (a)
Safety Injection
- a.
Manual Initiation
- b.
Automatic Actuation Logic and Actuation Relays
- c.
Containment Pressure -
High 1
- d.
Pressurizer Pressure -
Low 1,2,3,4 1,2,3,4 1,2,3 2
2 trains 3
4 B
SR 3.3.2.8 C
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 SR 3.3.2.13 D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 B
SR 3.3.2.8 C
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 E
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 2 1820 psig I
NA NA
_4.5 psig
- e.
Steam Line Pressure Low 3 per steam line
> 571 psig(c)
- 2.
. Containment Spray
- a.
Manual Initiation
- b.
Automatic Actuation Logic and Actuation Relays
- c.
Containment Pressure High - 3 1,2,3,4 1,2,3,4 2 per train, 2 trains 2 trains NA NA
- 5 28.3 psig 1,2,3 (continued)
(a) The Allowable Value defines the Limiting.Safety System Setting. See the Bases for the Trip Setpoints.
(b) Above the P-11 (Pressurizer Pressure) interlock and below P-11 unless the Function is blocked.
(c) Time constants used in the lead/lag controller are t, - 50 seconds and t2 < 5 seconds.
Wolf Creek - Unit 1 3.3-32 Amendment No. 1-23, 140
ESFAS Instrumentation 3.3.2 Table 3.3,2-1 (page 2 of 5)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (a)
- 3.
Containment Isolation
- a.
Phase A Isolation (1)
Manual Initiation (2) Automatic Actuation Logic and Actuation Relays (3)
Safety Injection
- b.
Phase B Isolation 1,2,3,4 1.2,3,4 2
2 trains B
SR 3.3.2.8 C
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 SR 3.3.2.13 NA NA Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
(1) Manual Initiation (2) Automatic Actuation Logic and Actuation Relays (3)
Containment Pressure -
High 3 1.2,3,4 1,2,3,4 1,2,3 2 per train, 2 trains 2 trains 4
B SR 3.3.2.8 C
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 E
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 NA NA
- 5 28.3 psig
- 4.
Steam Line Isolation
- a.
Manual Initiation
- b.
Automatic Actuation Logic and Actuation Relays (SSPS)
- c.
Automatic Actuation Logic (MSFIS)
- d.
Containment Pressure
- High 2 1,2(i), 3(i) 1,2(i), 3(i) 11,2(0), 3(i.)
1,2(0), 30i) 2 2 trains 2 trains 3
F SR 3.3.2.8 G
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 G
SR 3.3.2.6 D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 NA NA NA
< 18.3 psig (continued)
(a)
(i)
The Allowable Value defines the Limiting Safety System Setting. See the Bases for the Trip Setpoints.
Except when all MSIVs are closed.
Wolf Creek - Unit 1 3.3-33 Amendment No. 424, 175
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 5)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUI1URED.
SURVEILLAN14 CE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (a)
- 4.
Steam Line Isolation (continued)
- e.
Steam Line Pressure
>571 psig(c)
(1) Low 1,2(,3(b)(i) 3 per steam line D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 (2)
Negative Rate -
High 3(g)(i) 3 per steam line S 1 2 5(h) psi
- 5.
Turbine Trip and Feedwater Isolation
- a.
Automatic Actuation
- Logic and Actuation Relays (SSPS)
- b.
Automatic Actuation Logic (MSFIS)
- c.
SG Water Level -High High (P-14) 1,26).30) 1,20),30) 2 trains 2 trains 4 per SG G
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 SR 3.3.2.14 G
SR 3.3.2.6 I
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10 NA NA 1,20)
< 79.7% of Narrow Range Instrument Span
- d.
Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
.(continued)
(a) The Allowable Value defines the Limiting Safety System Setting. See the Bases for the Trip Setpoints.
(b) Above the P-11 (Pressurizer Pressure) Interlock and below P-l1 unless the Function is blocked.
(c) Time constants used in the 1-eadllag controller are t. Žn 50 seconds and t2 _< 5 seconds.
(g) Below the P-11 (Pressurizer Pressure) Interlock; however, may be blocked below P-11 when safety injection on low steam line pressure is not blocked.
(h) Time constant utilized in the rate/lag controller is > 50 seconds.
(i) Except when all MSIVs are closed.
- 0) Except when all MFIVs are closed.
Wolf Creek - Unit 1 3.3-34 Amendment No. 123,-132, 175
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 5)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED, REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (a)
- 6.
Auxiliary Feedwater
- a.
Manual Initiation
- b.
Automatic Actuation Logic and Actuation Relays (Solid State Protection System)
- c.
Automatic Actuation Logic and Actuation Relays (Balance of Plant ESFAS)
- d. SG Water Level Low -
Low
- e.
Safety Injection
- f.
Loss of Offsite Power
- g.
Trip of all Main Feedwater Pumps
- h.
Auxiliary Feedwater Pump Suction Transfer on Suction Pressure - Low 1,2,3 1,2,3 1,2,3 1 per pump 2 trains 2 trains 0
SR 3.3.2.8 G
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 N
SR 3.3.2.3 NA NA NA 1,2,3 4 per SG D
SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10
_> 22.3% of Narrow Range Instrument Span Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
1,2,3 1
1,2,3 2 trains 2 per pump 3
P SR 3.3.2.7 SR 3.3.2.10 J
SR 3.3.2.8 M
SR 3.3.2.1 SR 3.3.2.9 SR 3.3.2.10 SIR 3.3.2.12 NA I
NA 2! 20.53 psia (continued)
(a)
The Allowable Value defines the Limiting Safety System Setting. See the Bases for the Trip Setpoints.
Wolf Creek - Unit 1 3.3-35 Amendment No. 423,136
