W3F1-2003-0010, Supplement to Amendment Request NPF-38-243 Reactivity/Boron Concentration Changes
Letter Sequence Supplement | |
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TAC:MB6616, (Approved, Closed) | |
MONTHYEARML0307202882003-03-0707 March 2003
[Table View]Technical Specification Pages for Amendment No. 185 for Waterford Steam Electric Station, Unit 3 Project stage: Other ML0307106032003-03-0707 March 2003 Issuance of License Amendment No. 185, Revising TSs Relating to Positive Reactivity Additions While in Shutdown Modes by Clarifying TSs Involving Positive Reactivity Additions Project stage: Approval 2003-03-07 |
ML030420409 | |
Person / Time | |
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Site: | Waterford ![]() |
Issue date: | 02/04/2003 |
From: | Peters K Entergy Nuclear South, Entergy Operations |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
W3F1-2003-0010 | |
Download: ML030420409 (4) | |
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Category:Letter type:W
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Revision to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual ML20148M1062020-06-22022 June 2020 Corrections to Technical Specifications Issued in Amendments Nos. 102 and 225 and with the Renewed License ML20113E8362020-04-23023 April 2020 Summary of March 19, 2020, Category 1 Public Meeting with Entergy Operations Inc. a Planned LAR to Install Digital Systems in Accordance with Di&C ISG-06 Revision 2, Licensing Processes at Waterford Steam Electric Station ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule W3F1-2016-0010, Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR)2016-03-0303 March 2016 Responses to Request for Additional Information Regarding the Risk-Informed Surveillance Requirements License Amendment Request (LAR) ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times ML15244B3862015-09-0303 September 2015 Correction to Issuance of Amendment Extension of the Integrated Leak Rate Testing to 15 Years ML15139A4832015-08-31031 August 2015 Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power ML15217A1432015-08-24024 August 2015 Issuance of Amendment No. 244 Extension of the Integrated Leak Rate Testing to 15 Years ML15138A4402015-08-14014 August 2015 Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation W3F1-2015-0061, Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.42015-08-14014 August 2015 Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.4 ML15174A2272015-07-29029 July 2015 Issuance of Amendment of Technical Specifications 3.9.6 and 3.9.7 to the Technical Requirements Manual ML14321A7132014-12-10010 December 2014 Issuance of Amendment No. 241, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date W3F1-2014-0052, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-08-28028 August 2014 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications W3F1-2012-0084, Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink2012-10-0808 October 2012 Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink W3F1-2012-0028, Of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train2012-05-22022 May 2012 Of License Amendment Request to Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train W3F1-2011-0067, License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train2011-10-13013 October 2011 License Amendment Request, Proposed Change to Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train ML1125103192011-09-20020 September 2011 Correction of an Error in Amendment No. 226, Administrative Changes to Technical Specifications 6.9.1.11 and 6.9.1.11.1 Relating to Core Operating Limits Report ML1109501232011-04-0404 April 2011 Attachment 2 to W3F1-2011-0021, Proposed Operating License Change (Mark-up) and Attachment 3, Revised Operating License Page ML1021001582010-09-13013 September 2010 Issuance of Amendment No. 228, Modify Technical Specification Tables 2.2-1 and 3.3-1 to Clarify Notes and Actions ML1021504662010-09-13013 September 2010 Issuance of Amendment No. 227, Modify Technical Specification 3/4.9.7, Crane Travel - Fuel Handling Building to Permit Certain Operations Needed for Dry Cask Storage of Spent Nuclear Fuel W3F1-2010-0065, Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition2010-08-12012 August 2010 Response to Request for Additional Information Associated with Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2010-0047, License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System2010-07-20020 July 2010 License Amendment Request for Proposed Change to Technical Specification 3.7.1.2, Emergency Feedwater System 2CAN051001, Response to Request for Additional Information Associated with Core Operating Limits Report References2010-05-17017 May 2010 Response to Request for Additional Information Associated with Core Operating Limits Report References ML1011100352010-04-22022 April 2010 Correction to Technical Specification Page 3/4 3-10 Issued with Amendment No. 225 Technical Specification Change to Relocate Steam Generator Level - High Trip Function W3F1-2010-0011, License Amendment Request, Technical Specification Change Regarding Steam Generator Program2010-02-22022 February 2010 License Amendment Request, Technical Specification Change Regarding Steam Generator Program W3F1-2010-0019, Request for Amendment to Technical Specification Table 3.4-1 Isolation Valve Addition2010-02-22022 February 2010 Request for Amendment to Technical Specification Table 3.4-1 Isolation Valve Addition W3F1-2009-0045, License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-12009-10-22022 October 2009 License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-1 W3F1-2009-0021, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit2009-06-0303 June 2009 License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit W3F1-2008-0051, Entergys Response to NRCs Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 32009-01-0808 January 2009 Entergys Response to NRCs Request for Additional Information Regarding License Amendment Request to Modify Requirements Regarding Control Room Envelope Habitability, Waterford Unit 3 ML0819904722008-07-30030 July 2008 License and Technical Specification Pages, Issuance of Amendment No. 216, Modify Diesel Generator Fuel Oil Testing Surveillance Requirements ML0812700362008-05-0909 May 2008 Tech Spec Page for Correction to Amendment 214 Request to Support Next Generation Fuel; Review & Approval of Revised ECCS Performance Analysis; & Review & Approval of Supplement to ECCS Performance Analysis ML0803800062008-04-16016 April 2008 License Page 4 and Technical Specification Page 5-5, Issuance of Amendment No. 215 Use of Optimized ZIRLO-TM Fuel Rod Cladding ML0808800152008-04-15015 April 2008 Tech Spec Pages for Amendment 214, Request to Support Next Generation Fuel; Review and Approval of ECCS Performance Analysis; and Review and Approval of Supplement to ECCS Performance Analysis ML0804401272008-02-12012 February 2008 2/12/2008 E-mail from Licensee Enclosing Markup of Technical Specification Page 5-5, Supplement to 4/24/2007 License Amendment Request Use of Optimized ZIRLO-TM Fuel Rod Cladding W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves2008-01-0202 January 2008 License Amendment Request NPF-38-275, Containment Isolation Valves W3F1-2007-0033, License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability2007-08-16016 August 2007 License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability ML0723200662007-08-16016 August 2007 License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability 2024-08-07 |
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Entergy Nuclear South Entergy Operations, Inc 17265 River Road Killona, LA 70066 Enteg Tel 504 739 6440 Fax 504 739 6698 kpeters@entergy com Ken Peters Director, Nuclear Safety Assurance W3F1-2003-0010 Waterford 3 February 4, 2003 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Waterford Steam Electric Station, Unit 3 Docket No. 50-382 Supplement to Amendment Request NPF-38-243 Reactivity/Boron Concentration Changes
REFERENCE:
Entergy letter dated October 24, 2002, Reactivity/Boron Concentration Changes (W3F1-2002-0095)
Dear Sir or Madam:
By the referenced letter, Entergy Operations, Inc. (Entergy) proposed a change to the Waterford Steam Electric Station, Unit 3 (Waterford 3) Technical Specifications. The proposed amendment would revise Technical Specifications relating to positive reactivity additions while in shutdown modes by clarifying Technical Specifications involving positive reactivity additions.
The proposed changes are based on Technical Specifications Task Force (TSTF) -286, Revision 2 and allow for small, controlled, safe insertions of positive reactivity while in shutdown modes.
On January 22, 2003, Entergy was informed that the proposed wording for the note in Technical Specifications 3.9.8.1 and 3.9.8.2 must be revised to more closely conform with the wording in TSTF-286, Revision 2. The wording proposed by Entergy, in the referenced letter, was identical to wording the NRC had previously approved for amendment 122 at St. Lucie, Unit 2. As a result, the attachment to this letter contains corrected page 1 of 16 from Attachment 2 of the referenced letter. Please utilize this revised page in place of the original.
The required revision does not change the meaning, implementation, or intent of what was previously submitted therefore, no technical changes are being proposed by this supplement.
The original no significant hazards considerations included in the referenced letter is not affected by any information contained in this supplemental letter.
There are no new commitments contained in this letter.
If you have any questions or require additional information, please contact D. Bryan Miller at 504-739-6692.
W3F1-2003-0010 "Page 2 of 2 February 4, 2003 I declare under penalty of perjury that the foregoing is true and correct. Executed on February 4, 2003.
Sincerely, Kirector, Nuclear Safety Assurance KJP/DBM/cbh
Attachment:
Revised Page 1 of 16 from W3F1-2002-0095, Attachment 2 cc:
E.W. Merschoff, NRC Region IV N. Kalyanam, NRC-NRR J. Smith N.S. Reynolds NRC Resident Inspectors Office Louisiana DEQ/Surveillance Division American Nuclear Insurers
Attachment To W3FI -2003-0010 Revised Page 1 of 16 from W3FI-2002-0095, Attachment 2
- '7 Attachment to W3F1-2003-0010 Page 1 of I Revised Page 1 of 16 from W3FI-2002-0095, Attachment 2 W3F17-2002-0095 Page 1 of 16 INSERT I Limited plant cooldown or boron dilution is allowed provided the change is accounted for in the calculated SHUTDOWN MARGIN.
INSERT 2 Plant temperature changes are allowed provided the temperature change is accounted for in the calculated SHUTDOWN MARGIN.
INSERT 3 suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.1 or 3.1.1.2.
INSERT 4 operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of Technical Specification 3.9.1 INSERT 5 no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.1 or 3.1.1.2.
INSERT 6 no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the minimum requied boron concentration of Technical Specification 3.9.1.
INSERT 7 operations involving positive reactivity additions that could result in loss of required SHUTDOWN MARGIN or boron concentration INSERT 8 suspend operations that would cause introducton into the RCS, coolant with boron concentration less than required to meet SHUTDOWN MARGIN of Technical Specification 3.1.1.1 or 3.1.1.2.
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INSERT 9 no operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SHUTDOWN MARGIN of Technical Specification 3.1.1.1 or3.1.1.2.
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