Letter Sequence Other |
---|
|
|
MONTHYEARML0405504962004-02-24024 February 2004 (Bfn), TVA Revision to Implementation Plan Described in Units 2 & 3, Technical Specifications (TS) Change No. 441 Revision 1, Pressure Temperature (P-T) Curve Update Project stage: Other ML0404800132004-03-10010 March 2004 Amendments 288 & 247 to Licenses DPR-52 & DPR-68, Respectively. Amendments Revise Pressure-Temperature Limit Curves Project stage: Other ML0407501882004-03-10010 March 2004 Brown Ferry, Unit 2, Technical Specifications, Revising Pressure Temperature Limits Curves Project stage: Other ML0407501942004-03-10010 March 2004 Brown Ferry, Unit 3, Technical Specifications, Revising Pressure Temperature Limit Curves Project stage: Other 2004-02-24
[Table View] |
|
---|
Category:Technical Specifications
MONTHYEARCNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) ML21285A0682021-10-28028 October 2021 Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2 ML21214A1392021-08-30030 August 2021 Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters ML21075A0762021-04-30030 April 2021 Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis ML21041A4892021-04-0808 April 2021 Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3 ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20190A1052020-08-11011 August 2020 Correction to Amendment No. 319 Regarding Revisions to Technical Specification 3.3.6.1, Primary Containment Isolation Instrumentation ML20085G8962020-06-26026 June 2020 Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML18283A8972018-10-10010 October 2018 Enclosure 1: Proposed Changes to Browns Ferry Nuclear Plant Unit 1 Technical Specifications, Attachments 1, 2, & 3 ML18251A0032018-09-27027 September 2018 Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292) ML17215A2432017-10-0202 October 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566) CNL-17-015, Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects2017-01-20020 January 2017 Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safety Aspects NL-17-015, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Saf2017-01-20020 January 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Safe ML16330A1582017-01-17017 January 2017 Issuance of Amendments Regarding Revisions to Technical Specification 4.3.1.2, Fuel Storage Criticality ML16028A4142016-04-26026 April 2016 Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio ML15317A4782016-02-0909 February 2016 Issuance of Amendment to Revise Technical Specifications Related to Cycle 18 Safety Limit Minimum Critical Power Ratio ML15344A3212016-01-0707 January 2016 Issuance of Amendment Regarding Modification of Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits ML15321A4722015-12-23023 December 2015 Issuance of Amendments Regarding Revision to Table 3.3.6.1-1, Primary Containment Isolation Instrumentation ML15287A2132015-12-16016 December 2015 Issuance of Amendments Regarding Technical Specification Changes to Reactor Core Safety Limits ML15324A2472015-12-14014 December 2015 Issuance of Amendment to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Valves to Licensee Control ML15287A3712015-12-0404 December 2015 Issuance of Amendments for the Adoption of Technical Specifications Task Force Standard Technical Specifications Change Traveler TSTF-535 (CNL-15-029) ML15212A7962015-10-28028 October 2015 Issuance of Amendments to Transition to Fire Protection Program NFPA-805 ML15251A5402015-09-29029 September 2015 Issuance of Amendment Regarding Control Rod Scram Time Testing Frequency Per TSTF-460, Revision 0 CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2015-09-25025 September 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) CNL-15-073, Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And.2015-09-16016 September 2015 Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And. ML15065A0492015-06-0202 June 2015 Issuance of Amendment Revising Pressure and Temperature Limit Curves CNL-15-070, Withdrawal of Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs - TS-4852015-05-29029 May 2015 Withdrawal of Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs - TS-485 CNL-15-019, License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-460-A, Revision 0, Control Rod Scram Time Testing Frequency (TS-501)2015-03-0909 March 2015 License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-460-A, Revision 0, Control Rod Scram Time Testing Frequency (TS-501) CNL-15-029, License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502)2015-03-0909 March 2015 License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502) CNL-15-033, License Amendment Request Under Exigent Circumstances for the Change to Add a Reference to the ATRIUM-10 Xm NRC Safety Evaluation Approval in Technical Specification 5.6.5.b in Support of ATRIUM-10 Xm Fuel Use2015-02-12012 February 2015 License Amendment Request Under Exigent Circumstances for the Change to Add a Reference to the ATRIUM-10 Xm NRC Safety Evaluation Approval in Technical Specification 5.6.5.b in Support of ATRIUM-10 Xm Fuel Use CNL-14-156, Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Withdrawal of Requests and Update to EPU Plans and Schedules2014-09-18018 September 2014 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Withdrawal of Requests and Update to EPU Plans and Schedules NL-14-081, Browns Ferry, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Fer2014-05-16016 May 2014 Browns Ferry, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferr CNL-14-081, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferry2014-05-16016 May 2014 Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferry NL-13-148, Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484)2013-12-18018 December 2013 Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484) CNL-13-148, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484)2013-12-18018 December 2013 Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484) CNL-13-126, Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs-TS-4852013-11-22022 November 2013 Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs-TS-485 ML13199A2212013-08-30030 August 2013 Issuance of Amendments Re. Deletion of References to Section XI of the ASME Code and Incorporate References to the ASME OM Code and Allow Application of 25% Extension of Surveillance Intervals ML13092A3932013-03-27027 March 2013 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) (Technical Specification Change TS-480) ML13070A3072013-02-28028 February 2013 Technical Specification Change TS-478 - Addition of Analytical Methodologies to Technical Specification 5.6.5 for Browns Ferry 1, 2, & 3, & Revision of Technical Specification 2.1.1.2 for Browns Ferry Unit 2, in Support of ATRIUM-10 Xm Fuel ML11189A2172012-07-30030 July 2012 Issuance of Amendments Regarding Request to Add Technical Specification 3.7.3, Control Room Emergency Ventilation System, Action to Address Two Crev Subsystems Inoperable ML12114A0042012-04-18018 April 2012 Supplement to License Amendment Request to Transition to Areva Fuel ML1011601532010-04-16016 April 2010 Supplemental Information for Technical Specification Change TS-473 - Areva Fuel Transition Amendment Request ML0923700452009-11-19019 November 2009 Issuance of Amendments Regarding Technical Specification Improvement to Adopt Technical Specification Task Force (TSTF) TSTF-476, Revision 1 ML0931402652009-10-31031 October 2009 Attachment 13, Browns Ferry Unit 1 - Technical Specification Change 467, ANP-2864(NP), Revision 2, Reload Safety Analysis Report 2024-04-01
[Table view] |
Text
RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 --- NOTES-------------- --------
- 1. Only required to be performed during RCS heatup and cooldown operations or RCS inservice leak and hydrostatic testing when the vessel pressure is > 312 psig.
- 2. The limits of Figure 3.4.9-2 may be applied during nonnuclear heatup and ambient loss cooldown associated with inservice leak and hydrostatic testing provided that the heatup and cooldown rates are < 150 F/hour.
- 3. The limits of Figures 3.4.9-1 and 3.4.9-2 do not apply when the tension from the reactor head flange bolting studs is removed.
Verify: 30 minutes
- a. RCS pressure and RCS temperature are within the limits specified by Curves No. 1 and No. 2 of Figures 3.4.9-1 and 3.4.9-2; and
- b. RCS heatup and cooldown rates are
< 100F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
SR 3.4.9.2 Verify RCS pressure and RCS temperature Once within 15 are within the criticality limits specified in minutes prior to Figure 3.4.9-1, Curve No. 3. control rod withdrawal for the purpose of achieving criticality (continued)
BFN-UNIT 3 3.4-26 Amendment No.-242, 247
RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.4.9.5 ------------------------- I-NOTES-
- 1. Only required to be performed when tensioning the reactor vessel head bolting studs.
- 2. The reactor vessel head bolts may be partially tensioned (four sequences of the seating pass) provided the studs and flange materials are > 701F.
Verify reactor vessel flange and head flange 30 minutes temperatures are > 83 0F.
SR 3.4.9.6 --------------------------NOTE-------------------------
Not required to be performed until 30 minutes after RCS temperature < 850 F in MODE 4.
Verify reactor vessel flange and head flange 30 minutes temperatures are > 83 0F.
SR 3.4.9.7 ------------------------- NOTE-------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after RCS temperature < 1000 F in MODE 4.
Verify reactor vessel flange and head flange 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> temperatures are > 83 0F.
BFN-UNIT 3 3.4-28 Amendment No.-242- 247
RCS P/T Limits 3.4.9 150 0 Curve No. 1 1400 Minimum temperature for bottom head during
-- BROWNS FERRY UNIT 3 __
mechanical heatup or CURVES 1, 2. AND 3 1300 ARE VALID FOR 20 EFPY cooldown following nuclear OF OPERATION shutdown.
120 0 n
Curve No. 2 Minimum temperature for
- 110 0 upper RPV and beltline during mechanical heatup or 0 100 0 cooldown following nuclear ro 0
shutdown.
i 900 Curve No. 3 Minimum temperature for core R 800 operation (criticality).
0 H
U 700 Notes These curves include sufficient margin to provide 4 600 protection against feedwater nozzle degradation. The 500 curves allow for shifts in RTNDT of the Reactor vessel beltline 400 materials, in accordance with Reg. Guide 1.99, Rev. 2, to compensate for radiation 300 embrittlement for 20 EFPY.
The acceptable area for 200 BOTTOM--
HEAD 68oF i~ -
operation is to the right of the applicable curves.
100 FLANGE-REGION 83 F 0
0 50 100 150 200 250 300 MINIMUM REACTOR VESSEL MrALTEMERATURE (OF)
Figure 3.4.9-1 Pressure/Temperature Limits for Mechanical Heatup, Cooldown following Shutdown, and Reactor Critical Operations BFN-UNIT 3 3.4-29 Amendment No.-217, 233, 247
RCS P/T Limits 3.4.9 1400 Curve No. 1 Minimum temperature for bottom head during in-service 1300 leak or hydrostatic testing.
BROWNS FERRY UNIT 3
-CURVES 1 AND 2 ARE -_
VALID FOR 20 EFPY OF Curve No. 2 1200 -OPERATION __1____I Minimum temperature for upper RPV and beltline during in-c: 1100 service leak or hydrostatic testing.
P 1000 Notes 0 900 These curves include sufficient margin to provide protection (n 800 against feedwater nozzle degradation. The curves allow for shifts in RTNDT of the o 700 Reactor vessel beltline U materials, in accordance with Reg. Guide 1.99, Rev. 2, to M 600 compensate for radiation embrittlement for 20 EFPY.
t 500 The acceptable area for operation is to the right of the 9 400 applicable curves.
cn 9 300 BOTTOM 200 HE- FLANGE 68.F IREGION 830 F 100 0
0 50 100 150 200 MINIMUMREACTORVESSELMETALTEMPEAIhRE (OF)
Figure 3.4.9-2 Pressure/Temperature Limits for Reactor In-Service Leak and Hydrostatic Testing BFN-UNIT 3 3.4-29a Amendment No. 247
RCS P/T Limits 3.4.9 Curve No. 1 1500 Minimum temperature for 1400 _
_ 1 BROWNS FERRY'UNIT
_H171
__ t 1 3
-_ _ _ tl_
2 3
__bottom head during mechanical heatup or cooldown following
_-BURVES 1, 2, AND 3 _ _ _- _ _ _ _ - nuclear shutdown.
ARE VALID FOR 28 _ _ _ _ _
1300 EFPY OF OPERATION Curve No. 2
_- _Minimum temperature for upper 1200 - - - - RPVand beltlineduring
- _ _mechanical heatupor 1100 cooldown following nuclear
_ I Ishutdown.
1000 *--Curve No. 3
!- _ _ Minimum temperature forcore 900 I Ioperation -- (criticality).
Notes 800 7 These curves include sufficient
-_ -- -- -_- _ _ __margin to provide protection 700 _ _against feedwater nozzle
_ - -__degradation. The curves allow for shifts in RTNDT of the 600 --- Reactor vessel beltline
_- -materials, in accordance with 500 _- - / _ _ -- _- _ __Reg. Guide 1.99, Rev. 2, to IIIcompensate for radiation 400 s embrittlement for 28 EFPY.
- Theacceptableareafor 300 - ~- - -~ operation is to the right of the
-- tapplicable curves.
200 BOTTOM 100 HEAD FLNGE 830 0
0 50 100 150 200 250 300 MINIMUM REACTOR VESSELMETALTEMPERATURE (°F)
Figure 3.4.9-1 Pressure/Temperature Limits for Mechanical Heatup, Cooldown following Shutdown, and Reactor Critical Operations BFN-UNIT 3 3.4-29b Amendment No.247
RCS P/T Limits 3.4.9 1400 I I I I I I
__ BROWNS FERRY UNIT 3 I n/ 1 IV Curve No. 1 Minimum temperature for 1300 _---CURVES 1 AND 2 ARE bottom head during in-service VALID FOR 28 EFPY leak or hydrostatic testing.
__OF OPERATION -2 1200 Curve No. 2 Minimum temperature for upper F 1100 RPV and beltline during in-Cn service leak or hydrostatic testing.
P 1000 o* 900 0
Notes W These curves include sufficient n 800 margin to provide protection against feedwater nozzle O 700 degradation. The curves allow E_
U for shifts in RTNDT of the Reactor vessel beltline 9 600 materials, in accordance with Z Reg. Guide 1.99, Rev. 2, to 500 compensate for radiation embrittlement for 28 EFPY.
9 400 The acceptable area for operation is to the right of the applicable curves.
r 300 200 BOTTOM --- -----
HEAD IFLANGE 100 68 0 F REGION t4lLLw..z 83 ,
0 0 50 100 150 200 MINM=UM REACTOR VESSEL MTAL TEMPERATURE(°F)
Figure 3.4.9-2 Pressure/Temperature Limits for Reactor In-Service Leak and Hydrostatic Testing BFN-UNIT 3 3.4-29c Amendment No. 247