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| {{#Wiki_filter:N ExTeraENERGY !,,.,-ýSEýAB ROýOKJuly 9, 201510 CFR 50.90SBK-L-15132Docket No. 5 0-443U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001Seabrook StationResponse to Request for Additional Information for License Amendment Request 14-04Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 EffectiveFull Power Years | | {{#Wiki_filter:N ExTeraENERGY !,,.,-ýSEýAB ROýOKJuly 9, 201510 CFR 50.90SBK-L-15132 Docket No. 5 0-443U. S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, DC 20555-0001 Seabrook StationResponse to Request for Additional Information for License Amendment Request 14-04Revised Reactor Coolant System Pressure |
| | -Temperature Limits Applicable for 55 Effective Full Power Years |
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| ==References:== | | ==References:== |
| : 1. Seabrook Station License Amendment Request 14-04, "Revised Reactor Coolant SystemPressure -Temperature Limits Applicable for 55 Effective Full Power Years," SBK-L-14102, July 24, 2014 (ML14216A404).2. NRC letter to Seabrook Station, "Seabrook Station, Unit No. 1 -Request for AdditionalInformation Regarding License Amendment Request to Revise the TechnicalSpecification Pressure-Temperature Limits and Request for Exemption from 10 CFR Part50, Appendix G Minimum Temperature requirements (TAC Nos. MF4576 andMF4577)," dated January 9, 2015 (ML14363A367).3. Seabrook Station letter SBK-L-15040, "Response to Request for Additional Informationfor License Amendment Request 14-04 Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 Effective Full Power Years, dated March 9, 2015(ML15072A036).4. Seabrook Station letter SBK-L-15129, "Response to Request for Additional Informationfor License Amendment Request 14-04 Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 Effective Full Power Years, dated June 23, 2015.In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted License AmendmentRequest (LAR) 14-04 to the Technical Specifications (TS) for Seabrook Station and requested anexemption from the requirements of 10 CFR 50 Appendix G. The proposed change revises theNextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 U.S. Nuclear Regulatory CommissionSBK-L- 15132/Page 2pressure-temperature (P/T) limits in TS 3 /4.4.9 LCO 3.4.9.1, Reactor Coolant System Pressure-Temperature Limits, to be applicable to 55 effective full power years. The change also revisesTS 3 /4/4.9 LCO 3.4.9.3, Overpressure Protection Systems, by providing new overpressureprotection setpoints and lowering the RCS temperature at which the TS is applicable.In Reference 2, the NRC requested additional information to complete its review of LAR 14-04.NextEra provided the responses to RAIs 2.1.1, 2.1.2, 2.1.3 and 2.1.4 in Reference 3 along with arequest to extend its response to RAI 2.2.1 to June 30, 2015.The response to RAI 2.2.1 required additional input from the vendor to complete the response.In a conference call on June 17, 2015, the NRC requested an additional note be added to theSeabrook pressure-temperature curves restricting the heat-up rate to less than or equal to 20 'Fper hour for moderator temperatures less than 120 'F. In Reference 4, NextEra requestedadditional time to obtain the requested information from its vendor, Westinghouse and to submitits response to RAI 2.2.1.The response to RAI 2.2.1 is provided in the enclosure to this letter. The revised marked-uptechnical specification pages are provided in the attachment to this letter.The response to the NRC RAI-2.2-1 resulted in a change to the previously submitted LicenseAmendment Request 14-04 for the Seabrook Technical Specification (TS) 3.4.9.1, Pressure /Temperature Limits, by providing new reactor coolant system (RCS) pressure and temperature(P/T) limits that are applicable to 55 effective full power years (EFPY). As a result, a NoSignificant Hazards Consideration was performed for the revised Pressure Temperature Limits inTS Figures 3.4-2 and 3.4-3.This letter contains no regulatory commitments.Should you have any questions regarding this letter, please contact Mr. Michael Ossing,Licensing Manager, at (603) 773-7512.I declare under penalty of perjury that the foregoing is true and correct.Executed on July _\ ,2015.Sincerely,NextEra Energy Seabrook, LLCRalph A. Dodds, IIIPlant General ManagerEnclosure U.S. Nuclear Regulatory CommissionSBK-L-15132/Page 3cc: D. Dorman, NRC Region I AdministratorJ. Lamb, NRC Project Manager, Project Directorate 1-2P. Cataldo, NRC Senior Resident InspectorMr. Perry PlummerDirector Homeland Security and Emergency ManagementNew Hampshire Department of SafetyDivision of Homeland Security and Emergency ManagementBureau of Emergency Management33 Hazen DriveConcord, NH 03305John Giarrusso, Jr., Nuclear Preparedness ManagerThe Commonwealth of MassachusettsEmergency Management Agency400 Worcester RoadFramingham, MA 01702-5399 ENCLOSURE to SBK-L-15132Response to Request for Additional Information for License Amendment Request 14-04Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 EffectiveFull Power Years Response to Request for Additional Information for License Amendment Request 14-04Revised Reactor Coolant System Pressure -Temperature Limits Applicable for 55 EffectiveFull Power YearsNRC RAI2.2.1.: The current TS P-T limit curves for 23. 7 EFPY have margins to account for pressureand temperature instrument errors; the proposed 55 EFPY TS P-T limits do not have these margins.Please address how instrumentation errors will be accounted for to ensure that the RCS is operated inaccordance with the proposed TS P-T limits for 55 EFPYNextEra Response:The proposed TS P-T limit curves for 55 EFPY have been revised to include margins to account forpressure and temperature instrument uncertainty. Changes were also made to eliminate heat up and cooldown rates that are not achievable during normal plant operating conditions in the lower temperatureregions where the cold overpressure mitigation system (COMS) is enabled to protect the RCS withpower operated relief valves (PORVs) as identified in TS Figure 3.4-4. No changes were made to thePORV set point values TS Figure 3.4-4 as this figure already contains appropriate instrumentuncertainty as well as additional margins for pressure overshoot transients should an actuation occur.Specifically, the revised curves shift the heat up and cool down P-T Limits curve data points developedin WCAP-17441-NP by 100 psi downward and 20'F to the right to account for the instrumentuncertainty. An additional 15 psi uncertainty was applied to the heat up curve above the COMS enabletemperature where operationally the wide range pressure indication on the main control board could bethe only available indication in some unlikely but possible scenarios.In addition to accounting for instrument uncertainty, unachievable heat up and cool down rates wereeliminated or restricted.For the heat up limitation curve, proposed TS Figure 3.4-2, a heat up rate restriction of 20°F/hr wasadded at temperatures at or below 120'F, corresponding to the transient defined in WCAP-17444 andthe previous response to RAI 2.1.4. At temperatures greater than 120'F to less than 200'F the heat uprate of 80°F/hr maximum is specified and at greater than or equal to 200'F the maximum rate is100°F/hr. Instrument uncertainties of 20'F and 100 psi were added to the data points in WCAP-17441-NP Table 6-3. An additional pressure uncertainty of 15 psi was added to the heat up curve starting at200'F prior to the cold overpressure mitigation system being disabled. Considering the 20°F/hr raterestriction, pressure and temperature data from 60'F to 80'F (40°F to 60'F without the instrumentuncertainty of 20'F) were determined using the more limiting pressure rate change between the existing80°F/hr heat up data and the steady state data. Linear extrapolation of the 60'F to 65°F allowablepressure change of 13 psi per 5°F was applied to the heat up curve pressure limits from 60°F to 80'F.These heat up rate limitations and instrument uncertainties additions result in all pressure limitations ator below 225°F, in the COMS enable temperature region, being above and protected by the COMSsystem set point curve in TS Figure 3.4-4.For the cool down limitation curve, proposed TS Figure 3.4-3, the cool down rate is restricted to 20°F/hrat temperatures less than 150'F. Instrument uncertainties of 20'F and 100 psi were added to the datapoints in WCAP-17441-NP Table 6-4. Since the entire curve is to the left and above the COMS enabletemperature and pressure limits identified in TS Figure 3.4-4, the additional 15 psi uncertainty was notPage 1 of 6 necessary. Pressure and temperature data from 60'F to 80'F (40'F to 60'F without the instrumentuncertainty of 20'F) were determined by linear extrapolation of the pressure rate change between 60'Fto 65'F for the 20°F/hr cool down data and the steady state data which results in a 13 psi change per5°F. These cool down rate limitations and instrument uncertainties additions result in all pressurelimitations being above and protected by the COMS system set point curve in TS Figure 3.4-4.The bolt up temperature was maintained at 60'F as identified in WCAP-14040-A, Revision 4,"Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup andCooldown Limit Curves." The limiting closure head region material RTndt is 30°F allowing bolt uptemperature to be as low as 50'F with the application of uncertainty. However, the 60'F bolt uptemperature advised in WCAP-14040-A is maintained.The proposed heat up limitation curve, TS Figure 3.4-2, and the proposed cool down limitation curve,TS Figure 3.4-3 applicable for 55 EFPY have been revised to include margins to account for pressureand temperature instrument uncertainty as described above and are provided in the attachment. Therevised data points for the revised heat up and cool down curves are provided in Tables 1 and 2respectively.Page 2 of 6 Significant Hazards ConsiderationNo Significant Hazards Consideration:The response to the NRC RAI-2.2-1 resulted in a change to the previously submitted LicenseAmendment Request 14-04 for the Seabrook Technical Specification (TS) 3.4.9.1, Pressure /Temperature Limits, by providing new reactor coolant system (RCS) pressure and temperature (P/T)limits that are applicable to 55 effective full power years (EFPY). As a result, a No Significant HazardsConsideration was performed for the revised Pressure Temperature Limits in TS Figures 3.4-2 and 3.4-3.In accordance with 10 CFR 50.92, NextEra Energy Seabrook has concluded that the proposed changedoes not involve a significant hazards consideration (SHC). The basis for the conclusion that theproposed change does not involve a SHC is as follows:1. Does the proposed change involve a significant increase in the probability or consequences of anaccident previously evaluated?No. The proposed changes to the Technical Specifications (TS) do not impact the physical function ofplant structures, systems, or components (SSCs) or the manner in which SSCs perform their designfunction. Operation in accordance with the proposed TS will ensure that all analyzed accidents willcontinue to be mitigated by the SSCs as previously analyzed. The proposed changes do not alter orprevent the ability of operable SSCs to perform their intended function to mitigate the consequences ofan initiating event within assumed acceptance limits. The proposed changes neither adversely affectaccident initiators or precursors, nor alter design assumptions.Therefore, the proposed changes do not involve a significant increase in the probability or consequencesof an accident previously evaluated.2. Does the proposed change create the possibility of a new or different kind of accident from anypreviously evaluated?No. The proposed changes do not involve installation of new or different type of equipment, create newfailure modes for existing equipment, or create any new limiting single failures. The changes to thepressure -temperature limits will continue to ensure that appropriate fracture toughness margins aremaintained to protect against reactor vessel failure, during both normal and low temperature operation.The proposed changes are consistent with the applicable NRC approved methodologies (i.e., WCAP-14040, Rev. 4 and ASME Code Case N-641). Plant operation will not be altered, and all safety functionswill continue to perform as previously assumed in accident analyses.Therefore, the proposed changes do not create the possibility of a new or different kind of accident fromany accident previously evaluated.Page 3 of 6 | | : 1. Seabrook Station License Amendment Request 14-04, "Revised Reactor Coolant SystemPressure |
| : 3. Does the proposed change involve a significant reduction in the margin of safety?No. Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuelcladding, reactor coolant system pressure boundary, and containment structure) to limit the level ofradiation dose to the public. The proposed changes will not adversely affect the operation of plantequipment or the function of any equipment assumed in the accident analysis. The proposed changeswere developed using NRC approved methodologies and will continue to ensure an acceptable marginof safety is maintained. The safety analysis acceptance criteria are not affected by this change. Theproposed changes will not result in plant operation in a configuration outside the design basis. Theproposed changes do not adversely affect systems that respond to safely shutdown the plant and tomaintain the plant in a safe shutdown condition.Therefore, the proposed changes do not involve a significant reduction in a margin of safety.Based on the above, NextEra concludes that the proposed amendment does not involve a significanthazards consideration under the standards set forth in 10 CFR 50.92(b), and, accordingly, a finding of"no significant hazards consideration" is justified.Page 4 of 6 9 j° 5 OfcI96EZ 09Z_____ 90WW ____ ________VEOZ OSE8L81 StWS9ELI O-vz8091 £E__61I O _ _... ._ W8 ll OWW________890W1 sI _ __ _ __ _ ___ _ __ _8£0I £OW __-_.__-£66 OO £66 O0N ....... _.66 W61566 0611L6 £81616 081ZL8 £LI ___.I 8 OLI .... ...96EZ 00£ £6L £91 _ __....9O0W S6K 09L 091 "°17tOW 06 O£L Oft18L81 £8Z 1O1 O£19ELI 08Z "Z W89 £7 I _. ...8091 SLW _99 ON ....__,Z6tI OLW 91,9 SU99Z WE9 OT _ _Z6ZI 09Z WW9 £W _____90WI ££W N'19 Ozi t179 Ozi _____8W11 O.. 609 £i1 _______8£01 £1W .... L09 011 .. ..£66 o017 : L09 £ol£66 £E. L09 001£66 OE£ L09 £61O6 gZ .L09 06616 OW :L09 £8 .... __.ZL8 £TW L09 08 _ _M£8 O1W '_ _ L09 £L ________£61 SOZ _______ ,09 OL £8£E L6109L OO 06£ £9 £8£E L6111L L61 LL£ 09 0061 0810 L61 _ 0 09 0061 081(o (!s) (A.) (~d 8) (!d 8) (a.s) (A.)a I a I a I a I a ILA!lupa!a flnjuoH aq/ao001 dnjvoH q/Ao0R dnjuaH xq/,4,o0 Iso&L 3jua(saiouaa uo! juomni~sul aoj su!itmI qj!m puu 'qajoN 1noqj!m '3IX qj!i) S~ojopoqjoAW fD "ddvupuppyV OOOZ aqj q.noaql 8661 aqj 2uisn sOana dnI9oH I j!ufl 3looxquas {Aj Fc aq oj sju!od mujI alqui Table 2Data Points for the 55 EFPY Seabrook Unit 1 Cooldown Curves using the 1998 through the 2000 AddendaApp. G Methodology (with Kic, without Flange Notch, and with Margins for Instrumentation Errors)Steady-State 201F/hr Cooldown 100°F/hr Cooldown(00F/hr)T P P P(OF) (psig) T (0F) (psig) T (0F) (psig)60 0 60 060 577 60 53765 590 65 55070 603 70 56375 616 75 57680 629 80 58985 642 85 60290 656 90 61895 671 95 635100 689 100 654105 708 105 674110 729 110 697115 752 115 723120 778 120 751125 806 125 782130 838 130 817135 872 135 855140 911 140 897145 953 145 944150 1000 150 995 150 995155 1052 155 1052160 1109 160 1109165 1172 165 1172170 1242 170 1242175 1319 175 1319180 1404 180 1404185 1499 185 1499190 1603 190 1603195 1718 195 1718200 1846 200 1846205 1986 205 1986210 2142 210 2142215 2314 215 2314220 2504 1 220 2504Page 6 of 6 Attachment to SBK-L- 15132Marked-Up Technical Specification Pages 11v!SeRT-A (A/X 7 itCL --- L 1 --I- J , -I-.. T-r ---.--1 TL ----iea estI I I I I I I I iILinaccepta ' ''ceptableS Operati T,, .operation -Hea Rate [ ticaI irnit80 Deg. F/Hr 1 0DegF~r.L+/-. I IL.J, L.S Heatu I I I I I Ia Imit I I100 g. F/ -r ----i- -'-- --- " -FR-rIL AI II I iiIIi I I Ii tr I --I--I4 -I eP 4I-t I l tI l i-I- T -T 1-----Z --...1000 -/" A/ii._.IlO00I,300IRE (Deg. F, gI8500UP 0 23.7 EFPY/O /E tFESEABROOK -UNIT 13/4 4-23SEABROK -UNIT 3/44-23Amendment No. 19, 89, 115,13-5 Insert AMATERIAL PROPERTY BASISLIMITING MATERIAL: Lower Shell Plate RI 808-1 without using surveillance data, Position 1.1LIMITING ART VALUES AT 55 EFPY: 1/4T, 117°F (Axial Flaw)3/4T, 105'F (Axial Flaw)Curves applicable for the first 55 EFPY and contain margins for possible instrument errors25002250 _ _ ILeak Test Limit 2000 -_ _1750 "170Critical LimitIHeatup Curve-- 1500UnacceptableIOperation ICLIa _ 1250 .---p,U)Heatup rate belowrn- 1000 --120 F shall not -- , _-_ exceed 20OF/hr -Composite Heatup Curve750 Indicated RCS Maximum Alloy(fl Temperature Heatup RatT5 <120°F 20F/hrO ------ 200'F > T > 120°F 80°F/hr'5025000 50 100 150200 250 300 350 400 450 500 550RCS Temperature (Deg. F, 10 Deg. F per division)* Curve is Applicable for RCS Vacuum fillFIGURE 3.4-2REACTOR COOLANT SYSTEM HEATUP LIMITATIONS -APPLICABLE UP TO 55 EFPY 1,4,YW re(x-r F A, ejV1AERIAL PR ERTY BASISLimiting erial: LOWER 5 ELL P/LATE -,1808-1ART values a 3.7 EFPYI/4 , 109'F4T, 880PCurves appli lr the firs EFFY and ntain margin 20'F and 100 ig for possib instrument error-,onon --"-./ //802600 -24002200 -20001800 -wILS160CD* 1400-CO)120S1000-0-600200-r 1 -- -------1. -1'3rT- -''r- -------I/ I I I I .ptableII IIII peration --j.4 .L __- -_ -J ------- ------- ---------- --I-------, ----Co -ldown taUplo g I I I-- ---I ,----------- --r--iI I I I ------ '---, -I--P- --II I I I ----- --iI I I l t-l ...I -T r 7-- Cool n Rates t L ~ f...A L....L.i -....c Deg.F/Hr -, 2 I I I I I I I I I I-e. -,- -- ----- -- -----4.JWLJ. 80, 100 D .F/hr JIIAI JI -LJ L -..h-I-I I I I I I I I I I I I I I£ _ I £ I I! _ I I I I i I i J 'I I I IB I pI I I I II I I I I I I I I I I I I I I I I I II I I I I I I I I I I I I II I I I I I II I I II I I I I I I I Im pI I I I I I I I I II I I I III I I I I I I I II 1 I I//11/, 7''10 100 200 300 400 500R TEMPERAT (Deg. F, 2 eg. F PER DV ION)GURE 3.4-3ACTOR COO T SYSTEM OLDOWN LI11 ATIONS -LICABLE UP 23.7 EF YSEABROOK -UNIT 13/4 4-24Amendment No. 19, 89, 115, 135 Insert BMATERIAL PROPERTY BASISLIMITING MATERIAL: Lower Shell Plate RI 808-1 without using surveillance data, Position 1.1LIMITING ART VALUES AT 55 EFPY: 1/4T, 1177F (Axial Flaw)3/4T, 1057F (Axial Flaw)Curves applicable for the first 55 EFPY and contain margins for possible instrument errors2500225020001750C0> 1500CL0)0 1250CL0Lo)10007505)C,)W~ 500F neptableLgperaionjLi..AcetableI ItF--Composite Cooldown CurveIndicated RCS Maximum AllowableTemperature Cooldown RateT < 150°F 20°F/hrT > 150°F 100°F/hr2500I ..I ....I ....I .. ..0 50100 150 200 250 300 350 400 450500550RCS Temperature (Deg. F, 10 Deg. F per division)* Curve is Applicable for RCS Vacuum fillFIGURE 3.4-3REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS -APPLICABLE UP TO 55 EFPY}} | | -Temperature Limits Applicable for 55 Effective Full Power Years," SBK-L-14102, July 24, 2014 (ML14216A404). |
| | : 2. NRC letter to Seabrook |
| | : Station, "Seabrook |
| | : Station, Unit No. 1 -Request for Additional Information Regarding License Amendment Request to Revise the Technical Specification Pressure-Temperature Limits and Request for Exemption from 10 CFR Part50, Appendix G Minimum Temperature requirements (TAC Nos. MF4576 andMF4577)," |
| | dated January 9, 2015 (ML14363A367). |
| | : 3. Seabrook Station letter SBK-L-15040, "Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure |
| | -Temperature Limits Applicable for 55 Effective Full Power Years, dated March 9, 2015(ML15072A036). |
| | : 4. Seabrook Station letter SBK-L-15129, "Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure |
| | -Temperature Limits Applicable for 55 Effective Full Power Years, dated June 23, 2015.In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted License Amendment Request (LAR) 14-04 to the Technical Specifications (TS) for Seabrook Station and requested anexemption from the requirements of 10 CFR 50 Appendix G. The proposed change revises theNextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 U.S. Nuclear Regulatory Commission SBK-L- 15132/Page 2pressure-temperature (P/T) limits in TS 3 /4.4.9 LCO 3.4.9.1, Reactor Coolant System Pressure-Temperature Limits, to be applicable to 55 effective full power years. The change also revisesTS 3 /4/4.9 LCO 3.4.9.3, Overpressure Protection |
| | : Systems, by providing new overpressure protection setpoints and lowering the RCS temperature at which the TS is applicable. |
| | In Reference 2, the NRC requested additional information to complete its review of LAR 14-04.NextEra provided the responses to RAIs 2.1.1, 2.1.2, 2.1.3 and 2.1.4 in Reference 3 along with arequest to extend its response to RAI 2.2.1 to June 30, 2015.The response to RAI 2.2.1 required additional input from the vendor to complete the response. |
| | In a conference call on June 17, 2015, the NRC requested an additional note be added to theSeabrook pressure-temperature curves restricting the heat-up rate to less than or equal to 20 'Fper hour for moderator temperatures less than 120 'F. In Reference 4, NextEra requested additional time to obtain the requested information from its vendor, Westinghouse and to submitits response to RAI 2.2.1.The response to RAI 2.2.1 is provided in the enclosure to this letter. The revised marked-up technical specification pages are provided in the attachment to this letter.The response to the NRC RAI-2.2-1 resulted in a change to the previously submitted LicenseAmendment Request 14-04 for the Seabrook Technical Specification (TS) 3.4.9.1, Pressure |
| | /Temperature Limits, by providing new reactor coolant system (RCS) pressure and temperature (P/T) limits that are applicable to 55 effective full power years (EFPY). As a result, a NoSignificant Hazards Consideration was performed for the revised Pressure Temperature Limits inTS Figures 3.4-2 and 3.4-3.This letter contains no regulatory commitments. |
| | Should you have any questions regarding this letter, please contact Mr. Michael Ossing,Licensing |
| | : Manager, at (603) 773-7512. |
| | I declare under penalty of perjury that the foregoing is true and correct.Executed on July _\ ,2015.Sincerely, NextEra Energy Seabrook, LLCRalph A. Dodds, IIIPlant General ManagerEnclosure U.S. Nuclear Regulatory Commission SBK-L-15132/Page 3cc: D. Dorman, NRC Region I Administrator J. Lamb, NRC Project Manager, Project Directorate 1-2P. Cataldo, NRC Senior Resident Inspector Mr. Perry PlummerDirector Homeland Security and Emergency Management New Hampshire Department of SafetyDivision of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen DriveConcord, NH 03305John Giarrusso, Jr., Nuclear Preparedness ManagerThe Commonwealth of Massachusetts Emergency Management Agency400 Worcester RoadFramingham, MA 01702-5399 ENCLOSURE to SBK-L-15132 Response to Request for Additional Information for License Amendment Request 14-04Revised Reactor Coolant System Pressure |
| | -Temperature Limits Applicable for 55 Effective Full Power Years Response to Request for Additional Information for License Amendment Request 14-04Revised Reactor Coolant System Pressure |
| | -Temperature Limits Applicable for 55 Effective Full Power YearsNRC RAI2.2.1.: |
| | The current TS P-T limit curves for 23. 7 EFPY have margins to account for pressureand temperature instrument errors; the proposed 55 EFPY TS P-T limits do not have these margins.Please address how instrumentation errors will be accounted for to ensure that the RCS is operated inaccordance with the proposed TS P-T limits for 55 EFPYNextEra Response: |
| | The proposed TS P-T limit curves for 55 EFPY have been revised to include margins to account forpressure and temperature instrument uncertainty. |
| | Changes were also made to eliminate heat up and cooldown rates that are not achievable during normal plant operating conditions in the lower temperature regions where the cold overpressure mitigation system (COMS) is enabled to protect the RCS withpower operated relief valves (PORVs) as identified in TS Figure 3.4-4. No changes were made to thePORV set point values TS Figure 3.4-4 as this figure already contains appropriate instrument uncertainty as well as additional margins for pressure overshoot transients should an actuation occur.Specifically, the revised curves shift the heat up and cool down P-T Limits curve data points developed in WCAP-17441-NP by 100 psi downward and 20'F to the right to account for the instrument uncertainty. |
| | An additional 15 psi uncertainty was applied to the heat up curve above the COMS enabletemperature where operationally the wide range pressure indication on the main control board could bethe only available indication in some unlikely but possible scenarios. |
| | In addition to accounting for instrument uncertainty, unachievable heat up and cool down rates wereeliminated or restricted. |
| | For the heat up limitation curve, proposed TS Figure 3.4-2, a heat up rate restriction of 20°F/hr wasadded at temperatures at or below 120'F, corresponding to the transient defined in WCAP-17444 andthe previous response to RAI 2.1.4. At temperatures greater than 120'F to less than 200'F the heat uprate of 80°F/hr maximum is specified and at greater than or equal to 200'F the maximum rate is100°F/hr. |
| | Instrument uncertainties of 20'F and 100 psi were added to the data points in WCAP-17441-NP Table 6-3. An additional pressure uncertainty of 15 psi was added to the heat up curve starting at200'F prior to the cold overpressure mitigation system being disabled. |
| | Considering the 20°F/hr raterestriction, pressure and temperature data from 60'F to 80'F (40°F to 60'F without the instrument uncertainty of 20'F) were determined using the more limiting pressure rate change between the existing80°F/hr heat up data and the steady state data. Linear extrapolation of the 60'F to 65°F allowable pressure change of 13 psi per 5°F was applied to the heat up curve pressure limits from 60°F to 80'F.These heat up rate limitations and instrument uncertainties additions result in all pressure limitations ator below 225°F, in the COMS enable temperature region, being above and protected by the COMSsystem set point curve in TS Figure 3.4-4.For the cool down limitation curve, proposed TS Figure 3.4-3, the cool down rate is restricted to 20°F/hrat temperatures less than 150'F. Instrument uncertainties of 20'F and 100 psi were added to the datapoints in WCAP-17441-NP Table 6-4. Since the entire curve is to the left and above the COMS enabletemperature and pressure limits identified in TS Figure 3.4-4, the additional 15 psi uncertainty was notPage 1 of 6 necessary. |
| | Pressure and temperature data from 60'F to 80'F (40'F to 60'F without the instrument uncertainty of 20'F) were determined by linear extrapolation of the pressure rate change between 60'Fto 65'F for the 20°F/hr cool down data and the steady state data which results in a 13 psi change per5°F. These cool down rate limitations and instrument uncertainties additions result in all pressurelimitations being above and protected by the COMS system set point curve in TS Figure 3.4-4.The bolt up temperature was maintained at 60'F as identified in WCAP-14040-A, Revision 4,"Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup andCooldown Limit Curves." |
| | The limiting closure head region material RTndt is 30°F allowing bolt uptemperature to be as low as 50'F with the application of uncertainty. |
| | : However, the 60'F bolt uptemperature advised in WCAP-14040-A is maintained. |
| | The proposed heat up limitation curve, TS Figure 3.4-2, and the proposed cool down limitation curve,TS Figure 3.4-3 applicable for 55 EFPY have been revised to include margins to account for pressureand temperature instrument uncertainty as described above and are provided in the attachment. |
| | Therevised data points for the revised heat up and cool down curves are provided in Tables 1 and 2respectively. |
| | Page 2 of 6 Significant Hazards Consideration No Significant Hazards Consideration: |
| | The response to the NRC RAI-2.2-1 resulted in a change to the previously submitted LicenseAmendment Request 14-04 for the Seabrook Technical Specification (TS) 3.4.9.1, Pressure |
| | /Temperature Limits, by providing new reactor coolant system (RCS) pressure and temperature (P/T)limits that are applicable to 55 effective full power years (EFPY). As a result, a No Significant HazardsConsideration was performed for the revised Pressure Temperature Limits in TS Figures 3.4-2 and 3.4-3.In accordance with 10 CFR 50.92, NextEra Energy Seabrook has concluded that the proposed changedoes not involve a significant hazards consideration (SHC). The basis for the conclusion that theproposed change does not involve a SHC is as follows:1. Does the proposed change involve a significant increase in the probability or consequences of anaccident previously evaluated? |
| | No. The proposed changes to the Technical Specifications (TS) do not impact the physical function ofplant structures, |
| | : systems, or components (SSCs) or the manner in which SSCs perform their designfunction. |
| | Operation in accordance with the proposed TS will ensure that all analyzed accidents willcontinue to be mitigated by the SSCs as previously analyzed. |
| | The proposed changes do not alter orprevent the ability of operable SSCs to perform their intended function to mitigate the consequences ofan initiating event within assumed acceptance limits. The proposed changes neither adversely affectaccident initiators or precursors, nor alter design assumptions. |
| | Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. |
| | : 2. Does the proposed change create the possibility of a new or different kind of accident from anypreviously evaluated? |
| | No. The proposed changes do not involve installation of new or different type of equipment, create newfailure modes for existing equipment, or create any new limiting single failures. |
| | The changes to thepressure |
| | -temperature limits will continue to ensure that appropriate fracture toughness margins aremaintained to protect against reactor vessel failure, during both normal and low temperature operation. |
| | The proposed changes are consistent with the applicable NRC approved methodologies (i.e., WCAP-14040, Rev. 4 and ASME Code Case N-641). Plant operation will not be altered, and all safety functions will continue to perform as previously assumed in accident analyses. |
| | Therefore, the proposed changes do not create the possibility of a new or different kind of accident fromany accident previously evaluated. |
| | Page 3 of 6 |
| | : 3. Does the proposed change involve a significant reduction in the margin of safety?No. Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuelcladding, reactor coolant system pressure |
| | : boundary, and containment structure) to limit the level ofradiation dose to the public. The proposed changes will not adversely affect the operation of plantequipment or the function of any equipment assumed in the accident analysis. |
| | The proposed changeswere developed using NRC approved methodologies and will continue to ensure an acceptable marginof safety is maintained. |
| | The safety analysis acceptance criteria are not affected by this change. Theproposed changes will not result in plant operation in a configuration outside the design basis. Theproposed changes do not adversely affect systems that respond to safely shutdown the plant and tomaintain the plant in a safe shutdown condition. |
| | Therefore, the proposed changes do not involve a significant reduction in a margin of safety.Based on the above, NextEra concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(b), |
| | and, accordingly, a finding of"no significant hazards consideration" is justified. |
| | Page 4 of 6 9 j° 5 OfcI96EZ 09Z_____ 90WW ____ ________VEOZ OSE8L81 StWS9ELI O-vz8091 £E__61I O _ _... ._ W8 ll OWW________890W1 sI _ __ _ __ _ ___ _ __ _8£0I £OW __-_.__-£66 OO £66 O0N ....... _.66 W61566 0611L6 £81616 081ZL8 £LI ___.I 8 OLI .... ...96EZ 00£ £6L £91 _ __....9O0W S6K 09L 091 "°17tOW 06 O£L Oft18L81 £8Z 1O1 O£19ELI 08Z "Z W89 £7 I _. ...8091 SLW _99 ON ....__,Z6tI OLW 91,9 SU99Z WE9 OT _ _Z6ZI 09Z WW9 £W _____90WI ££W N'19 Ozi t179 Ozi _____8W11 O.. 609 £i1 _______8£01 £1W .... L09 011 .. ..£66 o017 : L09 £ol£66 £E. L09 001£66 OE£ L09 £61O6 gZ .L09 06616 OW :L09 £8 .... __.ZL8 £TW L09 08 _ _M£8 O1W '_ _ L09 £L ________£61 SOZ _______ ,09 OL £8£E L6109L OO 06£ £9 £8£E L6111L L61 LL£ 09 0061 0810 L61 _ 0 09 0061 081(o (!s) (A.) (~d 8) (!d 8) (a.s) (A.)a I a I a I a I a ILA!lupa!a flnjuoH aq/ao001 dnjvoH q/Ao0R dnjuaH xq/,4,o0 Iso&L 3jua(saiouaa uo! juomni~sul aoj su!itmI qj!m puu 'qajoN 1noqj!m '3IX qj!i) S~ojopoqjoAW fD "ddvupuppyV OOOZ aqj q.noaql 8661 aqj 2uisn sOana dnI9oH I j!ufl 3looxquas |
| | {Aj Fc aq oj sju!od mujI alqui Table 2Data Points for the 55 EFPY Seabrook Unit 1 Cooldown Curves using the 1998 through the 2000 AddendaApp. G Methodology (with Kic, without Flange Notch, and with Margins for Instrumentation Errors)Steady-State 201F/hr Cooldown 100°F/hr Cooldown(00F/hr)T P P P(OF) (psig) T (0F) (psig) T (0F) (psig)60 0 60 060 577 60 53765 590 65 55070 603 70 56375 616 75 57680 629 80 58985 642 85 60290 656 90 61895 671 95 635100 689 100 654105 708 105 674110 729 110 697115 752 115 723120 778 120 751125 806 125 782130 838 130 817135 872 135 855140 911 140 897145 953 145 944150 1000 150 995 150 995155 1052 155 1052160 1109 160 1109165 1172 165 1172170 1242 170 1242175 1319 175 1319180 1404 180 1404185 1499 185 1499190 1603 190 1603195 1718 195 1718200 1846 200 1846205 1986 205 1986210 2142 210 2142215 2314 215 2314220 2504 1 220 2504Page 6 of 6 Attachment to SBK-L- 15132Marked-Up Technical Specification Pages 11v!SeRT-A (A/X 7 itCL --- L 1 --I- J , -I-.. T-r ---.--1 TL ----iea estI I I I I I I I iILinaccepta |
| | ' ''ceptable S Operati T,, .operation |
| | -Hea Rate [ ticaI irnit80 Deg. F/Hr 1 0DegF~r.L+/-. |
| | I IL.J, L.S Heatu I I I I I Ia Imit I I100 g. F/ -r ----i- -'-- --- " -FR-rIL AI II I iiIIi I I Ii tr I --I--I4 -I eP 4I-t I l tI l i-I- T -T 1-----Z --...1000 -/" A/ii._.IlO00I,300IRE (Deg. F, gI8500UP 0 23.7 EFPY/O /E tFESEABROOK |
| | -UNIT 13/4 4-23SEABROK -UNIT 3/44-23Amendment No. 19, 89, 115,13-5 Insert AMATERIAL PROPERTY BASISLIMITING MATERIAL: |
| | Lower Shell Plate RI 808-1 without using surveillance data, Position 1.1LIMITING ART VALUES AT 55 EFPY: 1/4T, 117°F (Axial Flaw)3/4T, 105'F (Axial Flaw)Curves applicable for the first 55 EFPY and contain margins for possible instrument errors25002250 _ _ ILeak Test Limit 2000 -_ _1750 "170Critical LimitIHeatup Curve-- 1500Unacceptable IOperation ICLIa |
| | _ 1250 .---p,U)Heatup rate belowrn- 1000 --120 F shall not -- , _-_ exceed 20OF/hr -Composite Heatup Curve750 Indicated RCS Maximum Alloy(fl Temperature Heatup RatT5 <120°F 20F/hrO ------ 200'F > T > 120°F 80°F/hr'5025000 50 100 150200 250 300 350 400 450 500 550RCS Temperature (Deg. F, 10 Deg. F per division) |
| | * Curve is Applicable for RCS Vacuum fillFIGURE 3.4-2REACTOR COOLANT SYSTEM HEATUP LIMITATIONS |
| | -APPLICABLE UP TO 55 EFPY 1,4,YW re(x-r F A, ejV1AERIAL PR ERTY BASISLimiting erial: LOWER 5 ELL P/LATE -,1808-1ART values a 3.7 EFPYI/4 , 109'F4T, 880PCurves appli lr the firs EFFY and ntain margin 20'F and 100 ig for possib instrument error-,onon --"-./ //802600 -24002200 -20001800 -wILS160CD* 1400-CO)120S1000-0-600200-r 1 -- -------1. -1'3rT- -''r- -------I/ I I I I .ptableII IIII peration |
| | --j.4 .L __- -_ -J ------- ------- ---------- |
| | --I-------, |
| | ----Co -ldown taUplo g I I I-- ---I ,----------- |
| | --r--iI I I I ---- |
| | -- '---, -I--P- --II I I I ----- --iI I I l t-l ...I -T r 7-- Cool n Rates t L ~ f...A L....L.i |
| | -....c Deg.F/Hr |
| | -, 2 I I I I I I I I I I-e. -,- -- ----- -- -----4.JWLJ. 80, 100 D .F/hr JIIAI JI -LJ L -..h-I-I I I I I I I I I I I I I I£ _ I £ I I! _ I I I I i I i J 'I I I IB I pI I I I II I I I I I I I I I I I I I I I I I II I I I I I I I I I I I I II I I I I I II I I II I I I I I I I Im pI I I I I I I I I II I I I III I I I I I I I II 1 I I//11/, 7''10 100 200 300 400 500R TEMPERAT (Deg. F, 2 eg. F PER DV ION)GURE 3.4-3ACTOR COO T SYSTEM OLDOWN LI11 ATIONS -LICABLE UP 23.7 EF YSEABROOK |
| | -UNIT 13/4 4-24Amendment No. 19, 89, 115, 135 Insert BMATERIAL PROPERTY BASISLIMITING MATERIAL: |
| | Lower Shell Plate RI 808-1 without using surveillance data, Position 1.1LIMITING ART VALUES AT 55 EFPY: 1/4T, 1177F (Axial Flaw)3/4T, 1057F (Axial Flaw)Curves applicable for the first 55 EFPY and contain margins for possible instrument errors2500225020001750C0> 1500CL0)0 1250CL0Lo)10007505)C,)W~ 500F neptableLgperaionj Li..AcetableI ItF--Composite Cooldown CurveIndicated RCS Maximum Allowable Temperature Cooldown RateT < 150°F 20°F/hrT > 150°F 100°F/hr2500I ..I ....I ....I .. ..0 50100 150 200 250 300 350 400 450500550RCS Temperature (Deg. F, 10 Deg. F per division) |
| | * Curve is Applicable for RCS Vacuum fillFIGURE 3.4-3REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS |
| | -APPLICABLE UP TO 55 EFPY}} |
Letter Sequence Response to RAI |
|---|
|
|
MONTHYEARML14232A6222014-09-0909 September 2014
Acceptance of Requested Licensing Amendment Request and Exemption Regarding Revised Reactor Coolant System Pressure-Temperature Limits
Project stage: Acceptance Review
ML14363A3672015-01-0909 January 2015
Request for Additional Information Regarding the License Amendment Request to Revise the Technical Specification Pressure-Temperature Limits and Request for Exemption from 10 CFR Part 50, Appendix G Minimum Tempt Requirements
Project stage: RAI
SBK-L-15040, Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-03-0909 March 2015
Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
Project stage: Response to RAI
ML15084A3752015-04-0303 April 2015
Request for Withholding Information from Public Disclosure Regarding License Amendment Request 14-04 for Seabrook Station, Unit 1 (TAC Nos. MF4576 and MF4577)
Project stage: Withholding Request Acceptance
ML15128A1482015-06-0505 June 2015
Request for Withholding Information from Public Disclosure Regarding License Amendment Request 14-04 for Seabrook Station, Unit 1
Project stage: Withholding Request Acceptance
SBK-L-15129, Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-06-24024 June 2015
Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
Project stage: Response to RAI
SBK-L-15132, Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-07-0909 July 2015
Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
Project stage: Response to RAI
SBK-L-15151, Supplemental Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-07-20020 July 2015
Supplemental Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
Project stage: Supplement
SBK-L-15172, Clarification to Request for Additional Information (RAI-2.2-1) for License Amendment Request 14-04, Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years2015-09-0808 September 2015
Clarification to Request for Additional Information (RAI-2.2-1) for License Amendment Request 14-04, Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
Project stage: Supplement
ML15096A2552015-11-0202 November 2015
Issuance of Amendment Regarding License Amendment Request 14-04, Revised Reactor Coolant System Pressure-Temperature Limits Applicable for 44 Effective Full Power Years
Project stage: Approval
2015-04-03
[Table View] |
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Category:Letter
MONTHYEARIR 05000443/20240032024-10-30030 October 2024
Integrated Inspection Report 05000443/2024003
L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024
Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
ML24303A0352024-10-29029 October 2024
Operator Licensing Examination Approval
IR 05000443/20244022024-10-17017 October 2024
Material Control and Accounting Program Inspection Report 05000443/2024402 (Cover Letter Only)
L-2024-159, Core Operating Limits Report for Reload Cycle 242024-10-15015 October 2024
Core Operating Limits Report for Reload Cycle 24
L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes
ML24254A2552024-09-25025 September 2024
Alternative Request No. 4A-01 for the Fourth 10-Year Inservice Inspection Interval
L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
ML24239A5382024-09-20020 September 2024
Issuance of Amendment No. 175 One-Time Allowable Outage Time Extension to the Technical Specification 3.8.1.1, A.C. Sources – Operating, Limiting Condition for Operation
L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
IR 05000443/20240052024-08-29029 August 2024
Updated Inspection Plan for Seabrook Station (Report 05000443/2024005)
ML24232A1142024-08-21021 August 2024
Correction to Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves
L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024
Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be
L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024
Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .
IR 05000443/20240022024-08-0606 August 2024
Integrated Inspection Report 05000443/2024002 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2024001
ML24163A0012024-08-0505 August 2024
LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review
L-2024-127, Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent2024-08-0505 August 2024
Supplement to Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent
L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024
Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024
Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.
ML24193A2432024-07-12012 July 2024
– Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan
L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024
Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal
L-2024-102, Official Service List Update2024-06-19019 June 2024
Official Service List Update
L-2024-098, Preparation and Scheduling of Operator Licensing Examinations2024-06-12012 June 2024
Preparation and Scheduling of Operator Licensing Examinations
ML24149A2862024-06-12012 June 2024
NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter
L-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-05-30030 May 2024
Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld
IR 05000443/20240102024-05-29029 May 2024
Biennial Problem Identification and Resolution Inspection Report 05000443/2024010
IR 05000443/20240112024-05-24024 May 2024
Age-Related Degradation Inspection Report 05000443/2024011
IR 05000443/20240012024-05-13013 May 2024
Integrated Inspection Report 05000443/2024001
L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut2024-05-10010 May 2024
NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distributio
ML24046A0512024-05-0707 May 2024
Issuance of Amendment No. 174 to Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (LTOP) Curves
ML24127A0632024-05-0606 May 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-078, 2023 Annual Radioactive Effluent Release Report2024-05-0101 May 2024
2023 Annual Radioactive Effluent Release Report
L-2024-077, 2023 Annual Radiological Environmental Operating Report2024-04-30030 April 2024
2023 Annual Radiological Environmental Operating Report
IR 05000443/20245012024-04-22022 April 2024
Emergency Preparedness Biennial Exercise Inspection Report 05000443/2024501
05000443/LER-2024-001, Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources2024-04-19019 April 2024
Condition Prohibited by Technical Specifications - Transformer Bushing Failure - Offsite AC Sources
SBK-L-24030, 2023 Annual Environmental Operating Report2024-04-12012 April 2024
2023 Annual Environmental Operating Report
L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024
And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
ML24067A2622024-03-0808 March 2024
Issuance of Amendment No. 173 Revise Technical Specification 3/4.8.1 to Allow Replacement of Reserve Auxiliary Transformer (Emergency Circumstances)
L-2024-038, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0808 March 2024
To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
L-2024-037, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0606 March 2024
To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
L-2024-035, Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0505 March 2024
Supplement to Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
ML24065A2522024-03-0505 March 2024
Notice of Enforcement Discretion for Seabrook Station, Unit No. 1 (EPID: L-2024-033)
L-2024-033, Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B2024-03-0404 March 2024
Request for Enforcement Discretion - Technical Specification (TS) 3/4.8.1.1 Ac. Sources Required Action Completion Time to Replace ED-X-3-B
L-2024-032, Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source2024-03-0404 March 2024
Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
IR 05000443/20230062024-02-28028 February 2024
Annual Assessment Letter for Seabrook Station (Report 05000443/2023006)
L-2024-019, Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-02-28028 February 2024
Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld
L-2024-016, Radiological Emergency Plan (Ssrep), Revision 822024-02-13013 February 2024
Radiological Emergency Plan (Ssrep), Revision 82
IR 05000443/20230042024-02-12012 February 2024
Integrated Inspection Report 05000443/2023004
ML24009A1152024-01-29029 January 2024
– Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024
Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)
2024-09-25
[Table view]
Category:Response to Request for Additional Information (RAI)
MONTHYEARL-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024
Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2024-141, Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit2024-08-15015 August 2024
Third Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Be
L-2024-137, Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .2024-08-12012 August 2024
Second Supplement to NextEra Energy Seabrook, LLC, Letter L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent .
L-2024-108, Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.2024-07-16016 July 2024
Response to Request for Additional Information (RAI) Regarding One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite.
ML24127A0632024-05-0606 May 2024
Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes
L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023
Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654,
L-2023-098, And Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023
And Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
L-2023-005, Response to Request for Additional Information for Seabrook Relief Request 4RA-22-0012023-01-26026 January 2023
Response to Request for Additional Information for Seabrook Relief Request 4RA-22-001
ML22307A1682022-11-0303 November 2022
Cover Memo and Response to C-10 Questions Regarding 2Q2022 Inspection Report - Corrected
L-2022-157, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report2022-09-28028 September 2022
Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report
L-2022-106, Revised Response to Request for Additional Information (RAI) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-06-27027 June 2022
Revised Response to Request for Additional Information (RAI) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements
ML22109A0342022-04-19019 April 2022
Cover Memo and Response to C-10 Questions Regarding 4Q2021 Inspection Report
SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022
Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements
ML21280A2622021-10-0707 October 2021
Response Letter to N. Treat (C-10 Research and Education Foundation) Regarding 2Q 2021 Integrated Inspection Report Questions
SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-022021-06-24024 June 2021
Revision to Updated Final Response to NRC Generic Letter 2004-02
SBK-L-21056, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:2021-05-20020 May 2021
Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:
SBK-L-21033, Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements2021-03-24024 March 2021
Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements
SBK-L-20149, Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-12-0808 December 2020
Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic
SBK-L-20117, Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request2020-09-23023 September 2020
Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request
SBK-L-20092, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-4182020-07-13013 July 2020
Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-418
SBK-L-20057, Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request2020-05-20020 May 2020
Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request
SBK-L-19120, Response to Request for Additional Information Related to Seabrook Inverter Amendment2019-10-30030 October 2019
Response to Request for Additional Information Related to Seabrook Inverter Amendment
SBK-L-18106, Response to Requests for Additional Information Related to License Renewal Application Environmental Review2018-06-14014 June 2018
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SBK-L-18074, Response to Request for Additional Information Regarding License Amendment Request 16-032018-06-0707 June 2018
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L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018
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SBK-L-18028, 0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program2018-02-28028 February 2018
0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program
SBK-L-18027, Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program2018-02-28028 February 2018
Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program
SBK-L-17202, Response to Seabrook Station, Unit No. 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption2017-12-14014 December 2017
Response to Seabrook Station, Unit No. 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption
SBK-L-17204, Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007)2017-12-11011 December 2017
Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007)
SBK-L-17180, Supplement 58, Revised Alkali-Silica Reaction Aging Management Program2017-11-0303 November 2017
Supplement 58, Revised Alkali-Silica Reaction Aging Management Program
SBK-L-17169, Supplement 58 - Non-Proprietary Enclosure 1 to SBK-L-171552017-10-17017 October 2017
Supplement 58 - Non-Proprietary Enclosure 1 to SBK-L-17155
SBK-L-17170, Non-Proprietary Enclosure 1 to SBK-L-171562017-10-17017 October 2017
Non-Proprietary Enclosure 1 to SBK-L-17156
SBK-L-17156, Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction2017-10-0303 October 2017
Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction
SBK-L-17155, Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction2017-10-0303 October 2017
Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction
SBK-L-17133, Clarification to Supplement 55 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Bolting Integrity Program2017-08-11011 August 2017
Clarification to Supplement 55 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Bolting Integrity Program
SBK-L-17103, Supplement 55 - Response to Request for Additional Information for the Review of the License Renewal Application - Bolting Integrity Program2017-06-20020 June 2017
Supplement 55 - Response to Request for Additional Information for the Review of the License Renewal Application - Bolting Integrity Program
SBK-L-17087, Supplement 53 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components2017-05-25025 May 2017
Supplement 53 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components
SBK-L-17082, Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 -Changes to Aging Management Guidance for Various Steam Generator Components2017-05-19019 May 2017
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SBK-L-17063, Response to Request for Additional Information Regarding License Amendment Request 17-01 One-Time Exigent Change to the Seabrook Licensing Basis Regarding Service Water Cooling Tower Functionality2017-04-0808 April 2017
Response to Request for Additional Information Regarding License Amendment Request 17-01 One-Time Exigent Change to the Seabrook Licensing Basis Regarding Service Water Cooling Tower Functionality
SBK-L-16205, Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency and EMCB-RAI-22016-12-30030 December 2016
Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency and EMCB-RAI-2
SBK-L-16196, Response to Request for Supplemental Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive...2016-12-15015 December 2016
Response to Request for Supplemental Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive...
SBK-L-16186, Supplement 50, Response to Request for Additional Information for the Review of License Renewal Application Providing Changes to Buried and Underground Piping and Tank Recommendations2016-11-23023 November 2016
Supplement 50, Response to Request for Additional Information for the Review of License Renewal Application Providing Changes to Buried and Underground Piping and Tank Recommendations
SBK-L-16190, Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency2016-11-17017 November 2016
Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency
ML16314D4272016-11-0707 November 2016
Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.1, Flooding - Submittal of Flooding Hazards Reevaluation Report, Revision 1
L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016
Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)
SBK-L-16162, Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2016-10-27027 October 2016
Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
SBK-L-16170, Response to Request for Additional Information for the 04/22/2016 Steam Generator Tube Inspection Report2016-10-27027 October 2016
Response to Request for Additional Information for the 04/22/2016 Steam Generator Tube Inspection Report
SBK-L-16165, Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency2016-10-27027 October 2016
Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency
SBK-L-16156, Response to Issuance of LR-ISG-2015-01 Changes to Buried and Underground Piping and Tank Recommendations2016-10-0707 October 2016
Response to Issuance of LR-ISG-2015-01 Changes to Buried and Underground Piping and Tank Recommendations
SBK-L-16134, Response to RAI Related to Severe Accident Mitigation Alternatives License Renewal Application2016-09-0606 September 2016
Response to RAI Related to Severe Accident Mitigation Alternatives License Renewal Application
2024-09-16
[Table view] |
Text
N ExTeraENERGY !,,.,-ýSEýAB ROýOKJuly 9, 201510 CFR 50.90SBK-L-15132 Docket No. 5 0-443U. S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, DC 20555-0001 Seabrook StationResponse to Request for Additional Information for License Amendment Request 14-04Revised Reactor Coolant System Pressure
-Temperature Limits Applicable for 55 Effective Full Power Years
References:
- 1. Seabrook Station License Amendment Request 14-04, "Revised Reactor Coolant SystemPressure
-Temperature Limits Applicable for 55 Effective Full Power Years," SBK-L-14102, July 24, 2014 (ML14216A404).
- 2. NRC letter to Seabrook
- Station, "Seabrook
- Station, Unit No. 1 -Request for Additional Information Regarding License Amendment Request to Revise the Technical Specification Pressure-Temperature Limits and Request for Exemption from 10 CFR Part50, Appendix G Minimum Temperature requirements (TAC Nos. MF4576 andMF4577),"
dated January 9, 2015 (ML14363A367).
- 3. Seabrook Station letter SBK-L-15040, "Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure
-Temperature Limits Applicable for 55 Effective Full Power Years, dated March 9, 2015(ML15072A036).
- 4. Seabrook Station letter SBK-L-15129, "Response to Request for Additional Information for License Amendment Request 14-04 Revised Reactor Coolant System Pressure
-Temperature Limits Applicable for 55 Effective Full Power Years, dated June 23, 2015.In Reference 1, NextEra Energy Seabrook, LLC (NextEra) submitted License Amendment Request (LAR) 14-04 to the Technical Specifications (TS) for Seabrook Station and requested anexemption from the requirements of 10 CFR 50 Appendix G. The proposed change revises theNextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874 U.S. Nuclear Regulatory Commission SBK-L- 15132/Page 2pressure-temperature (P/T) limits in TS 3 /4.4.9 LCO 3.4.9.1, Reactor Coolant System Pressure-Temperature Limits, to be applicable to 55 effective full power years. The change also revisesTS 3 /4/4.9 LCO 3.4.9.3, Overpressure Protection
- Systems, by providing new overpressure protection setpoints and lowering the RCS temperature at which the TS is applicable.
In Reference 2, the NRC requested additional information to complete its review of LAR 14-04.NextEra provided the responses to RAIs 2.1.1, 2.1.2, 2.1.3 and 2.1.4 in Reference 3 along with arequest to extend its response to RAI 2.2.1 to June 30, 2015.The response to RAI 2.2.1 required additional input from the vendor to complete the response.
In a conference call on June 17, 2015, the NRC requested an additional note be added to theSeabrook pressure-temperature curves restricting the heat-up rate to less than or equal to 20 'Fper hour for moderator temperatures less than 120 'F. In Reference 4, NextEra requested additional time to obtain the requested information from its vendor, Westinghouse and to submitits response to RAI 2.2.1.The response to RAI 2.2.1 is provided in the enclosure to this letter. The revised marked-up technical specification pages are provided in the attachment to this letter.The response to the NRC RAI-2.2-1 resulted in a change to the previously submitted LicenseAmendment Request 14-04 for the Seabrook Technical Specification (TS) 3.4.9.1, Pressure
/Temperature Limits, by providing new reactor coolant system (RCS) pressure and temperature (P/T) limits that are applicable to 55 effective full power years (EFPY). As a result, a NoSignificant Hazards Consideration was performed for the revised Pressure Temperature Limits inTS Figures 3.4-2 and 3.4-3.This letter contains no regulatory commitments.
Should you have any questions regarding this letter, please contact Mr. Michael Ossing,Licensing
- Manager, at (603) 773-7512.
I declare under penalty of perjury that the foregoing is true and correct.Executed on July _\ ,2015.Sincerely, NextEra Energy Seabrook, LLCRalph A. Dodds, IIIPlant General ManagerEnclosure U.S. Nuclear Regulatory Commission SBK-L-15132/Page 3cc: D. Dorman, NRC Region I Administrator J. Lamb, NRC Project Manager, Project Directorate 1-2P. Cataldo, NRC Senior Resident Inspector Mr. Perry PlummerDirector Homeland Security and Emergency Management New Hampshire Department of SafetyDivision of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen DriveConcord, NH 03305John Giarrusso, Jr., Nuclear Preparedness ManagerThe Commonwealth of Massachusetts Emergency Management Agency400 Worcester RoadFramingham, MA 01702-5399 ENCLOSURE to SBK-L-15132 Response to Request for Additional Information for License Amendment Request 14-04Revised Reactor Coolant System Pressure
-Temperature Limits Applicable for 55 Effective Full Power Years Response to Request for Additional Information for License Amendment Request 14-04Revised Reactor Coolant System Pressure
-Temperature Limits Applicable for 55 Effective Full Power YearsNRC RAI2.2.1.:
The current TS P-T limit curves for 23. 7 EFPY have margins to account for pressureand temperature instrument errors; the proposed 55 EFPY TS P-T limits do not have these margins.Please address how instrumentation errors will be accounted for to ensure that the RCS is operated inaccordance with the proposed TS P-T limits for 55 EFPYNextEra Response:
The proposed TS P-T limit curves for 55 EFPY have been revised to include margins to account forpressure and temperature instrument uncertainty.
Changes were also made to eliminate heat up and cooldown rates that are not achievable during normal plant operating conditions in the lower temperature regions where the cold overpressure mitigation system (COMS) is enabled to protect the RCS withpower operated relief valves (PORVs) as identified in TS Figure 3.4-4. No changes were made to thePORV set point values TS Figure 3.4-4 as this figure already contains appropriate instrument uncertainty as well as additional margins for pressure overshoot transients should an actuation occur.Specifically, the revised curves shift the heat up and cool down P-T Limits curve data points developed in WCAP-17441-NP by 100 psi downward and 20'F to the right to account for the instrument uncertainty.
An additional 15 psi uncertainty was applied to the heat up curve above the COMS enabletemperature where operationally the wide range pressure indication on the main control board could bethe only available indication in some unlikely but possible scenarios.
In addition to accounting for instrument uncertainty, unachievable heat up and cool down rates wereeliminated or restricted.
For the heat up limitation curve, proposed TS Figure 3.4-2, a heat up rate restriction of 20°F/hr wasadded at temperatures at or below 120'F, corresponding to the transient defined in WCAP-17444 andthe previous response to RAI 2.1.4. At temperatures greater than 120'F to less than 200'F the heat uprate of 80°F/hr maximum is specified and at greater than or equal to 200'F the maximum rate is100°F/hr.
Instrument uncertainties of 20'F and 100 psi were added to the data points in WCAP-17441-NP Table 6-3. An additional pressure uncertainty of 15 psi was added to the heat up curve starting at200'F prior to the cold overpressure mitigation system being disabled.
Considering the 20°F/hr raterestriction, pressure and temperature data from 60'F to 80'F (40°F to 60'F without the instrument uncertainty of 20'F) were determined using the more limiting pressure rate change between the existing80°F/hr heat up data and the steady state data. Linear extrapolation of the 60'F to 65°F allowable pressure change of 13 psi per 5°F was applied to the heat up curve pressure limits from 60°F to 80'F.These heat up rate limitations and instrument uncertainties additions result in all pressure limitations ator below 225°F, in the COMS enable temperature region, being above and protected by the COMSsystem set point curve in TS Figure 3.4-4.For the cool down limitation curve, proposed TS Figure 3.4-3, the cool down rate is restricted to 20°F/hrat temperatures less than 150'F. Instrument uncertainties of 20'F and 100 psi were added to the datapoints in WCAP-17441-NP Table 6-4. Since the entire curve is to the left and above the COMS enabletemperature and pressure limits identified in TS Figure 3.4-4, the additional 15 psi uncertainty was notPage 1 of 6 necessary.
Pressure and temperature data from 60'F to 80'F (40'F to 60'F without the instrument uncertainty of 20'F) were determined by linear extrapolation of the pressure rate change between 60'Fto 65'F for the 20°F/hr cool down data and the steady state data which results in a 13 psi change per5°F. These cool down rate limitations and instrument uncertainties additions result in all pressurelimitations being above and protected by the COMS system set point curve in TS Figure 3.4-4.The bolt up temperature was maintained at 60'F as identified in WCAP-14040-A, Revision 4,"Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup andCooldown Limit Curves."
The limiting closure head region material RTndt is 30°F allowing bolt uptemperature to be as low as 50'F with the application of uncertainty.
- However, the 60'F bolt uptemperature advised in WCAP-14040-A is maintained.
The proposed heat up limitation curve, TS Figure 3.4-2, and the proposed cool down limitation curve,TS Figure 3.4-3 applicable for 55 EFPY have been revised to include margins to account for pressureand temperature instrument uncertainty as described above and are provided in the attachment.
Therevised data points for the revised heat up and cool down curves are provided in Tables 1 and 2respectively.
Page 2 of 6 Significant Hazards Consideration No Significant Hazards Consideration:
The response to the NRC RAI-2.2-1 resulted in a change to the previously submitted LicenseAmendment Request 14-04 for the Seabrook Technical Specification (TS) 3.4.9.1, Pressure
/Temperature Limits, by providing new reactor coolant system (RCS) pressure and temperature (P/T)limits that are applicable to 55 effective full power years (EFPY). As a result, a No Significant HazardsConsideration was performed for the revised Pressure Temperature Limits in TS Figures 3.4-2 and 3.4-3.In accordance with 10 CFR 50.92, NextEra Energy Seabrook has concluded that the proposed changedoes not involve a significant hazards consideration (SHC). The basis for the conclusion that theproposed change does not involve a SHC is as follows:1. Does the proposed change involve a significant increase in the probability or consequences of anaccident previously evaluated?
No. The proposed changes to the Technical Specifications (TS) do not impact the physical function ofplant structures,
- systems, or components (SSCs) or the manner in which SSCs perform their designfunction.
Operation in accordance with the proposed TS will ensure that all analyzed accidents willcontinue to be mitigated by the SSCs as previously analyzed.
The proposed changes do not alter orprevent the ability of operable SSCs to perform their intended function to mitigate the consequences ofan initiating event within assumed acceptance limits. The proposed changes neither adversely affectaccident initiators or precursors, nor alter design assumptions.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from anypreviously evaluated?
No. The proposed changes do not involve installation of new or different type of equipment, create newfailure modes for existing equipment, or create any new limiting single failures.
The changes to thepressure
-temperature limits will continue to ensure that appropriate fracture toughness margins aremaintained to protect against reactor vessel failure, during both normal and low temperature operation.
The proposed changes are consistent with the applicable NRC approved methodologies (i.e., WCAP-14040, Rev. 4 and ASME Code Case N-641). Plant operation will not be altered, and all safety functions will continue to perform as previously assumed in accident analyses.
Therefore, the proposed changes do not create the possibility of a new or different kind of accident fromany accident previously evaluated.
Page 3 of 6
- 3. Does the proposed change involve a significant reduction in the margin of safety?No. Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuelcladding, reactor coolant system pressure
- boundary, and containment structure) to limit the level ofradiation dose to the public. The proposed changes will not adversely affect the operation of plantequipment or the function of any equipment assumed in the accident analysis.
The proposed changeswere developed using NRC approved methodologies and will continue to ensure an acceptable marginof safety is maintained.
The safety analysis acceptance criteria are not affected by this change. Theproposed changes will not result in plant operation in a configuration outside the design basis. Theproposed changes do not adversely affect systems that respond to safely shutdown the plant and tomaintain the plant in a safe shutdown condition.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.Based on the above, NextEra concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(b),
and, accordingly, a finding of"no significant hazards consideration" is justified.
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{Aj Fc aq oj sju!od mujI alqui Table 2Data Points for the 55 EFPY Seabrook Unit 1 Cooldown Curves using the 1998 through the 2000 AddendaApp. G Methodology (with Kic, without Flange Notch, and with Margins for Instrumentation Errors)Steady-State 201F/hr Cooldown 100°F/hr Cooldown(00F/hr)T P P P(OF) (psig) T (0F) (psig) T (0F) (psig)60 0 60 060 577 60 53765 590 65 55070 603 70 56375 616 75 57680 629 80 58985 642 85 60290 656 90 61895 671 95 635100 689 100 654105 708 105 674110 729 110 697115 752 115 723120 778 120 751125 806 125 782130 838 130 817135 872 135 855140 911 140 897145 953 145 944150 1000 150 995 150 995155 1052 155 1052160 1109 160 1109165 1172 165 1172170 1242 170 1242175 1319 175 1319180 1404 180 1404185 1499 185 1499190 1603 190 1603195 1718 195 1718200 1846 200 1846205 1986 205 1986210 2142 210 2142215 2314 215 2314220 2504 1 220 2504Page 6 of 6 Attachment to SBK-L- 15132Marked-Up Technical Specification Pages 11v!SeRT-A (A/X 7 itCL --- L 1 --I- J , -I-.. T-r ---.--1 TL ----iea estI I I I I I I I iILinaccepta
' ceptable S Operati T,, .operation
-Hea Rate [ ticaI irnit80 Deg. F/Hr 1 0DegF~r.L+/-.
I IL.J, L.S Heatu I I I I I Ia Imit I I100 g. F/ -r ----i- -'-- --- " -FR-rIL AI II I iiIIi I I Ii tr I --I--I4 -I eP 4I-t I l tI l i-I- T -T 1-----Z --...1000 -/" A/ii._.IlO00I,300IRE (Deg. F, gI8500UP 0 23.7 EFPY/O /E tFESEABROOK
-UNIT 13/4 4-23SEABROK -UNIT 3/44-23Amendment No. 19, 89, 115,13-5 Insert AMATERIAL PROPERTY BASISLIMITING MATERIAL:
Lower Shell Plate RI 808-1 without using surveillance data, Position 1.1LIMITING ART VALUES AT 55 EFPY: 1/4T, 117°F (Axial Flaw)3/4T, 105'F (Axial Flaw)Curves applicable for the first 55 EFPY and contain margins for possible instrument errors25002250 _ _ ILeak Test Limit 2000 -_ _1750 "170Critical LimitIHeatup Curve-- 1500Unacceptable IOperation ICLIa
_ 1250 .---p,U)Heatup rate belowrn- 1000 --120 F shall not -- , _-_ exceed 20OF/hr -Composite Heatup Curve750 Indicated RCS Maximum Alloy(fl Temperature Heatup RatT5 <120°F 20F/hrO ------ 200'F > T > 120°F 80°F/hr'5025000 50 100 150200 250 300 350 400 450 500 550RCS Temperature (Deg. F, 10 Deg. F per division)
- Curve is Applicable for RCS Vacuum fillFIGURE 3.4-2REACTOR COOLANT SYSTEM HEATUP LIMITATIONS
-APPLICABLE UP TO 55 EFPY 1,4,YW re(x-r F A, ejV1AERIAL PR ERTY BASISLimiting erial: LOWER 5 ELL P/LATE -,1808-1ART values a 3.7 EFPYI/4 , 109'F4T, 880PCurves appli lr the firs EFFY and ntain margin 20'F and 100 ig for possib instrument error-,onon --"-./ //802600 -24002200 -20001800 -wILS160CD* 1400-CO)120S1000-0-600200-r 1 -- -------1. -1'3rT- -r- -------I/ I I I I .ptableII IIII peration
--j.4 .L __- -_ -J ------- ------- ----------
--I-------,
Co -ldown taUplo g I I I-- ---I ,-----------
--r--iI I I I ----
-- '---, -I--P- --II I I I ----- --iI I I l t-l ...I -T r 7-- Cool n Rates t L ~ f...A L....L.i
-....c Deg.F/Hr
-, 2 I I I I I I I I I I-e. -,- -- ----- -- -----4.JWLJ. 80, 100 D .F/hr JIIAI JI -LJ L -..h-I-I I I I I I I I I I I I I I£ _ I £ I I! _ I I I I i I i J 'I I I IB I pI I I I II I I I I I I I I I I I I I I I I I II I I I I I I I I I I I I II I I I I I II I I II I I I I I I I Im pI I I I I I I I I II I I I III I I I I I I I II 1 I I//11/, 710 100 200 300 400 500R TEMPERAT (Deg. F, 2 eg. F PER DV ION)GURE 3.4-3ACTOR COO T SYSTEM OLDOWN LI11 ATIONS -LICABLE UP 23.7 EF YSEABROOK
-UNIT 13/4 4-24Amendment No. 19, 89, 115, 135 Insert BMATERIAL PROPERTY BASISLIMITING MATERIAL:
Lower Shell Plate RI 808-1 without using surveillance data, Position 1.1LIMITING ART VALUES AT 55 EFPY: 1/4T, 1177F (Axial Flaw)3/4T, 1057F (Axial Flaw)Curves applicable for the first 55 EFPY and contain margins for possible instrument errors2500225020001750C0> 1500CL0)0 1250CL0Lo)10007505)C,)W~ 500F neptableLgperaionj Li..AcetableI ItF--Composite Cooldown CurveIndicated RCS Maximum Allowable Temperature Cooldown RateT < 150°F 20°F/hrT > 150°F 100°F/hr2500I ..I ....I ....I .. ..0 50100 150 200 250 300 350 400 450500550RCS Temperature (Deg. F, 10 Deg. F per division)
- Curve is Applicable for RCS Vacuum fillFIGURE 3.4-3REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS
-APPLICABLE UP TO 55 EFPY
