ML030840628
| ML030840628 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 03/14/2003 |
| From: | Coutu T Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC-03-025 | |
| Download: ML030840628 (17) | |
Text
Committed to Nuclear Excellence Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC NRC-03-025 10 CFR 50.90 March 14, 2003 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 KEWAUNEE NUCLEAR POWER PLANT DOCKET 50-305 LICENSE No. DPR-43 LICENSE AMENDMENT REQUEST 187b TO THE KEWAUNEE NUCLEAR POWER PLANT TECHNICAL SPECIFICATIONS References- 1) Letter from Mark E. Warner (NMC) to Document Control Desk (NRC),
"License Amendment Request 187 to the Kewaunee Nuclear Power Plant Technical Specifications, Conforming Technical Specification Changes for Use of Westinghouse Vantage + Fuel," dated July 26, 2002.
- 2) Letter from John G. Lamb (NRC) to Thomas Coutu (NMC), "Kewaunee Nuclear Power Plant - Request for Additional Information Regarding Proposed Amendment Request Conforming Technical Specification Changes for Use of Westinghouse Vantage + Fuel," (TAC NO. MB5718) dated January 21, 2003.
- 3) Letter from Thomas Coutu (NMC) to Document Control Desk (NRC),
"License Amendment Request 187a to the Kewaunee Nuclear Power Plant Technical Specifications, Conforming Technical Specification Changes for Use of Westinghouse Vantage + Fuel," dated February 27, 2003.
In reference 3, The Nuclear Management Company, LLC, (NMC) submitted a response to the Nuclear Regulatory Commission (NRC) request for additional information (RAI) (reference 2) concerning License Amendment Request (LAR) 187 (reference 1) to the Kewaunee Nuclear Power Plant (KNPP) Technical Specifications (TS) revising KNPP TS to allow transitioning to Westinghouse 422V+ nuclear fuel.
N490 Highway 42 a Kewaunee, Wisconsin 54216-9510 Telephone: 920 388 2560 A
Docket 50-305 NRC-03-025 March 14, 2003 Page 2 Prior to the submittal of reference 3, February 25, 2003, the NRC Project Manager for KNPP made a verbal request to submit a matrix showing the relationship of the TS parameters that are relocated to the core operating limits report (COLR) versus the methodology used to develop that parameter. On development of this matrix a comparison was performed of another similar Westinghouse plant's COLR. From this comparison, one of the WCAP's referenced in the similar plant's COLR was questioned. When Westinghouse was asked about this WCAP (WCAP-14449-P-A, Application of Best-Estimate Large-Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection, Rev. 1) Westinghouse responded that this WCAP should be included in the methods use for KNPP's relocated parameters and also WCAP-12945-P-A, Westinghouse Code Qualification Document for Best-Estimate Loss-of Coolant Accident Analysis, Volume I, Rev. 2, and Volumes 11-V, Rev. 1. This submittal makes changes to the KNPP Technical Specification to add these WCAP's.
Because KNPP axial offset control is changing from the constant axial offset control (CAOC) to the relaxed axial offset control (RAOC) the methods associated with CAOC are also being removed. These CAOC methods being removed are: 1) XN-NF-77-57, "Exxon Nuclear Power Distribution Control for Pressurized Water Reactors, Phase II,dated January 1978, and Supplement 2, dated October 1981," and 2) WCAP-8385, "Power Distribution Control and Load Following Procedures-Topical Report," September 1974 (Westinghouse Proprietary). As these methods apply to CAOC and not to RAOC they are being removed from the approved methods for use at KNPP. to this letter contains the strike-out Technical Specification pages for the proposed changes. Attachment 2 contains the affected Technical Specification pages as revised. contains the matrix of relocated parameters to the NRC approved methods used in the development of those parameters.
Additionally, based on an email from the NRC Project Manager on March 7, 2003, a change needed to be made to Cycle 26 COLR Sections 2.9 and 2.10. This change is in the OTDT and OPDT equations. TS LAR 187a, reference 3, changed TS associated with OTDT and OPDT but these changes were not made to the associated COLR sections. Attachment 4 contains these changes.
As the above changes are administrative in nature the analysis provided in reference 1 bounds these changes.
If you have any further questions concerning this subject please call Jerry Riste, of my staff, at (920) 388-8424.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on March 14, 2003.
Thomas Coutu Site Vice-President, Kewaunee Plant GOR Attach.
cc- US NRC, Region III US NRC Senior Resident Inspector Electric Division, PSCW
ATTACHMENT 1 NUCLEAR MANAGEMENT COMPANY, LLC KEWAUNEE NUCLEAR PLANT DOCKET 50-305 March 14, 2003 Letter from Thomas Coutu (NMC)
To Document Control Desk (NRC)
License Amendment Request 187b Strike Out TS Pages:
TS 6.9-5 TS 6.9-6
(3) Nissley, M.E. et, 1., "Westinghouse Large. . eak LOCA Best Estimate MetIhdology," VCAP-r-1O924r- A, Volume 1, Revision 1, Add"ndumn 4, Mar1h 1991, Volumle 1- Model Des.ription and Validation; Addendum. 4, Model Revisions.q M Rniorpk et nl WCAP-19q45-P-A (Propriptary) Westinghnitse Code OQualification Dlociment for Rpst--Fctimate I ocscs-nf Coolnt Ar.rcidpnt Anliyq VnI'imp I Reyv 9 and Volume II-V Rev I and W(VAP-14747 (Nnn-Prnpriet-ry) Marnh 1.9P (4) N. Lee et al., "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," WCAP-10054-P-A (Proprietary) and WCAP-10081-NP-A (Non-Proprietary), dated August 1985.
(5) C.M. Thompson, et al., "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model,"
WCAP-10054-P-A, Addendum 2, Revision 1 (Proprietary) and WCAP-10081-NP (Non-Proprietary), dated July 1997.
(6) XN-NF-82-06 (P)(A) Revision 1 and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup, Exxon Nuclear Company, dated October 1986.
(7) ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Megihodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, dated December 1991.
(8) EMF-92-116 (P)(A) Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, dated February 1999.
(9) WCAP-10I9l-P-A Reyv JA "RIayntinn of Constant Ayial (Off-s-t Control FQ Siurvyeillncp Teprhnirl Speoificrtinn" Fpehrury 1994 (W Prprietorv) "N NF 77-57, Exxon Nuclear Power Distribution Control for Pressurized Water Reactors, Phase 1 , d ated J anuary 1978, and Supplement 2, dated October 1981-.
(10) WCAP-9272-P-A "Westinghouise Reload Sr*fty F:v*hl*tion Methodology" .111ly 1989 (Wý Prortry WAP11-26-P A,-Rev If,, "Relaxation Of Constant Axial Offset Control FE) Surveillance Technical Specification," February 1994 (W Proprietary).
(11) WCAP-8745-P-A Dpesign Bases for the Thermal Ovirtemperalure.
AT and Thermal OverpowPwr AT trip fiinrinnr , Septenh r 19Q8 (19) S I FederIr et al WCAP -1444.q-P-A Apnliratinnn nf RBet FEstimate I arg_-Rreak I CQA MethodoIogy to W'"_tinghnii.1 PWRs.
with Inpp~r Plpnlim Iniection Ryv 1 (Prpritefry) and WCAP 14450-NP-A Ryv I (Non-Proprieftry) Ocftnht.r t999
-t- AR6.9 TS 6.9-5 0*114/2O03
(13) WCAP-1610-P-A "VANTA(GF+ Fi'pl Assemhly Refprpnc. Cnort Rennrt" April 1995 fflestinahnhisp- Propr tLy4 WCAr-83-5-,
"rower Distribution Control and Load Following Prroedures Topial Report," September 1974 (Westinghouse Proprietary)
(14) WCAP-113q97-P-A "Reviked Thermal De*fign Proredilr- "April
_1989_WCAP "261" P A, "V"'""- "'E Assmbl Fuel " R-efer.....
Core Report," April 1995 (Westinghouse Proprietary).
(+5-)1 C. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
D. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
TS 6.9-6 L12O3
ATTACHMENT 2 NUCLEAR MANAGEMENT COMPANY, LLC KEWAUNEE NUCLEAR PLANT DOCKET 50-305 March 14, 2003 Letter from Thomas Coutu (NMC)
To Document Control Desk (NRC)
License Amendment Request 187b Affected TS Pages:
TS 6.9-4 TS 6.9-5
(3) S.M. Bajorek, et al., WCAP-12945-P-A (Proprietary),
Westinghouse Code Qualification Document for Best-Estimate Loss-of Coolant Accident Analysis, Volume I, Rev. 2, and Volume Il-V, Rev. 1, and WCAP-14747 (Non-Proprietary) March 1998.
(4) N. Lee et al., "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," WCAP-10054-P-A (Proprietary) and WCAP-1 0081-NP-A (Non-Proprietary), dated August 1985.
(5) C.M. Thompson, et al., "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model,"
WCAP-10054-P-A, Addendum 2, Revision 1 (Proprietary) and WCAP-1 0081-NP (Non-Proprietary), dated July 1997.
(6) XN-NF-82-06 (P)(A) Revision 1 and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup, Exxon Nuclear Company, dated October 1986.
(7) ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, dated December 1991.
(8) EMF-92-116 (P)(A) Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, dated February 1999.
(9) WCAP-10216-P-A, Rev. 1A, "Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification," February 1994 (W Proprietary).
(10) WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (W Proprietary).
(11) WCAP-8745-P-A, Design Bases for the Thermal Overtemperature AT and Thermal Overpower AT trip functions, September 1986.
(12) S.I. Dederer, et al., WCAP -14449-P-A, Application of Best Estimate Large-Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection, Rev. 1 (Proprietary) and WCAP 14450-NP-A, Rev. 1 (Non-Proprietary), October 1999.
TS 6.9-4
(13) WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995 (Westinghouse Proprietary).
(14) WCAP-11397-P-A, "Revised Thermal Design Procedure, "April 1989.
C. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
D. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
TS 6.9-5
ATTACHMENT 3 NUCLEAR MANAGEMENT COMPANY, LLC KEWAUNEE NUCLEAR PLANT DOCKET 50-305 March 14, 2003 Letter from Thomas Coutu (NMC)
To Document Control Desk (NRC)
License Amendment Request 187b Relocated Parameter and Approved Methods
Docket 50-305 NRC-03-025 March 14, 2003 , Page 1 Relocated Parameter and Approved Methods Parameter NRC Approved Methodology SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON "QUALIFICATIONS OF REACTOR PHYSICS METHODS FOR APPLICATION TO KEWAUNEE" REPORT, dated August 21, 1979, report date September 29, 1978 KEWAUNEE NUCLEAR POWER PLANT - REVIEW FOR KEWAUNEE RELOAD SAFETY EVALUATION METHODS TOPICAL REPORT WPSRSEM-NP, REVISION 3 Reactor Core Safety Limits (TAC NO MB0306) dated September 10 2001.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (W Proprietary)
WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995 (Westinghouse Proprietary).
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON "QUALIFICATIONS OF REACTOR PHYSICS METHODS FOR APPLICATION TO Shutdown Margin KEWAUNEE" REPORT, dated August 21, 1979, report date September 29, 1978 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (W Proprietary)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON "QUALIFICATIONS OF REACTOR PHYSICS METHODS FOR APPLICATION TO Moderator Temperature Coefficient KEWAUNEE" REPORT, dated August 21, 1979, report date September 29, 1978 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (W Proprietary)
Docket 50-305 NRC-03-025 March 14, 2003 , Page 2 Relocated Parameter and Approved Methods Parameter I NRC Approved Methodology SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON "QUALIFICATIONS OF REACTOR PHYSICS METHODS FOR APPLICATION TO KEWAUNEE" REPORT, dated August 21, 1979, report date September 29, 1978 Shutdown Bank Insertion Limits KEWAUNEE NUCLEAR POWER PLANT - REVIEW FOR KEWAUNEE RELOAD SAFETY EVALUATION METHODS TOPICAL REPORT WPSRSEM-NP, REVISION 3 (TAC NO MB0306) dated September 10 2001.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (W Proprietary)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON "QUALIFICATIONS OF REACTOR PHYSICS METHODS FOR APPLICATION TO KEWAUNEE" REPORT, dated August 21, 1979, report date September 29, 1978 Control Bank Insertion Limits KEWAUNEE NUCLEAR POWER PLANT - REVIEW FOR KEWAUNEE RELOAD SAFETY EVALUATION METHODS TOPICAL REPORT WPSRSEM-NP, REVISION 3 (TAC NO MB0306) dated September 10 2001.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (W Proprietary)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON "QUALIFICATIONS OF REACTOR PHYSICS METHODS FOR APPLICATION TO KEWAUNEE" REPORT, dated August 21, 1979, report date September 29, 1978 N. Lee et al., "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code,"
Heghtpndent HactorFlx H WCAP-10054-P-A (Proprietary) and WCAP-10081-NP-A (Non-Proprietary), dated August 1985.
Channel Factor (FQ)
C.M. Thompson, et al., "Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection into the Broken Loop and COSI Condensation Model," WCAP-10054-P-A, Addendum 2, Revision 1 (Proprietary) and WCAP-10081-NP (Non-Proprietary), dated July 1997.
Docket 50-305 NRC-03-025 March 14, 2003 , Page 3 Relocated Parameter and Approved Methods Parameter NRC Approved Methodology ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, dated December 1991 WCAP-10216-P-A, Rev. 1A, "Relaxation Of Constant Axial Offset Control Fq Surveillance Technical Specification," February 1994 (W Proprietary).
WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," April 1995 (Westinghouse Proprietary).
S. I. Dederer, et al., WCAP-14449-P-A, Application of Best-Estimate Large-Break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection, Rev. 1 (Proprietary) and WCAP-14450-NP-A, Rev. 1 (Non-Proprietary), October 1999.
S. M. Bajorek, et al., WCAP-12945-P-A (Proprietary), Westinghouse Code Qualification Document for Best-Estimate Loss-of-Coolant Accident Analysis, Volume I, Rev. 2, and Volumes II-V, Rev. 1, and WCAP-14747 (Non-Proprietary), March 1998.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON "QUALIFICATIONS OF REACTOR PHYSICS METHODS FOR APPLICATION TO KEWAUNEE" REPORT, Dated August 21, 1979, Report Date September 29, 1978 KEWAUNEE NUCLEAR POWER PLANT - REVIEW FOR KEWAUNEE RELOAD SAFETY EVALUATION METHODS TOPICAL REPORT WPSRSEM-NP, REVISION 3 (TAC NO MB0306)
Dated September 10 2001.
Nuclear Nuclar Enthalpy E p Rise Rs Hot Ht Channel CXN-NF-82-06 (P)(A) Revision 1 and Supplements 2, 4, and 5, "Qualification of Exxon Factor (FNA*H) Nuclear Fuel for Extended Burnup, Exxon Nuclear Company, dated October 1986.
ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, dated December 1991.
EMF-92-116 (P)(A) Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, dated February 1999
Docket 50-305 NRC-03-025 March 14, 2003 , Page 4 Relocated Parameter and Approved Methods Parameter NRC Approved Methodology WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (W Proprietary)
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON "QUALIFICATIONS OF REACTOR PHYSICS METHODS FOR APPLICATION TO KEWAUNEE" REPORT, dated August 21, 1979, report date September 29, 1978 KEWAUNEE NUCLEAR POWER PLANT - REVIEW FOR KEWAUNEE RELOAD SAFETY Axial Flux Difference EVALUATION METHODS TOPICAL REPORT WPSRSEM-NP, REVISION 3 (TAC NO MB0306) dated September 10 2001.
WCAP-10216-P-A, Rev. 1A, "Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification," February 1994 (W Proprietary).
KEWAUNEE NUCLEAR POWER PLANT - REVIEW FOR KEWAUNEE RELOAD SAFETY EVALUATION METHODS TOPICAL REPORT WPSRSEM-NP, REVISION 3 (TAC NO Overtemperature AT MB0306) dated September 10 2001.
WCAP-8745-P-A, "Design Basis For The Thermal Overpower Delta-T And Thermal Overtemperature Delta-T Trip Functions, September 1986" KEWAUNEE NUCLEAR POWER PLANT - REVIEW FOR KEWAUNEE RELOAD SAFETY EVALUATION METHODS TOPICAL REPORT WPSRSEM-NP, REVISION 3 (TAC NO Overpower AT MB0306) dated September 10 2001.
WCAP-8745-P-A, "Design Basis For The Thermal Overpower Delta-T And Thermal Overtemperature Delta-T Trip Functions, September 1986" KEWAUNEE NUCLEAR POWER PLANT - REVIEW FOR KEWAUNEE RELOAD SAFETY EVALUATION METHODS TOPICAL REPORT WPSRSEM-NP, REVISION 3 DNB Limits (TAC NO MB0306) dated September 10 2001.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (W Proprietary)
Docket 50-305 NRC-03-025 March 14, 2003 , Page 5 Relocated Parameter and Approved Methods Parameter NRC Approved Methodology WCAP-1 1397-P-A, "Revised Thermal Design Procedure, "April 1989 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ON "QUALIFICATIONS OF REACTOR PHYSICS METHODS FOR APPLICATION TO Refueling Boron Concentration KEWAUNEE" REPORT, dated August 21, 1979, report date September 29, 1978 WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (W Proprietary)
ATTACHMENT 4 NUCLEAR MANAGEMENT COMPANY, LLC KEWAUNEE NUCLEAR PLANT DOCKET 50-305 March 14, 2003 Letter from Thomas Coutu (NMC)
To Document Control Desk (NRC)
License Amendment Request 187b COLR Pages 6 of 16
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 10 DRAFT CORE OPERATING LIMITS REPORT CYCLE 2-526 2.9 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values:
ATo = Indicated AT at RATED POWER, %
T = Average temperature, OF T' *67-.3573-5= OF P = Pressurizer Pressure, psig P = 2235 psig K, = 44120 K2 = 0.00900.015/°F K3 = .0.005.0.00072lps6 1 - 30 seconds "T2 = 4 seconds f(AI) = An even function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RATED POWER, such that (a) For qt - qb within 222, +9-12%, f(AI) = 0 (b) For each percent that the magnitude of qt - qb exceeds +9-12 %
the AT trip setpoint shall be automatically reduced by an equivalent of 2-.50M % of RATED POWER.
(c) For each percent that the magnitude of qt - qb exceed 2-22%
the AT trip setpoint shall be automatically reduced by an equivalent of 4-1.5_.86 % of RATED POWER.
2.10 Overpower AT Setpoint Overpower AT setpoint parameter values:
AT0 = Indicated AT at RATED POWER, %
T = Average temperature, OF T' = 5673573.0 F K(4 =< 440__95 K15 >- 002750,0275/°F for increasing T; 0 for decreasing T K6 >= 0.0020_0103Efor T > T' ; 0 for T < T' 3 = 10 seconds f(AI) = Same as in 2.90 forall Al Cycle 2-526 Page 6 of 16 Rev. 10 DRAFT
KEWAUNEE NUCLEAR POWER PLANT TRM 2.1 TECHNICAL REQUIREMENTS MANUAL Revision 1 DRAFT CORE OPERATING LIMITS REPORT CYCLE 26 2.9 Overtemperature AT Setpoint Overtemperature AT setpoint parameter values:
ATo Indicated AT at RATED POWER, %
T = Average temperature, OF T' < 573.0 OF P = Pressurizer Pressure, psig P = 2235 psig K, = 1.20 K2 = 0.015I°F K3 = 0.00072/psig
- = 30 seconds "T = 4 seconds f(AI) = An even function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + qb is total core power in percent of RATED POWER, such that (a) For qt - qb within -22, +12 %, f(AI) = 0 (b) For each percent that the magnitude of qt - qb exceeds +12 % the AT trip setpoint shall be automatically reduced by an equivalent of 0.96 % of RATED POWER.
(c) For each percent that the magnitude of qt - qb exceed -22 % the AT trip setpoint shall be automatically reduced byan equivalent of 0.86 % of RATED POWER.
2.10 Overpower AT Setpoint Overpower AT setpoint parameter values:
ATo = Indicated AT at RATED POWER, %
T = Average temperature, OF Tv <* 573.0 OF K4 _ 1.095 K5 > 0.0275/0 F for increasing T; 0 for decreasing T K6 > 0.00103/°F for T > T' ; 0 for T < T' "T = 10 seconds f(AI) = 0for all Al Cycle 26 Page 6 of 16 Rev. 1 DRAFT