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| {{#Wiki_filter:ACCELERATED D TtuBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9107120105 DOC.DATE: 91/07/08 NOTARIZED: | | {{#Wiki_filter:ACCELERATED D TtuBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| YES'OCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION BOHLKE,W.H.. | | ACCESSION NBR:9107120105 DOC.DATE: 91/07/08 NOTARIZED: YES 'OCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION BOHLKE,W.H.. Florida Power & Light Co. |
| Florida Power&Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)SUBZECT: 'Responds to NRC 910606 request for addi info re 901219 application for amends to Licenses DPR-31 6 DPR-41,revising Tech Specs Section 2.2,"Limiting Safety Sys Settings>>S Section 3/4.3.2,."ESF Actuation Sys Intrumentation." DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR (ENCL Q SIZE: E~TITLE: OR Submittal: | | RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
| General Distribution NOTES D RECIPIENT ID CODE/NAME PD2-2 LA AULUCK,R INTERNAL: NRR/DET/ECMB 7D NRR/DOEA/OTS B1 1 NRR/DST/SELB 7E NRR/DST/SRXB 8E 0/M EG FIL 01 EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 0 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS3 RES/DSIR/EIB NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0'1 1 1 1 D D R D NOTE TO ALL"RIDS" RECIPIENTS: | | SUBZECT: 'Responds to NRC 910606 request for addi info re 901219 application for amends to Licenses DPR-31 6 DPR-41,revising Tech Specs Section 2.2, "Limiting Safety Sys Settings>> S D Section 3/4.3.2,. "ESF Actuation Sys Intrumentation." |
| D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 16 L'
| | DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR ( ENCL Q SIZE: E~ |
| P.O.Box14000, Juno Beach, FL 33408-0420 JULDS 8N L-91-186 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DE C.20555 Gentlemen:
| | TITLE: OR Submittal: General Distribution NOTES RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 AULUCK,R 2 2 D INTERNAL: NRR/DET/ECMB 7D 1 1 NRR/DET/ESGB 1 1 NRR/DOEA/OTS B1 1 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 7E 1 1 NRR/DST/SICB8H7 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 0 /M 1 0 OGC/HDS3 1 0 EG FIL 01 1 1 RES/DSIR/EIB '1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 R |
| Re: Turkey Point Units 3 and 4 Docket Nos.50-250 and 50-251 Response to RAI on Reactor Protection System Setpoints TAC Nos.79402 and 79403 By letter L-90 417r dated December 19, 1990, Florida Power and Light (FPL)submitted a request to amend the Turkey Point Technical Specifications.
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| The proposed amendment revised Section 2.2, Limiting Safety System Settings and Section 3/4.3.2, Engineered Safety Features Actuation System Instrumentation.
| | D NOTE TO ALL "RIDS" RECIPIENTS: |
| By letter dated June 6, 1991, the NRC requested additional information concerning the reactor protection system (RPS)setpoints~In response to this request Attachment 1 is provided.Attachment 2 provides the proposed revised Technical Specification change, as generated as a result of this response.FPL has determined that the proposed Technical Specification change does not alter the No Significant Hazards Determination provided in L-90-417.In accordance with 10 CFR 50.91(b)(1), a copy of this Proposed License Amendment is being forwarded to the State Designee for the State of Florida.The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.Should there be any questions, please contact us.Very truly yours, W.H.Bohlke Vice President Nuclear Engineering and Licensing Attachment WHB/RJT/rjt CC: Stewart D.Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Mr.Jacob Daniel Nash, Florida De'partment of Health and Rehabilitative Services 9107220105 9l0708'"'DR ADOCK 05000250 P ,,'DR.i~~~~~an FPL Group company
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
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| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 16 |
| STATE OF FLORIDA))ss.COUNTY OF PALM BEACH)W.H.Bohlke being first duly sworn, deposes and says: That he is Vice President Nuclear En ineerin and Licensin , of Florida Power and Light Company, the Licensee herein;That he has executed the foregoing document;that the statements made in this document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Licensees W.H.Bohlke Subscribed and sworn to before me this nQ day of 1991.NOTARY PUBLIC, in and for the County of Palm Beach, State of Florida Notary PublIc, State of Horlda My Comm.Exp.Feb, 18, 1995 My COmmiSSiOn eXpires BonrtsdthruPIGHARD lns.Agency,
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| ATTACHMENT 1 Response to Recgxest for Additional Information
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| L-91-186 Attachment 1 Page 1 of 5 1)Has FPL verified that the bases document used by Westinghouse to determine the instrument allowances (uncertainties) is correct and applicable to Turkey Point as configured? | | P.O. Box14000, Juno Beach, FL 33408-0420 JULDS 8N L-91-186 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DE C. 20555 Gentlemen: |
| In addition, please provide the following:
| | Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Response to RAI on Reactor Protection System Setpoints TAC Nos. 79402 and 79403 By letter L-90 417r dated December 19, 1990, Florida Power and Light (FPL) submitted a request to amend the Turkey Point Technical Specifications. The proposed amendment revised Section 2.2, Limiting Safety System Settings and Section 3/4.3.2, Engineered Safety Features Actuation System Instrumentation. |
| All assumptions and inputs used as the bases in developing the setpoint study over the last two years have been re-verified.
| | By letter dated June 6, 1991, the NRC requested additional information concerning the reactor protection system (RPS) setpoints ~ In response to this request Attachment 1 is provided. |
| As a result of this review, all inputs have been re-verified and remain, valid for the setpoints documented in WCAP-12745, with the exception of four functions.
| | Attachment 2 provides the proposed revised Technical Specification change, as generated as a result of this response. |
| For the Containment Pressure-High and High-High functions, the pressure switches used in determining the setpoints were replaced with switches by the same vendor but different models.Subsequently, Westinghouse evaluated this hardware substitution.
| | FPL has determined that the proposed Technical Specification change does not alter the No Significant Hazards Determination provided in L-90-417. |
| The evaluation concluded that the current Nominal Trip Setpoints remain valid.However, due to changes in the instrument span, the previously submitted TA and Z values, listed'n the Technical Specifications in percent span, and the Allowable Values should be modified.The Turbine Trip Auto Stop Oil'Pressure instrumentation has a larger span than that used in the original calculations.
| | In accordance with 10 CFR 50.91(b) (1), a copy of this Proposed License Amendment is being forwarded to the State Designee for the State of Florida. |
| Subsequently, Westinghouse evaluated the hardware utilizing the larger span.The evaluation concluded that the current Nominal Trip Setpoint remains valid.However, due to changes in the instrument span of the device, the previously submitted TA and Z values, listed in the Technical Specifications in percent span, and the Allowable Value must be modified.Retention of the current Nominal Trip Setpoint results in no change to the operational margin of the plant.The Turbine Trip Auto Stop Oil Pressure function is not credited in the safety analysis.The protective relay used in determining the setpoint for the Reactor Coolant Pump Underfrequency function was replaced with a relay by the same vendor but with a different model.Subsequently, Westinghouse evaluated this hardware substitution.
| | The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board. |
| The evaluation concluded that the current Nominal Trip Setpoint remains valid.However, due to changes in the instrument span, the previously submitted TA and Z values, listed in the Technical Specifications in percent span, must be modified.Retention of the current Nominal Trip Setpoints results in no change to the operational or safety margins for the plant.
| | Should there be any questions, please contact us. |
| ~~
| | Very truly yours, W. H. Bohlke Vice President Nuclear Engineering and Licensing Attachment WHB/RJT/rjt CC: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Mr. Jacob Daniel Nash, Florida De'partment of Health and Rehabilitative Services |
| L-91-186 Attachment 1 Page 2 of 5 In conclusion, the modifications to the Technical Specifications for these four protection functions reflect changes in the instrument span.In the above cases the instrumentation preserves the assumptions of the various safety analyses.Therefore, the discussions and conclusions provided in the previous No Significant Hazards Consideration remain valid.l.a)What are the inputs for the bases documents The primary inputs for the uncertainties identified and documented in WCAP-12745 are listed in Table 3-23 of that document.The inputs used in the Setpoint Study are developed from specific plant information and Westinghouse documentation.
| | .i ~ ~~ |
| For example: specific plant information consists of Turkey Point Units 3 and 4 plant procedures and hardware specifications.
| | 9107220105 9l0708 |
| The Westinghouse documentation includes information such as testing and evaluations to determine such parameters as Process Measurement Accuracy (PHA)terms.1.b)Were there any"generic" allowance (uncertainty) values used by Westinghouse when plant-specific information was not available or not based on Turkey Point specifications and procedures?
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| If so, what confidence level does FPL have that these values reflect (or bound)the as-configured condition of the plantf"Generic" allowances for instrumentation uncertainties were reviewed and determined to be applicable for Turkey Point Units 3 8 4."Generic" values were included in the review and were determined either applicable or bounding for application to Turkey Point Units 3&4.FPL has a high confidence level that these"generic values" reflect or bound the as-configured condition of the plant.1.c)Are the allowance (uncertainty) values used applicable and conservative with respect to the as-configured plant7 The uncertainty values used by Westinghouse are applicable and conservative with respect to the as-configured plant conditions.
| | ~ |
| The corrections for the four functions were re-evaluated and will be included in Revision 1 of WCAP-12745, to document the acceptability of the nominal trip setpoints to preserve the Safety Analysis Limits.
| | , 'DR ADOCK 05000250 |
| L-91-186 Attachment 1 Page 3 of 5 2)Recently approved Amendments 135 and 140 approved specific values in the OThT and OPhT equations (table notes 1, 3).The amendment under current review proposes some of those values in a different form, i.e.from note 1: proposed p'2235 from note 3: proposed K,<1.09 K,>0.02/'F~(Tau),>10 secs Are these new proposed values conservative (in the conservative direction) with respect to the existing TS (Amendments 135 and 140)7 The existing values are the same as those defined in the previous submittal and remain conservative.
| | ~ an FPL Group company |
| As noted below, the only change was~to include an inequality in the Technical Specifications denoting the conservative direction of the parameter.
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| 1)Explanation of conservative direction of inequalities in OThT and OPhT Reactor Trip functions.
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| In a simplified form (without lead/lag, rate lag or lag filters), the equation for OThT is: AT hT, (K,-K,(T-T')+K,(P-P')-f,(hI))Where: 4T hTo T T'pt f,(hI)KKK, is the measured hT is the indicated hT at 100 X RTP is the measured Tavg is the design full power Tavg (574.2'F)is the measured Pressurizer Pressure is the design Pressurizer Pressure (2235 psig)is the hI penalty are constants From this equation, the following can be seen: a)A decrease in the magnitude of K, results in a decrease in the trip setpoint which the measured dT is compared against.b)An increase in the magnitude of K, results in a decrease in the trip setpoint when T T', since K,{T-T')is subtracted from K,.
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| L-91-186 Attachment 1 Page 4 of 5 c)An increase in the magnitude of K, results in a decrease in the trip setpoint when P s P', since K,{P-P'}would then be a negative value and is added to K,.d)A decrease in the magnitude of T'esults in a decrease in the trip setpoint because (T-T'}would become positive at a lower measured value of T and K,(T-T'}is subtracted from K,.e)An increase in the magnitude of P'esults in a decrease in the trip setpoint because{P-P')would become a larger negative value (or would remain a negative value until a higher pressure is reached)and K,{P-P'}is added to K,.Thus the inequality | | ~ |
| <is the conservative direction for K, and T', and the inequality | | ~ |
| .is the conservative direction for KK, and P'.In a simplified form (without lead/lag, rate lag or lag filters), the equation for OPhT is: hT-hTo (K4 K5T Ks(T T}fz(hI)}Where: hT hTo T'II f,(hI)K4, Kis the measured hT is the indicated hT at 100 X RTP is the measured Tavg is the design full power Tavg (574.2'F)is the hI penalty K, are constants From this equation, the following can be seen: a)A decrease in the magnitude of K, results in a deer'ease in the trip setpoint which the measured hT is compared against.b)An increase in the magnitude of K, results in a decrease in the trip setpoint since K,(T}is subtracted from K,.c)An increase in the magnitude of K, results in a decrease in the trip setpoint when T>T", since K,(T-T"}is subtracted from K,.d)A decrease in the magnitude of T" results in a decrease in the trip setpoint because (T-T"}would become positive at a lower measured value of T and K,{T-T"}is subtracted from K,. | | |
| L-91-186 Attachment 1 Page 5 of 5 For a rate-lag function e.g., (~,s)/(1+~,s), an increasing value of~, results in a faster buildup of the parameter and thus approaches the trip value quicker.Thus the inequality is the conservative direction for K, and T" and the inequality is the conservative direction for KK, and~,.2)The Westinghouse calculations of uncertainties for equipment supplied by others were based on: a)A review of the calibration and functional test procedures for each protection function, as supplied by FPL, and b)A review of the vendor specification sheet data for each sensor transmitter, as supplied by FPL.}} | | STATE OF FLORIDA ) |
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| | COUNTY OF PALM BEACH ) |
| | W. H. Bohlke being first duly sworn, deposes and says: |
| | That he is Vice President Nuclear En ineerin and Licensin , of Florida Power and Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Licensees W. H. Bohlke Subscribed and sworn to before me this nQ day of 1991. |
| | NOTARY PUBLIC, in and for the County of Palm Beach, State of Florida Notary PublIc, State of Horlda My Comm. Exp. Feb, 18, 1995 My COmmiSSiOn eXpires BonrtsdthruPIGHARD lns.Agency, |
| | |
| | ATTACHMENT 1 Response to Recgxest for Additional Information |
| | |
| | L-91-186 Page 1 of 5 |
| | : 1) Has FPL verified that the bases document used by Westinghouse to determine the instrument allowances (uncertainties) is correct and applicable to Turkey Point as configured? In addition, please provide the following: |
| | All assumptions and inputs used as the bases in developing the setpoint study over the last two years have been re-verified. |
| | As a result of this review, all inputs have been re-verified and remain, valid for the setpoints documented in WCAP-12745, with the exception of four functions. |
| | For the Containment Pressure-High and High-High functions, the pressure switches used in determining the setpoints were replaced with switches by the same vendor but different models. |
| | Subsequently, Westinghouse evaluated this hardware substitution. |
| | The evaluation concluded that the current Nominal Trip Setpoints remain valid. However, due to changes in the instrument span, the previously submitted TA and Z values, listed'n the Technical Specifications in percent span, and the Allowable Values should be modified. |
| | The Turbine Trip Auto Stop Oil 'Pressure instrumentation has a larger span than that used in the original calculations. |
| | Subsequently, Westinghouse evaluated the hardware utilizing the larger span. The evaluation concluded that the current Nominal Trip Setpoint remains valid. However, due to changes in the instrument span of the device, the previously submitted TA and Z values, listed in the Technical Specifications in percent span, and the Allowable Value must be modified. Retention of the current Nominal Trip Setpoint results in no change to the operational margin of the plant. The Turbine Trip Auto Stop Oil Pressure function is not credited in the safety analysis. |
| | The protective relay used in determining the setpoint for the Reactor Coolant Pump Underfrequency function was replaced with a relay by the same vendor but with a different model. |
| | Subsequently, Westinghouse evaluated this hardware substitution. |
| | The evaluation concluded that the current Nominal Trip Setpoint remains valid. However, due to changes in the instrument span, the previously submitted TA and Z values, listed in the Technical Specifications in percent span, must be modified. Retention of the current Nominal Trip Setpoints results in no change to the operational or safety margins for the plant. |
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| | L-91-186 Page 2 of 5 In conclusion, the modifications to the Technical Specifications for these four protection functions reflect changes in the instrument span. |
| | In the above cases the instrumentation preserves the assumptions of the various safety analyses. Therefore, the discussions and conclusions provided in the previous No Significant Hazards Consideration remain valid. |
| | l.a) What are the inputs for the bases documents The primary inputs for the uncertainties identified and documented in WCAP-12745 are listed in Table 3-23 of that document. The inputs used in the Setpoint Study are developed from specific plant information and Westinghouse documentation. For example: specific plant information consists of Turkey Point Units 3 and 4 plant procedures and hardware specifications. The Westinghouse documentation includes information such as testing and evaluations to determine such parameters as Process Measurement Accuracy (PHA) terms. |
| | 1.b) Were there any "generic" allowance (uncertainty) values used by Westinghouse when plant-specific information was not available or not based on Turkey Point specifications and procedures? If so, what confidence level does FPL have that these values reflect (or bound) the as-configured condition of the plantf "Generic" allowances for instrumentation uncertainties were reviewed and determined to be applicable for Turkey Point Units 3 8 4. "Generic" values were included in the review and were determined either applicable or bounding for application to Turkey Point Units 3 & 4. FPL has a high confidence level that these "generic values" reflect or bound the as-configured condition of the plant. |
| | 1.c) Are the allowance (uncertainty) values used applicable and conservative with respect to the as-configured plant7 The uncertainty values used by Westinghouse are applicable and conservative with respect to the as-configured plant conditions. The corrections for the four functions were re-evaluated and will be included in Revision 1 of WCAP-12745, to document the acceptability of the nominal trip setpoints to preserve the Safety Analysis Limits. |
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| | L-91-186 Page 3 of 5 |
| | : 2) Recently approved Amendments 135 and 140 approved specific values in the OThT and OPhT equations (table notes 1, 3). The amendment under current review proposes some of those values in a different form, i.e. |
| | from note 1: proposed p' 2235 from note 3: proposed K, < 1.09 K, > 0.02/'F |
| | ~(Tau), > 10 secs Are these new proposed values conservative (in the conservative direction) with respect to the existing TS (Amendments 135 and 140)7 The existing values are the same as those defined in the previous submittal and remain conservative. As noted below, the only change was |
| | ~ |
| | to include an inequality in the Technical Specifications denoting the conservative direction of the parameter. |
| | : 1) Explanation of conservative direction of inequalities in OThT and OPhT Reactor Trip functions. |
| | In a simplified form (without lead/lag, rate lag or lag filters), the equation for OThT is: |
| | AT hT, (K, - K,(T - T') + K,(P P') - f,(hI)) |
| | Where: |
| | 4T is the measured hT hTo is the indicated hT at 100 X RTP T is the measured Tavg T' is the design full power Tavg (574.2 'F) is the measured Pressurizer Pressure pt is the design Pressurizer Pressure (2235 psig) f,(hI) is the hI penalty KKK, are constants From this equation, the following can be seen: |
| | a) A decrease in the magnitude of K, results in a decrease in the trip setpoint which the measured dT is compared against. |
| | b) An increase in the magnitude of K, results in a decrease in the trip setpoint when T T', since K,{T - T') is subtracted from K,. |
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| | L-91-186 Page 4 of 5 c) An increase in the magnitude of K, results in a decrease in the trip setpoint when P s P', since K,{P P'} would then be a negative value and is added to K,. |
| | d) A decrease in the magnitude of T'esults in a decrease in the trip setpoint because (T - T'} would become positive at a lower measured value of T and K,(T T'} is subtracted from K,. |
| | e) An increase in the magnitude of P'esults in a decrease in the trip setpoint because {P - P') would become a larger negative value (or would remain a negative value until a higher pressure is reached) and K,{P - P'} is added to K,. |
| | Thus the inequality < is the conservative direction for K, and T', and the inequality . is the conservative direction for K K, and P'. |
| | In a simplified form (without lead/lag, rate lag or lag filters), the equation for OPhT is: |
| | hT - hTo (K4 K5T Ks(T T } fz(hI)} |
| | Where: |
| | hT is the measured hT T' |
| | hTo is the indicated hT at 100 X RTP is the measured Tavg II is the design full power Tavg (574.2 'F) f,(hI) is the hI penalty K4, K K, are constants From this equation, the following can be seen: |
| | a) A decrease in the magnitude of K, results in a deer'ease in the trip setpoint which the measured hT is compared against. |
| | b) An increase in the magnitude of K, results in a decrease in the trip setpoint since K,(T} is subtracted from K,. |
| | c) An increase in the magnitude of K, results in a decrease in the trip setpoint when T > T", since K,(T T"} is subtracted from K,. |
| | d) A decrease in the magnitude of T" results in a decrease in the trip setpoint because (T - T"} would become positive at a lower measured value of T and K,{T T"} is subtracted from K,. |
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| | L-91-186 Page 5 of 5 For a rate-lag function e.g., (~,s)/(1 + ~,s), an increasing value of ~, |
| | results in a faster buildup of the parameter and thus approaches the trip value quicker. |
| | Thus the inequality is the conservative direction for K, and T" and the inequality is the conservative direction for K K, and ~,. |
| | : 2) The Westinghouse calculations of uncertainties for equipment supplied by others were based on: |
| | a) A review of the calibration and functional test procedures for each protection function, as supplied by FPL, and b) A review of the vendor specification sheet data for each sensor transmitter, as supplied by FPL.}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML20212M1601999-09-28028 September 1999 Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17355A4601999-10-26026 October 1999 Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted ML17355A4301999-10-0808 October 1999 Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included ML17355A4461999-10-0404 October 1999 Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999 Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included ML17355A4291999-10-0404 October 1999 Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days ML17355A4251999-09-22022 September 1999 Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820 ML17355A4111999-09-0909 September 1999 Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08 ML17355A4131999-09-0707 September 1999 Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC ML17355A4141999-09-0202 September 1999 Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830 ML17355A4041999-08-23023 August 1999 Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4 ML17355A4071999-08-23023 August 1999 Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. ML17355A4061999-08-23023 August 1999 Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included ML17355A4001999-08-20020 August 1999 Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ML17355A3941999-07-27027 July 1999 Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01 ML17355A3871999-07-16016 July 1999 Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants ML17355A3851999-07-14014 July 1999 Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept ML17355A3711999-07-0606 July 1999 Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes ML17355A3591999-06-30030 June 1999 Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators ML17355A3661999-06-30030 June 1999 Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998 ML17355A3571999-06-28028 June 1999 Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness ML17355A3521999-06-18018 June 1999 Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML17355A3491999-06-0404 June 1999 Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions. ML17355A3441999-05-27027 May 1999 Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031 ML17355A3451999-05-24024 May 1999 Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley ML17355A2921999-04-22022 April 1999 Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330 ML17355A2891999-04-0909 April 1999 Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001 ML17355A2861999-04-0505 April 1999 Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7 ML17336A0681999-04-0101 April 1999 Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4 ML17355A2751999-03-25025 March 1999 Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000 ML17355A2641999-03-19019 March 1999 Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence ML17355A2651999-03-19019 March 1999 Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4. ML17355A2621999-03-16016 March 1999 Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI ML17355A2631999-03-12012 March 1999 Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit ML20204C6991999-03-10010 March 1999 Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested ML17355A2451999-03-0909 March 1999 Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3) ML17355A2501999-03-0808 March 1999 Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl ML17355A2441999-03-0101 March 1999 Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4 ML17355A2431999-02-25025 February 1999 Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE) ML17355A2341999-02-18018 February 1999 Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations. L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999 Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3) ML17355A2361999-02-18018 February 1999 Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998 ML17355A2301999-02-18018 February 1999 Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4 ML17355A2231999-02-0808 February 1999 Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance ML17355A2031999-01-29029 January 1999 Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan ML17355A2171999-01-20020 January 1999 Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI ML17354B2241999-01-0606 January 1999 Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation ML17354B2081998-12-15015 December 1998 Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II ML17354B2091998-12-15015 December 1998 Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b) ML17354B2061998-12-0909 December 1998 Informs That Request for Exemption Specified in Section II.B.3 Will Not Be Needed Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg ML17354B1981998-11-25025 November 1998 Forwards Scope & Objective for 1999 Plant Annual Emergency Preparedness Exercise.Objectives Developed in Conjunction with State & Local Govts.Exercise Scheduled for 990210 1999-09-09
[Table view] |
Text
ACCELERATED D TtuBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9107120105 DOC.DATE: 91/07/08 NOTARIZED: YES 'OCKET FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION BOHLKE,W.H.. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBZECT: 'Responds to NRC 910606 request for addi info re 901219 application for amends to Licenses DPR-31 6 DPR-41,revising Tech Specs Section 2.2, "Limiting Safety Sys Settings>> S D Section 3/4.3.2,. "ESF Actuation Sys Intrumentation."
DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR ( ENCL Q SIZE: E~
TITLE: OR Submittal: General Distribution NOTES RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 AULUCK,R 2 2 D INTERNAL: NRR/DET/ECMB 7D 1 1 NRR/DET/ESGB 1 1 NRR/DOEA/OTS B1 1 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 7E 1 1 NRR/DST/SICB8H7 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 0 /M 1 0 OGC/HDS3 1 0 EG FIL 01 1 1 RES/DSIR/EIB '1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 R
D D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 16
L
P.O. Box14000, Juno Beach, FL 33408-0420 JULDS 8N L-91-186 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DE C. 20555 Gentlemen:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Response to RAI on Reactor Protection System Setpoints TAC Nos. 79402 and 79403 By letter L-90 417r dated December 19, 1990, Florida Power and Light (FPL) submitted a request to amend the Turkey Point Technical Specifications. The proposed amendment revised Section 2.2, Limiting Safety System Settings and Section 3/4.3.2, Engineered Safety Features Actuation System Instrumentation.
By letter dated June 6, 1991, the NRC requested additional information concerning the reactor protection system (RPS) setpoints ~ In response to this request Attachment 1 is provided.
Attachment 2 provides the proposed revised Technical Specification change, as generated as a result of this response.
FPL has determined that the proposed Technical Specification change does not alter the No Significant Hazards Determination provided in L-90-417.
In accordance with 10 CFR 50.91(b) (1), a copy of this Proposed License Amendment is being forwarded to the State Designee for the State of Florida.
The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.
Should there be any questions, please contact us.
Very truly yours, W. H. Bohlke Vice President Nuclear Engineering and Licensing Attachment WHB/RJT/rjt CC: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Mr. Jacob Daniel Nash, Florida De'partment of Health and Rehabilitative Services
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STATE OF FLORIDA )
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COUNTY OF PALM BEACH )
W. H. Bohlke being first duly sworn, deposes and says:
That he is Vice President Nuclear En ineerin and Licensin , of Florida Power and Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Licensees W. H. Bohlke Subscribed and sworn to before me this nQ day of 1991.
NOTARY PUBLIC, in and for the County of Palm Beach, State of Florida Notary PublIc, State of Horlda My Comm. Exp. Feb, 18, 1995 My COmmiSSiOn eXpires BonrtsdthruPIGHARD lns.Agency,
ATTACHMENT 1 Response to Recgxest for Additional Information
L-91-186 Page 1 of 5
- 1) Has FPL verified that the bases document used by Westinghouse to determine the instrument allowances (uncertainties) is correct and applicable to Turkey Point as configured? In addition, please provide the following:
All assumptions and inputs used as the bases in developing the setpoint study over the last two years have been re-verified.
As a result of this review, all inputs have been re-verified and remain, valid for the setpoints documented in WCAP-12745, with the exception of four functions.
For the Containment Pressure-High and High-High functions, the pressure switches used in determining the setpoints were replaced with switches by the same vendor but different models.
Subsequently, Westinghouse evaluated this hardware substitution.
The evaluation concluded that the current Nominal Trip Setpoints remain valid. However, due to changes in the instrument span, the previously submitted TA and Z values, listed'n the Technical Specifications in percent span, and the Allowable Values should be modified.
The Turbine Trip Auto Stop Oil 'Pressure instrumentation has a larger span than that used in the original calculations.
Subsequently, Westinghouse evaluated the hardware utilizing the larger span. The evaluation concluded that the current Nominal Trip Setpoint remains valid. However, due to changes in the instrument span of the device, the previously submitted TA and Z values, listed in the Technical Specifications in percent span, and the Allowable Value must be modified. Retention of the current Nominal Trip Setpoint results in no change to the operational margin of the plant. The Turbine Trip Auto Stop Oil Pressure function is not credited in the safety analysis.
The protective relay used in determining the setpoint for the Reactor Coolant Pump Underfrequency function was replaced with a relay by the same vendor but with a different model.
Subsequently, Westinghouse evaluated this hardware substitution.
The evaluation concluded that the current Nominal Trip Setpoint remains valid. However, due to changes in the instrument span, the previously submitted TA and Z values, listed in the Technical Specifications in percent span, must be modified. Retention of the current Nominal Trip Setpoints results in no change to the operational or safety margins for the plant.
~ ~
L-91-186 Page 2 of 5 In conclusion, the modifications to the Technical Specifications for these four protection functions reflect changes in the instrument span.
In the above cases the instrumentation preserves the assumptions of the various safety analyses. Therefore, the discussions and conclusions provided in the previous No Significant Hazards Consideration remain valid.
l.a) What are the inputs for the bases documents The primary inputs for the uncertainties identified and documented in WCAP-12745 are listed in Table 3-23 of that document. The inputs used in the Setpoint Study are developed from specific plant information and Westinghouse documentation. For example: specific plant information consists of Turkey Point Units 3 and 4 plant procedures and hardware specifications. The Westinghouse documentation includes information such as testing and evaluations to determine such parameters as Process Measurement Accuracy (PHA) terms.
1.b) Were there any "generic" allowance (uncertainty) values used by Westinghouse when plant-specific information was not available or not based on Turkey Point specifications and procedures? If so, what confidence level does FPL have that these values reflect (or bound) the as-configured condition of the plantf "Generic" allowances for instrumentation uncertainties were reviewed and determined to be applicable for Turkey Point Units 3 8 4. "Generic" values were included in the review and were determined either applicable or bounding for application to Turkey Point Units 3 & 4. FPL has a high confidence level that these "generic values" reflect or bound the as-configured condition of the plant.
1.c) Are the allowance (uncertainty) values used applicable and conservative with respect to the as-configured plant7 The uncertainty values used by Westinghouse are applicable and conservative with respect to the as-configured plant conditions. The corrections for the four functions were re-evaluated and will be included in Revision 1 of WCAP-12745, to document the acceptability of the nominal trip setpoints to preserve the Safety Analysis Limits.
L-91-186 Page 3 of 5
- 2) Recently approved Amendments 135 and 140 approved specific values in the OThT and OPhT equations (table notes 1, 3). The amendment under current review proposes some of those values in a different form, i.e.
from note 1: proposed p' 2235 from note 3: proposed K, < 1.09 K, > 0.02/'F
~(Tau), > 10 secs Are these new proposed values conservative (in the conservative direction) with respect to the existing TS (Amendments 135 and 140)7 The existing values are the same as those defined in the previous submittal and remain conservative. As noted below, the only change was
~
to include an inequality in the Technical Specifications denoting the conservative direction of the parameter.
- 1) Explanation of conservative direction of inequalities in OThT and OPhT Reactor Trip functions.
In a simplified form (without lead/lag, rate lag or lag filters), the equation for OThT is:
AT hT, (K, - K,(T - T') + K,(P P') - f,(hI))
Where:
4T is the measured hT hTo is the indicated hT at 100 X RTP T is the measured Tavg T' is the design full power Tavg (574.2 'F) is the measured Pressurizer Pressure pt is the design Pressurizer Pressure (2235 psig) f,(hI) is the hI penalty KKK, are constants From this equation, the following can be seen:
a) A decrease in the magnitude of K, results in a decrease in the trip setpoint which the measured dT is compared against.
b) An increase in the magnitude of K, results in a decrease in the trip setpoint when T T', since K,{T - T') is subtracted from K,.
L-91-186 Page 4 of 5 c) An increase in the magnitude of K, results in a decrease in the trip setpoint when P s P', since K,{P P'} would then be a negative value and is added to K,.
d) A decrease in the magnitude of T'esults in a decrease in the trip setpoint because (T - T'} would become positive at a lower measured value of T and K,(T T'} is subtracted from K,.
e) An increase in the magnitude of P'esults in a decrease in the trip setpoint because {P - P') would become a larger negative value (or would remain a negative value until a higher pressure is reached) and K,{P - P'} is added to K,.
Thus the inequality < is the conservative direction for K, and T', and the inequality . is the conservative direction for K K, and P'.
In a simplified form (without lead/lag, rate lag or lag filters), the equation for OPhT is:
hT - hTo (K4 K5T Ks(T T } fz(hI)}
Where:
hT is the measured hT T'
hTo is the indicated hT at 100 X RTP is the measured Tavg II is the design full power Tavg (574.2 'F) f,(hI) is the hI penalty K4, K K, are constants From this equation, the following can be seen:
a) A decrease in the magnitude of K, results in a deer'ease in the trip setpoint which the measured hT is compared against.
b) An increase in the magnitude of K, results in a decrease in the trip setpoint since K,(T} is subtracted from K,.
c) An increase in the magnitude of K, results in a decrease in the trip setpoint when T > T", since K,(T T"} is subtracted from K,.
d) A decrease in the magnitude of T" results in a decrease in the trip setpoint because (T - T"} would become positive at a lower measured value of T and K,{T T"} is subtracted from K,.
L-91-186 Page 5 of 5 For a rate-lag function e.g., (~,s)/(1 + ~,s), an increasing value of ~,
results in a faster buildup of the parameter and thus approaches the trip value quicker.
Thus the inequality is the conservative direction for K, and T" and the inequality is the conservative direction for K K, and ~,.
- 2) The Westinghouse calculations of uncertainties for equipment supplied by others were based on:
a) A review of the calibration and functional test procedures for each protection function, as supplied by FPL, and b) A review of the vendor specification sheet data for each sensor transmitter, as supplied by FPL.