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| {{#Wiki_filter:REGULA A JR Y LNFORHATION 0 I STRI8U TIDIES SYSTEM (RIDS)AU UHRIGR R~E~RECIP~NAME EISENHUTED | | {{#Wiki_filter:REGULA JR A Y LNFORHATION 0 I STRI8U TIDIES SYSTEM (RIDS) |
| ~G~ACCESSION NaR;8}04270260 Duc.nATE.:
| | ACCESSION FACIL:5 0 |
| 8}/O~/}7 NOTARIZED: | | << 'rkey NaR;8}04270260 251 Point urKey Point Duc.nATE.: |
| YES FACIL:5<<'rkey Point Planti Unit 3E Florida Power and Light C 0 251 urKey Point chianti Unit OE Florida Power and Lignt C AUTHOR At FILIATION Florioa Power 8 Light Co~RECIPIENr AFFILIATION Division of Licensing DOCKET 05000250 0500025}RECIPIENT ID CODE/NAME | | Planti Unit chianti Unit 8}/O~/}7 3E OE Florida Florida NOTARIZED: YES Power and Light Power and Lignt C |
| | C DOCKET 05000250 0500025} |
| | AU AUTHOR At FILIATION UHRIGR R ~ E ~ Florioa Power 8 Light Co ~ |
| | RECIP ~ NAME RECIPIENr AFFILIATION EISENHUTED ~ G ~ Division of Licensing |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Requests amends to Licenses DPR 31 h DPiA'}to specify scooe ot.steam generator insp program<acceptance criteria reoorting requirements, Request supplements 8}0402 reauest.DISTRIBUTION CODE: AOO IS COPIES RECEIVED:LTR Ll ENCL+SIZE: TITLE: Gener al Distr itiution for.af ter Issuance of Operating License Nl/cffsQ l/00~oo RECIPIENT COPIFS COPIES IO CODE/NAME i.TTR FNCL LTTR ENCL ACTION: VAIiGA E S~OQ}3 13 INTERNAL: D/OIREHUH FACOS Iah, Oo OELD i}RAD AS>lT BR 1 1 2 1 0 1 1 DIRE DIV OF LIC NRC PDR 02 0 AS ESS 8R 10 G 01 1 1 1 1 1 0 1=1 EXTERNAL: ACRS Nslc 09 05}0 16 1 1 LPDR 1 1 II TOTAL NU'ABER OF COPIES REQUIRED: LTTR 40 ENCL 38 | | Requests amends to Licenses DPR 31 h DPiA'} to specify scooe ot .steam generator insp program<acceptance criteria reoorting requirements, Request supplements 8}0402 reauest. |
| | DISTRIBUTION CODE: AOO IS COPIES RECEIVED:LTR Ll ENCL + SIZE: |
| | Nl/cffsQ RECIPIENT l |
| | TITLE: Gener al Distr itiution for af ter Issuance |
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| | COPIFS |
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| | RECIPIENT of Operating License COPIES IO CODE/NAME i.TTR FNCL ID CODE/NAME LTTR ENCL ACTION: VAIiGAE S ~ OQ }3 13 INTERNAL: D/OIREHUH FACOS 1 1 DIRE DIV OF LIC 1 1 Iah, Oo 2 NRC PDR 02 1 1 OELD i} 1 0 0 AS ESS 8R 10 1 0 RAD AS>lT BR 1 1 G 01 1 = 1 EXTERNAL: ACRS 09 }0 16 LPDR 1 1 Nslc 05 1 1 II TOTAL NU'ABER OF COPIES REQUIRED: LTTR 40 ENCL 38 |
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| Office of Nuclear Reactor Regulation Attention: | | April 17, 1981 L-81-172 s,cO Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, D'irector Division of Licensing U.S. Nuclear Regulatory Commission Washington D.C. 20555 |
| Mr.Darrell G.Eisenhut, D'irector Division of Licensing U.S.Nuclear Regulatory Commission Washington D.C.20555 | |
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| ==Dear Mr.Eisenhut:== | | ==Dear Mr. Eisenhut:== |
| Re: Turkey Point Units 3 5 4 Docket Nos.50-250 and 50-251 Proposed License Amendments April 17, 1981 L-81-172 s,cO r g t In accordance with 10 CFR 50.30, Florida Power 8 Light Company submits herewith three signed originals and forty copies of a request to amend Facility Operating Licenses DPR-31 and DPR-41.This request supplements our request of April 2.1981 (L-81-144).
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| The proposed amendment is described below and shown on the accompanying pages bearing the date of this letter in the, lower right hand corner.The License conditions have been modified to specify in the license the scope of the steam generator inspection program and acceptance crit'eria and the reporting requirements.
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| This amendment is administrative in nature since it does not change the technical content of the inspection and plugging program.The proposed amendment has been revi.ewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board.We have determined that since this request supplements the previous request but involves a duplicate amendment, the request should be classified as a Class I Amendment pursuant to 10 CFR 170.Accordingly, a check for$400 is enclosed.Vice President Advanced Systems and Technology REU/JEM/mbd Attachment cc: Mr.James P.O'Reilly, Region II Harold F.Reis, Esquire*Q t.k 2>.Q QlcrQ P gooi 5~h~/z~: g psn.nn
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| DPR-31 Page 3 B.Tech~nical S ecificaciona The Technical Specifications contain~d in Appendices A and B, as revis~d through Amendment No.62 are hereby incorporated in the license.The licensee shall operate the facility in accordance with Technical Specifications.. | | Re: Turkey Point Units 3 5 4 r g Docket Nos. 50-250 and 50-251 t Proposed License Amendments In accordance with 10 CFR 50.30, Florida Power 8 Light Company submits herewith three signed originals and forty copies of a request to amend Facility Operating Licenses DPR-31 and DPR-41. This request supplements our request of April 2. 1981 (L-81-144). |
| C.~Re orts FPL shall issue certain reports to the NRC in accordance with the requirements of the Technical Specifications. | | The proposed amendment is described below and shown on the accompanying pages bearing the date of this letter in the, lower right hand corner. |
| D.Records FPL shall originate and maintain facility operating records in accordance with the requirements of the Technical Specifications. | | The License conditions have been modified to specify in the license the scope of the steam generator inspection program and acceptance crit'eria and the reporting requirements. This amendment is administrative in nature since it does not change the technical content of the inspection and plugging program. |
| E.Steam Generator Inspections 1.After operation of six equivalent full power months from the last inspection of all three steam generators Turkey Point Unit 3 shall be brought to the cold shutdown condition and al 1 three steam generators shall be inspected unless: (1)an inspection of the steam generators is performed within this period, or (2)an extention is granted by the NRC to authorize continued operation beyond the authorized period of operation. | | The proposed amendment has been revi.ewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board. |
| Any request for continued operation must be submitted at least 45 days prior to the expiration date of the authorized period of operation. | | We have determined that since this request supplements the previous request but involves a duplicate amendment, the request should be classified as a Class I Amendment pursuant to 10 CFR 170. Accordingly, a check for $ 400 is enclosed. |
| For the purpose of this requirement, equivalent operation is defined as operation>>ith the reactor coolant at a temperature greater than 350"F.2.Reactor coolant to secondary leakage through the steam generator tubes shall be limited to 0.3 gpm per steam generator. | | Vice President Advanced Systems and Technology gooi REU/JEM/mbd 5 Attachment ~h cc: Mr. James P. O'Reilly, Region II ~/z~: |
| tlith a steam generator tube leakage greater than this limit.the reactor shall be brought to the cold shutdown condition within 24 hours and an inspection of the leaking steam generator shall be performed. | | Harold F. Reis, Esquire g psn. nn |
| 3.The concentration of radioiodine in the reactor coolant shall be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients. | | * Q t.k 2 > .Q QlcrQ P |
| 4.If primary to secondary leakage attributable to the denting phenonmena is detected in 2 or more tubes during any 20 day period an inspection of the leaking steam generator shall be performed by the licensee.5.The inspection and plugging results from 1, 2, or 4 above shall be submitted to the NRC no later than 14 days following the return to power operation. | | |
| Any unusual results from the denting inspections shall be reported within 24 hours.It in the inspections performed under regulatory position C.5 of Regulatory Guide 1.83, more than 10%of the total tubes inspected have detectable wall penetration | | DPR-31 Page 3 B. Tech~nical S ecificaciona The Technical Specifications contain~d in Appendices A and B, as revis~d through Amendment No. 62 are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.. |
| (>205)or more than three of the tubes inspected exceed the plugging limit, the inspection results shall be reported within 24 hours.4/17/8l | | C. ~Re orts FPL shall issue certain reports to the NRC in accordance with the requirements of the Technical Specifications. |
| | D. Records FPL shall originate and maintain facility operating records in accordance with the requirements of the Technical Specifications. |
| | E. Steam Generator Inspections |
| | : 1. After operation of six equivalent full power months from the last inspection of all three steam generators Turkey Point Unit 3 shall be brought to the cold shutdown condition and al 1 three steam generators shall be inspected unless: (1) an inspection of the steam generators is performed within this period, or (2) an extention is granted by the NRC to authorize continued operation beyond the authorized period of operation. Any request for continued operation must be submitted at least 45 days prior to the expiration date of the authorized period of operation. For the purpose of this requirement, equivalent operation is defined as operation >>ith the reactor coolant at a temperature greater than 350"F. |
| | : 2. Reactor coolant to secondary leakage through the steam generator tubes shall be limited to 0.3 gpm per steam generator. tlith a steam generator tube leakage greater than this limit. the reactor shall be brought to the cold shutdown condition within 24 hours and an inspection of the leaking steam generator shall be performed. |
| | : 3. The concentration of radioiodine in the reactor coolant shall be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients. |
| | : 4. If primary to secondary leakage attributable to the denting phenonmena is detected in 2 or more tubes during any 20 day period an inspection of the leaking steam generator shall be performed by the licensee. |
| | : 5. The inspection and plugging results from 1, 2, or 4 above shall be submitted to the NRC no later than 14 days following the return to power operation. Any unusual results from the denting inspections shall be reported within 24 hours. It in the inspections performed under regulatory position C.5 of Regulatory Guide 1.83, more than 10% |
| | of the total tubes inspected have detectable wall penetration (>205) or more than three of the tubes inspected exceed the plugging limit, the inspection results shall be reported within 24 hours. |
| | 4/17/8l |
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| | DPR-31 Page 4 |
| | : 6. The scope of the steam generator inspections (including eddy current, gauging and visual inspection) and tube plugging criteria shall be consistant with FPL letter L-80-412 dated December 18, 1980. The scope of the program shall be increased as appropriate to reflect operating experience and/or analysis. |
| | : 7. Prior to resumption of power operation following inspections per 1, 2, and 4 above the licensee shall perform a 'safety analysis per 10 CFR 50 Section 59. |
| | F. The licensee shall maintain in effect and fully implement all provisions of the Commission-approved phvsical securitv oian, includinq amendments and changes made pursuant to the authority of 10 CFR 50.54 (p). The approved security plan documents, witheld from public disclosure pursuant to 10 CFR 2.790(d), collectivelv titled "Turkev Point Plant Unit Nos. 3 and 4 ohvsical Securitv Plan". dated October 18. 1979. as sunnlemented Februarv 20. 1979. |
| | G. The licensee mav nrnce~d wi th and is reaui r~d to orovide a schedule for and to comolete the modifications indentified in Paraaraohs 3.1.1 throuoh |
| | : 3. 1.19 nf the NRC s Fire Pr nt~rtinn Safetv Evaluation. dated March 21, 1979 for the facility. These modifications are to be comoleted orior to December 1980. If anv modifications cannot be cnmnleted on schedule the licensee shall submit a reoort exolaininq the circumstances toaether with a revised schedule. |
| | In addition. the licensee shall submit the additional information indentified in Sections 3.1 and 3.2 of the related Safetv Evaluation in accordance with the ~chedule rnnt~incd thar> in ln tha avant these dates for submittal cannot be met, the licensee shall submit a rennrt. |
| | explaining the circumstances, together with a revised schedule. |
| | The licensee is requi red to develop and implement the administrative controls which are consistent with the licensee's letters of August 28 and November 7, 1978 within three months from the date of this amendment. |
| | H. Safeguards Contingency Plan The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Safequards Contingency Plan, including amendments and chanqes made pursuant to the authority of 10 CFR 50.54(p). The approved Continqency Plan consists of documents witheld from oublic disclosure oursuant to 10 CFR 2.790(d) and identified as "Turkev Point Plant Safequards Continaencv Plan" dated June 17, 1980 and submitted oursuant to 10 CFR 73.40. The Continaencv Plan shall be fullv imolemented. in accordance with 10 CFR 73.40(b). within 30 davs of this aonroval. |
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| | DPR-41 D. Steam Generator Inspections Page 4 After operation of six equivalent full power months from the last inspection of all three steam generators, Turkey Point Unit 4 shall be brought to the cold shutdown condition and all three steam generaters shall be inspected unless" (1) an inspection of the steam generators is performed within this period, or (2) an extention is granted by the NRC to authorize continued operation beyond the authorized period of operation. Any request for continued operation must be submitted at least 45 days prior to the expiration date of the authorized period of operation. For the purpose of this requirement, equivalent operation is defined as operation with the reactor coolant at a temperature greater than 350'F. |
| | : 2. Reactor coolant to secondary leakage through the steam generator tubes shall be limited to 0.3 gpm per steam generator. With a steam generator tube leakage greater than this limit, the reactor shall be brought to the cold shutdown condition within 24 hours and an inspection of the leaking steam generator shall be performed. |
| | : 3. The concentration of radioiodine in the reactor coolant shall'be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients. |
| | 4 If primary to secondary leakage attributable to the denting phenonmena is detected in 2 or more tubes during any 20 day period an inspection of the leaking steam generator shall be performed by the lic'ensee. |
| | : 5. The Metal Impact Monitoring System (MIMS) shall be continued in operatio'n with the capability of detecting loose objects. If the MIMS is out of service in other than cold shutdown or refueling mode of operation, this fact shall be reported to the NRC. Any abnormal indications from the MIMS shall also be reported to the NRC by telephone by the next working day and by a written evaluation within two weeks. |
| | : 6. Following each startup from below 350'F, core barrel movement shall be evaluated using Neutron Noise Technique. |
| | : 7. The inspection and plugging results from 1, 2, or 4 above shall be submitted to the NRC no later than 14 days following the return to power operation. Any unusual results from the denting inspections shall be reported within 24 hours. If, in the inspections performed under regulatory position C.5 of Regulatory Guide 1.83, more than 105 of the total tubes inspected have detectable wall penetration (>205,) or more than three of the tubes inspected exceed the plugging limit, the inspection results shall be reported within 24 hours. |
| | : 8. The scope of the steam generator inspections (including eddy current, guaging and visual inspection) and tube plugging criteria shall be consistant with FPL letter i-80-412 dated December 18, 1980. The scope of the program shall be increased as appropriate to reflect operating ri expe ence and/or anal ys i s. |
| | : 9. Prior to resumption of power operation fol lowing inspections per 1, 2, and 4 above the licensee shall perform a safety analysis per 10 CFR 50 Section 59. |
| | 4/17/81 |
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| | STATE OF FLORI DA ) |
| | ) ss. |
| | COUNTY OF DADE ) |
| | Robert E. Uhrig, being first duly sworn, deposes and says: |
| | That he is a Vice President of Florida Power & Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said 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 Licensee. |
| | Robert E. Unrig Subscribed and sworn to before me this |
| | ~clay of NOTARY PUBLIC, and for the county of Dade, State of Florida I' |
| | ', |
| | 1 M'/ CdiTi l&ldrt Ptf8$ CCidd.r commission expires: |
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| DPR-31 Page 4 6.The scope of the steam generator inspections (including eddy current, gauging and visual inspection) and tube plugging criteria shall be consistant with FPL letter L-80-412 dated December 18, 1980.The scope of the program shall be increased as appropriate to reflect operating experience and/or analysis.7.Prior to resumption of power operation following inspections per 1, 2, and 4 above the licensee shall perform a'safety analysis per 10 CFR 50 Section 59.F.The licensee shall maintain in effect and fully implement all provisions of the Commission-approved phvsical securitv oian, includinq amendments and changes made pursuant to the authority of 10 CFR 50.54 (p).The approved security plan documents, witheld from public disclosure pursuant to 10 CFR 2.790(d), collectivelv titled"Turkev Point Plant Unit Nos.3 and 4 ohvsical Securitv Plan".dated October 18.1979.as sunnlemented Februarv 20.1979.G.The licensee mav nrnce~d wi th and is reaui r~d to orovide a schedule for and to comolete the modifications indentified in Paraaraohs 3.1.1 throuoh 3.1.19 nf the NRC s Fire Pr nt~rtinn Safetv Evaluation.
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| dated March 21, 1979 for the facility.These modifications are to be comoleted orior to December 1980.If anv modifications cannot be cnmnleted on schedule the licensee shall submit a reoort exolaininq the circumstances toaether with a revised schedule.In addition.the licensee shall submit the additional information indentified in Sections 3.1 and 3.2 of the related Safetv Evaluation in accordance with the~chedule rnnt~incd thar>in ln tha avant these dates for submittal cannot be met, the licensee shall submit a rennrt.explaining the circumstances, together with a revised schedule.The licensee is requi red to develop and implement the administrative controls which are consistent with the licensee's letters of August 28 and November 7, 1978 within three months from the date of this amendment.
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| H.Safeguards Contingency Plan The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Safequards Contingency Plan, including amendments and chanqes made pursuant to the authority of 10 CFR 50.54(p).The approved Continqency Plan consists of documents witheld from oublic disclosure oursuant to 10 CFR 2.790(d)and identified as"Turkev Point Plant Safequards Continaencv Plan" dated June 17, 1980 and submitted oursuant to 10 CFR 73.40.The Continaencv Plan shall be fullv imolemented.
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| in accordance with 10 CFR 73.40(b).within 30 davs of this aonroval.4/17/8l D.Steam Generator Inspections DPR-41 Page 4 2.3.4 5.After operation of six equivalent full power months from the last inspection of all three steam generators, Turkey Point Unit 4 shall be brought to the cold shutdown condition and all three steam generaters shall be inspected unless" (1)an inspection of the steam generators is performed within this period, or (2)an extention is granted by the NRC to authorize continued operation beyond the authorized period of operation.
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| Any request for continued operation must be submitted at least 45 days prior to the expiration date of the authorized period of operation.
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| For the purpose of this requirement, equivalent operation is defined as operation with the reactor coolant at a temperature greater than 350'F.Reactor coolant to secondary leakage through the steam generator tubes shall be limited to 0.3 gpm per steam generator.
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| With a steam generator tube leakage greater than this limit, the reactor shall be brought to the cold shutdown condition within 24 hours and an inspection of the leaking steam generator shall be performed.
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| The concentration of radioiodine in the reactor coolant shall'be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients.
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| If primary to secondary leakage attributable to the denting phenonmena is detected in 2 or more tubes during any 20 day period an inspection of the leaking steam generator shall be performed by the lic'ensee.
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| The Metal Impact Monitoring System (MIMS)shall be continued in operatio'n with the capability of detecting loose objects.If the MIMS is out of service in other than cold shutdown or refueling mode of operation, this fact shall be reported to the NRC.Any abnormal indications from the MIMS shall also be reported to the NRC by telephone by the next working day and by a written evaluation within two weeks.6.7.8.9.Following each startup from below 350'F, core barrel movement shall be evaluated using Neutron Noise Technique.
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| The inspection and plugging results from 1, 2, or 4 above shall be submitted to the NRC no later than 14 days following the return to power operation.
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| Any unusual results from the denting inspections shall be reported within 24 hours.If, in the inspections performed under regulatory position C.5 of Regulatory Guide 1.83, more than 105 of the total tubes inspected have detectable wall penetration
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| (>205,)or more than three of the tubes inspected exceed the plugging limit, the inspection results shall be reported within 24 hours.The scope of the steam generator inspections (including eddy current, guaging and visual inspection) and tube plugging criteria shall be consistant with FPL letter i-80-412 dated December 18, 1980.The scope of the program shall be increased as appropriate to reflect operating expe ri ence and/or anal ys i s.Prior to resumption of power operation fol lowing inspections per 1, 2, and 4 above the licensee shall perform a safety analysis per 10 CFR 50 Section 59.4/17/81 STATE OF FLORI DA))COUNTY OF DADE)ss.Robert E.Uhrig, being first duly sworn, deposes and says: That he is a Vice President of Florida Power&Light Company, the Licensee herein;That he has executed the foregoing document;that the state-ments made in this said 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 Licensee.Robert E.Unrig Subscribed and sworn to before me this~clay of NOTARY PUBLIC, and for the county of Dade, State of Florida 1 I'M'/CdiTi l&ldrt C Ptf8$CCidd.r', Ny commission expires:
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17355A3901999-07-27027 July 1999 Application for Amend to License DPR-31,modifying TSs 3.8.1.1,3.4.3 & 3.5.2 to Extend AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3021999-04-26026 April 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2471999-03-0808 March 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Certain Requirements from TS Section 6.0 That Are Adequately Controlled by Existing Regulations Other than 10CFR50.36 & TS ML17355A2391999-02-24024 February 1999 Application for Amends to Licenses DPR-31 & DPR-41,removing Restrictions on Location at Which Temp of UHS May Be Monitored in TS 3/4.7.4 ML17354B1621998-10-27027 October 1998 Application for Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi- Discipline Supervisor Position Into TS ML17354A8321998-03-12012 March 1998 Application for Amends to Licenses DPR-31 & DPR-41,deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7601998-01-0909 January 1998 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 5.3.1 & 6.9.1.7 to Allow Implementation of Zirlo Fuel Rod Cladding ML17309A9111997-12-29029 December 1997 Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17354A6141997-08-27027 August 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Turkey Point Units 3 & 4 TS to Allow Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4201997-02-24024 February 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs 6.9.1.7, COLR & Adding Best Estimate Large Break Loss of Coolant Accident Analysis to COLR ML17354A3721996-12-17017 December 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3501996-11-22022 November 1996 Application for Amends to Licenses DPR-31 & DPR-41, Requesting Rev to Allow Unit 3 Diesel Fuel Oil Storage Tank to Be Drained,Inspected & Cleaned While Maintaining at Least One Unit 3 Diesel Operable ML17354A2851996-10-0303 October 1996 Application for Amend to Licenses DPR-31 & DPR-41 to Modify Plants Units 3 & 4 to Revise TS Allowing Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7971996-07-17017 July 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7091996-05-28028 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Section 6.0, Administrative Controls, IAW 10CFR50.90 to Address Licensed Qualifications of Operations Manager ML17353A6881996-05-10010 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6501996-04-23023 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 7.4 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation. ML17353A6561996-04-19019 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6151996-03-21021 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6061996-03-20020 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.5.1 to Remove SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels from Ts,Per Line-Item 7.4 from GL 93-05 ML17353A5981996-03-0505 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 4.4.3.3 & 4.5.2 to Reduce Frequency of Surveillances & Insps in Accordance W/Gl 93-05 Items,6.6 & 7.5 ML17353A5011995-12-18018 December 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising Definition of RTP from 2,200 Mwt to 2,300 Mwt.Proprietary TR WCAP-13719,Rev 2 & Nonproprietary TRs WCAP-13718,Rev 2 & WCAP-14276,Rev 1 Encl.Proprietary TR WCAP-13719 Withheld ML17353A4521995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Index to Delete Bases Re Administrative Controls & Reviews ML17353A4491995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs w/Line-Item 10.1 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation, Per GL 94-01 ML17353A3951995-10-0404 October 1995 Application for Amend to License DPR-31 & DPR-41,modifying Plant TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/ Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3811995-09-28028 September 1995 Application for Amends to Licenses DPR-31 & DPR-41, Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3511995-09-11011 September 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 10.1 from GL 93-05, Line-Item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation & Guidance in GL 94-01 ML17353A2811995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Per Selected Line Items from NRC GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation. ML17353A2771995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 ML17353A2741995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2711995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2681995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.1.3.1, Movable Control Assemblies - Group Height & 3/4.1.3.2, Position Indication Sys - Operating & Asociated Bases ML17353A2651995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Table 4.3-1 Re Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17352B1821995-05-23023 May 1995 Application for Amends to Licenses DPR-31 & DPR-41.Amends Would Use Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation Setpoints ML17352B0851995-03-30030 March 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot- Start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 ML17352B0001995-01-17017 January 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl ML17352A8361994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3.9.4 & 1.9,allowing Containment Personnel Airlock Doors to Be Opened During Core Operations & Movement of Irradiated Fuel in Containment ML17352A8291994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.4.9.1 to Remove Schedule for Withdrawal of Rv Matl Surveillance Specimens,Gl 91-01 ML17352A7221994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3.1.3.6, Reactivity Control Sys CR Insertion Limits, 3/4.2.2, Heat Flux Hot Channel Factor - Fq(Z) & 6.9.1.7, COLR & Associated Bases,Per GL 88-16.COLRs Encl ML17352A7301994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.7.1 & Associated Bases Which Address Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML17352A7271994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.8.1.1.2e & 4.8.1.1.2f Re EDG Fuel Oil Testing Program ML17352A5451994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.0.5a, Applicability - Srs, to Reflect Intent of Revised STS (NUREG-1431) for ISI & Testing Programs,In Accordance W/Recommendations in Draft NUREG-1482 ML17352A5421994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.6.2.1.d, CSS Surveillance Interval for Air or Smoke Flow Test Through CS Header from at Least Once Per 5 Yrs to at Least Once Per 10 Yrs,Per GL 93-05 & NUREG-1366 ML17352A4611994-02-18018 February 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.5.2.8, Audits by Deleting Frequencies Performed Under Cognizance of Nuclear Review Board,Per GL 93-07 ML17352A4351993-12-28028 December 1993 Application for Amends to Licenses DPR-31 & DPR-41,proposing Addition of SG Water Level - high-high Protection to TS Tables 3.3-2,3.3-3,4.3-2 & Associated Bases,In Accordance W/ Commitment to GL 89-19 for Resolution of USI A-47 ML17352A2621993-10-0404 October 1993 Application for Amend to Licenses DPR-31 & DPR-41 Revising Surveillance Requirement 4.6.1.2a & Associated Bases to Conform w/NUREG-1431,Standard Ts,Westinghouse Plants,Rev 0 ML17352A2201993-09-0303 September 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3/4.7.1.6, Standby FW Sys & Associated Bases to Eliminate Cranking DGs ML17352A2011993-08-17017 August 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising License Conditions 3.G & 3.F Respectively,To Conform to Std Fire Protection License Proposed as Stated in GL 86-10 ML17352A1061993-07-20020 July 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Definitions to Ensure Consistency W/New 10CFR20 Requirements & Changing Radiological Effluent Release Rept Frequency ML17349A8771993-05-21021 May 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 5.2.2, Design Pressure & Temp & Associated Bases to Correct Ref to Max Containment Design Internal Pressure from 59 Psig to 55 Psig 1999-07-27
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17355A3901999-07-27027 July 1999 Application for Amend to License DPR-31,modifying TSs 3.8.1.1,3.4.3 & 3.5.2 to Extend AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3021999-04-26026 April 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2471999-03-0808 March 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Certain Requirements from TS Section 6.0 That Are Adequately Controlled by Existing Regulations Other than 10CFR50.36 & TS ML17355A2391999-02-24024 February 1999 Application for Amends to Licenses DPR-31 & DPR-41,removing Restrictions on Location at Which Temp of UHS May Be Monitored in TS 3/4.7.4 ML17354B1621998-10-27027 October 1998 Application for Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi- Discipline Supervisor Position Into TS ML17354A8321998-03-12012 March 1998 Application for Amends to Licenses DPR-31 & DPR-41,deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7601998-01-0909 January 1998 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 5.3.1 & 6.9.1.7 to Allow Implementation of Zirlo Fuel Rod Cladding ML17309A9111997-12-29029 December 1997 Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17354A6141997-08-27027 August 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Turkey Point Units 3 & 4 TS to Allow Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4201997-02-24024 February 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs 6.9.1.7, COLR & Adding Best Estimate Large Break Loss of Coolant Accident Analysis to COLR ML17354A3721996-12-17017 December 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3501996-11-22022 November 1996 Application for Amends to Licenses DPR-31 & DPR-41, Requesting Rev to Allow Unit 3 Diesel Fuel Oil Storage Tank to Be Drained,Inspected & Cleaned While Maintaining at Least One Unit 3 Diesel Operable ML17354A2851996-10-0303 October 1996 Application for Amend to Licenses DPR-31 & DPR-41 to Modify Plants Units 3 & 4 to Revise TS Allowing Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7971996-07-17017 July 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7091996-05-28028 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Section 6.0, Administrative Controls, IAW 10CFR50.90 to Address Licensed Qualifications of Operations Manager ML17353A6881996-05-10010 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6501996-04-23023 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 7.4 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation. ML17353A6561996-04-19019 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6151996-03-21021 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6061996-03-20020 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.5.1 to Remove SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels from Ts,Per Line-Item 7.4 from GL 93-05 ML17353A5981996-03-0505 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 4.4.3.3 & 4.5.2 to Reduce Frequency of Surveillances & Insps in Accordance W/Gl 93-05 Items,6.6 & 7.5 ML17353A5011995-12-18018 December 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising Definition of RTP from 2,200 Mwt to 2,300 Mwt.Proprietary TR WCAP-13719,Rev 2 & Nonproprietary TRs WCAP-13718,Rev 2 & WCAP-14276,Rev 1 Encl.Proprietary TR WCAP-13719 Withheld ML17353A4521995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Index to Delete Bases Re Administrative Controls & Reviews ML17353A4491995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs w/Line-Item 10.1 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation, Per GL 94-01 ML17353A3951995-10-0404 October 1995 Application for Amend to License DPR-31 & DPR-41,modifying Plant TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/ Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3811995-09-28028 September 1995 Application for Amends to Licenses DPR-31 & DPR-41, Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3511995-09-11011 September 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 10.1 from GL 93-05, Line-Item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation & Guidance in GL 94-01 ML17353A2811995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Per Selected Line Items from NRC GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation. ML17353A2771995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 ML17353A2741995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2711995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2681995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.1.3.1, Movable Control Assemblies - Group Height & 3/4.1.3.2, Position Indication Sys - Operating & Asociated Bases ML17353A2651995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Table 4.3-1 Re Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17352B1821995-05-23023 May 1995 Application for Amends to Licenses DPR-31 & DPR-41.Amends Would Use Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation Setpoints ML17352B0851995-03-30030 March 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot- Start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 ML17352B0001995-01-17017 January 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl ML17352A8361994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3.9.4 & 1.9,allowing Containment Personnel Airlock Doors to Be Opened During Core Operations & Movement of Irradiated Fuel in Containment ML17352A8291994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.4.9.1 to Remove Schedule for Withdrawal of Rv Matl Surveillance Specimens,Gl 91-01 ML17352A7221994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3.1.3.6, Reactivity Control Sys CR Insertion Limits, 3/4.2.2, Heat Flux Hot Channel Factor - Fq(Z) & 6.9.1.7, COLR & Associated Bases,Per GL 88-16.COLRs Encl ML17352A7301994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.7.1 & Associated Bases Which Address Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML17352A7271994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.8.1.1.2e & 4.8.1.1.2f Re EDG Fuel Oil Testing Program ML17352A5451994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.0.5a, Applicability - Srs, to Reflect Intent of Revised STS (NUREG-1431) for ISI & Testing Programs,In Accordance W/Recommendations in Draft NUREG-1482 ML17352A5421994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.6.2.1.d, CSS Surveillance Interval for Air or Smoke Flow Test Through CS Header from at Least Once Per 5 Yrs to at Least Once Per 10 Yrs,Per GL 93-05 & NUREG-1366 ML17352A4611994-02-18018 February 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.5.2.8, Audits by Deleting Frequencies Performed Under Cognizance of Nuclear Review Board,Per GL 93-07 ML17352A4351993-12-28028 December 1993 Application for Amends to Licenses DPR-31 & DPR-41,proposing Addition of SG Water Level - high-high Protection to TS Tables 3.3-2,3.3-3,4.3-2 & Associated Bases,In Accordance W/ Commitment to GL 89-19 for Resolution of USI A-47 ML17352A2621993-10-0404 October 1993 Application for Amend to Licenses DPR-31 & DPR-41 Revising Surveillance Requirement 4.6.1.2a & Associated Bases to Conform w/NUREG-1431,Standard Ts,Westinghouse Plants,Rev 0 ML17352A2201993-09-0303 September 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3/4.7.1.6, Standby FW Sys & Associated Bases to Eliminate Cranking DGs ML17352A2011993-08-17017 August 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising License Conditions 3.G & 3.F Respectively,To Conform to Std Fire Protection License Proposed as Stated in GL 86-10 ML17352A1061993-07-20020 July 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Definitions to Ensure Consistency W/New 10CFR20 Requirements & Changing Radiological Effluent Release Rept Frequency ML17349A8771993-05-21021 May 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 5.2.2, Design Pressure & Temp & Associated Bases to Correct Ref to Max Containment Design Internal Pressure from 59 Psig to 55 Psig 1999-07-27
[Table view] |
Text
REGULA JR A Y LNFORHATION 0 I STRI8U TIDIES SYSTEM (RIDS)
ACCESSION FACIL:5 0
<< 'rkey NaR;8}04270260 251 Point urKey Point Duc.nATE.:
Planti Unit chianti Unit 8}/O~/}7 3E OE Florida Florida NOTARIZED: YES Power and Light Power and Lignt C
C DOCKET 05000250 0500025}
AU AUTHOR At FILIATION UHRIGR R ~ E ~ Florioa Power 8 Light Co ~
RECIP ~ NAME RECIPIENr AFFILIATION EISENHUTED ~ G ~ Division of Licensing
SUBJECT:
Requests amends to Licenses DPR 31 h DPiA'} to specify scooe ot .steam generator insp program<acceptance criteria reoorting requirements, Request supplements 8}0402 reauest.
DISTRIBUTION CODE: AOO IS COPIES RECEIVED:LTR Ll ENCL + SIZE:
Nl/cffsQ RECIPIENT l
TITLE: Gener al Distr itiution for af ter Issuance
/00 oo
~
COPIFS
.
RECIPIENT of Operating License COPIES IO CODE/NAME i.TTR FNCL ID CODE/NAME LTTR ENCL ACTION: VAIiGAE S ~ OQ }3 13 INTERNAL: D/OIREHUH FACOS 1 1 DIRE DIV OF LIC 1 1 Iah, Oo 2 NRC PDR 02 1 1 OELD i} 1 0 0 AS ESS 8R 10 1 0 RAD AS>lT BR 1 1 G 01 1 = 1 EXTERNAL: ACRS 09 }0 16 LPDR 1 1 Nslc 05 1 1 II TOTAL NU'ABER OF COPIES REQUIRED: LTTR 40 ENCL 38
April 17, 1981 L-81-172 s,cO Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, D'irector Division of Licensing U.S. Nuclear Regulatory Commission Washington D.C. 20555
Dear Mr. Eisenhut:
Re: Turkey Point Units 3 5 4 r g Docket Nos. 50-250 and 50-251 t Proposed License Amendments In accordance with 10 CFR 50.30, Florida Power 8 Light Company submits herewith three signed originals and forty copies of a request to amend Facility Operating Licenses DPR-31 and DPR-41. This request supplements our request of April 2. 1981 (L-81-144).
The proposed amendment is described below and shown on the accompanying pages bearing the date of this letter in the, lower right hand corner.
The License conditions have been modified to specify in the license the scope of the steam generator inspection program and acceptance crit'eria and the reporting requirements. This amendment is administrative in nature since it does not change the technical content of the inspection and plugging program.
The proposed amendment has been revi.ewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board.
We have determined that since this request supplements the previous request but involves a duplicate amendment, the request should be classified as a Class I Amendment pursuant to 10 CFR 170. Accordingly, a check for $ 400 is enclosed.
Vice President Advanced Systems and Technology gooi REU/JEM/mbd 5 Attachment ~h cc: Mr. James P. O'Reilly, Region II ~/z~:
Harold F. Reis, Esquire g psn. nn
DPR-31 Page 3 B. Tech~nical S ecificaciona The Technical Specifications contain~d in Appendices A and B, as revis~d through Amendment No. 62 are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications..
C. ~Re orts FPL shall issue certain reports to the NRC in accordance with the requirements of the Technical Specifications.
D. Records FPL shall originate and maintain facility operating records in accordance with the requirements of the Technical Specifications.
E. Steam Generator Inspections
- 1. After operation of six equivalent full power months from the last inspection of all three steam generators Turkey Point Unit 3 shall be brought to the cold shutdown condition and al 1 three steam generators shall be inspected unless: (1) an inspection of the steam generators is performed within this period, or (2) an extention is granted by the NRC to authorize continued operation beyond the authorized period of operation. Any request for continued operation must be submitted at least 45 days prior to the expiration date of the authorized period of operation. For the purpose of this requirement, equivalent operation is defined as operation >>ith the reactor coolant at a temperature greater than 350"F.
- 2. Reactor coolant to secondary leakage through the steam generator tubes shall be limited to 0.3 gpm per steam generator. tlith a steam generator tube leakage greater than this limit. the reactor shall be brought to the cold shutdown condition within 24 hours and an inspection of the leaking steam generator shall be performed.
- 3. The concentration of radioiodine in the reactor coolant shall be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients.
- 4. If primary to secondary leakage attributable to the denting phenonmena is detected in 2 or more tubes during any 20 day period an inspection of the leaking steam generator shall be performed by the licensee.
- 5. The inspection and plugging results from 1, 2, or 4 above shall be submitted to the NRC no later than 14 days following the return to power operation. Any unusual results from the denting inspections shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. It in the inspections performed under regulatory position C.5 of Regulatory Guide 1.83, more than 10%
of the total tubes inspected have detectable wall penetration (>205) or more than three of the tubes inspected exceed the plugging limit, the inspection results shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4/17/8l
DPR-31 Page 4
- 6. The scope of the steam generator inspections (including eddy current, gauging and visual inspection) and tube plugging criteria shall be consistant with FPL letter L-80-412 dated December 18, 1980. The scope of the program shall be increased as appropriate to reflect operating experience and/or analysis.
- 7. Prior to resumption of power operation following inspections per 1, 2, and 4 above the licensee shall perform a 'safety analysis per 10 CFR 50 Section 59.
F. The licensee shall maintain in effect and fully implement all provisions of the Commission-approved phvsical securitv oian, includinq amendments and changes made pursuant to the authority of 10 CFR 50.54 (p). The approved security plan documents, witheld from public disclosure pursuant to 10 CFR 2.790(d), collectivelv titled "Turkev Point Plant Unit Nos. 3 and 4 ohvsical Securitv Plan". dated October 18. 1979. as sunnlemented Februarv 20. 1979.
G. The licensee mav nrnce~d wi th and is reaui r~d to orovide a schedule for and to comolete the modifications indentified in Paraaraohs 3.1.1 throuoh
- 3. 1.19 nf the NRC s Fire Pr nt~rtinn Safetv Evaluation. dated March 21, 1979 for the facility. These modifications are to be comoleted orior to December 1980. If anv modifications cannot be cnmnleted on schedule the licensee shall submit a reoort exolaininq the circumstances toaether with a revised schedule.
In addition. the licensee shall submit the additional information indentified in Sections 3.1 and 3.2 of the related Safetv Evaluation in accordance with the ~chedule rnnt~incd thar> in ln tha avant these dates for submittal cannot be met, the licensee shall submit a rennrt.
explaining the circumstances, together with a revised schedule.
The licensee is requi red to develop and implement the administrative controls which are consistent with the licensee's letters of August 28 and November 7, 1978 within three months from the date of this amendment.
H. Safeguards Contingency Plan The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Safequards Contingency Plan, including amendments and chanqes made pursuant to the authority of 10 CFR 50.54(p). The approved Continqency Plan consists of documents witheld from oublic disclosure oursuant to 10 CFR 2.790(d) and identified as "Turkev Point Plant Safequards Continaencv Plan" dated June 17, 1980 and submitted oursuant to 10 CFR 73.40. The Continaencv Plan shall be fullv imolemented. in accordance with 10 CFR 73.40(b). within 30 davs of this aonroval.
4/17/8l
DPR-41 D. Steam Generator Inspections Page 4 After operation of six equivalent full power months from the last inspection of all three steam generators, Turkey Point Unit 4 shall be brought to the cold shutdown condition and all three steam generaters shall be inspected unless" (1) an inspection of the steam generators is performed within this period, or (2) an extention is granted by the NRC to authorize continued operation beyond the authorized period of operation. Any request for continued operation must be submitted at least 45 days prior to the expiration date of the authorized period of operation. For the purpose of this requirement, equivalent operation is defined as operation with the reactor coolant at a temperature greater than 350'F.
- 2. Reactor coolant to secondary leakage through the steam generator tubes shall be limited to 0.3 gpm per steam generator. With a steam generator tube leakage greater than this limit, the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and an inspection of the leaking steam generator shall be performed.
- 3. The concentration of radioiodine in the reactor coolant shall'be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients.
4 If primary to secondary leakage attributable to the denting phenonmena is detected in 2 or more tubes during any 20 day period an inspection of the leaking steam generator shall be performed by the lic'ensee.
- 5. The Metal Impact Monitoring System (MIMS) shall be continued in operatio'n with the capability of detecting loose objects. If the MIMS is out of service in other than cold shutdown or refueling mode of operation, this fact shall be reported to the NRC. Any abnormal indications from the MIMS shall also be reported to the NRC by telephone by the next working day and by a written evaluation within two weeks.
- 6. Following each startup from below 350'F, core barrel movement shall be evaluated using Neutron Noise Technique.
- 7. The inspection and plugging results from 1, 2, or 4 above shall be submitted to the NRC no later than 14 days following the return to power operation. Any unusual results from the denting inspections shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If, in the inspections performed under regulatory position C.5 of Regulatory Guide 1.83, more than 105 of the total tubes inspected have detectable wall penetration (>205,) or more than three of the tubes inspected exceed the plugging limit, the inspection results shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 8. The scope of the steam generator inspections (including eddy current, guaging and visual inspection) and tube plugging criteria shall be consistant with FPL letter i-80-412 dated December 18, 1980. The scope of the program shall be increased as appropriate to reflect operating ri expe ence and/or anal ys i s.
- 9. Prior to resumption of power operation fol lowing inspections per 1, 2, and 4 above the licensee shall perform a safety analysis per 10 CFR 50 Section 59.
4/17/81
STATE OF FLORI DA )
) ss.
COUNTY OF DADE )
Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power & Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said 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 Licensee.
Robert E. Unrig Subscribed and sworn to before me this
~clay of NOTARY PUBLIC, and for the county of Dade, State of Florida I'
',
1 M'/ CdiTi l&ldrt Ptf8$ CCidd.r commission expires:
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