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| | issue date = 01/31/1982 | | | issue date = 01/31/1982 |
| | title = Tech Specs for Insp of Steam Generators,Turkey Point Units 3 & 4, Technical Evaluation Rept | | | title = Tech Specs for Insp of Steam Generators,Turkey Point Units 3 & 4, Technical Evaluation Rept |
| | author name = STEVENSON J A | | | author name = Stevenson J |
| | author affiliation = EG&G, INC. | | | author affiliation = EG&G, INC. |
| | addressee name = DONOHEW J N | | | addressee name = Donohew J |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000250, 05000251 | | | docket = 05000250, 05000251 |
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| {{#Wiki_filter:++E&g&Idaho.Inc.n FOAM EQXG4Sb (Aev.11 TPj INTERIM REPORT Accession No.Report No EGG-EA-5743 Contract Program or Project Title: Selected Operating Reactor Issues Program (III)Subject of this Document: Technical Specifications for the Inspection of Steam Generators, Turkey Point, Unit Nos.3 and 4 Type of Document: Technical Evaluation Report Author(s): | | {{#Wiki_filter:n E&g& |
| J.A.Steverson Date of Document: January 1982 Responsible NRC Individual and NRC Office or Division: J.N.Donohew, Division of Licensing This document was prepared primarily for preliminary or internal use.It has not received full review and approval.Since there may be substantive changes.this document should not be considered final.EGB G Idaho.Inc.Idaho Falls, Idaho 83415 Prepared for the U.S.Nuclear Regulatory Commission Washington, O.C.Under OOE Contract No.OE-AC07-76I001570 NRC FIN No A6429 INTERIM REPORT
| | ++ |
| /I j TECHNICAL SPECIFICATIONS FOR THE INSPECTION OF STEAM GENERATORS TURKEY POINT, UNIT NOS.3 ANO 4 Docket Nos.50-250, 50-251 January 1982 by J.A.Steverson Reliability and Statistics Branch Engineering Analysis Division EG&G Idaho, Inc.
| | FOAM EQXG4Sb Idaho. Inc. |
| ABSTRACT This report reviews the Turkey Point, Unit Nos.3 and 4 technical specifications for stean generator inspection.
| | (Aev. 11 TPj INTERIM REPORT Accession No. |
| FORD+D This report is supplied as part of the"Selected Operating Reactor Issues Program (III)" being conducted for.the U.S.Nuclear Regulatory Comnission, Office of Nuclear Reactor Regulation, Division of Licensing, by EG&G Idaho, Inc., Reliability and Statistics Br anch.The U.S.Nuclear Regulatory Commission funded the work under the authorization, MR 20 19 02 06, FIN No.A6429.
| | Report No EGG-EA-5743 Contract Program or Project |
| C>f,~
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| TECHNICAL EVALUATION REPORT TECHNICAL SPECIFICATIONS FOR THE INSPECTION OF STEAM GENERATORS K PO N UN NO.3 ANO 1.0 INTROOUCTION Turkey Point steam generator s have been inspected according to special license conditions imposed originally by Amendment 20, dated Oecember 3, 1976, for Unit'4 and by Amendment 22, dated January 14, 1977, for Unit 3.Thus, technical specifications for the inservice inspection of the steam generator tubes were not required.By letter, dated July 1, 1981, the NRC 1 requested Turkey Point 3 and 4 review their submittals and appropriately modify them, using as a guide the technical specifications for steam gener-ator inspection provided by the NRC.On Oecember 18, 1981, Florida Power and Light (FPEL)submitted pro-posed changes to their technical specifications (TS).The following 2 discussion evaluates the proposed Turkey Point TS and notes any differences existing between them and the NRC model TS.2.0 OISCUSS ION ANO EVALUATION Turkey Point, Units 3 and 4 are three loop Westinghouse PWR Plants.The specific sections of the Westinghouse Standard Technical Specifica-tions that apply to this task are as follows: 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.6 STEAM GENERATORS 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE The licensee proposed the following changes and incorporations to their technical specifications.
| |
| First, Specification 3.1.3.6 was revised and 3.1.3.g was added to incorporate limiting conditions for operation regarding primary-to-secondary leakage through steam generator tubes.This satisfies requirements 3.4.7.2.c and 3.4.7.2.d in the NRC standard TS.Secondly, a O.1 C>>
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| steam generator inspection program was added to the licensee's section on Reactor Coolant System Inservice Inspection.
| |
| The progr'am is in Section 4.2.5, Steam Generator Inspection, and in Tables 4.2-2 and 4.2-3 of their proposed TS and coincides with Section 3/4.4.6, Steam'Generators, and with Tables 4.4-1 and 4.4-2 of the Mestinghouse Standard TS.Also in the steam generator inspection p~ogram, the Mestinghouse Stan-dard TS in Section 4.4.6.3.a, Inspection Frequencies, require the first inservice inspection to be per formed after six effective full power nnnths but within 24 calendar months of initial criticality.
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| The licensee's cor-responding requirem nt in Section 4.2.5.3.a, requires the first inservice inspection to be performed after the first refueling following initial criticality or replacement of steam generators (whichever is later).3.0 CONCLUS ION The proposed TS submitted by FPQ.for Turkey Point, Units 3 and 4 included revisions and/or additions regarding (1)primary-to-secondary leakage through steam generator tubes, and (2)a steam generator inspection program.A basis for the steam generato~inspection was also added to the specification.
| |
| The TS proposed by Turkey Point are in agreement with the Westinghouse Standard TS with two exceptions.
| |
| The pr'eceeding evaluation noted (1)an omission in the Turkey Point TS concerning the inspection of the fir st sample of stean generator tubes, and (2)a difference in the timing of the first inservice inspection of a steam generator.
| |
| 4.0 R EFERENCES 1.NRC letter, S.A.Varga, to FP&L, R.E.Uhrig, dated July 1, 1981.2.FP5L letter, R.E.Uhrig, to NRC, D.G.Eisenhut, dated December 18, 1981.3.Standard Technical Specifications for Westinghouse PMRs, NUREG-0452, Rev.3, Fall 1980.
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| I~g~
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| 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS.50-250 AND 50-251 FLORIDA POWER AND LIGHT COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U.S.Nuclear Regulatory Commission (the Commission) has issued Amendment No.81 to Facility,Operating License No.DPR-31, and Amendment No.75 to Facility Operating License No.DPR-41 issued to Florida Power and Light Company'(the licensee), which revised Technical Specifications for operation of Turkey Point Plant, Unit Nos.3 and 4 (the facilities) located in Dade County, Florida.The amendments are effective as of the date of issuance.The amendments incorporate the steam generator inservice inspection requirements into the Techncial Specifications.
| |
| These specifications replace Facility Operating License No.DPR-31 condition 3.E for Unit 3 effective as of the date of this amendment and Facility Operating License No.DPR-41 condition 3.D for Unit 4 effective as of the date of completion of the steam generator replacement in Unit 4, The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
| |
| The Commission has, made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.
| |
| Prior public notice of these amendments has not required since the amendments do not involve a significant hazards consideration.
| |
| 7590-01-2-The Commission has determined that the issuance of these amendments will not result in any significant environmental impact'nd that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration 4 and environmental impact appraisal need not be prepared in connection with issuance of these amendments.
| |
| For further details with respect to this action, see (1)the application for amendments dated December 18, 1981, (2)Amendment Nos.81 and 75 to License Nos.DPR-31 and DPR-41, and (3)the Commission's related Safety Evaluation.
| |
| All of these items are available for public inspection at the Commission's Public Document Room, 1717.H Street, N.W., Washington, D.C.ll and at the Environmental and Urban Affairs Library, Florida International University, Miami, Florida 33199.A copy of items (2)and (3)may be obtained upon request addressed to the U.S.Nuclear Regulatory Commission, Washington, D.C.20555, Attention:
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| Director, Division of Licensing.
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| Dated at Bethesda, Maryland, this 24th day of March, 1982.F R THE NUC EGULATORY COMMISSION arga, C f Operating Reactors nch 81 Division of Licensing 1 II 4 o f A~
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| 4 I'J~.f'o~MAR 17 1982 Docket Nos.56~250 and 50-251 Dr.Robert E.Uhrig, Vice President Advanced Systems and Technology Florida Power and'ight Company Post Office Box 529100 Hiami, Florida 33152 These amendments revise the Technical Specifications to specify new power distribution limits for base load and radial burndown operation.
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| Itle have received you letter dated March 15, 1982 which satisfied the curr ent requirements of Technical Specification 6.9.3 for Unit 3.Such a r eport is not necessary for Unit 4 at this time because PT is not less than 1.Ile have found it necessary to make changes in certain of the Technical Specifications.
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| Ite have discussed the changes with your staff.They found the changes acceptable and the chhn)es have been incorporated.
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| Copies of the Safety Evaluation and the Notice of Issuance are a)sd enclosed.Sincerely,-D~GINAL SZCNK5~1 DI STRI B UTI ON Dockets MDunnel fel d NRC PDR Gray File L PDR J NSIC ORB¹l Rdg DEisenhut IE-2 ACRS-10 Q 8FQQ~~TBarnhart-8 g~~~4 LSchneider
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| ~p 8 jgap~DBrinkman OPA Tlpj'~@~ee"'RDiggs 6 NGrotenhuis CParrish
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| ==Dear Dr.Uhrig:== | | ==Title:== |
| l~1 ASLAB The Commission has issued the enclosed Amendment Ho.80 to Facility Operating License No.DPR-31 and Amendment No.74 to Facility Operating License No.DPR-41 for the Turkhy Point Plant Unit Hos.3 and 4, respectively. | | Selected Operating Reactor Issues Program (III) |
| The amendments consist of changes to the Technical Specifications in response to your application transmitted by letterrdated IIay 14, 1981, as supplemented November 23, 1981 and January 28, 1982. | | Subject of this Document: |
| | Technical Specifications for the Inspection of Steam Generators, Turkey Point, Unit Nos. 3 and 4 Type of Document: |
| | Technical Evaluation Report Author(s): |
| | J. A. Steverson Date of Document: |
| | January 1982 Responsible NRC Individual and NRC Office or Division: |
| | J. N. Donohew, Division of Licensing This document was prepared primarily for preliminary or internal use. It has not received full review and approval. Since there may be substantive changes. this document should not be considered final. |
| | EGB G Idaho. Inc. |
| | Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, O.C. |
| | Under OOE Contract No. OE-AC07-76I001570 NRC FIN No A6429 INTERIM REPORT |
| | |
| | / I j TECHNICAL SPECIFICATIONS FOR THE INSPECTION OF STEAM GENERATORS TURKEY POINT, UNIT NOS. 3 ANO 4 Docket Nos. 50-250, 50-251 January 1982 by J. A. Steverson Reliability and Statistics Branch Engineering Analysis Division EG&G Idaho, Inc. |
| | |
| | ABSTRACT This report reviews the Turkey Point, Unit Nos. 3 and 4 technical specifications for stean generator inspection. |
| | FORD+D This report is supplied as part of the "Selected Operating Reactor Issues Program (III)" being conducted for. the U.S. Nuclear Regulatory Comnission, Office of Nuclear Reactor Regulation, Division of Licensing, by EG&G Idaho, Inc., Reliability and Statistics Br anch. |
| | The U.S. Nuclear Regulatory Commission funded the work under the authorization, MR 20 19 02 06, FIN No. A6429. |
| | |
| | C> f, ~ |
| | TECHNICAL EVALUATION REPORT TECHNICAL SPECIFICATIONS FOR THE INSPECTION OF STEAM GENERATORS K PO N UN NO . 3 ANO |
| | : 1. 0 INTROOUCTION Turkey Point steam generator s have been inspected according to special license conditions imposed originally by Amendment 20, dated Oecember 3, 1976, for Unit '4 and by Amendment 22, dated January 14, 1977, for Unit 3. |
| | Thus, technical specifications for the inservice inspection of the steam 1 |
| | generator tubes were not required. By letter, dated July 1, 1981, the NRC requested Turkey Point 3 and 4 review their submittals and appropriately modify them, using as a guide the technical specifications for steam gener-ator inspection provided by the NRC. |
| | On Oecember 18, 1981, Florida Power and Light (FPEL) submitted pro-2 posed changes to their technical specifications (TS). The following discussion evaluates the proposed Turkey Point TS and notes any differences existing between them and the NRC model TS. |
| | 2.0 OISCUSS ION ANO EVALUATION Turkey Point, Units 3 and 4 are three loop Westinghouse PWR Plants. |
| | The specific sections of the Westinghouse Standard Technical Specifica-tions that apply to this task are as follows: |
| | 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.6 STEAM GENERATORS 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE The licensee proposed the following changes and incorporations to their technical specifications. First, Specification 3.1.3.6 was revised and |
| | : 3. 1.3.g was added to incorporate limiting conditions for operation regarding primary-to-secondary leakage through steam generator tubes. This satisfies requirements 3.4.7.2.c and 3.4.7.2.d in the NRC standard TS. Secondly, a |
| | |
| | O. 1 C>> |
| | steam generator inspection program was added to the licensee's section on Reactor Coolant System Inservice Inspection. The progr'am is in Section 4.2.5, Steam Generator Inspection, and in Tables 4.2-2 and 4.2-3 of their proposed TS and coincides with Section 3/4.4.6, Steam'Generators, and with Tables 4.4-1 and 4.4-2 of the Mestinghouse Standard TS. |
| | Also in the steam generator inspection p~ogram, the Mestinghouse Stan-dard TS in Section 4.4.6.3.a, Inspection Frequencies, require the first inservice inspection to be per formed after six effective full power nnnths but within 24 calendar months of initial criticality. The licensee's cor-responding requirem nt in Section 4.2.5.3.a, requires the first inservice inspection to be performed after the first refueling following initial criticality or replacement of steam generators (whichever is later). |
| | : 3. 0 CONCLUS ION The proposed TS submitted by FPQ. for Turkey Point, Units 3 and 4 included revisions and/or additions regarding (1) primary-to-secondary leakage through steam generator tubes, and (2) a steam generator inspection program. A basis for the steam generato~ inspection was also added to the specification. |
| | The TS proposed by Turkey Point are in agreement with the Westinghouse Standard TS with two exceptions. The pr'eceeding evaluation noted (1) an omission in the Turkey Point TS concerning the inspection of the fir st sample of stean generator tubes, and (2) a difference in the timing of the first inservice inspection of a steam generator. |
| | : 4. 0 R EFERENCES |
| | : 1. NRC letter, S. A. Varga, to FP&L, R. E. Uhrig, dated July 1, 1981. |
| | : 2. FP5L letter, R. E. Uhrig, to NRC, D. G. Eisenhut, dated December 18, 1981. |
| | : 3. Standard Technical Specifications for Westinghouse PMRs, NUREG-0452, Rev. 3, Fall 1980. |
| | |
| | I~ g ~ |
| | 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-250 AND 50-251 FLORIDA POWER AND LIGHT COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 81 to Facility,Operating License No. DPR-31, and Amendment No. 75 to Facility Operating License No. DPR-41 issued to Florida Power and Light Company'(the licensee), which revised Technical Specifications for operation of Turkey Point Plant, Unit Nos. 3 and 4 (the facilities) located in Dade County, Florida. The amendments are effective as of the date of issuance. |
| | The amendments incorporate the steam generator inservice inspection requirements into the Techncial Specifications. These specifications replace Facility Operating License No. DPR-31 condition 3.E for Unit 3 effective as of the date of this amendment and Facility Operating License No. DPR-41 condition 3.D for Unit 4 effective as of the date of completion of the steam generator replacement in Unit 4, The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has, made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments. Prior public notice of these amendments has not required since the amendments do not involve a significant hazards consideration. |
| | |
| | 7590-01 The Commission has determined that the issuance of these amendments will not result in any significant environmental impact'nd that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration 4 |
| | and environmental impact appraisal need not be prepared in connection with issuance of these amendments. |
| | For further details with respect to this action, see (1) the application for amendments dated December 18, 1981, (2) Amendment Nos. 81 and 75 to License Nos. DPR-31 and DPR-41, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Document Room, 1717. H Street, N.W., Washington, ll D.C. |
| | and at the Environmental and Urban Affairs Library, Florida International University, Miami, Florida 33199. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Director, Division of Licensing. |
| | Dated at Bethesda, Maryland, this 24th day of March, 1982. |
| | F R THE NUC EGULATORY COMMISSION arga, C f Operating Reactors nch 81 Division of Licensing |
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| | o f A ~ |
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| | ~. 'o f ~ |
| | ~1 DI STRI B UTI ON Dockets MDunnel fel d NRC PDR Gray File L PDR J |
| | MAR 17 1982 NSIC Docket Nos. 56~250 ORB¹l Rdg and 50-251 DEisenhut IE-2 ACRS-10 Dr. Robert E. Uhrig, Vice President Q 8FQQ~~ TBarnhart-8 Advanced Systems and Technology |
| | ~ 4 LSchneider g~~ 8 DBrinkman Florida Power and'ight Company ~p jgap~ |
| | OPA Post Office Box 529100 '~@~ee "' |
| | Hiami, Florida 33152 Tlpj RDiggs 6 NGrotenhuis |
| | |
| | ==Dear Dr. Uhrig:== |
| | l CParrish |
| | ~ 1 ASLAB The Commission has issued the enclosed Amendment Ho. 80 to Facility Operating License No. DPR-31 and Amendment No. 74 to Facility Operating License No. |
| | DPR-41 for the Turkhy Point Plant Unit Hos. 3 and 4, respectively. The amendments consist of changes to the Technical Specifications in response to your application transmitted by letterrdated IIay 14, 1981, as supplemented November 23, 1981 and January 28, 1982. |
| | These amendments revise the Technical Specifications to specify new power distribution limits for base load and radial burndown operation. |
| | Itle have received you letter dated March 15, 1982 which satisfied the curr ent requirements of Technical Specification 6.9.3 for Unit 3. Such a r eport is not necessary for Unit 4 at this time because PT is not less than 1. |
| | Ile have found it necessary to make changes in certain of the Technical Specifications. Ite have discussed the changes with your staff. They found the changes acceptable and the chhn)es have been incorporated. |
| | Copies of the Safety Evaluation and the Notice of Issuance are a)sd enclosed. |
| | Sincerely, |
| | -D~GINAL SZCNK5 tlarshall Grotenhuis, Project Manager Operating Reactors Branch ¹1 Division of Licensing |
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| ==Enclosures:== | | ==Enclosures:== |
| | : l. Amendment Ho. 80 to DPR-31 |
| | : 2. Amendment No. 74 to DPR-41 |
| | : 3. Safety Evaluation |
| | : 4. Notice of Issuance % |
| | ()y)0 cc w/enclosures: |
| | *Previous concur rence see next page ORB¹1:DL* ORB¹1:DL* ORB¹l:DL* AD/OR:DL* OELD* |
| | OFFICE/ |
| | SURNAME/ ~~~ |
| | CParrish |
| | ~ ~~ ~ ~ ~ ~ ~ ~ ~0 ~~~ ~ |
| | MGrotenhui s SYarga Tt(oyak |
| | '~ OATEN |
| | ;.NI..../BZ.... .OA/.(Q/82.;dr ...03.I.....N.? .. k3/..../k2 ,,03K, J82 NR( |
| | O'FORM318 1080 ) NRCM0240,'Il'<'",'i'i- '' "< "OFFICIAL RECORD COPY VSOPO: 1991~960 |
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| l.Amendment Ho.80 to 2.Amendment No.74 to 3.Safety Evaluation 4.Notice of Issuance DPR-31 DPR-41 tlarshall Grotenhuis, Project Manager Operating Reactors Branch¹1 Division of Licensing ()y)0%cc w/enclosures:
| | DISTRIBUTION Dockets ASLAB NRC PDR Gray File L PDR MDunnenfeld TERA Docket Nos. 60-260 NSIC and 50-251 ORBkl Rdg DEisenhut OELD IE-4 ACRS-10 GDeegan-8 LSnyder DBrinkman OPA RDiggs |
| *Previous concur rence see next page ORB¹1:DL*OFFICE/SURNAME/CParrish'~OATEN~~~~~~~~~~~~~0~~~~;.NI..../BZ....
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| MGrotenhui s.OA/.(Q/82.;dr SYarga...03.I.....N.?
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| ..ORB¹1:DL*ORB¹l:DL*AD/OR:DL*Tt(oyak k3/..../k2 OELD*,,03K, J82 O'FORM318 1080 NRCM0240,'Il'<'",'i'i-
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| ''"<"OFFICIAL RECORD COPY NR()VSOPO: 1991~960 f 1'1 1 II tt Docket Nos.60-260 and 50-251 Copies of the Safety Evaluation and the Notice of Issuance are alsoeenclosed.
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| Sincer ely, DISTRIBUTION Dockets ASLAB NRC PDR Gray File L PDR MDunnenfeld TERA NSIC ORBkl Rdg DEisenhut OELD IE-4 ACRS-10 GDeegan-8 LSnyder DBrinkman OPA RDiggs
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| ==Dear Dr.Uhrig:== | | ==Dear Dr. Uhrig:== |
| MGrotenhuis CParrish The Commission has iqqued the enclosed Amendment No.to Facility Operating License f(o.DPR-31 and Amendment No.to Facility Operating License No.DPR-41 for the Turkey Point Plant Unit Nos.3 and 4, respectively. | | MGrotenhuis CParrish The Commission has iqqued the enclosed Amendment No. to Facility Operating License f(o. DPR-31 and Amendment No. to Facility Operating License No. |
| The amendments consist of changes to the Technical Specifications in response to your application transmitted by letter dated May 14, 1987, as supplemented November 23, 1981 and January 28, 1982.These amendments revise the Technical Specifications related to base, load and radial burndown. | | DPR-41 for the Turkey Point Plant Unit Nos. 3 and 4, respectively. The amendments consist of changes to the Technical Specifications in response to your application transmitted by letter dated May 14, 1987, as supplemented November 23, 1981 and January 28, 1982. |
| | These amendments revise the Technical Specifications related to base, load and radial burndown. |
| | Copies of the Safety Evaluation and the Notice of Issuance are alsoeenclosed. |
| | Sincer ely, Marshall Grotenhuis, Project Manager Operating Reactors Branch 01 Division of Licensing |
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| ==Enclosures:== | | ==Enclosures:== |
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| '1.Amendment No.to DPR-31 2."Amendment No.to DPR-41 3.Safety Evaluation 4.Notice of Issuance Marshall Grotenhuis, Project Manager Operating Reactors Branch 01 Division of Licensing cc v(/enclosures: | | '1. Amendment No. to DPR-31 |
| See next page OFFICE I 8 UR NAME II ORB A'1: DL CParrish~.np,/'R/Rp DATE f~~o'@~a~~~~~~~RB81: L HGrotenhui s g2J]J82:ds R~~~r~~02 TNo~~~0~~~\~~~~QP./82 OELD 02 (g/82 NRC FORM 318 (10-80)NRCM'0240 OFFICIAL RECORD COPY USGPO: 1991~9-960 1~4~~ | | : 2. "Amendment No. to DPR-41 |
| Robert"=.Uhrig Florida Power and Light Company CC: fir.Robert Lowenstein, Esquire Lowenstein, Newman, Reis and Axelrad 1025 Connecticut Avenue, N.M.Sui te'1214 Vashington, D.C.2"-035 Environmental and Urban Affairs Library Florida International University Miami, Florida 33199 Hr.t<orman A.Coll, Esquire.Steel, Hector and Davis 1400 Southeast First, National Bank Building Miami, Florida 33131 h1r.Henry Yaeger, Plant Manager Turkey Point Plant Florida Power and L~ht Company P.0.Box 013100 Miami, Florida 33101 Honorable Dewey Knight County tianager of Metropolitan Dade County t'li ami, Florida 33130 Bureau of Intergovernmental Relations 560 Apalachee Parkway Tallahassee, Florida 32304 Resident Inspector Turkey Point nuclear Generating Station U.S.nuclear Regulatory Commission Post Office Box 1207 Homestead, Florida 33030 Regional Radiation Pepresentative EPA Region IV 345 Courtland Street, H.M.Atlanta;Georgia 30308 her.Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee; Florida 32304 Admini strator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 James P.O'Reilly Regional Administrator | | : 3. Safety Evaluation |
| -Region II U.S.Nuclear Regulatory Commission 101 Marietta Street-Suite 3100 Atlanta, Georgia 30303 T}}
| | : 4. Notice of Issuance cc v(/enclosures: |
| | See next page ORB A'1: DL OFFICE I RB81: L ~ |
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| | r OELD 8 UR NAME II CParrish ~ . HGrotenhui s TNo |
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| | 'R/Rp np,/ @~a ~ ~ ~ ~ ~ ~ ~ g2J J82:ds 02 ~ |
| | QP. /82 02 (g/82 NRC FORM 318 (10-80) NRCM'0240 OFFICIAL RECORD COPY USGPO: 1991~9-960 |
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| | Robert "=. Uhrig Florida Power and Light Company CC: fir. Robert Lowenstein, Esquire her. Jack Shreve Lowenstein, Newman, Reis and Axelrad Office of the Public Counsel 1025 Connecticut Avenue, N.M. Room 4, Holland Building Sui te'1214 Tallahassee; Florida 32304 Vashington, D. C. 2"-035 Admini strator Environmental and Urban Affairs Library Department of Environmental Florida International University Regulation Miami, Florida 33199 Power Plant Siting Section State of Florida Hr. t<orman A. Coll, Esquire. 2600 Blair Stone Road Steel, Hector and Davis Tallahassee, Florida 32301 1400 Southeast First, National Bank Building James P. O'Reilly Miami, Florida 33131 Regional Administrator - Region II U. S. Nuclear Regulatory Commission h1r. Henry Yaeger, Plant Manager 101 Marietta Street - Suite 3100 Turkey Point Plant Atlanta, Georgia 30303 Florida Power and L~ht Company P. 0. Box 013100 Miami, Florida 33101 Honorable Dewey Knight County tianager of Metropolitan Dade County t'li ami, Florida 33130 Bureau of Intergovernmental Relations 560 Apalachee Parkway Tallahassee, Florida 32304 Resident Inspector Turkey Point nuclear Generating Station U. S. nuclear Regulatory Commission Post Office Box 1207 Homestead, Florida 33030 Regional Radiation Pepresentative EPA Region IV 345 Courtland Street, H.M. |
| | Atlanta; Georgia 30308 |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML17355A2801998-09-30030 September 1998
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ML17349A4171991-12-21021 December 1991
IPE Back-End Audit,Task 3,Technical Evaluation Rept,December 21,1991,Rev 1
ML17349A4151991-12-21021 December 1991
Ipe:Front End Audit.
ML17348B1241991-07-31031 July 1991
Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Turkey Point,Units 3 & 4.
ML20043F6331990-06-11011 June 1990
Technical Evaluation Rept Turkey Point Units 2 & 3 Station Blackout Evaluation, Final Rept
ML20058K1031989-05-30030 May 1989
Conformance to Generic Ltr 83-28,Item 2.2-1 - Equipment Classification for All Other Safety-Related Components, Turkey Point-3/-4, Technical Evaluation Rept
ML17347A5931987-07-31031 July 1987
Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept
ML17342A7541987-06-30030 June 1987
Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Turkey Point 3 & 4, Final Rept
ML17342A7641987-06-30030 June 1987
TMI Action-NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Turkey Point Units 3 & 4, Informal Technical Evaluation Rept
ML20211N5031987-01-0909 January 1987
Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept
ML20198A2481986-04-0404 April 1986
Metallurgical Failure Analysis of Check Valve Guide Pin
ML20138J9491985-09-30030 September 1985
Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Farley Units 1 & 2,Turkey Point Units 3 & 4,Robinson Unit 2 & Summer Unit 1
ML17342A3571985-09-30030 September 1985
Addendum a to First Interval Inservice Insp Program for Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17342A3341985-09-30030 September 1985
Inservice Insp Program,Second Interval Technical Evaluation Rept.
ML17342A1601985-07-19019 July 1985
Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic...), Item 1.2., `Post-Trip Review:Data & Info Capability,' for Turkey Point Plant..., Technical Evaluation Rept
ML20244D3871985-07-10010 July 1985
Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant.
ML20244D4381985-06-30030 June 1985
Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities
ML20111B1661984-12-0505 December 1984
Masonry Wall Design, Technical Evaluation Rept
ML20080E0711984-01-13013 January 1984
Evaluations of Detailed Control Room Design Reviews for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20080Q5131983-10-10010 October 1983
Control of Heavy Loads (C-10),Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20079Q6871983-03-14014 March 1983
Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept
ML17354A2561983-02-14014 February 1983
Post-Fire Safe Shutdown Capability, Technical Evaluation Rept
ML20072B1201983-01-0606 January 1983
Control of Heavy Loads (C-10),Turkey Point Units 3 & 4, Draft Technical Evaluation Rept.Request for Addl Info Encl
ML20076C3691982-11-29029 November 1982
ECCS Repts (F-47):TMI Action Plan Requirements,Turkey Point,Units 3 & 4, Technical Evaluation Rept
ML17341B4711982-10-28028 October 1982
Proposed Design Mod & Tech Spec Changes on Grid Voltage Degradation for Turkey Point Nuclear Generating Plant, Units 3 & 4, Technical Evaluation Rept
ML20069G5861982-09-30030 September 1982
Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Turkey Point Unit 4, Vols 1 & 2,technical Evaluation Rept
ML17345B2391982-09-17017 September 1982
Seismic Qualification of Auxiliary Feedwater Sys,Turkey Point Nuclear Plant,Units 3 & 4, Technical Evaluation Rept
ML20023A4891982-09-10010 September 1982
Inservice Insp Program, Technical Evaluation Rept
ML17341B4661982-08-31031 August 1982
Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Turkey Point,Units 3 & 4, Technical Evaluation Rept
ML20071L7081982-08-0808 August 1982
Adequacy of Station Electric Distribution Sys Voltages for Turkey Point Nuclear Generating Plant Units 3 & 4, Technical Evaluation Rept
ML17341B4001982-06-18018 June 1982
Auxiliary Feedwater Sys Automatic Initiation & Flow Indication,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20052F6841982-02-28028 February 1982
Tech Specs for Redundant Decay Heat Removal Capability, Turkey Point,Units 3 & 4, Preliminary Rept for Feb 1982
ML17341A9181982-01-31031 January 1982
Tech Specs for Insp of Steam Generators,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17341A8291981-12-29029 December 1981
Control of Heavy Loads, Draft Technical Evaluation Rept
ML20038D1341981-12-11011 December 1981
Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.
ML20039A1691981-12-11011 December 1981
Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.
ML17341A2081981-06-0505 June 1981
Containment Leakage Rate Testing,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20003C2581981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Crystal River Nuclear Power Plant,Unit 3.
ML20003C2611981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Indian Point 3 Nuclear Power Plant.
ML17340A7621981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Turkey Point Nuclear Power Station,Units 3 & 4.
ML19336A4071980-09-30030 September 1980
In-Plant Source Term Measurements at Turkey Point Station Units 3 & 4.
ML17339B1191980-05-31031 May 1980
Proposed Amend to Facility OLs DPR-31 & DPR-41,Delta T Vs Reactor Power Shift Check,Turkey Point Units 3 & 4, Informal Rept
1998-09-30
[Table view]
Category:QUICK LOOK
MONTHYEARML17355A2801998-09-30030 September 1998
Rev 1,Ltr Rept, Technical Evaluation of Florida Power & Light Fire Barrier Ampacity Derating Assessment for St.Lucie & Turkey Point.
ML17354B1731998-01-31031 January 1998
Final TER on 'Submittal-Only' Review of IPEEE at Turkey Point Nuclear Plant Units 3 & 4.
ML17353A4031995-09-30030 September 1995
Evaluation of Turkey Point Nuclear Plant Units 3 & 4 Offsite Dose Calculation Manual,Rev 4.
ML20080K1101995-02-28028 February 1995
Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan:Florida Power & Light Co,Turkey Point Nuclear Power Plant,Units 3 & 4
ML20076K9841994-09-30030 September 1994
Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01:Turkey Point-3/4, Technical Evaluation Rept
ML20076F2701994-09-30030 September 1994
Fpl,Pump & Valve Inservice Testing Program,Rev 0,Third Ten-Year Interval
ML20114A6001992-08-31031 August 1992
TER Pump & Valve Inservice Testing Program Turkey Point, Units 3 & 4
ML17349A2131992-04-30030 April 1992
Auxiliary Feedwater System RISK-BASED Inspection Guide for the Turkey Point Nuclear Power Plant
ML17349A4181991-12-31031 December 1991
Step 2 Review,Turkey Point Units 3 & 4 IPE Submittal, Human Reliability Analysis
ML17349A4171991-12-21021 December 1991
IPE Back-End Audit,Task 3,Technical Evaluation Rept,December 21,1991,Rev 1
ML17349A4151991-12-21021 December 1991
Ipe:Front End Audit.
ML17348B1241991-07-31031 July 1991
Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Turkey Point,Units 3 & 4.
ML20043F6331990-06-11011 June 1990
Technical Evaluation Rept Turkey Point Units 2 & 3 Station Blackout Evaluation, Final Rept
ML20058K1031989-05-30030 May 1989
Conformance to Generic Ltr 83-28,Item 2.2-1 - Equipment Classification for All Other Safety-Related Components, Turkey Point-3/-4, Technical Evaluation Rept
ML17347A5931987-07-31031 July 1987
Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept
ML17342A7541987-06-30030 June 1987
Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Turkey Point 3 & 4, Final Rept
ML17342A7641987-06-30030 June 1987
TMI Action-NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Turkey Point Units 3 & 4, Informal Technical Evaluation Rept
ML20211N5031987-01-0909 January 1987
Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept
ML20198A2481986-04-0404 April 1986
Metallurgical Failure Analysis of Check Valve Guide Pin
ML20138J9491985-09-30030 September 1985
Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Farley Units 1 & 2,Turkey Point Units 3 & 4,Robinson Unit 2 & Summer Unit 1
ML17342A3571985-09-30030 September 1985
Addendum a to First Interval Inservice Insp Program for Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17342A3341985-09-30030 September 1985
Inservice Insp Program,Second Interval Technical Evaluation Rept.
ML17342A1601985-07-19019 July 1985
Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic...), Item 1.2., `Post-Trip Review:Data & Info Capability,' for Turkey Point Plant..., Technical Evaluation Rept
ML20244D3871985-07-10010 July 1985
Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant.
ML20244D4381985-06-30030 June 1985
Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities
ML20111B1661984-12-0505 December 1984
Masonry Wall Design, Technical Evaluation Rept
ML20080E0711984-01-13013 January 1984
Evaluations of Detailed Control Room Design Reviews for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20080Q5131983-10-10010 October 1983
Control of Heavy Loads (C-10),Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20079Q6871983-03-14014 March 1983
Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept
ML17354A2561983-02-14014 February 1983
Post-Fire Safe Shutdown Capability, Technical Evaluation Rept
ML20072B1201983-01-0606 January 1983
Control of Heavy Loads (C-10),Turkey Point Units 3 & 4, Draft Technical Evaluation Rept.Request for Addl Info Encl
ML20076C3691982-11-29029 November 1982
ECCS Repts (F-47):TMI Action Plan Requirements,Turkey Point,Units 3 & 4, Technical Evaluation Rept
ML17341B4711982-10-28028 October 1982
Proposed Design Mod & Tech Spec Changes on Grid Voltage Degradation for Turkey Point Nuclear Generating Plant, Units 3 & 4, Technical Evaluation Rept
ML20069G5861982-09-30030 September 1982
Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Turkey Point Unit 4, Vols 1 & 2,technical Evaluation Rept
ML17345B2391982-09-17017 September 1982
Seismic Qualification of Auxiliary Feedwater Sys,Turkey Point Nuclear Plant,Units 3 & 4, Technical Evaluation Rept
ML20023A4891982-09-10010 September 1982
Inservice Insp Program, Technical Evaluation Rept
ML17341B4661982-08-31031 August 1982
Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Turkey Point,Units 3 & 4, Technical Evaluation Rept
ML20071L7081982-08-0808 August 1982
Adequacy of Station Electric Distribution Sys Voltages for Turkey Point Nuclear Generating Plant Units 3 & 4, Technical Evaluation Rept
ML17341B4001982-06-18018 June 1982
Auxiliary Feedwater Sys Automatic Initiation & Flow Indication,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20052F6841982-02-28028 February 1982
Tech Specs for Redundant Decay Heat Removal Capability, Turkey Point,Units 3 & 4, Preliminary Rept for Feb 1982
ML17341A9181982-01-31031 January 1982
Tech Specs for Insp of Steam Generators,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17341A8291981-12-29029 December 1981
Control of Heavy Loads, Draft Technical Evaluation Rept
ML20038D1341981-12-11011 December 1981
Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.
ML20039A1691981-12-11011 December 1981
Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.
ML17341A2081981-06-0505 June 1981
Containment Leakage Rate Testing,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20003C2581981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Crystal River Nuclear Power Plant,Unit 3.
ML20003C2611981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Indian Point 3 Nuclear Power Plant.
ML17340A7621981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Turkey Point Nuclear Power Station,Units 3 & 4.
ML19336A4071980-09-30030 September 1980
In-Plant Source Term Measurements at Turkey Point Station Units 3 & 4.
ML17339B1191980-05-31031 May 1980
Proposed Amend to Facility OLs DPR-31 & DPR-41,Delta T Vs Reactor Power Shift Check,Turkey Point Units 3 & 4, Informal Rept
1998-09-30
[Table view]
Category:ETC. (PERIODIC
MONTHYEARML17355A2801998-09-30030 September 1998
Rev 1,Ltr Rept, Technical Evaluation of Florida Power & Light Fire Barrier Ampacity Derating Assessment for St.Lucie & Turkey Point.
ML17354B1731998-01-31031 January 1998
Final TER on 'Submittal-Only' Review of IPEEE at Turkey Point Nuclear Plant Units 3 & 4.
ML17353A4031995-09-30030 September 1995
Evaluation of Turkey Point Nuclear Plant Units 3 & 4 Offsite Dose Calculation Manual,Rev 4.
ML20080K1101995-02-28028 February 1995
Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan:Florida Power & Light Co,Turkey Point Nuclear Power Plant,Units 3 & 4
ML20076K9841994-09-30030 September 1994
Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01:Turkey Point-3/4, Technical Evaluation Rept
ML20076F2701994-09-30030 September 1994
Fpl,Pump & Valve Inservice Testing Program,Rev 0,Third Ten-Year Interval
ML20114A6001992-08-31031 August 1992
TER Pump & Valve Inservice Testing Program Turkey Point, Units 3 & 4
ML17349A2131992-04-30030 April 1992
Auxiliary Feedwater System RISK-BASED Inspection Guide for the Turkey Point Nuclear Power Plant
ML17349A4181991-12-31031 December 1991
Step 2 Review,Turkey Point Units 3 & 4 IPE Submittal, Human Reliability Analysis
ML17349A4171991-12-21021 December 1991
IPE Back-End Audit,Task 3,Technical Evaluation Rept,December 21,1991,Rev 1
ML17349A4151991-12-21021 December 1991
Ipe:Front End Audit.
ML17348B1241991-07-31031 July 1991
Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Turkey Point,Units 3 & 4.
ML20043F6331990-06-11011 June 1990
Technical Evaluation Rept Turkey Point Units 2 & 3 Station Blackout Evaluation, Final Rept
ML20058K1031989-05-30030 May 1989
Conformance to Generic Ltr 83-28,Item 2.2-1 - Equipment Classification for All Other Safety-Related Components, Turkey Point-3/-4, Technical Evaluation Rept
ML17347A5931987-07-31031 July 1987
Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept
ML17342A7541987-06-30030 June 1987
Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Turkey Point 3 & 4, Final Rept
ML17342A7641987-06-30030 June 1987
TMI Action-NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Turkey Point Units 3 & 4, Informal Technical Evaluation Rept
ML20211N5031987-01-0909 January 1987
Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept
ML20198A2481986-04-0404 April 1986
Metallurgical Failure Analysis of Check Valve Guide Pin
ML20138J9491985-09-30030 September 1985
Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Farley Units 1 & 2,Turkey Point Units 3 & 4,Robinson Unit 2 & Summer Unit 1
ML17342A3571985-09-30030 September 1985
Addendum a to First Interval Inservice Insp Program for Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17342A3341985-09-30030 September 1985
Inservice Insp Program,Second Interval Technical Evaluation Rept.
ML17342A1601985-07-19019 July 1985
Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic...), Item 1.2., `Post-Trip Review:Data & Info Capability,' for Turkey Point Plant..., Technical Evaluation Rept
ML20244D3871985-07-10010 July 1985
Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant.
ML20244D4381985-06-30030 June 1985
Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities
ML20111B1661984-12-0505 December 1984
Masonry Wall Design, Technical Evaluation Rept
ML20080E0711984-01-13013 January 1984
Evaluations of Detailed Control Room Design Reviews for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20080Q5131983-10-10010 October 1983
Control of Heavy Loads (C-10),Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20079Q6871983-03-14014 March 1983
Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept
ML17354A2561983-02-14014 February 1983
Post-Fire Safe Shutdown Capability, Technical Evaluation Rept
ML20072B1201983-01-0606 January 1983
Control of Heavy Loads (C-10),Turkey Point Units 3 & 4, Draft Technical Evaluation Rept.Request for Addl Info Encl
ML20076C3691982-11-29029 November 1982
ECCS Repts (F-47):TMI Action Plan Requirements,Turkey Point,Units 3 & 4, Technical Evaluation Rept
ML17341B4711982-10-28028 October 1982
Proposed Design Mod & Tech Spec Changes on Grid Voltage Degradation for Turkey Point Nuclear Generating Plant, Units 3 & 4, Technical Evaluation Rept
ML20069G5861982-09-30030 September 1982
Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Turkey Point Unit 4, Vols 1 & 2,technical Evaluation Rept
ML17345B2391982-09-17017 September 1982
Seismic Qualification of Auxiliary Feedwater Sys,Turkey Point Nuclear Plant,Units 3 & 4, Technical Evaluation Rept
ML20023A4891982-09-10010 September 1982
Inservice Insp Program, Technical Evaluation Rept
ML17341B4661982-08-31031 August 1982
Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Turkey Point,Units 3 & 4, Technical Evaluation Rept
ML20071L7081982-08-0808 August 1982
Adequacy of Station Electric Distribution Sys Voltages for Turkey Point Nuclear Generating Plant Units 3 & 4, Technical Evaluation Rept
ML17341B4001982-06-18018 June 1982
Auxiliary Feedwater Sys Automatic Initiation & Flow Indication,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20052F6841982-02-28028 February 1982
Tech Specs for Redundant Decay Heat Removal Capability, Turkey Point,Units 3 & 4, Preliminary Rept for Feb 1982
ML17341A9181982-01-31031 January 1982
Tech Specs for Insp of Steam Generators,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17341A8291981-12-29029 December 1981
Control of Heavy Loads, Draft Technical Evaluation Rept
ML20038D1341981-12-11011 December 1981
Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.
ML20039A1691981-12-11011 December 1981
Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.
ML17341A2081981-06-0505 June 1981
Containment Leakage Rate Testing,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20003C2581981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Crystal River Nuclear Power Plant,Unit 3.
ML20003C2611981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Indian Point 3 Nuclear Power Plant.
ML17340A7621981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Turkey Point Nuclear Power Station,Units 3 & 4.
ML19336A4071980-09-30030 September 1980
In-Plant Source Term Measurements at Turkey Point Station Units 3 & 4.
ML17339B1191980-05-31031 May 1980
Proposed Amend to Facility OLs DPR-31 & DPR-41,Delta T Vs Reactor Power Shift Check,Turkey Point Units 3 & 4, Informal Rept
1998-09-30
[Table view]
Category:RESEARCH AND TECHNICAL ASSISTANCE REPORTS
MONTHYEARML20052F6841982-02-28028 February 1982
Tech Specs for Redundant Decay Heat Removal Capability, Turkey Point,Units 3 & 4, Preliminary Rept for Feb 1982
ML17341A9181982-01-31031 January 1982
Tech Specs for Insp of Steam Generators,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17339B1191980-05-31031 May 1980
Proposed Amend to Facility OLs DPR-31 & DPR-41,Delta T Vs Reactor Power Shift Check,Turkey Point Units 3 & 4, Informal Rept
1982-02-28
[Table view]
Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML17355A2801998-09-30030 September 1998
Rev 1,Ltr Rept, Technical Evaluation of Florida Power & Light Fire Barrier Ampacity Derating Assessment for St.Lucie & Turkey Point.
ML17354B1731998-01-31031 January 1998
Final TER on 'Submittal-Only' Review of IPEEE at Turkey Point Nuclear Plant Units 3 & 4.
ML17353A4031995-09-30030 September 1995
Evaluation of Turkey Point Nuclear Plant Units 3 & 4 Offsite Dose Calculation Manual,Rev 4.
ML20080K1101995-02-28028 February 1995
Technical Evaluation Rept on Third 10-yr Interval Inservice Insp Program Plan:Florida Power & Light Co,Turkey Point Nuclear Power Plant,Units 3 & 4
ML20076K9841994-09-30030 September 1994
Evaluation of Utility Response to Suppl 1 to NRC Bulletin 90-01:Turkey Point-3/4, Technical Evaluation Rept
ML20076F2701994-09-30030 September 1994
Fpl,Pump & Valve Inservice Testing Program,Rev 0,Third Ten-Year Interval
ML20114A6001992-08-31031 August 1992
TER Pump & Valve Inservice Testing Program Turkey Point, Units 3 & 4
ML17349A2131992-04-30030 April 1992
Auxiliary Feedwater System RISK-BASED Inspection Guide for the Turkey Point Nuclear Power Plant
ML17349A4181991-12-31031 December 1991
Step 2 Review,Turkey Point Units 3 & 4 IPE Submittal, Human Reliability Analysis
ML17349A4171991-12-21021 December 1991
IPE Back-End Audit,Task 3,Technical Evaluation Rept,December 21,1991,Rev 1
ML17349A4151991-12-21021 December 1991
Ipe:Front End Audit.
ML17348B1241991-07-31031 July 1991
Technical Evaluation Rept,Pump & Valve Inservice Testing Program,Turkey Point,Units 3 & 4.
ML20043F6331990-06-11011 June 1990
Technical Evaluation Rept Turkey Point Units 2 & 3 Station Blackout Evaluation, Final Rept
ML20058K1031989-05-30030 May 1989
Conformance to Generic Ltr 83-28,Item 2.2-1 - Equipment Classification for All Other Safety-Related Components, Turkey Point-3/-4, Technical Evaluation Rept
ML17347A5931987-07-31031 July 1987
Retran Code:Transient Analysis Model Qualification, Technical Evaluation Rept
ML17342A7541987-06-30030 June 1987
Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components: Turkey Point 3 & 4, Final Rept
ML17342A7641987-06-30030 June 1987
TMI Action-NUREG-0737 (II.D.1),Relief & Safety Valve Testing,Turkey Point Units 3 & 4, Informal Technical Evaluation Rept
ML20211N5031987-01-0909 January 1987
Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,HB Robinson Steam Electric Plant,Unit 2, Salem Generating Station Units 1 & 2,Shearon Harris Nuclear Power Plant Unit 1..., Technical Evaluation Rept
ML20198A2481986-04-0404 April 1986
Metallurgical Failure Analysis of Check Valve Guide Pin
ML20138J9491985-09-30030 September 1985
Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Farley Units 1 & 2,Turkey Point Units 3 & 4,Robinson Unit 2 & Summer Unit 1
ML17342A3571985-09-30030 September 1985
Addendum a to First Interval Inservice Insp Program for Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17342A3341985-09-30030 September 1985
Inservice Insp Program,Second Interval Technical Evaluation Rept.
ML17342A1601985-07-19019 July 1985
Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic...), Item 1.2., `Post-Trip Review:Data & Info Capability,' for Turkey Point Plant..., Technical Evaluation Rept
ML20244D3871985-07-10010 July 1985
Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant.
ML20244D4381985-06-30030 June 1985
Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities
ML20111B1661984-12-0505 December 1984
Masonry Wall Design, Technical Evaluation Rept
ML20080E0711984-01-13013 January 1984
Evaluations of Detailed Control Room Design Reviews for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20080Q5131983-10-10010 October 1983
Control of Heavy Loads (C-10),Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20079Q6871983-03-14014 March 1983
Selected Operating Reactor Issues Program Ii:Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept
ML17354A2561983-02-14014 February 1983
Post-Fire Safe Shutdown Capability, Technical Evaluation Rept
ML20072B1201983-01-0606 January 1983
Control of Heavy Loads (C-10),Turkey Point Units 3 & 4, Draft Technical Evaluation Rept.Request for Addl Info Encl
ML20076C3691982-11-29029 November 1982
ECCS Repts (F-47):TMI Action Plan Requirements,Turkey Point,Units 3 & 4, Technical Evaluation Rept
ML17341B4711982-10-28028 October 1982
Proposed Design Mod & Tech Spec Changes on Grid Voltage Degradation for Turkey Point Nuclear Generating Plant, Units 3 & 4, Technical Evaluation Rept
ML20069G5861982-09-30030 September 1982
Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Turkey Point Unit 4, Vols 1 & 2,technical Evaluation Rept
ML17345B2391982-09-17017 September 1982
Seismic Qualification of Auxiliary Feedwater Sys,Turkey Point Nuclear Plant,Units 3 & 4, Technical Evaluation Rept
ML20023A4891982-09-10010 September 1982
Inservice Insp Program, Technical Evaluation Rept
ML17341B4661982-08-31031 August 1982
Improvements in Training & Requalification Programs as Required by TMI Action Items I.A.2.1 & II.B.4 for Turkey Point,Units 3 & 4, Technical Evaluation Rept
ML20071L7081982-08-0808 August 1982
Adequacy of Station Electric Distribution Sys Voltages for Turkey Point Nuclear Generating Plant Units 3 & 4, Technical Evaluation Rept
ML17341B4001982-06-18018 June 1982
Auxiliary Feedwater Sys Automatic Initiation & Flow Indication,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20052F6841982-02-28028 February 1982
Tech Specs for Redundant Decay Heat Removal Capability, Turkey Point,Units 3 & 4, Preliminary Rept for Feb 1982
ML17341A9181982-01-31031 January 1982
Tech Specs for Insp of Steam Generators,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17341A8291981-12-29029 December 1981
Control of Heavy Loads, Draft Technical Evaluation Rept
ML20038D1341981-12-11011 December 1981
Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.
ML20039A1691981-12-11011 December 1981
Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.
ML17341A2081981-06-0505 June 1981
Containment Leakage Rate Testing,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML20003C2581981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Crystal River Nuclear Power Plant,Unit 3.
ML20003C2611981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Indian Point 3 Nuclear Power Plant.
ML17340A7621981-01-31031 January 1981
Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of Override of Containment Purge Valve Isolation & Other Engineered Safety Feature Signals for Turkey Point Nuclear Power Station,Units 3 & 4.
ML19336A4071980-09-30030 September 1980
In-Plant Source Term Measurements at Turkey Point Station Units 3 & 4.
ML17339B1191980-05-31031 May 1980
Proposed Amend to Facility OLs DPR-31 & DPR-41,Delta T Vs Reactor Power Shift Check,Turkey Point Units 3 & 4, Informal Rept
1998-09-30
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FOAM EQXG4Sb Idaho. Inc.
(Aev. 11 TPj INTERIM REPORT Accession No.
Report No EGG-EA-5743 Contract Program or Project
Title:
Selected Operating Reactor Issues Program (III)
Subject of this Document:
Technical Specifications for the Inspection of Steam Generators, Turkey Point, Unit Nos. 3 and 4 Type of Document:
Technical Evaluation Report Author(s):
J. A. Steverson Date of Document:
January 1982 Responsible NRC Individual and NRC Office or Division:
J. N. Donohew, Division of Licensing This document was prepared primarily for preliminary or internal use. It has not received full review and approval. Since there may be substantive changes. this document should not be considered final.
EGB G Idaho. Inc.
Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, O.C.
Under OOE Contract No. OE-AC07-76I001570 NRC FIN No A6429 INTERIM REPORT
/ I j TECHNICAL SPECIFICATIONS FOR THE INSPECTION OF STEAM GENERATORS TURKEY POINT, UNIT NOS. 3 ANO 4 Docket Nos. 50-250, 50-251 January 1982 by J. A. Steverson Reliability and Statistics Branch Engineering Analysis Division EG&G Idaho, Inc.
ABSTRACT This report reviews the Turkey Point, Unit Nos. 3 and 4 technical specifications for stean generator inspection.
FORD+D This report is supplied as part of the "Selected Operating Reactor Issues Program (III)" being conducted for. the U.S. Nuclear Regulatory Comnission, Office of Nuclear Reactor Regulation, Division of Licensing, by EG&G Idaho, Inc., Reliability and Statistics Br anch.
The U.S. Nuclear Regulatory Commission funded the work under the authorization, MR 20 19 02 06, FIN No. A6429.
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TECHNICAL EVALUATION REPORT TECHNICAL SPECIFICATIONS FOR THE INSPECTION OF STEAM GENERATORS K PO N UN NO . 3 ANO
- 1. 0 INTROOUCTION Turkey Point steam generator s have been inspected according to special license conditions imposed originally by Amendment 20, dated Oecember 3, 1976, for Unit '4 and by Amendment 22, dated January 14, 1977, for Unit 3.
Thus, technical specifications for the inservice inspection of the steam 1
generator tubes were not required. By letter, dated July 1, 1981, the NRC requested Turkey Point 3 and 4 review their submittals and appropriately modify them, using as a guide the technical specifications for steam gener-ator inspection provided by the NRC.
On Oecember 18, 1981, Florida Power and Light (FPEL) submitted pro-2 posed changes to their technical specifications (TS). The following discussion evaluates the proposed Turkey Point TS and notes any differences existing between them and the NRC model TS.
2.0 OISCUSS ION ANO EVALUATION Turkey Point, Units 3 and 4 are three loop Westinghouse PWR Plants.
The specific sections of the Westinghouse Standard Technical Specifica-tions that apply to this task are as follows:
3/4.4 REACTOR COOLANT SYSTEM 3/4.4.6 STEAM GENERATORS 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE The licensee proposed the following changes and incorporations to their technical specifications. First, Specification 3.1.3.6 was revised and
- 3. 1.3.g was added to incorporate limiting conditions for operation regarding primary-to-secondary leakage through steam generator tubes. This satisfies requirements 3.4.7.2.c and 3.4.7.2.d in the NRC standard TS. Secondly, a
O. 1 C>>
steam generator inspection program was added to the licensee's section on Reactor Coolant System Inservice Inspection. The progr'am is in Section 4.2.5, Steam Generator Inspection, and in Tables 4.2-2 and 4.2-3 of their proposed TS and coincides with Section 3/4.4.6, Steam'Generators, and with Tables 4.4-1 and 4.4-2 of the Mestinghouse Standard TS.
Also in the steam generator inspection p~ogram, the Mestinghouse Stan-dard TS in Section 4.4.6.3.a, Inspection Frequencies, require the first inservice inspection to be per formed after six effective full power nnnths but within 24 calendar months of initial criticality. The licensee's cor-responding requirem nt in Section 4.2.5.3.a, requires the first inservice inspection to be performed after the first refueling following initial criticality or replacement of steam generators (whichever is later).
- 3. 0 CONCLUS ION The proposed TS submitted by FPQ. for Turkey Point, Units 3 and 4 included revisions and/or additions regarding (1) primary-to-secondary leakage through steam generator tubes, and (2) a steam generator inspection program. A basis for the steam generato~ inspection was also added to the specification.
The TS proposed by Turkey Point are in agreement with the Westinghouse Standard TS with two exceptions. The pr'eceeding evaluation noted (1) an omission in the Turkey Point TS concerning the inspection of the fir st sample of stean generator tubes, and (2) a difference in the timing of the first inservice inspection of a steam generator.
- 4. 0 R EFERENCES
- 1. NRC letter, S. A. Varga, to FP&L, R. E. Uhrig, dated July 1, 1981.
- 2. FP5L letter, R. E. Uhrig, to NRC, D. G. Eisenhut, dated December 18, 1981.
- 3. Standard Technical Specifications for Westinghouse PMRs, NUREG-0452, Rev. 3, Fall 1980.
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-250 AND 50-251 FLORIDA POWER AND LIGHT COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 81 to Facility,Operating License No. DPR-31, and Amendment No. 75 to Facility Operating License No. DPR-41 issued to Florida Power and Light Company'(the licensee), which revised Technical Specifications for operation of Turkey Point Plant, Unit Nos. 3 and 4 (the facilities) located in Dade County, Florida. The amendments are effective as of the date of issuance.
The amendments incorporate the steam generator inservice inspection requirements into the Techncial Specifications. These specifications replace Facility Operating License No. DPR-31 condition 3.E for Unit 3 effective as of the date of this amendment and Facility Operating License No. DPR-41 condition 3.D for Unit 4 effective as of the date of completion of the steam generator replacement in Unit 4, The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has, made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments. Prior public notice of these amendments has not required since the amendments do not involve a significant hazards consideration.
7590-01 The Commission has determined that the issuance of these amendments will not result in any significant environmental impact'nd that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration 4
and environmental impact appraisal need not be prepared in connection with issuance of these amendments.
For further details with respect to this action, see (1) the application for amendments dated December 18, 1981, (2) Amendment Nos. 81 and 75 to License Nos. DPR-31 and DPR-41, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Document Room, 1717. H Street, N.W., Washington, ll D.C.
and at the Environmental and Urban Affairs Library, Florida International University, Miami, Florida 33199. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Director, Division of Licensing.
Dated at Bethesda, Maryland, this 24th day of March, 1982.
F R THE NUC EGULATORY COMMISSION arga, C f Operating Reactors nch 81 Division of Licensing
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~1 DI STRI B UTI ON Dockets MDunnel fel d NRC PDR Gray File L PDR J
MAR 17 1982 NSIC Docket Nos. 56~250 ORB¹l Rdg and 50-251 DEisenhut IE-2 ACRS-10 Dr. Robert E. Uhrig, Vice President Q 8FQQ~~ TBarnhart-8 Advanced Systems and Technology
~ 4 LSchneider g~~ 8 DBrinkman Florida Power and'ight Company ~p jgap~
OPA Post Office Box 529100 '~@~ee "'
Hiami, Florida 33152 Tlpj RDiggs 6 NGrotenhuis
Dear Dr. Uhrig:
l CParrish
~ 1 ASLAB The Commission has issued the enclosed Amendment Ho. 80 to Facility Operating License No. DPR-31 and Amendment No. 74 to Facility Operating License No.
DPR-41 for the Turkhy Point Plant Unit Hos. 3 and 4, respectively. The amendments consist of changes to the Technical Specifications in response to your application transmitted by letterrdated IIay 14, 1981, as supplemented November 23, 1981 and January 28, 1982.
These amendments revise the Technical Specifications to specify new power distribution limits for base load and radial burndown operation.
Itle have received you letter dated March 15, 1982 which satisfied the curr ent requirements of Technical Specification 6.9.3 for Unit 3. Such a r eport is not necessary for Unit 4 at this time because PT is not less than 1.
Ile have found it necessary to make changes in certain of the Technical Specifications. Ite have discussed the changes with your staff. They found the changes acceptable and the chhn)es have been incorporated.
Copies of the Safety Evaluation and the Notice of Issuance are a)sd enclosed.
Sincerely,
-D~GINAL SZCNK5 tlarshall Grotenhuis, Project Manager Operating Reactors Branch ¹1 Division of Licensing
Enclosures:
- l. Amendment Ho. 80 to DPR-31
- 2. Amendment No. 74 to DPR-41
- 3. Safety Evaluation
- 4. Notice of Issuance %
()y)0 cc w/enclosures:
- Previous concur rence see next page ORB¹1:DL* ORB¹1:DL* ORB¹l:DL* AD/OR:DL* OELD*
OFFICE/
SURNAME/ ~~~
CParrish
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O'FORM318 1080 ) NRCM0240,'Il'<'",'i'i- "< "OFFICIAL RECORD COPY VSOPO: 1991~960
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DISTRIBUTION Dockets ASLAB NRC PDR Gray File L PDR MDunnenfeld TERA Docket Nos.60-260 NSIC and 50-251 ORBkl Rdg DEisenhut OELD IE-4 ACRS-10 GDeegan-8 LSnyder DBrinkman OPA RDiggs
Dear Dr. Uhrig:
MGrotenhuis CParrish The Commission has iqqued the enclosed Amendment No. to Facility Operating License f(o. DPR-31 and Amendment No. to Facility Operating License No.
DPR-41 for the Turkey Point Plant Unit Nos. 3 and 4, respectively. The amendments consist of changes to the Technical Specifications in response to your application transmitted by letter dated May 14, 1987, as supplemented November 23, 1981 and January 28, 1982.
These amendments revise the Technical Specifications related to base, load and radial burndown.
Copies of the Safety Evaluation and the Notice of Issuance are alsoeenclosed.
Sincer ely, Marshall Grotenhuis, Project Manager Operating Reactors Branch 01 Division of Licensing
Enclosures:
'1. Amendment No. to DPR-31
- 2. "Amendment No. to DPR-41
- 3. Safety Evaluation
- 4. Notice of Issuance cc v(/enclosures:
See next page ORB A'1: DL OFFICE I RB81: L ~
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QP. /82 02 (g/82 NRC FORM 318 (10-80) NRCM'0240 OFFICIAL RECORD COPY USGPO: 1991~9-960
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Robert "=. Uhrig Florida Power and Light Company CC: fir. Robert Lowenstein, Esquire her. Jack Shreve Lowenstein, Newman, Reis and Axelrad Office of the Public Counsel 1025 Connecticut Avenue, N.M. Room 4, Holland Building Sui te'1214 Tallahassee; Florida 32304 Vashington, D. C. 2"-035 Admini strator Environmental and Urban Affairs Library Department of Environmental Florida International University Regulation Miami, Florida 33199 Power Plant Siting Section State of Florida Hr. t<orman A. Coll, Esquire. 2600 Blair Stone Road Steel, Hector and Davis Tallahassee, Florida 32301 1400 Southeast First, National Bank Building James P. O'Reilly Miami, Florida 33131 Regional Administrator - Region II U. S. Nuclear Regulatory Commission h1r. Henry Yaeger, Plant Manager 101 Marietta Street - Suite 3100 Turkey Point Plant Atlanta, Georgia 30303 Florida Power and L~ht Company P. 0. Box 013100 Miami, Florida 33101 Honorable Dewey Knight County tianager of Metropolitan Dade County t'li ami, Florida 33130 Bureau of Intergovernmental Relations 560 Apalachee Parkway Tallahassee, Florida 32304 Resident Inspector Turkey Point nuclear Generating Station U. S. nuclear Regulatory Commission Post Office Box 1207 Homestead, Florida 33030 Regional Radiation Pepresentative EPA Region IV 345 Courtland Street, H.M.
Atlanta; Georgia 30308
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