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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  
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/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 Title:
C>f,~
Selected Operating Reactor Issues Program               (III)
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.
Subject of this Document:
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>>
Technical Specifications         for the Inspection of       Steam Generators, Turkey Point, Unit Nos.         3 and 4 Type of Document:
steam generator inspection program was added to the licensee's section on Reactor Coolant System Inservice Inspection.
Technical Evaluation Report Author(s):
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.
J. A. Steverson Date of Document:
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.
January 1982 Responsible NRC Individual and NRC Office or Division:
The TS proposed by Turkey Point are in agreement with the Westinghouse Standard TS with two exceptions.
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.
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.
EGB G Idaho. Inc.
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.
Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, O.C.
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Under OOE Contract No. OE-AC07-76I001570 NRC FIN No       A6429 INTERIM REPORT
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:
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 1 II 4 o f A~
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.
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 SZCNK5~1 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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==Dear Dr.Uhrig:==
/ 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.
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.
 
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.
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.
 
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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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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:==
==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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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 Branch&#xb9;1 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 ORB&#xb9;1:DL*OFFICE/SURNAME/CParrish'~OATEN~~~~~~~~~~~~~0~~~~;.NI..../BZ....
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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.
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  


==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


==Enclosures:==
==Enclosures:==


'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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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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Revision as of 09:38, 22 October 2019

Tech Specs for Insp of Steam Generators,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17341A918
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 01/31/1982
From: Stevenson J
EG&G, INC.
To: Donohew J
Office of Nuclear Reactor Regulation
References
CON-FIN-A-6429 EGG-EA-5743, NUDOCS 8203040588
Download: ML17341A918 (18)
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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

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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. 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  %

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  • Previous concur rence see next page ORB¹1:DL* ORB¹1:DL* ORB¹l:DL* AD/OR:DL* OELD*

OFFICE/

SURNAME/ ~~~

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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:

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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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