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| | issue date = 05/20/1977 | | | issue date = 05/20/1977 |
| | title = Proposed Amendment to Facility Operating License DPR-67 Regarding Secondary Water Chemistry Program | | | title = Proposed Amendment to Facility Operating License DPR-67 Regarding Secondary Water Chemistry Program |
| | author name = Uhrig R E | | | author name = Uhrig R |
| | author affiliation = Florida Power & Light Co | | | author affiliation = Florida Power & Light Co |
| | addressee name = Stello V | | | addressee name = Stello V |
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| =Text= | | =Text= |
| {{#Wiki_filter:NRC FoRM 196 U,S, NUCLEAR REGULATORY Co SION Ig.7BI~gRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL DOCKET NUMIIF R ,M-BBS FILE NUMBER 4 TQr Mr.Victor Stello FROM: Florida Power Bc Light Company Miami, Florida Ri E~Uhrig DATE OF DOCUMENT 5/20/77 DATE RECEIVED 5/23/77 g.'ETTER g<)RIGINAL P COPY, DESCRIPTION PNOTORI2ED NC LASS I F I E 0 PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED D~icA~-R~~~~~~I I'mdti to OL/change to.Appendix A tech specs', notoriz'ed 5/20/77're secondary-- | | {{#Wiki_filter:,M - BBS NRC FoRM 196 U,S, NUCLEAR REGULATORY Co SION DOCKET NUMIIFR Ig.7BI FILE NUMBER |
| water chemzstry program~~~~~I.iu[(i'I$@LLlg PLANT NAME: 'St+Lucie Unit No.1 (3-P)(5-P)muon ilBkl[E RJL SAFETY ASSIGNED AD: NQH QK~RO~Ol IA NAG L C ASST FOR ACTION/INFORMATION CKXP PROJECT MANAGER LXC ASST~REG FIT PDR I&E OELD GOSSICK&STAFF MIPC CASE HANAUER HARLESS PROJECT MANAGEIKNT BOYD P COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVIIOLT LPDR TIC: NSIC: INTERNAL D IST SYSTEMS SAFETY HEXNEIIAN SCHROEDER ENGXNEERXNG MACARRY BOSNAK SXINEXL PAWLXCK REACTOR SAFE ROSS ROSZTOCZY CHECK AT&I SALT ZMAN RIJTBERG EXTERNAL DISTRIBUTION NAT LAB REG V IE LA PDR RI BUTION PLANT SYSTEMS TEDESCO XPPOLXTO OPERATING REACTORS STELLO OPERATING TECH EISENHUT 0+KjQgp ULRIKSON QRN SXTE SAFE E ERNST BALLARD YOUN CBLOOD SXTE TECH GAMMXLL STEPP HULMAN SITE ANALYSIS VOLLIIER BIJNCH J~COLLINS KREGER CONTROL NUMBER 771440 1 i%CONSULTANTS! | | ~gRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL 4 |
| ASLB: ACRS CYS RMMSlG/E T CrPf P.O.BOX 3100 MIAMI, FLORIDA 33101 p',.FLORIDA POWER&LIGHT COMPANY May'20, 1977 L-77-151 f$B CJ RBgglgtOT'J Director of Nuclear Reactor Regulation Attention:
| | TQr FROM: DATE OF DOCUMENT Florida Power Bc Light Company 5/20/77 Miami, Florida DATE RECEIVED Mr. Victor Stello Ri E ~ Uhrig 5/23/77 g .'ETTER PNOTORI2ED PROP INPUT FORM NUMBER OF COPIES RECEIVED D ~icA~- |
| Mr.Victor Stello, Director Division of Operating Records U.S.Nuclear Regulatory Commission Washington, D.C.20555
| | g<)RIGINAL NC LASS I F I E 0 P COPY, DESCRIPTION ENCLOSURE |
| | ~ ~ ~ ~ ~ ~ to OL/change to.Appendix A tech I'mdti I |
| | R specs', notoriz'ed 5/20/77 ' re secondary-- |
| | water chemzstry program ~ ~ ~ ~ ~ |
| | I.iu [( i'I$ @LLlg (3-P) (5-P) muon ilBkl[E PLANT NAME: |
| | 'St+ Lucie Unit No. 1 RJL SAFETY FOR ACTION/INFORMATION ASSIGNED AD: |
| | NQH QK CKXP |
| | ~RO ~Ol IANAG PROJECT MANAGER L C ASST LXC ASST INTERNAL D IST RI BUTION |
| | ~ REG FIT SYSTEMS SAFETY PLANT SYSTEMS SXTE SAFE PDR HEXNEIIAN TEDESCO I & E SCHROEDER OELD GOSSICK & STAFF ENGXNEERXNG XPPOLXTO E MIPC MACARRY ERNST CASE BOSNAK BALLARD HANAUER SXINEXL OPERATING REACTORS YOUNCBLOOD HARLESS PAWLXCK STELLO SXTE TECH PROJECT MANAGEIKNT REACTOR SAFE OPERATING TECH GAMMXLL BOYD ROSS EISENHUT STEPP P COLLINS HULMAN HOUSTON ROSZTOCZY PETERSON CHECK SITE ANALYSIS MELTZ VOLLIIER HELTEMES AT& I BIJNCH SKOVIIOLT SALTZMAN J~ COLLINS RIJTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR NAT LAB 0+KjQgp TIC: REG V IE ULRIKSON QRN NSIC: LA PDR 771440 1 i% |
| | ASLB: CONSULTANTS! |
| | ACRS CYS RMMSlG/ E T CrPf |
|
| |
|
| ==Dear Mr.Stello:==
| | P.O. BOX 3100 MIAMI, FLORIDA 33101 p',. |
| .aECf).MAY23 197/~LI,II, FeaFAR atOUPIOC 9'e: St.Lucie Unit 1 Docket No.50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 A November 15, 1976 letter from Mr.Dennis L.Ziemann of your staff requested that we submit a secondary water chemistry program for inclusion in our St.Lucie Unit 1 Technical Specifications. | | FLORIDA POWER & LIGHT COMPANY May'20, 1977 L-77-151 CJ RBgglgtOT'J f$B Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director U. S. |
| We have considered the bases and effects of such technical specifi-cations and have concluded that, for the following reasons, limiting conditions for operation should not be placed on secondary water chemistry:
| | Division of Operating Records Nuclear Regulatory Commission . aECf ) . |
| l.The safety aspects of steam generator pressure boundary integrity are addressed by Technical Specification 3.4.6.2.C.
| | Washington, D.C. 20555 MAY23 197/~ |
| This specification establishes a steam generator tube leakage limit and requirements for plant shutdown should the limit be exceeded.2.Technical Specification 4.4.5 is directed toward ensuring the integrity of steam generators by means of eddy current testing consistent with Regulatory Guide 1.83,"Xnservice Xnspection of Pressurized Water Reactor Steam Generator Tubes." Such testing provides a means by which the integrity of individual tubes can be evaluated during periodic planned outages.3.Technical Specification 4.4.5 is directed toward assuring the integrity of the steam generators without identifying the causes, if any, of their possible degradation.
| | LI,II, FeaFAR atOUPIOC |
| Potential causes might be deficiencies in design (including material selection), quality assurance, installation, and primary or secondary environments of the steam generator.
| | |
| Lengthy techni-cal specifications could conceivably be written to bar each potential cause of degradation.
| | ==Dear Mr. Stello:== |
| This would not, HELPING BUILD FLORIDA
| | 9'e: |
| 'P II A El k
| | St. Lucie Unit 1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 A November 15, 1976 letter from Mr. Dennis L. Ziemann of your staff requested that we submit a secondary water chemistry program for inclusion in our St. Lucie Unit 1 Technical Specifications. We have considered the bases and effects of such technical specifi-cations and have concluded that, for the following reasons, limiting conditions for operation should not be placed on secondary water chemistry: |
| ,l)irector of Nuclear ctor Regulation Page 2 April 5, 1977 however, be consistent with our understanding of the purpose of technical specifications as authorized by the Atomic Energy Act and as utilized by the Nuclear Regula-tory Commission.
| | : l. The safety aspects of steam generator pressure boundary integrity are addressed by Technical Specification 3.4.6.2.C. This specification establishes a steam generator tube leakage limit and requirements for plant shutdown should the limit be exceeded. |
| We understand that the purpose of technical specifications is to identify those parameters of design and operation whose violation, by some margin, would or could present an unacceptable safety risk.Thus, the term"limiting condi-tions for operation" is defined in 10 CFR 50.36(c)(2)as"the lowest functional capability of performance levels of equipment required for safe operation of the facility." Xt is therefore appropriate to place a technical specifi-cation limit on the leakage through a primary boundary such as the steam generator tubing.However, in our judgment, it would not be appropriate to write a technical specification addressing the potential causes of degradation of such boundaries.
| | : 2. Technical Specification 4.4.5 is directed toward ensuring the integrity of steam generators by means of eddy current testing consistent with Regulatory Guide 1.83, "Xnservice Xnspection of Pressurized Water Reactor Steam Generator Tubes." Such testing provides a means by which the integrity of individual tubes can be evaluated during periodic planned outages. |
| 4.Technical specifications would be particularly inappropriate to secondary water chemistry parameters whose equilibrium conditions fluctuate during normal plant operational modes, such as power changes, startups and shutdowns.
| | : 3. Technical Specification 4.4.5 is directed toward assuring the integrity of the steam generators without identifying the causes, if any, of their possible degradation. Potential causes might be deficiencies in design (including material selection), quality assurance, installation, and primary or secondary environments of the steam generator. Lengthy techni-cal specifications could conceivably be written to bar each potential cause of degradation. This would not, HELPING BUILD FLORIDA |
| There is no evidence that short-term variations in secondary water chemistry are significant to steam generator tube integrity.
| | |
| Technical specification limitations on such fluctuations could only res'ult in enforcement problems, lack of operational flexibility and diminution of the safety significance of technical specifications.
| | P II A |
| Deviations from secondary water quality guidelines are not a safety problem and are therefore not appropriately the subject of technical specifications; the condition of steam generator tubes, on the other hand, is appropriate for such consideration and technical speci-fications exist to provide for direct monitoring of the condition of the steam generator tubes in order to assure that continued integrity is maintained.
| | El k |
| 5.6.The unnecessary proliferation of technical specifications should be avoided.Since the addition, deletion or revi-sion of technical specifications involves the formal, time-consuming license amendment process, the technical specifications should contain only those requirements that are directly relatable to safe operation, Other means should be utilized for providing direction on matters that, are indirectly related to the safety of operation.
| | |
| There are many examples of this philosophy at operating plants, wherein many operating practices, procedures, tests, plans, etc., are covered by means other than the imposition of technical specifications.
| | ,l)irector of Nuclear ctor Regulation Page 2 April 5, 1977 however, be consistent with our understanding of the purpose of technical specifications as authorized by the Atomic Energy Act and as utilized by the Nuclear Regula-tory Commission. |
| The November 15, 1976 letter also addresses the need for continual monitoring and control of steam side water chemistry in order to ensure against an accumulation of harmful impurities in the steam generators.
| | We understand that the purpose of technical specifications is to identify those parameters of design and operation whose violation, by some margin, would or could present an unacceptable safety risk. Thus, the term "limiting condi-tions for operation" is defined in 10 CFR 50.36(c) (2) as "the lowest functional capability of performance levels of equipment required for safe operation of the facility." |
| We agree that for long-term reliability and continued assurance of tube integrity, a chemistry iDirector of Nuclear R tor Regulation Page 3 April 5, 1977 control program is necessary.
| | Xt is therefore appropriate to place a technical specifi-cation limit on the leakage through a primary boundary such as the steam generator tubing. However, in our judgment, it would not be appropriate to write a technical specification addressing the potential causes of degradation of such boundaries. |
| The specific chemistry guidelines are periodically updated in conjunction with the steam system supplier recommendations.
| | : 4. Technical specifications would be particularly inappropriate to secondary water chemistry parameters whose equilibrium conditions fluctuate during normal plant operational modes, such as power changes, startups and shutdowns. There is no evidence that short-term variations in secondary water chemistry are significant to steam generator tube integrity. |
| Chemistry data and records are maintained at the plant site and are subject to review by the NRC or any other authorized activity.Regulatory review can then result in,a critique of our ability to maintain chemistry within established guidelines and can result in corrective action when necessary.
| | Technical specification limitations on such fluctuations could only res'ult in enforcement problems, lack of operational flexibility and diminution of the safety significance of technical specifications. Deviations from secondary water quality guidelines are not a safety problem and are therefore not appropriately the subject of technical specifications; the condition of steam generator tubes, on the other hand, is appropriate for such consideration and technical speci-fications exist to provide for direct monitoring of the condition of the steam generator tubes in order to assure that continued integrity is maintained. |
| The above arguments against limiting conditions for operation also apply to detailed surveillance requirements, however, an entry into the technical specifications requiring that a surveillance program be practiced is not objectionable.
| | : 5. The unnecessary proliferation of technical specifications should be avoided. Since the addition, deletion or revi-sion of technical specifications involves the formal, time-consuming license amendment process, the technical specifications should contain only those requirements that are directly relatable to safe operation, Other means should be utilized for providing direction on matters that, are indirectly related to the safety of operation. There are many examples of this philosophy at operating plants, wherein many operating practices, procedures, tests, plans, etc., are covered by means other than the imposition of technical specifications. |
| Therefore, we have prepared a proposed amendment along those lines and now submit it.for your review.Xn accordance with 10 CFR 50.30, three (3)originals and forty (40)copies of the proposal to amend Appendix A of Operating License DPR-67 are hereby submitted for your consideration.
| | : 6. The November 15, 1976 letter also addresses the need for continual monitoring and control of steam side water chemistry in order to ensure against an accumulation of harmful impurities in the steam generators. We agree that for long-term reliability and continued assurance of tube integrity, a chemistry |
| The proposed changes are described below and shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner.Pages 3/4 7-10 through 7-12 Specification 3.7.1.6 is revised and Specification 4.7.1.6 is revised to refer to approved plant procedures. | | |
| Page B 3/4 7-3 Bases section 3/4.7.1.6 is revised to be consistent with our position on secondary water chemistry.
| | iDirector of Nuclear R tor Regulation Page 3 April 5, 1977 control program is necessary. The specific chemistry guidelines are periodically updated in conjunction with the steam system supplier recommendations. Chemistry data and records are maintained at the plant site and are subject to review by the NRC or any other authorized activity. |
| The proposed amendment has been reviewed by the St.Lucie Facility Review Group and the Florida Power a.Light Company Nuclear Review Board.They have concluded that it does not involve an unreviewed safety question.Very yours, R.E.Uhrig Vice President REU/MAS/pg Attachment cc: Norman C.Moseley, Region XI Robert Lowenstein, Esquire I l l'r-a PLANT SYSTEMS SECONDARY lJATER CHEMISTRY LIMITIHG CONDITION FOR OPERATION 3.7.1.6 There are no 1imiting conditions for operation associated with secondary water chemistry. | | Regulatory review can then result in,a critique of our ability to maintain chemistry within established guidelines and can result in corrective action when necessary. |
| SURVEILLANCE REQUIREMENTS 4.7.1.6 The secondary~ater chemistry shall'be determined to be within procedural limits by analysis in accordance with approved plant procedures.
| | The above arguments against limiting conditions for operation also apply to detailed surveillance requirements, however, an entry into the technical specifications requiring that a surveillance program be practiced is not objectionable. Therefore, we have prepared a proposed amendment along those lines and now submit it. for your review. Xn accordance with 10 CFR 50.30, three (3) originals and forty (40) copies of the proposal to amend Appendix A of Operating License DPR-67 are hereby submitted for your consideration. The proposed changes are described below and shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner. |
| ST.LUCIE-UNIT 1 3/4 7-10.5/20/77 BLANK ST.LUCIE-UNIT 1 3/a 7-zz 1
| | Pages 3/4 7-10 through 7-12 Specification 3.7.1.6 is revised and Specification 4.7.1.6 is revised to refer to approved plant procedures. |
| BLANK ST.LUCIE-UNIT 1 3/4 7-12 PLANT SYSTEHS BASES 3/4.7.1.5 HAIN STEAH LINE ISOL'ATION VALVES\The OPERABILITY of the main steam line iso'lation valves ensures'hat no more than one steam generator will blowdown in the event of a steam'line rupture.'This r estriction is required to 1)minimize the positive reactivity effects of the Reactor Coolant System cooldown--associated with the blowdown, and 2)limit the pressure-rise within containment in the event the steam'line rupture occurs within contain-ment.The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions"used in the accident analyses.3/4.7.1.6 SECONDARY llATER CllEHISTRY Operating history wi11 be used to establish appropriate limits ,on secondary~ater chemistry,and to determine appropriate frequencies for monitoring these parameters.
| | Page B 3/4 7-3 Bases section 3/4.7.1.6 is revised to be consistent with our position on secondary water chemistry. |
| Approved plant procedures will be used to administratively control secondary water chemistry.
| | The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power a. Light Company Nuclear Review Board. They have concluded that safety question. |
| 3/4.7.2 STEAN GENERATOR PRESSURE/TEHPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators'.
| | it does not involve an unreviewed Very yours, R. E. Uhrig Vice President REU/MAS/pg Attachment cc: Norman C. Moseley, Region XI Robert Lowenstein, Esquire |
| do not exceed the maximum allowable fracture toughness stress limits.'The limitations of 70'F and 200-'psig are based on a steam generator RTNDT of 50'F and are sufficient to prevent brittle fracture.ST.LUCIE-UNIT 1 B 3/4 7-3 5/20/77 STATE OF FLORlDA))COUNTY OF DADE)ss being first duly sworn, deposes and says: That he is Executive Vice Preside Light Company, the Licensee herein'f Florida Power 6 That he has executed the foregoing document;that the state-ments made in this said document are true and correct to the.best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee E..Adomat Subscribed and sworn to before me this day of NOTARY P BLOC, in and for the County of Dade, State o Florida"MATE QF PLORiDA'Y COMIAISSION EXPIRES JAN.26,)979 ENDED ThRLI GENLRAL INSURANCE UNDERWR(IERS My commission expires:
| | |
| RECQyFg~socks'~~~"'"~."~
| | I l |
| Qlp/Q Qft/"j}} | | l' r-a |
| | |
| | PLANT SYSTEMS SECONDARY lJATER CHEMISTRY LIMITIHG CONDITION FOR OPERATION 3.7.1.6 There are no 1imiting conditions for operation associated with secondary water chemistry. |
| | SURVEILLANCE REQUIREMENTS 4.7.1.6 The secondary ~ater chemistry shall 'be determined to be within procedural limits by analysis in accordance with approved plant procedures. |
| | ST. LUCIE - UNIT 1 3/4 7-10 . 5/20/77 |
| | |
| | BLANK ST. LUCIE UNIT 1 3/a 7-zz |
| | |
| | 1 BLANK ST. LUCIE UNIT 1 3/4 7-12 |
| | |
| | PLANT SYSTEHS BASES 3/4.7.1.5 HAIN STEAH LINE ISOL'ATION VALVES |
| | \ |
| | The OPERABILITY of the main steam line iso'lation valves no more than one steam generator will blowdown in the event ensures'hat of a steam 'line rupture.'This r estriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown -- |
| | associated with the blowdown, and 2) limit the pressure-rise within containment in the event the steam 'line rupture occurs within contain-ment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions "used in the accident analyses. |
| | 3/4.7.1.6 SECONDARY llATER CllEHISTRY Operating history wi11 be used to establish appropriate limits |
| | ,on secondary ~ater chemistry,and to determine appropriate frequencies for monitoring these parameters. Approved plant procedures will be used to administratively control secondary water chemistry. |
| | 3/4.7. 2 STEAN GENERATOR PRESSURE/TEHPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators'. do not exceed the maximum allowable fracture toughness stress limits. 'The limitations of 70'F and 200-'psig are based on a steam generator RTNDT of 50'F and are sufficient to prevent brittle fracture. |
| | ST. LUCIE - UNIT 1 B 3/4 7-3 5/20/77 |
| | |
| | STATE OF FLORlDA ) |
| | ) ss COUNTY OF DADE ) |
| | being first duly sworn, deposes and says: |
| | That he Light is herein'f Executive Vice Preside Company, the Licensee Florida Power 6 That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the |
| | . best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee E. . Adomat Subscribed and sworn to before me this day of NOTARY P BLOC, in and for the County of Dade, State o Florida "MATE QF PLORiDA COMIAISSION EXPIRES JAN. |
| | 'Y 26, )979 ENDED ThRLI GENLRAL INSURANCE UNDERWR(IERS My commission expires: |
| | |
| | RECQyFg |
| | ~socks'~~~"'"~."~ |
| | Qlp/Q Qft/ "j}} |
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Category:Letter type:L
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L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023
Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update
L-2023-042, Periodic Update of Population Data within 10 and 50 Miles of the Plant2023-03-27027 March 2023
Periodic Update of Population Data within 10 and 50 Miles of the Plant
L-2023-026, Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 42023-03-27027 March 2023
Subsequent License Renewal Application - Aging Management Requests for Additional Information Set 4
L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023
and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023
Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1
L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023
and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)
L-2023-039, Cycle 27 Core Operating Limits Report2023-03-0707 March 2023
Cycle 27 Core Operating Limits Report
L-2023-032, 2022 Annual Radioactive Effluent Release Report2023-02-28028 February 2023
2022 Annual Radioactive Effluent Release Report
L-2023-038, 2022 Annual Operating Report2023-02-28028 February 2023
2022 Annual Operating Report
L-2023-016, Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan2023-02-15015 February 2023
Radiological Emergency Plan - Revision 74 Report of Changes to Emergency Plan
L-2023-019, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 20222023-02-15015 February 2023
Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2022
L-2023-009, Owner'S Activity Report2023-01-31031 January 2023
Owner'S Activity Report
L-2022-188, Unusual or Important Environmental Event - Turtle Mortality2022-12-19019 December 2022
Unusual or Important Environmental Event - Turtle Mortality
L-2022-185, Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-12-0909 December 2022
Turkey Points, Units 3 & 4; Seabrook Station; and Point Beach, Units 1 and 2 - Supplement to License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022
Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2022-180, CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2022-11-0909 November 2022
CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
L-2022-165, Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response2022-10-26026 October 2022
Subsequent License Renewal Application - Aging Management Request for Additional Information (RAI) 4.3.1-1a(second Round) - Class 1 Fatigue Response
L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022
Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
2024-01-08
[Table view]
Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023
License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5
ML23275A1142023-10-0202 October 2023
Improved Technical Specifications Conversion, Chapter 2.0, Safety Limits, Revision 1 - Volume 4
L-2023-126, Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal2023-10-0202 October 2023
Enclosure 1: Contents of Improved Technical Specifications (ITS) Submittal
ML23275A1262023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 5.0, Administrative Controls, Revision 2 - Volume 16
ML23275A1252023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 4.0, Design Features, Revision 2 - Volume 15
ML23275A1242023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 3.9, Refueling Operations, Revision 2 - Volume 14
ML23275A1232023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 3.8, Electrical Systems, Revision 2 - Volume 13
ML23275A1222023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 3.7, Plant Systems, Revision 2 - Volume 12
ML23275A1212023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 3.6, Containment Systems, Revision 2 - Volume 11
ML23275A1192023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 2 - Volume 9
ML23275A1202023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 3.5, Emergency Core Cooling Systems, Revision 2 - Volume 10
ML23275A1182023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 3.3, Instrumentation, Revision 2 - Volume 8
ML23275A1162023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6
ML23275A1172023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 3.2, Power Distribution Limits, Revision 2 - Volume 7
ML23275A1152023-10-0202 October 2023
Improved Technical Specifications Conversion, Section 3.0, LCO and SR Applicability, Revision 2 - Volume 5
ML23275A1102023-10-0202 October 2023
License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5
ML23275A1112023-10-0202 October 2023
Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16
ML23275A1122023-10-0202 October 2023
Improved Technical Specifications Conversion License Amendment Request Self-Identified Administrative Changes - Volume 2
L-2023-082, Subsequent License Renewal Application Revision 1, Supplement 52023-06-14014 June 2023
Subsequent License Renewal Application Revision 1, Supplement 5
L-2022-175, Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2022-12-0202 December 2022
Application to Adopt 10 CPR 50.69, 'Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022
Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
L-2022-154, Subsequent License Renewal Application Revision 1, Supplement 42022-09-22022 September 2022
Subsequent License Renewal Application Revision 1, Supplement 4
L-2022-046, Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal2022-04-13013 April 2022
Subsequent License Renewal Application Revision - Documents WCAP-18623-P/NP Revision 1 Submittal
L-2022-043, Subsequent License Renewal Application Revision 1 - Supplement 12022-04-0707 April 2022
Subsequent License Renewal Application Revision 1 - Supplement 1
ML22010A0962022-01-0505 January 2022
Trp 010 St Lucie SLRA - Boricacidcorrbreakoutq - Makar
ML21285A1072021-10-12012 October 2021
Subsequent Licensee Renewal Application, Revision 1
ML21285A1082021-10-12012 October 2021
Enclosure 1: St. Lucie Nuclear Plant, Units 1 and 2, Subsequent Licensee Renewal Application, Revision 1
ML21285A1112021-10-12012 October 2021
Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report
L-2021-192, Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report2021-10-12012 October 2021
Subsequent Licensee Renewal Application, Revision 1, Appendix E, Applicant'S Environmental Report
L-2021-142, Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-08-0303 August 2021
Westinghouse Report LTR-REA-21-1-NP, Revision 1, St. Lucie Nuclear Plant, Units 1 and 2, Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021
ML21215A3152021-08-0303 August 2021
Application for Subsequent Renewed Facility Operating Licenses
ML21215A3162021-08-0303 August 2021
Enclosure 1: Subsequent License Renewal Application Enclosures Summary
ML21215A3192021-08-0303 August 2021
Appendix E - Applicant'S Environmental Report for St. Lucie
L-2021-192, Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 20212021-05-26026 May 2021
Westinghouse, Report LTR-REA-21-1-NP, Revision 1, St. Lucie Units 1 & 2 Subsequent License Renewal: Unit 1 Reactor Vessel, Vessel Support, and Bioshield Concrete Exposure Data, May 26, 2021
L-2020-164, License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements2020-12-21021 December 2020
License Amendment to Allow Risk Informed Completion Times (RICT) for the 120-Volt AC Instrument Bus Requirements
L-2020-020, License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years2020-02-18018 February 2020
License Amendment Request for RCS Pressure/ Temperature Limits and LTOP Applicable for 55 Effective Full Power Years
L-2019-091, License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements2019-10-0909 October 2019
License Amendment Request to Modify the Reactor Coolant Pump (RCP) Flywheel Inspection Program Requirements
L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019
Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG
L-2018-161, License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation2018-12-20020 December 2018
License Amendment Request to Allow Performance of Selected Emergency Diesel Generator (EDG) Surveillance Requirements (Srs) During Power Operation
L-2018-182, License Amendment Request Iodine Removal System Elimination2018-11-0909 November 2018
License Amendment Request Iodine Removal System Elimination
L-2018-201, Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-0909 November 2018
Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
L-2018-147, Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications2018-08-0202 August 2018
Submittal of License Amendment Request to Remove the Site Area Map from Technical Specifications
L-2018-121, License Amendment Request to Reduce the Number of Control Element Assemblies2018-06-29029 June 2018
License Amendment Request to Reduce the Number of Control Element Assemblies
L-2018-120, License Amendment Request to Remove the Site Area Map from the Technical Specifications2018-06-25025 June 2018
License Amendment Request to Remove the Site Area Map from the Technical Specifications
L-2018-111, Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-06-0707 June 2018
Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
L-2018-049, Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2018-05-29029 May 2018
Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications
L-2018-031, License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme2018-01-31031 January 2018
License Amendment Request Focused Adoption of NEI 99-01. Revision 6 Unusual Event Fire-Related Emergency Action Level Scheme
L-2017-155, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2017-12-19019 December 2017
Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
L-2017-139, License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply2017-09-14014 September 2017
License Amendment Request to Add New Required Actions for an Inoperable Auxiliary Feedwater Pump Steam Supply
2023-06-14
[Table view]
Category:Technical Specification
MONTHYEARL-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023
License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5
L-2023-107, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42023-09-0606 September 2023
Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2022-017, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42022-03-0707 March 2022
Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019
Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG
L-2019-076, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42019-03-28028 March 2019
Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2019-055, Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2019-03-26026 March 2019
Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications
L-2018-215, Resubmittal of Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-30030 November 2018
Resubmittal of Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
L-2018-178, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42018-10-0202 October 2018
Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
ML18096B4482018-04-0606 April 2018
Proposed Technical Specifications
L-2017-166, Submittal of Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42017-09-20020 September 2017
Submittal of Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2017-077, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42017-05-0404 May 2017
Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2017-041, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month,' Using the Consolidated Line Item Improvement Process2017-03-30030 March 2017
Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month,' Using the Consolidated Line Item Improvement Process
L-2016-227, License Amendment Request Change to P /T Limit Curve and LTOP Period of Applicability2016-12-22022 December 2016
License Amendment Request Change to P /T Limit Curve and LTOP Period of Applicability
L-2016-087, Florida Power & Light Company, on Periodic Report of Changes to the St. Lucie Unit 2 Technical Specification Base2016-04-15015 April 2016
Florida Power & Light Company, on Periodic Report of Changes to the St. Lucie Unit 2 Technical Specification Base
L-2016-008, Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle2016-01-19019 January 2016
Application for Technical Specification Change Regarding Moderator Temperature Coefficient (Mtc) Surveillance Test Elimination at the End of Cycle
ML15280A3922015-10-19019 October 2015
Correction to Amendment Nos. 226 and 176 Change to Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program.
L-2015-222, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.42015-10-15015 October 2015
Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4
L-2015-180, Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR2015-06-30030 June 2015
Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR
ML15198A0302015-06-30030 June 2015
St. Lucie, Units 1 and 2 - Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR
L-2015-091, St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel2015-03-23023 March 2015
St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel
ML15084A0112015-03-23023 March 2015
St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel
L-2015-030, Application for Technical Specifications Changes to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents2015-03-10010 March 2015
Application for Technical Specifications Changes to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents
L-2014-230, License Amendment Request Application for Technical Specifications Change to Permanently Extend the Integrated Leak Rate Test (ILRT) Frequency to 15 Years2014-08-26026 August 2014
License Amendment Request Application for Technical Specifications Change to Permanently Extend the Integrated Leak Rate Test (ILRT) Frequency to 15 Years
L-2014-205, Application for Technical Specification Change to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents2014-08-0808 August 2014
Application for Technical Specification Change to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents
L-2014-160, Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C, Using the Consolidated Line Item Improvement Process2014-08-0707 August 2014
Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6B & 6C, Using the Consolidated Line Item Improvement Process
L-2014-124, Technical Specification Bases Control Program Periodic Report of Bases Change TS 6.8.4.j.42014-05-0707 May 2014
Technical Specification Bases Control Program Periodic Report of Bases Change TS 6.8.4.j.4
L-2013-233, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2014-02-26026 February 2014
Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
L-2014-015, Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2014-02-20020 February 2014
Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
L-2014-027, Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements2014-01-30030 January 2014
Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements
L-2012-362, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.42012-10-0101 October 2012
Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4
L-2012-048, License Amendment Request, Station Battery Surveillance Requirement Changes2012-08-10010 August 2012
License Amendment Request, Station Battery Surveillance Requirement Changes
L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages2011-02-25025 February 2011
St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages
L-2011-021, St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups2011-02-25025 February 2011
St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups
ML1107302982011-02-25025 February 2011
St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups
ML1107302842011-02-25025 February 2011
St. Lucie, Unit 2 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages
L-2010-259, St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages2010-12-15015 December 2010
St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages
ML1035604272010-12-15015 December 2010
St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 3; Renewed Facility Operating License and Technical Specifications Markups and Clean Pages
L-2010-259, St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups2010-12-15015 December 2010
St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups
ML1035604282010-12-15015 December 2010
St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 4; Technical Specifications Bases Markups
ML1011601922010-04-16016 April 2010
Attachment 4, St. Lucie License Amendment Request Extended Power Uprate, Technical Specifications Bases Markups (for Information Only)
L-2010-078, Attachment 4, St. Lucie License Amendment Request Extended Power Uprate, Technical Specifications Bases Markups (for Information Only)2010-04-16016 April 2010
Attachment 4, St. Lucie License Amendment Request Extended Power Uprate, Technical Specifications Bases Markups (for Information Only)
L-2009-099, Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.42009-04-21021 April 2009
Technical Specification Bases Control Program, Periodic Report of Bases Changes TS 6.8.4.j.4
L-2008-120, Proposed License Amendments Diesel Fuel Oil Test Program TSTF-3742008-07-10010 July 2008
Proposed License Amendments Diesel Fuel Oil Test Program TSTF-374
L-2008-149, Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42008-06-26026 June 2008
Technical Specification Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
L-2007-198, Proposed License Amendment Update PT Curve and LTOP for 55 EFPY2008-01-23023 January 2008
Proposed License Amendment Update PT Curve and LTOP for 55 EFPY
L-2007-168, Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.42007-10-29029 October 2007
Technical Specifications Bases Control Program Periodic Report of Bases Changes TS 6.8.4.j.4
ML0729808602007-10-22022 October 2007
Tech Spec Pages for Amendments 202 and 149 Regarding Minor Changes and Corrections to the Technical Specifications
L-2007-087, Proposed License Amendment, Alternative Source Term and Conforming Amendment2007-07-16016 July 2007
Proposed License Amendment, Alternative Source Term and Conforming Amendment
L-2007-028, Proposed License Amendments, Removal of Hydrogen Recombiners and Analyzers from Technical Specifications2007-06-0404 June 2007
Proposed License Amendments, Removal of Hydrogen Recombiners and Analyzers from Technical Specifications
L-2006-264, Technical Specification Bases Control Program Periodic Record of Bases Changes TS 6.8.4.j.42006-12-0505 December 2006
Technical Specification Bases Control Program Periodic Record of Bases Changes TS 6.8.4.j.4
2023-09-06
[Table view]
Category:Amendment
MONTHYEARL-2023-168, License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 52023-12-12012 December 2023
License Amendment Request Supplement to Revision 2 for the Technical Specifications Conversion to NUREG-1432 Revision 5
L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG2019-07-19019 July 2019
Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG
L-2019-055, Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications2019-03-26026 March 2019
Stations - Supplement to Application to Add Limiting Condition for Operation (LCO) 3.0.6 to the Technical Specifications
L-2018-215, Resubmittal of Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2018-11-30030 November 2018
Resubmittal of Fourth Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML18096B4482018-04-0606 April 2018
Proposed Technical Specifications
L-2016-227, License Amendment Request Change to P /T Limit Curve and LTOP Period of Applicability2016-12-22022 December 2016
License Amendment Request Change to P /T Limit Curve and LTOP Period of Applicability
ML15280A3922015-10-19019 October 2015
Correction to Amendment Nos. 226 and 176 Change to Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program.
L-2015-180, Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR2015-06-30030 June 2015
Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR
ML15198A0302015-06-30030 June 2015
St. Lucie, Units 1 and 2 - Proposed TS Changes for TSTF-523 LAR Incorporating Approved TSTF-425 LAR
L-2015-091, St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel2015-03-23023 March 2015
St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel
ML15084A0112015-03-23023 March 2015
St. Lucie, Unit 2 - Supplemental Information for Technical Specification Change and Exemption Request Regarding the Transitioning to Areva Fuel
L-2015-030, Application for Technical Specifications Changes to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents2015-03-10010 March 2015
Application for Technical Specifications Changes to Remove Communications and Manipulator Crane Requirements and Relocate to Licensee-Controlled Documents
L-2014-205, Application for Technical Specification Change to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents2014-08-0808 August 2014
Application for Technical Specification Change to Remove RCS Chemistry Requirements and Relocate to Licensee-Controlled Documents
L-2014-027, Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements2014-01-30030 January 2014
Fourth Ten-Year Inservice Inspection Interval License Amendment Request, Changes to Snubber Surveillance Requirements
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ML18088B2641978-03-20020 March 1978
Proposed Amendment for Operating License DPR-67 to Support the Replacement of Selected Safety-Related Hydraulic During Upcoming Refueling Outage
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L-77-339, Proposed Amendment to Facility Operating License No. DPR-67. Proposed Change Concerns Deletion of the Requirement for Annual Operating Report1977-11-0101 November 1977
Proposed Amendment to Facility Operating License No. DPR-67. Proposed Change Concerns Deletion of the Requirement for Annual Operating Report
ML18088B3051977-09-16016 September 1977
Attachment C to L-77-291 Proposed Technical Specification Changes
L-77-214, Proposed Amendment to Facility Operating License. Relationship Between Linear Heat Rate & Thermal Power in Specification 4.2.1.3.c Is Revised & Rod Bow Penalty Factor in Specification 4.2.1.4.b Is Deleted1977-07-0707 July 1977
Proposed Amendment to Facility Operating License. Relationship Between Linear Heat Rate & Thermal Power in Specification 4.2.1.3.c Is Revised & Rod Bow Penalty Factor in Specification 4.2.1.4.b Is Deleted
2023-12-12
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Text
,M - BBS NRC FoRM 196 U,S, NUCLEAR REGULATORY Co SION DOCKET NUMIIFR Ig.7BI FILE NUMBER
~gRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL 4
TQr FROM: DATE OF DOCUMENT Florida Power Bc Light Company 5/20/77 Miami, Florida DATE RECEIVED Mr. Victor Stello Ri E ~ Uhrig 5/23/77 g .'ETTER PNOTORI2ED PROP INPUT FORM NUMBER OF COPIES RECEIVED D ~icA~-
g<)RIGINAL NC LASS I F I E 0 P COPY, DESCRIPTION ENCLOSURE
~ ~ ~ ~ ~ ~ to OL/change to.Appendix A tech I'mdti I
R specs', notoriz'ed 5/20/77 ' re secondary--
water chemzstry program ~ ~ ~ ~ ~
I.iu [( i'I$ @LLlg (3-P) (5-P) muon ilBkl[E PLANT NAME:
'St+ Lucie Unit No. 1 RJL SAFETY FOR ACTION/INFORMATION ASSIGNED AD:
NQH QK CKXP
~RO ~Ol IANAG PROJECT MANAGER L C ASST LXC ASST INTERNAL D IST RI BUTION
~ REG FIT SYSTEMS SAFETY PLANT SYSTEMS SXTE SAFE PDR HEXNEIIAN TEDESCO I & E SCHROEDER OELD GOSSICK & STAFF ENGXNEERXNG XPPOLXTO E MIPC MACARRY ERNST CASE BOSNAK BALLARD HANAUER SXINEXL OPERATING REACTORS YOUNCBLOOD HARLESS PAWLXCK STELLO SXTE TECH PROJECT MANAGEIKNT REACTOR SAFE OPERATING TECH GAMMXLL BOYD ROSS EISENHUT STEPP P COLLINS HULMAN HOUSTON ROSZTOCZY PETERSON CHECK SITE ANALYSIS MELTZ VOLLIIER HELTEMES AT& I BIJNCH SKOVIIOLT SALTZMAN J~ COLLINS RIJTBERG KREGER EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR NAT LAB 0+KjQgp TIC: REG V IE ULRIKSON QRN NSIC: LA PDR 771440 1 i%
ASLB: CONSULTANTS!
ACRS CYS RMMSlG/ E T CrPf
P.O. BOX 3100 MIAMI, FLORIDA 33101 p',.
FLORIDA POWER & LIGHT COMPANY May'20, 1977 L-77-151 CJ RBgglgtOT'J f$B Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director U. S.
Division of Operating Records Nuclear Regulatory Commission . aECf ) .
Washington, D.C. 20555 MAY23 197/~
LI,II, FeaFAR atOUPIOC
Dear Mr. Stello:
9'e:
St. Lucie Unit 1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 A November 15, 1976 letter from Mr. Dennis L. Ziemann of your staff requested that we submit a secondary water chemistry program for inclusion in our St. Lucie Unit 1 Technical Specifications. We have considered the bases and effects of such technical specifi-cations and have concluded that, for the following reasons, limiting conditions for operation should not be placed on secondary water chemistry:
- l. The safety aspects of steam generator pressure boundary integrity are addressed by Technical Specification 3.4.6.2.C. This specification establishes a steam generator tube leakage limit and requirements for plant shutdown should the limit be exceeded.
- 2. Technical Specification 4.4.5 is directed toward ensuring the integrity of steam generators by means of eddy current testing consistent with Regulatory Guide 1.83, "Xnservice Xnspection of Pressurized Water Reactor Steam Generator Tubes." Such testing provides a means by which the integrity of individual tubes can be evaluated during periodic planned outages.
- 3. Technical Specification 4.4.5 is directed toward assuring the integrity of the steam generators without identifying the causes, if any, of their possible degradation. Potential causes might be deficiencies in design (including material selection), quality assurance, installation, and primary or secondary environments of the steam generator. Lengthy techni-cal specifications could conceivably be written to bar each potential cause of degradation. This would not, HELPING BUILD FLORIDA
P II A
El k
,l)irector of Nuclear ctor Regulation Page 2 April 5, 1977 however, be consistent with our understanding of the purpose of technical specifications as authorized by the Atomic Energy Act and as utilized by the Nuclear Regula-tory Commission.
We understand that the purpose of technical specifications is to identify those parameters of design and operation whose violation, by some margin, would or could present an unacceptable safety risk. Thus, the term "limiting condi-tions for operation" is defined in 10 CFR 50.36(c) (2) as "the lowest functional capability of performance levels of equipment required for safe operation of the facility."
Xt is therefore appropriate to place a technical specifi-cation limit on the leakage through a primary boundary such as the steam generator tubing. However, in our judgment, it would not be appropriate to write a technical specification addressing the potential causes of degradation of such boundaries.
- 4. Technical specifications would be particularly inappropriate to secondary water chemistry parameters whose equilibrium conditions fluctuate during normal plant operational modes, such as power changes, startups and shutdowns. There is no evidence that short-term variations in secondary water chemistry are significant to steam generator tube integrity.
Technical specification limitations on such fluctuations could only res'ult in enforcement problems, lack of operational flexibility and diminution of the safety significance of technical specifications. Deviations from secondary water quality guidelines are not a safety problem and are therefore not appropriately the subject of technical specifications; the condition of steam generator tubes, on the other hand, is appropriate for such consideration and technical speci-fications exist to provide for direct monitoring of the condition of the steam generator tubes in order to assure that continued integrity is maintained.
- 5. The unnecessary proliferation of technical specifications should be avoided. Since the addition, deletion or revi-sion of technical specifications involves the formal, time-consuming license amendment process, the technical specifications should contain only those requirements that are directly relatable to safe operation, Other means should be utilized for providing direction on matters that, are indirectly related to the safety of operation. There are many examples of this philosophy at operating plants, wherein many operating practices, procedures, tests, plans, etc., are covered by means other than the imposition of technical specifications.
- 6. The November 15, 1976 letter also addresses the need for continual monitoring and control of steam side water chemistry in order to ensure against an accumulation of harmful impurities in the steam generators. We agree that for long-term reliability and continued assurance of tube integrity, a chemistry
iDirector of Nuclear R tor Regulation Page 3 April 5, 1977 control program is necessary. The specific chemistry guidelines are periodically updated in conjunction with the steam system supplier recommendations. Chemistry data and records are maintained at the plant site and are subject to review by the NRC or any other authorized activity.
Regulatory review can then result in,a critique of our ability to maintain chemistry within established guidelines and can result in corrective action when necessary.
The above arguments against limiting conditions for operation also apply to detailed surveillance requirements, however, an entry into the technical specifications requiring that a surveillance program be practiced is not objectionable. Therefore, we have prepared a proposed amendment along those lines and now submit it. for your review. Xn accordance with 10 CFR 50.30, three (3) originals and forty (40) copies of the proposal to amend Appendix A of Operating License DPR-67 are hereby submitted for your consideration. The proposed changes are described below and shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner.
Pages 3/4 7-10 through 7-12 Specification 3.7.1.6 is revised and Specification 4.7.1.6 is revised to refer to approved plant procedures.
Page B 3/4 7-3 Bases section 3/4.7.1.6 is revised to be consistent with our position on secondary water chemistry.
The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power a. Light Company Nuclear Review Board. They have concluded that safety question.
it does not involve an unreviewed Very yours, R. E. Uhrig Vice President REU/MAS/pg Attachment cc: Norman C. Moseley, Region XI Robert Lowenstein, Esquire
I l
l' r-a
PLANT SYSTEMS SECONDARY lJATER CHEMISTRY LIMITIHG CONDITION FOR OPERATION 3.7.1.6 There are no 1imiting conditions for operation associated with secondary water chemistry.
SURVEILLANCE REQUIREMENTS 4.7.1.6 The secondary ~ater chemistry shall 'be determined to be within procedural limits by analysis in accordance with approved plant procedures.
ST. LUCIE - UNIT 1 3/4 7-10 . 5/20/77
BLANK ST. LUCIE UNIT 1 3/a 7-zz
1 BLANK ST. LUCIE UNIT 1 3/4 7-12
PLANT SYSTEHS BASES 3/4.7.1.5 HAIN STEAH LINE ISOL'ATION VALVES
\
The OPERABILITY of the main steam line iso'lation valves no more than one steam generator will blowdown in the event ensures'hat of a steam 'line rupture.'This r estriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown --
associated with the blowdown, and 2) limit the pressure-rise within containment in the event the steam 'line rupture occurs within contain-ment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions "used in the accident analyses.
3/4.7.1.6 SECONDARY llATER CllEHISTRY Operating history wi11 be used to establish appropriate limits
,on secondary ~ater chemistry,and to determine appropriate frequencies for monitoring these parameters. Approved plant procedures will be used to administratively control secondary water chemistry.
3/4.7. 2 STEAN GENERATOR PRESSURE/TEHPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators'. do not exceed the maximum allowable fracture toughness stress limits. 'The limitations of 70'F and 200-'psig are based on a steam generator RTNDT of 50'F and are sufficient to prevent brittle fracture.
ST. LUCIE - UNIT 1 B 3/4 7-3 5/20/77
STATE OF FLORlDA )
) ss COUNTY OF DADE )
being first duly sworn, deposes and says:
That he Light is herein'f Executive Vice Preside Company, the Licensee Florida Power 6 That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the
. best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee E. . Adomat Subscribed and sworn to before me this day of NOTARY P BLOC, in and for the County of Dade, State o Florida "MATE QF PLORiDA COMIAISSION EXPIRES JAN.
'Y 26, )979 ENDED ThRLI GENLRAL INSURANCE UNDERWR(IERS My commission expires:
RECQyFg
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