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| {{#Wiki_filter:REGULA Y INFORMATION DISTRIBUTI YSTEM (RIDS)ACCESSION NBR: 8802090521 DOC.DATE: 88/02/03 NQTAR I ZED: YES DOCKET FACIL: 50-250 Turkey Point Planti Unit 3i Florida Power and Light C 05000250 50-251 Turkey Point Planti Unit 4i Florida Poeer and Light C 05000251 AUTH.NAME AUTHOR AFFILIATION NOODYi C.O.Florida Power 5 Light Co.REC IP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | | {{#Wiki_filter:REGULA Y INFORMATION DISTRIBUTI YSTEM (RIDS) |
| | ACCESSION NBR: 8802090521 DOC. DATE: 88/02/03 NQTAR I ZED: YES DOCKET FACIL: 50-250 Turkey Point Planti Unit 3i Florida Power and Light C 05000250 50-251 Turkey Point Planti Unit 4i Florida Poeer and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION NOODYi C. O. Florida Power 5 Light Co. |
| | REC IP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application for amends to Licenses DPR-31 8c DPR-41>taking current requirement For safety ingectionaccumulators consolidating requirements into one limiting condition for operation section 8c one surveillance section.Fee paid.DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR)ENCL I SIZE: TITLE: OR Submittal: | | Application for amends to Licenses DPR-31 8c DPR-41> taking current requirement For safety ingection accumulators consolidating requirements into one limiting condition for operation section 8c one surveillance section. Fee paid. |
| General Distribution NOTES: REC IP KENT ID CODE/NAME PD2-2 LA EDISONi G COPIES LTTR ENCL 0 1 REC IP IENT ID CODE/NAME PD2-2 PD COPIES LTTR ENCL 5 5 INTERNAL: ARM/DAF/LFMB NRR/DEBT/CEB NRR/DEBT/RSB NRR/P RB 01 EXTERNAL: LPDR NSIC 0 1 1 1 1 1 1 1 1 1 NRR/DEBT/*DS NRR/DEST/MTB NRR/DOEA/TSB OGC/HDS2 RES/DE/EIB NRC PDR 1 1 1 1 1 1 1 0 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 17 V e,!'4 f, h P.O.14000, JUNO BEACH, FL 33408.0420 | | DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR ) ENCL I SIZE: |
| +/1<~<6~FEBRUARY.3 1988 L-88-50 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
| | TITLE: OR Submittal: General Distribution NOTES: |
| Re: Turkey Point Units 3 and 4 Docket Nos.50-250 and 50-251 Proposed License Amendment Safet In'ection Accumulators By letter dated September 29, 1986 (FPL letter L-86-393)Florida Power&Light Company (FPL)submitted a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41 to upgrade the current plant Technical Specifications and include, within limitations, the guidance of NUREG-0452, Standard Technical Specifications (STS)for Westinghouse Pressur'ized Water Reactors.The proposed changes remove the custom versions of the limiting condition for operation and surveillance requir'ements for the accumulators from Technical'Specifications 3.4 and 4.1 and place them in a separate section in the STS format with additional STS requirements.
| | REC IP KENT COPIES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 0 PD2-2 PD 5 5 EDISONi G 1 INTERNAL: ARM/DAF/LFMB 0 NRR/DEBT/*DS 1 1 NRR/DEBT/CEB 1 NRR/DEST/MTB 1 1 NRR/DEBT/RSB 1 NRR/DOEA/TSB 1 1 NRR/P RB 1 1 OGC/HDS2 1 0 01 1 1 RES/DE/EIB 1 EXTERNAL: LPDR 1 NRC PDR 1 1 NSIC 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 17 V |
| FPL requests that these changes be reviewed and issued independent of the technical specification upgrade review effort.This separate issuance will provide the collective action discussed in our response to Inspection Report 87-35 to preclude further recurrence of operating problems associated with the chemical sampling of the accumulators.
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| PLP/004.PLA I'880209052i 880203 PDR ADOCN, 05000250 P.PDR~pool>(k~)c rr t(<'~(gy an FPL Group compan+
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| ~H'I 1 U.S.Nuclear Regulatory Commission L-88-50 Page two The proposed specification and supporting documentation, are attached.In accordance with 10 CFR 50.91(b)(1), a copy of this proposed license amendment is being forwarded to the State Designee for the State of Florida.In accordance with 10 CFR 170.12(c), FPL Check No.7153 for$150 is attached as remittance for the licensee amendment application fee.The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.If there are any questions, please call us.Very truly yours, C.0.ody Exec ave Vice President COW/PLP/gp Attachments cc: Dr.J.Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Mr.Jacob Nash, Florida Dept.of Health and Rehabilitative Services PLP/004.PLA STATE OF FLORlDA))ss.COUNTY OF PALM BEACH)~C.O.W d fd d!,d d That he is Executive Vice President of Florida Power Bc Light Company, the Licensee herein;That he has executed the foregoing document;that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.C.0 dy Subscribed and sworn to before me this , l9~.j>>0 d'gP WJ/d s NOTARY!PQBLIC, in and for the County:,~'.~,,of Palm 8'each, State of Florida HOIARY PUBLIC SIAIE OF FLORIDA NY COHttISSION EXP SEPt l8,1989~BOttOEO THRU GENERAL ItiS.Uti0 My Commission expires:
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| d*P)I Pv I A TURKEY POINT UNITS 3 AND 4 PROPOSED LICENSE AMENDMENT PLA-051 TITLE: ACCUMULATORS DESCRIPTION:
| |
| This proposed amendment to the Turkey Point Technical Specifications (TS)takes the current requirement for the safety injection accumulators from several TS sections and consolidates the requirements into one limiting condition for operation (LCO)section and one surveillance section.This proposed change has been drafted following the guidelines of NUREG 0452, Standardized Technical Specifications for Westinghouse Pressurized Water Reactors (WSTS)and the proposed Upgraded Technical Specifications submitted to the NRC on September 30, 1986 as a part of the Performance Enhancement Program (PEP).The changes are as follows: Pacae i The Table of Contents has been revised to reflect the changes described below., Pa es 1-7 1-8 1-9 These pages of definitions have been consolidated to allow the addition of a definition for the ANALOG CHANNEL OPERATIONAL TEST.TABLE 1.1 The Average Coolant Temperature requirement for Mode 5 (cold shutdown)has been revised to correct a typographical error.This requirement has been revised to read less than or equal to 200 F.Pa es 3.4-1 3.4-2 and 3.4-2.a The requirements for the accumulators have been deleted and the other sections renumbered as required.PLP/004.PLA a'
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| Pa e 3.4-2.b A new TS section (3.4.1.f)has been added describing the LCO and action requirements for the accumulators.
| |
| The operability requirements were revised as follows: The contained borated water volume was converted from cu.ft.to gallons (875-891 cu.ft.vs 6545-6665 gallons)to reflect installed instrumentation; upper bounds for boron concentration (2350 ppm)and nitrogen cover pressure (675psig)were added.The revised LCO is consistent with the accumulator design parameters specified in the FSAR (Table 6.2-4).The LCO applicability was extended to include Mode 3 (with pressurizer pressure above 1000 psig).This is more conservative than the current TS requirements which specify that the reactor is not to be made critical except, for low power physics tests, unless the accumulators are operable.The action requirements were revised using the WSTS as guidance.The proposed action statements for one accumulator inoperable, except as a result of a closed isolation valve, and one accumulator inoperable due to the isolation valve being closed, are more conservative than the current TS requirements in that.they require that the plant be placed in a mode where the capability of the accumulators is not required (i.e.pressurizer pressure less than 1000 psig)in a shorter time than required by the current TS.The current TS would allow the plant to be kept in hot shutdown (reactor subcritical and with Tavg above 540 F)for a maximum of 48 hours before going to c'old shutdown.Plant procedures for going from hot standby to cold shutdown require that the accumulators be isolated from the RCS when the pressurizer pressure is between 1000 psig and 700 psig.Since the accumulators are isolated and no"longer required, there, is no requirement to take the, plant all the way to cold shutdown as specified in the current TS.Table 4.1-1 Sheet 2 Table 4.1-2 Sheet 2 and Pa e 4.5-2 The surveillance requirements for the accumulators have been removed from these TS sections and other sections have been renumbered as required."PLP/004.PLA
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| )q R j4 Pa e 4.5-3 A new section has been added to consolidate the accumulator surveillance requirements.
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| In addition-to the current'equirements, a once per shift surveillance to verify that the isolation valves are open and to verify that the power supply to the isolation valves is disconnected by a locked open breaker was added.Also a monthly ANALOG CHANNEL OPERATIONAL TEST has been added for the level and pressure channels.Pa es B3.4-1 and B3.4-2 The previous basis section for the accumulators has been deleted and a new basis section has been added.The new basis sections conforms to the WSTS format and the Turkey Point Final Safety Analysis Report.Pa e B4.5-1 The references to accumulators has been deleted because the basis section added to B3.4 adequately describes the basis for the accumulator TS requirements.
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| PLP/004.PLA 0
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| BASIS FOR NO SIGNXFXCANT HAZARDS CONSIDERATXON DETERMINATION The standards used to arrive at a proposed determination that the changes described above involve no significant, hazards consideration are included in 10CFR50.92.
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| The regulations state that if operation of the facility in accordance with the proposed amendment could not: (1)involve a significant increase in the probability or consecpxences of an accident previously evaluated, or (2)create the possibility of a new or different kind of accident from any accident previously evaluated, or (3)involve a significant reduction in a margin of safety, then a no significant hazards determination can be made.Operation of Turkey Point Units 3 and 4 in accordance with the proposed amendments would not: (1)and (2)involve asignificant increase in the probability or consequences of an accident previously evaluated, or create the possibility of a new or different kind of accident, from any accident previously evaluated.
| |
| The proposed changes are either administrative (i.e., consolidation of accumulator LCO, action and surveillance requirements in a separate section, conversion of the borated water volume from cu.ft.to gallons), or provide requirements that are as restrictive or more restrictive than the current requirements (i.e., upper bounds on boron concentration and nitrogen cover pressure, broader mode applicability, action requirements requiring the plant to be placed in a mode where the capability of the accumulators is not required in a shorter time period, and additional surveillance requirements).
| |
| They are consistent with the design basis, and do not affect the assumptions used for accumulator injection in the safety analyses.The action required in the event of an inoperable accumulator is to place the plant in a mode where capability of the accumulators is not required,, which is consistent with the intent of the current TS.(3)involve a significant reduction in a margin of safety.The action requirement to reduce pressure to less than 1000 psig rather than go to cold shutdown, as required by the current TS, would not result in a reduction in a margin of safety since the plant would similarly be placed in a mode where the accumulators are not recpxired to be operable.In addition, the Commission has provided guidance concerning the application of standards for determination whether a significant hazards consideration exists by providing certain examples (48 FR 14870)of amendments that are considered not likely to involve a significant hazards consideration.
| |
| Example (1)relates to a purely administrative change to Technical Specifications:
| |
| correction of an error, or a change in nomenclature.
| |
| Example (ii)relates to a change that constitutes an additional
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|
| |
|
| limitation, restriction, or control not presently included in the Technical Specifications: | | e, |
| for example, a more stringent surveillance requirement. | | !' |
| (1)The proposed change as described above is similar to example (i)of 48 FR 14870 in that it is an administrative change which consolidates current requirements for the accumulators into a technical specification format consistent with the Standard Technical Specifications, and converts the required borated water volume from cu.ft.to gallons.(2)The proposed change as described above is similar to example (ii)of 48 FR 14870 in that it provides additional restrictions in the form of mode applicability requirements, upper bounds on the accumulator boron concentration and nitrogen cover pressure, shorter required action time limits, and additional surveillance requirements. | | 4 f, |
| Based on the above considerations, the changes included in the proposed amendment are not considered to involve a significant hazards consideration as defined in 10CFR50.92. | | h |
| Further, there is reasonable assurance that the health and safety of the public will not be endangered by the proposed changes.PLP/004.PLA}} | | |
| | P. O. 14000, JUNO BEACH, FL 33408.0420 |
| | +/1<~<6~ |
| | FEBRUARY. 3 1988 L-88-50 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| | Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed License Amendment Safet In'ection Accumulators By letter dated September 29, 1986 (FPL letter L-86-393) |
| | Florida Power & Light Company (FPL) submitted a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41 to upgrade the current plant Technical Specifications and include, within limitations, the guidance of NUREG-0452, Standard Technical Specifications (STS) for Westinghouse Pressur'ized Water Reactors. |
| | The proposed changes remove the custom versions of the limiting condition for operation and surveillance requir'ements for the accumulators from Technical |
| | 'Specifications 3.4 and 4.1 and place them in a separate section in the STS format with additional STS requirements. |
| | FPL requests that these changes be reviewed and issued independent of the technical specification upgrade review effort. |
| | This separate issuance will provide the collective action discussed in our response to Inspection Report 87-35 to preclude further recurrence of operating problems associated with the chemical sampling of the accumulators. |
| | pool PLP/004.PLA |
| | > ( |
| | I'880209052i 880203 k PDR ADOCN, 05000250 ~)c rr P. PDR ~ t(<'~(gy an FPL Group compan+ |
| | |
| | ~ H |
| | 'I 1 |
| | |
| | U. S. Nuclear Regulatory Commission L-88-50 Page two The proposed specification and supporting documentation, are attached. |
| | In accordance with 10 CFR 50.91(b)(1), a copy of this proposed license amendment is being forwarded to the State Designee for the State of Florida. |
| | In accordance with 10 CFR 170.12(c), FPL Check No. 7153 for |
| | $ 150 is attached as remittance for the licensee amendment application fee. |
| | The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board. |
| | If there are any questions, please call us. |
| | Very truly yours, C. 0. ody Exec ave Vice President COW/PLP/gp Attachments cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Mr. Jacob Nash, Florida Dept. of Health and Rehabilitative Services PLP/004.PLA |
| | |
| | STATE OF FLORlDA ) |
| | ) ss. |
| | COUNTY OF PALM BEACH ) |
| | ~C.O.W d fd d!,d d That he is Executive Vice President of Florida Power Bc Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee. |
| | C. 0 dy Subscribed and sworn to before me this |
| | , l9~. |
| | j>> 0 d'gP WJ/ d s NOTARY!PQBLIC, in and for the County |
| | :,~'. ~,,of Palm 8'each, State of Florida HOIARY PUBLIC SIAIE OF FLORIDA NY COHttISSION EXP SEPt l8,1989 BOttOEO THRU GENERAL ItiS. Uti0 My Commission expires: ~ |
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| | d Pv |
| | * I P I) |
| | A |
| | |
| | TURKEY POINT UNITS 3 AND 4 PLA-051 PROPOSED LICENSE AMENDMENT TITLE: ACCUMULATORS DESCRIPTION: |
| | This proposed amendment to the Turkey Point Technical Specifications (TS) takes the current requirement for the safety injection accumulators from several TS sections and consolidates the requirements into one limiting condition for operation (LCO) section and one surveillance section. This proposed change has been drafted following the guidelines of NUREG 0452, Standardized Technical Specifications for Westinghouse Pressurized Water Reactors (WSTS) and the proposed Upgraded Technical Specifications submitted to the NRC on September 30, 1986 as a part of the Performance Enhancement Program (PEP). The changes are as follows: |
| | Pacae i The Table of Contents has been revised to reflect the changes described below. |
| | , Pa es 1-7 1-8 1-9 These pages of definitions have been consolidated to allow the addition of a definition for the ANALOG CHANNEL OPERATIONAL TEST. |
| | TABLE 1.1 The Average Coolant Temperature requirement for Mode 5 (cold shutdown) has been revised to correct a typographical error. |
| | This requirement has been revised to read less than or equal to 200 F. |
| | Pa es 3.4-1 3.4-2 and 3.4-2.a The requirements for the accumulators have been deleted and the other sections renumbered as required. |
| | PLP/004.PLA |
| | |
| | ' a Pa e 3.4-2.b A new TS section (3.4.1.f) has been added describing the LCO and action requirements for the accumulators. |
| | The operability requirements were revised as follows: |
| | The contained borated water volume was converted from cu. |
| | to gallons (875-891 cu. ft. vs 6545-6665 gallons) to reflect ft. |
| | installed instrumentation; upper bounds for boron concentration (2350 ppm) and nitrogen cover pressure (675psig) were added. The revised LCO is consistent with the accumulator design parameters specified in the FSAR (Table 6.2-4) . |
| | The LCO applicability was extended to include Mode 3 (with pressurizer pressure above 1000 psig). This is more conservative than the current TS requirements which specify that the reactor is not to be made critical except, for low power physics tests, unless the accumulators are operable. |
| | The action requirements were revised using the WSTS as guidance. The proposed action statements for one accumulator inoperable, except as a result of a closed isolation valve, and one accumulator inoperable due to the isolation valve being closed, are more conservative than the current TS requirements in that. they require that the plant be placed in a mode where the capability of the accumulators is not required (i.e. pressurizer pressure less than 1000 psig) in a shorter time than required by the current TS. The current TS would allow the plant to be kept in hot shutdown (reactor subcritical and with Tavg above 540 F) for a maximum of 48 hours before going to c'old shutdown. Plant procedures for going from hot standby to cold shutdown require that the accumulators be isolated from the RCS when the pressurizer pressure is between 1000 psig and 700 psig. Since the accumulators are isolated and no "longer required, there, is no requirement to take the, plant all the way to cold shutdown as specified in the current TS. |
| | Table 4.1-1 Sheet 2 Table 4.1-2 Sheet 2 and Pa e 4.5-2 The surveillance requirements for the accumulators have been removed from these TS sections and other sections have been renumbered as required. |
| | "PLP/004.PLA |
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| | )q R |
| | j4 |
| | |
| | Pa e 4.5-3 A new section has been added to consolidate the accumulator surveillance requirements. In addition -to the a once per shift surveillance to verify that current'equirements, the isolation valves are open and to verify that the power supply to the isolation valves is disconnected by a locked open breaker was added. Also a monthly ANALOG CHANNEL OPERATIONAL TEST has been added for the level and pressure channels. |
| | Pa es B3.4-1 and B3.4-2 The previous basis section for the accumulators has been deleted and a new basis section has been added. The new basis sections conforms to the WSTS format and the Turkey Point Final Safety Analysis Report. |
| | Pa e B4.5-1 The references to accumulators has been deleted because the basis section added to B3.4 adequately describes the basis for the accumulator TS requirements. |
| | PLP/004.PLA |
| | |
| | 0 BASIS FOR NO SIGNXFXCANT HAZARDS CONSIDERATXON DETERMINATION The standards used to arrive at a proposed determination that the changes described above involve no significant, hazards consideration are included in 10CFR50.92. The regulations state that if operation of the facility in accordance with the proposed amendment could not: (1) involve a significant increase in the probability or consecpxences of an accident previously evaluated, or (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety, then a no significant hazards determination can be made. |
| | Operation of Turkey Point Units 3 and 4 in accordance with the proposed amendments would not: |
| | (1) and (2) involve a significant increase in the probability or consequences of an accident previously evaluated, or create the possibility of a new or different kind of accident, from any accident previously evaluated. |
| | The proposed changes are either administrative (i.e., |
| | consolidation of accumulator LCO, action and surveillance requirements in a separate section, conversion of the borated water volume from cu. ft. to gallons), or provide requirements that are as restrictive or more restrictive than the current requirements (i.e., upper bounds on boron concentration and nitrogen cover pressure, broader mode applicability, action requirements requiring the plant to be placed in a mode where the capability of the accumulators is not required in a shorter time period, and additional surveillance requirements). They are consistent with the design basis, and do not affect the assumptions used for accumulator injection in the safety analyses. The action required in the event of an inoperable accumulator is to place the plant in a mode where capability of the accumulators is not required,, which is consistent with the intent of the current TS. |
| | (3) involve a significant reduction in a margin of safety. |
| | The action requirement to reduce pressure to less than 1000 psig rather than go to cold shutdown, as required by the current TS, would not result in a reduction in a margin of safety since the plant would similarly be placed in a mode where the accumulators are not recpxired to be operable. |
| | In addition, the Commission has provided guidance concerning the application of standards for determination whether a significant hazards consideration exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve a significant hazards consideration. Example (1) relates to a purely administrative change to Technical Specifications: |
| | correction of an error, or a change in nomenclature. Example (ii) relates to a change that constitutes an additional |
| | |
| | limitation, restriction, or control not presently included in the Technical Specifications: for example, a more stringent surveillance requirement. |
| | (1) The proposed change as described above is similar to example (i) of 48 FR 14870 in that change which consolidates it is an administrative current requirements for the accumulators into a technical specification format consistent with the Standard Technical Specifications, and converts the required borated water volume from cu. ft. to gallons. |
| | (2) The proposed change as described above is similar to example (ii) of 48 FR 14870 in that it provides additional restrictions in the form of mode applicability requirements, upper bounds on the accumulator boron concentration and nitrogen cover pressure, shorter required action time limits, and additional surveillance requirements. |
| | Based on the above considerations, the changes included in the proposed amendment are not considered to involve a significant hazards consideration as defined in 10CFR50.92. Further, there is reasonable assurance that the health and safety of the public will not be endangered by the proposed changes. |
| | PLP/004.PLA}} |
|
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17355A3901999-07-27027 July 1999 Application for Amend to License DPR-31,modifying TSs 3.8.1.1,3.4.3 & 3.5.2 to Extend AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3021999-04-26026 April 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2471999-03-0808 March 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Certain Requirements from TS Section 6.0 That Are Adequately Controlled by Existing Regulations Other than 10CFR50.36 & TS ML17355A2391999-02-24024 February 1999 Application for Amends to Licenses DPR-31 & DPR-41,removing Restrictions on Location at Which Temp of UHS May Be Monitored in TS 3/4.7.4 ML17354B1621998-10-27027 October 1998 Application for Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi- Discipline Supervisor Position Into TS ML17354A8321998-03-12012 March 1998 Application for Amends to Licenses DPR-31 & DPR-41,deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7601998-01-0909 January 1998 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 5.3.1 & 6.9.1.7 to Allow Implementation of Zirlo Fuel Rod Cladding ML17309A9111997-12-29029 December 1997 Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17354A6141997-08-27027 August 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Turkey Point Units 3 & 4 TS to Allow Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4201997-02-24024 February 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs 6.9.1.7, COLR & Adding Best Estimate Large Break Loss of Coolant Accident Analysis to COLR ML17354A3721996-12-17017 December 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3501996-11-22022 November 1996 Application for Amends to Licenses DPR-31 & DPR-41, Requesting Rev to Allow Unit 3 Diesel Fuel Oil Storage Tank to Be Drained,Inspected & Cleaned While Maintaining at Least One Unit 3 Diesel Operable ML17354A2851996-10-0303 October 1996 Application for Amend to Licenses DPR-31 & DPR-41 to Modify Plants Units 3 & 4 to Revise TS Allowing Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7971996-07-17017 July 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7091996-05-28028 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Section 6.0, Administrative Controls, IAW 10CFR50.90 to Address Licensed Qualifications of Operations Manager ML17353A6881996-05-10010 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6501996-04-23023 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 7.4 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation. ML17353A6561996-04-19019 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6151996-03-21021 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6061996-03-20020 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.5.1 to Remove SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels from Ts,Per Line-Item 7.4 from GL 93-05 ML17353A5981996-03-0505 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 4.4.3.3 & 4.5.2 to Reduce Frequency of Surveillances & Insps in Accordance W/Gl 93-05 Items,6.6 & 7.5 ML17353A5011995-12-18018 December 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising Definition of RTP from 2,200 Mwt to 2,300 Mwt.Proprietary TR WCAP-13719,Rev 2 & Nonproprietary TRs WCAP-13718,Rev 2 & WCAP-14276,Rev 1 Encl.Proprietary TR WCAP-13719 Withheld ML17353A4521995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Index to Delete Bases Re Administrative Controls & Reviews ML17353A4491995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs w/Line-Item 10.1 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation, Per GL 94-01 ML17353A3951995-10-0404 October 1995 Application for Amend to License DPR-31 & DPR-41,modifying Plant TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/ Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3811995-09-28028 September 1995 Application for Amends to Licenses DPR-31 & DPR-41, Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3511995-09-11011 September 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 10.1 from GL 93-05, Line-Item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation & Guidance in GL 94-01 ML17353A2811995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Per Selected Line Items from NRC GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation. ML17353A2771995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 ML17353A2741995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2711995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2681995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.1.3.1, Movable Control Assemblies - Group Height & 3/4.1.3.2, Position Indication Sys - Operating & Asociated Bases ML17353A2651995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Table 4.3-1 Re Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17352B1821995-05-23023 May 1995 Application for Amends to Licenses DPR-31 & DPR-41.Amends Would Use Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation Setpoints ML17352B0851995-03-30030 March 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot- Start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 ML17352B0001995-01-17017 January 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl ML17352A8361994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3.9.4 & 1.9,allowing Containment Personnel Airlock Doors to Be Opened During Core Operations & Movement of Irradiated Fuel in Containment ML17352A8291994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.4.9.1 to Remove Schedule for Withdrawal of Rv Matl Surveillance Specimens,Gl 91-01 ML17352A7221994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3.1.3.6, Reactivity Control Sys CR Insertion Limits, 3/4.2.2, Heat Flux Hot Channel Factor - Fq(Z) & 6.9.1.7, COLR & Associated Bases,Per GL 88-16.COLRs Encl ML17352A7301994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.7.1 & Associated Bases Which Address Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML17352A7271994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.8.1.1.2e & 4.8.1.1.2f Re EDG Fuel Oil Testing Program ML17352A5451994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.0.5a, Applicability - Srs, to Reflect Intent of Revised STS (NUREG-1431) for ISI & Testing Programs,In Accordance W/Recommendations in Draft NUREG-1482 ML17352A5421994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.6.2.1.d, CSS Surveillance Interval for Air or Smoke Flow Test Through CS Header from at Least Once Per 5 Yrs to at Least Once Per 10 Yrs,Per GL 93-05 & NUREG-1366 ML17352A4611994-02-18018 February 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.5.2.8, Audits by Deleting Frequencies Performed Under Cognizance of Nuclear Review Board,Per GL 93-07 ML17352A4351993-12-28028 December 1993 Application for Amends to Licenses DPR-31 & DPR-41,proposing Addition of SG Water Level - high-high Protection to TS Tables 3.3-2,3.3-3,4.3-2 & Associated Bases,In Accordance W/ Commitment to GL 89-19 for Resolution of USI A-47 ML17352A2621993-10-0404 October 1993 Application for Amend to Licenses DPR-31 & DPR-41 Revising Surveillance Requirement 4.6.1.2a & Associated Bases to Conform w/NUREG-1431,Standard Ts,Westinghouse Plants,Rev 0 ML17352A2201993-09-0303 September 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3/4.7.1.6, Standby FW Sys & Associated Bases to Eliminate Cranking DGs ML17352A2011993-08-17017 August 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising License Conditions 3.G & 3.F Respectively,To Conform to Std Fire Protection License Proposed as Stated in GL 86-10 ML17352A1061993-07-20020 July 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Definitions to Ensure Consistency W/New 10CFR20 Requirements & Changing Radiological Effluent Release Rept Frequency ML17349A8771993-05-21021 May 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 5.2.2, Design Pressure & Temp & Associated Bases to Correct Ref to Max Containment Design Internal Pressure from 59 Psig to 55 Psig 1999-07-27
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17355A3901999-07-27027 July 1999 Application for Amend to License DPR-31,modifying TSs 3.8.1.1,3.4.3 & 3.5.2 to Extend AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3021999-04-26026 April 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2471999-03-0808 March 1999 Application for Amends to Licenses DPR-31 & DPR-41,deleting Certain Requirements from TS Section 6.0 That Are Adequately Controlled by Existing Regulations Other than 10CFR50.36 & TS ML17355A2391999-02-24024 February 1999 Application for Amends to Licenses DPR-31 & DPR-41,removing Restrictions on Location at Which Temp of UHS May Be Monitored in TS 3/4.7.4 ML17354B1621998-10-27027 October 1998 Application for Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi- Discipline Supervisor Position Into TS ML17354A8321998-03-12012 March 1998 Application for Amends to Licenses DPR-31 & DPR-41,deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7601998-01-0909 January 1998 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 5.3.1 & 6.9.1.7 to Allow Implementation of Zirlo Fuel Rod Cladding ML17309A9111997-12-29029 December 1997 Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17354A6141997-08-27027 August 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Turkey Point Units 3 & 4 TS to Allow Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4201997-02-24024 February 1997 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs 6.9.1.7, COLR & Adding Best Estimate Large Break Loss of Coolant Accident Analysis to COLR ML17354A3721996-12-17017 December 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3501996-11-22022 November 1996 Application for Amends to Licenses DPR-31 & DPR-41, Requesting Rev to Allow Unit 3 Diesel Fuel Oil Storage Tank to Be Drained,Inspected & Cleaned While Maintaining at Least One Unit 3 Diesel Operable ML17354A2851996-10-0303 October 1996 Application for Amend to Licenses DPR-31 & DPR-41 to Modify Plants Units 3 & 4 to Revise TS Allowing Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7971996-07-17017 July 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7091996-05-28028 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Section 6.0, Administrative Controls, IAW 10CFR50.90 to Address Licensed Qualifications of Operations Manager ML17353A6881996-05-10010 May 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6501996-04-23023 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 7.4 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation. ML17353A6561996-04-19019 April 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6151996-03-21021 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6061996-03-20020 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.5.1 to Remove SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels from Ts,Per Line-Item 7.4 from GL 93-05 ML17353A5981996-03-0505 March 1996 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 4.4.3.3 & 4.5.2 to Reduce Frequency of Surveillances & Insps in Accordance W/Gl 93-05 Items,6.6 & 7.5 ML17353A5011995-12-18018 December 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising Definition of RTP from 2,200 Mwt to 2,300 Mwt.Proprietary TR WCAP-13719,Rev 2 & Nonproprietary TRs WCAP-13718,Rev 2 & WCAP-14276,Rev 1 Encl.Proprietary TR WCAP-13719 Withheld ML17353A4521995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Index to Delete Bases Re Administrative Controls & Reviews ML17353A4491995-11-22022 November 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs w/Line-Item 10.1 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation, Per GL 94-01 ML17353A3951995-10-0404 October 1995 Application for Amend to License DPR-31 & DPR-41,modifying Plant TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/ Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3811995-09-28028 September 1995 Application for Amends to Licenses DPR-31 & DPR-41, Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3511995-09-11011 September 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 10.1 from GL 93-05, Line-Item TS Improvements to Reduce Surveillance Requirements for Testing During Power Operation & Guidance in GL 94-01 ML17353A2811995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Per Selected Line Items from NRC GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation. ML17353A2771995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 ML17353A2741995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2711995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2681995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.1.3.1, Movable Control Assemblies - Group Height & 3/4.1.3.2, Position Indication Sys - Operating & Asociated Bases ML17353A2651995-07-26026 July 1995 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Table 4.3-1 Re Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17352B1821995-05-23023 May 1995 Application for Amends to Licenses DPR-31 & DPR-41.Amends Would Use Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation Setpoints ML17352B0851995-03-30030 March 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot- Start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 ML17352B0001995-01-17017 January 1995 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.9.1.7, COLR, Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters.Fpl Topical Rept NF-TR-95-01, Nuclear Physics Methodology... Encl ML17352A8361994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3.9.4 & 1.9,allowing Containment Personnel Airlock Doors to Be Opened During Core Operations & Movement of Irradiated Fuel in Containment ML17352A8291994-10-20020 October 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.4.9.1 to Remove Schedule for Withdrawal of Rv Matl Surveillance Specimens,Gl 91-01 ML17352A7221994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3.1.3.6, Reactivity Control Sys CR Insertion Limits, 3/4.2.2, Heat Flux Hot Channel Factor - Fq(Z) & 6.9.1.7, COLR & Associated Bases,Per GL 88-16.COLRs Encl ML17352A7301994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.7.1 & Associated Bases Which Address Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves ML17352A7271994-07-19019 July 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.8.1.1.2e & 4.8.1.1.2f Re EDG Fuel Oil Testing Program ML17352A5451994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.0.5a, Applicability - Srs, to Reflect Intent of Revised STS (NUREG-1431) for ISI & Testing Programs,In Accordance W/Recommendations in Draft NUREG-1482 ML17352A5421994-04-19019 April 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 4.6.2.1.d, CSS Surveillance Interval for Air or Smoke Flow Test Through CS Header from at Least Once Per 5 Yrs to at Least Once Per 10 Yrs,Per GL 93-05 & NUREG-1366 ML17352A4611994-02-18018 February 1994 Application for Amends to Licenses DPR-31 & DPR-41,revising TS 6.5.2.8, Audits by Deleting Frequencies Performed Under Cognizance of Nuclear Review Board,Per GL 93-07 ML17352A4351993-12-28028 December 1993 Application for Amends to Licenses DPR-31 & DPR-41,proposing Addition of SG Water Level - high-high Protection to TS Tables 3.3-2,3.3-3,4.3-2 & Associated Bases,In Accordance W/ Commitment to GL 89-19 for Resolution of USI A-47 ML17352A2621993-10-0404 October 1993 Application for Amend to Licenses DPR-31 & DPR-41 Revising Surveillance Requirement 4.6.1.2a & Associated Bases to Conform w/NUREG-1431,Standard Ts,Westinghouse Plants,Rev 0 ML17352A2201993-09-0303 September 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 3/4.7.1.6, Standby FW Sys & Associated Bases to Eliminate Cranking DGs ML17352A2011993-08-17017 August 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising License Conditions 3.G & 3.F Respectively,To Conform to Std Fire Protection License Proposed as Stated in GL 86-10 ML17352A1061993-07-20020 July 1993 Application for Amends to Licenses DPR-31 & DPR-41,revising TS Definitions to Ensure Consistency W/New 10CFR20 Requirements & Changing Radiological Effluent Release Rept Frequency ML17349A8771993-05-21021 May 1993 Application for Amends to Licenses DPR-31 & DPR-41,modifying TS 5.2.2, Design Pressure & Temp & Associated Bases to Correct Ref to Max Containment Design Internal Pressure from 59 Psig to 55 Psig 1999-07-27
[Table view] |
Text
REGULA Y INFORMATION DISTRIBUTI YSTEM (RIDS)
ACCESSION NBR: 8802090521 DOC. DATE: 88/02/03 NQTAR I ZED: YES DOCKET FACIL: 50-250 Turkey Point Planti Unit 3i Florida Power and Light C 05000250 50-251 Turkey Point Planti Unit 4i Florida Poeer and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION NOODYi C. O. Florida Power 5 Light Co.
REC IP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to Licenses DPR-31 8c DPR-41> taking current requirement For safety ingection accumulators consolidating requirements into one limiting condition for operation section 8c one surveillance section. Fee paid.
DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR ) ENCL I SIZE:
TITLE: OR Submittal: General Distribution NOTES:
REC IP KENT COPIES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 0 PD2-2 PD 5 5 EDISONi G 1 INTERNAL: ARM/DAF/LFMB 0 NRR/DEBT/*DS 1 1 NRR/DEBT/CEB 1 NRR/DEST/MTB 1 1 NRR/DEBT/RSB 1 NRR/DOEA/TSB 1 1 NRR/P RB 1 1 OGC/HDS2 1 0 01 1 1 RES/DE/EIB 1 EXTERNAL: LPDR 1 NRC PDR 1 1 NSIC 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 17 V
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P. O. 14000, JUNO BEACH, FL 33408.0420
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FEBRUARY. 3 1988 L-88-50 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed License Amendment Safet In'ection Accumulators By letter dated September 29, 1986 (FPL letter L-86-393)
Florida Power & Light Company (FPL) submitted a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41 to upgrade the current plant Technical Specifications and include, within limitations, the guidance of NUREG-0452, Standard Technical Specifications (STS) for Westinghouse Pressur'ized Water Reactors.
The proposed changes remove the custom versions of the limiting condition for operation and surveillance requir'ements for the accumulators from Technical
'Specifications 3.4 and 4.1 and place them in a separate section in the STS format with additional STS requirements.
FPL requests that these changes be reviewed and issued independent of the technical specification upgrade review effort.
This separate issuance will provide the collective action discussed in our response to Inspection Report 87-35 to preclude further recurrence of operating problems associated with the chemical sampling of the accumulators.
pool PLP/004.PLA
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I'880209052i 880203 k PDR ADOCN, 05000250 ~)c rr P. PDR ~ t(<'~(gy an FPL Group compan+
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U. S. Nuclear Regulatory Commission L-88-50 Page two The proposed specification and supporting documentation, are attached.
In accordance with 10 CFR 50.91(b)(1), a copy of this proposed license amendment is being forwarded to the State Designee for the State of Florida.
In accordance with 10 CFR 170.12(c), FPL Check No. 7153 for
$ 150 is attached as remittance for the licensee amendment application fee.
The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.
If there are any questions, please call us.
Very truly yours, C. 0. ody Exec ave Vice President COW/PLP/gp Attachments cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Mr. Jacob Nash, Florida Dept. of Health and Rehabilitative Services PLP/004.PLA
STATE OF FLORlDA )
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COUNTY OF PALM BEACH )
~C.O.W d fd d!,d d That he is Executive Vice President of Florida Power Bc Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
C. 0 dy Subscribed and sworn to before me this
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j>> 0 d'gP WJ/ d s NOTARY!PQBLIC, in and for the County
- ,~'. ~,,of Palm 8'each, State of Florida HOIARY PUBLIC SIAIE OF FLORIDA NY COHttISSION EXP SEPt l8,1989 BOttOEO THRU GENERAL ItiS. Uti0 My Commission expires: ~
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TURKEY POINT UNITS 3 AND 4 PLA-051 PROPOSED LICENSE AMENDMENT TITLE: ACCUMULATORS DESCRIPTION:
This proposed amendment to the Turkey Point Technical Specifications (TS) takes the current requirement for the safety injection accumulators from several TS sections and consolidates the requirements into one limiting condition for operation (LCO) section and one surveillance section. This proposed change has been drafted following the guidelines of NUREG 0452, Standardized Technical Specifications for Westinghouse Pressurized Water Reactors (WSTS) and the proposed Upgraded Technical Specifications submitted to the NRC on September 30, 1986 as a part of the Performance Enhancement Program (PEP). The changes are as follows:
Pacae i The Table of Contents has been revised to reflect the changes described below.
, Pa es 1-7 1-8 1-9 These pages of definitions have been consolidated to allow the addition of a definition for the ANALOG CHANNEL OPERATIONAL TEST.
TABLE 1.1 The Average Coolant Temperature requirement for Mode 5 (cold shutdown) has been revised to correct a typographical error.
This requirement has been revised to read less than or equal to 200 F.
Pa es 3.4-1 3.4-2 and 3.4-2.a The requirements for the accumulators have been deleted and the other sections renumbered as required.
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' a Pa e 3.4-2.b A new TS section (3.4.1.f) has been added describing the LCO and action requirements for the accumulators.
The operability requirements were revised as follows:
The contained borated water volume was converted from cu.
to gallons (875-891 cu. ft. vs 6545-6665 gallons) to reflect ft.
installed instrumentation; upper bounds for boron concentration (2350 ppm) and nitrogen cover pressure (675psig) were added. The revised LCO is consistent with the accumulator design parameters specified in the FSAR (Table 6.2-4) .
The LCO applicability was extended to include Mode 3 (with pressurizer pressure above 1000 psig). This is more conservative than the current TS requirements which specify that the reactor is not to be made critical except, for low power physics tests, unless the accumulators are operable.
The action requirements were revised using the WSTS as guidance. The proposed action statements for one accumulator inoperable, except as a result of a closed isolation valve, and one accumulator inoperable due to the isolation valve being closed, are more conservative than the current TS requirements in that. they require that the plant be placed in a mode where the capability of the accumulators is not required (i.e. pressurizer pressure less than 1000 psig) in a shorter time than required by the current TS. The current TS would allow the plant to be kept in hot shutdown (reactor subcritical and with Tavg above 540 F) for a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before going to c'old shutdown. Plant procedures for going from hot standby to cold shutdown require that the accumulators be isolated from the RCS when the pressurizer pressure is between 1000 psig and 700 psig. Since the accumulators are isolated and no "longer required, there, is no requirement to take the, plant all the way to cold shutdown as specified in the current TS.
Table 4.1-1 Sheet 2 Table 4.1-2 Sheet 2 and Pa e 4.5-2 The surveillance requirements for the accumulators have been removed from these TS sections and other sections have been renumbered as required.
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Pa e 4.5-3 A new section has been added to consolidate the accumulator surveillance requirements. In addition -to the a once per shift surveillance to verify that current'equirements, the isolation valves are open and to verify that the power supply to the isolation valves is disconnected by a locked open breaker was added. Also a monthly ANALOG CHANNEL OPERATIONAL TEST has been added for the level and pressure channels.
Pa es B3.4-1 and B3.4-2 The previous basis section for the accumulators has been deleted and a new basis section has been added. The new basis sections conforms to the WSTS format and the Turkey Point Final Safety Analysis Report.
Pa e B4.5-1 The references to accumulators has been deleted because the basis section added to B3.4 adequately describes the basis for the accumulator TS requirements.
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0 BASIS FOR NO SIGNXFXCANT HAZARDS CONSIDERATXON DETERMINATION The standards used to arrive at a proposed determination that the changes described above involve no significant, hazards consideration are included in 10CFR50.92. The regulations state that if operation of the facility in accordance with the proposed amendment could not: (1) involve a significant increase in the probability or consecpxences of an accident previously evaluated, or (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety, then a no significant hazards determination can be made.
Operation of Turkey Point Units 3 and 4 in accordance with the proposed amendments would not:
(1) and (2) involve a significant increase in the probability or consequences of an accident previously evaluated, or create the possibility of a new or different kind of accident, from any accident previously evaluated.
The proposed changes are either administrative (i.e.,
consolidation of accumulator LCO, action and surveillance requirements in a separate section, conversion of the borated water volume from cu. ft. to gallons), or provide requirements that are as restrictive or more restrictive than the current requirements (i.e., upper bounds on boron concentration and nitrogen cover pressure, broader mode applicability, action requirements requiring the plant to be placed in a mode where the capability of the accumulators is not required in a shorter time period, and additional surveillance requirements). They are consistent with the design basis, and do not affect the assumptions used for accumulator injection in the safety analyses. The action required in the event of an inoperable accumulator is to place the plant in a mode where capability of the accumulators is not required,, which is consistent with the intent of the current TS.
(3) involve a significant reduction in a margin of safety.
The action requirement to reduce pressure to less than 1000 psig rather than go to cold shutdown, as required by the current TS, would not result in a reduction in a margin of safety since the plant would similarly be placed in a mode where the accumulators are not recpxired to be operable.
In addition, the Commission has provided guidance concerning the application of standards for determination whether a significant hazards consideration exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve a significant hazards consideration. Example (1) relates to a purely administrative change to Technical Specifications:
correction of an error, or a change in nomenclature. Example (ii) relates to a change that constitutes an additional
limitation, restriction, or control not presently included in the Technical Specifications: for example, a more stringent surveillance requirement.
(1) The proposed change as described above is similar to example (i) of 48 FR 14870 in that change which consolidates it is an administrative current requirements for the accumulators into a technical specification format consistent with the Standard Technical Specifications, and converts the required borated water volume from cu. ft. to gallons.
(2) The proposed change as described above is similar to example (ii) of 48 FR 14870 in that it provides additional restrictions in the form of mode applicability requirements, upper bounds on the accumulator boron concentration and nitrogen cover pressure, shorter required action time limits, and additional surveillance requirements.
Based on the above considerations, the changes included in the proposed amendment are not considered to involve a significant hazards consideration as defined in 10CFR50.92. Further, there is reasonable assurance that the health and safety of the public will not be endangered by the proposed changes.
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