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| | issue date = 03/07/1985 | | | issue date = 03/07/1985 |
| | title = Application for Amend to Licenses DPR-31 & DPR-41,removing Inconsistencies within Licenses & Clarifying Surveillance of Fission Detectors.Fee Paid | | | title = Application for Amend to Licenses DPR-31 & DPR-41,removing Inconsistencies within Licenses & Clarifying Surveillance of Fission Detectors.Fee Paid |
| | author name = WILLIAMS J W | | | author name = Williams J |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = THOMPSON H L | | | addressee name = Thompson H |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000250, 05000251 | | | docket = 05000250, 05000251 |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 18 | | | page count = 18 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:P.X I 4000, JUNO BEACH.F L 33408 FLORIDA POWER&LIGHT COMPANY Office of Nuclear Reactor Regulation Attention: | | {{#Wiki_filter:P. X I 4000, JUNO BEACH. F L 33408 FLORIDA POWER & LIGHT COMPANY March 7, 1985 L-85-IOO Office of Nuclear Reactor Regulation Attention: Mr. Hugh L. Thompson, Jr. Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 |
| Mr.Hugh L.Thompson, Jr.Director Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555 | |
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| ==Dear Mr.Thompson:== | | ==Dear Mr. Thompson:== |
| Re: Turkey Point Units 3 8 4 Docket Nos.50-250 6 50-25 I Proposed Amendment to Facility 0 ratin Licenses DPR 3 I and 4 I March 7, 1985 L-85-IOO In accordance with IO CFR 50.90, Florida Power&Light Company (FPL)submits herewith three signed originals and forty copies of a request to amend Facility Operating License's DPR-3 I and 4!.The purpose of this amendment is to remove inconsistencies within the license and provide.clarification regarding the surveillance of fission detectors.
| |
| The proposed modifications will involve Technical Specification changes as described below and as shown on the accompanying Technical Specification pages (Attachment I).Pa e 4.13-I This page is revised to clearly indicate the leak testing surveillance intervals for fission detectors.
| |
| Pa es 5.2-l 8 5.2-2 The paragraph on page 5.2-2 discussing the amount of enriched fissionable material allowed on site for the purposes of monitoring neutron flux is being deleted to be consistent with the Operating License, Section II.C.Pages 5.2-I and 5.2-2 have been consolidated as page 5.2-I.These proposed changes have been reviewed and approved by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.Attachment 2 provides an evaluation of the proposed action in light of the three standards contained in IO CFR 50.92 regarding the issue of no significant hazards.Attachment 3 provides the basis for the proposed modification.
| |
| PEOPLE SERVING PEOPLE In summary, FPL submits that the activities associated with the proposed amendment do not constitute a significant hazard to the public health and safety or to the environment and therefore that these amendments do not involve a significant hazards consideration.
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| FPL respectfully requests that this application be processed and approved as'soon as possible.This change is required to support the installation of a new excore neutron flux monitoring system during the upcoming Unit 3 refueling outage.MSO~Om~~7-PDR ADOCK 05000250 P P Page 2 Office of Nuclear Reactor Regulations Mr.Hugh L.Thompson, Jr., Director In accordance with IO CFR l70.2 I, an application fee of$I50.00 is attached.In accordance with IO CFR 50.9 I (b)(l), a copy of the proposed amendment is being forwarded to the state designee for the State of Florida.lf you have any questions, please contact us.Yours very truly, J.W.Williams, Jr.Group Vice President Nuclear Energy JWW/G JK/cab Attachments cc: Dr.J.Nelson Grace, Region II Harold F.Reis, Esquire Lyle E.Jerrett, Administrator Radiological Health Bc Rehabilitative Services
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| ATTACHMENT 1 T/S p.4.13-1 p.5.2-1
| | Re: Turkey Point Units 3 8 4 Docket Nos. 50-250 6 50-25 I Proposed Amendment to Facility 0 ratin Licenses DPR 3 I and 4 I In accordance with IO CFR 50.90, Florida Power & Light Company (FPL) submits herewith three signed originals and forty copies of a request to amend Facility Operating License's DPR-3 I and 4!. |
| | The purpose of this amendment is to remove inconsistencies within the license and provide. clarification regarding the surveillance of fission detectors. |
| | The proposed modifications will involve Technical Specification changes as described below and as shown on the accompanying Technical Specification pages (Attachment I). |
| | Pa e 4.13-I This page is revised to clearly indicate the leak testing surveillance intervals for fission detectors. |
| | Pa es 5.2-l 8 5.2-2 The paragraph on page 5.2-2 discussing the amount of enriched fissionable material allowed on site for the purposes of monitoring neutron flux is being deleted to be consistent with the Operating License, Section II.C. |
| | Pages 5.2- I and 5.2-2 have been consolidated as page 5.2- I. |
| | These proposed changes have been reviewed and approved by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board. |
| | Attachment 2 provides an evaluation of the proposed action in light of the three standards contained in IO CFR 50.92 regarding the issue of no significant hazards. Attachment 3 provides the basis for the proposed modification. |
| | In summary, FPL submits that the activities associated with the proposed amendment do not constitute a significant hazard to the public health and safety or to the environment and therefore that these amendments do not involve a significant hazards consideration. FPL respectfully requests that this application be processed and approved as'soon as possible. This change is required to support the installation of a new excore neutron flux monitoring system during the upcoming Unit 3 refueling outage. |
| | MSO~Om~~7-PDR ADOCK P 05000250 PEOPLE SERVING PEOPLE P |
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| 4.13 RADIOACTIVE MATERIALS SOURCES SURVEILLANCE Applies to leakage testing of by-product, source and special nuclear radioactive material sources.O~b'ective:
| | Page 2 Office of Nuclear Reactor Regulations Mr. Hugh L. Thompson, Jr., Director In accordance with IO CFR l70.2 I, an application fee of $ I50.00 is attached. |
| To assure that leakage from by-product, source and special nuclear radioactive material sources does not exceed allowable limits.Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement State, as follows: 1.Each sealed source, except fission detectors and startup sources subject to core flux or those exempted by Specification 3.11 containing radioactive material, other than Hydrogen 3, with a half-life greater than 30 days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months.2.The periodic leak test required does not apply to sealed sources that are stored and not being used.The sources excepted from this test shall be tested for leakage prior to any use or transfer to another user unless they have been leak tested within six months prior to the date of use or transfer.In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the transfer, sealed sources shall not be put into use until tested.3.Startup sources and fission detectors shall be leak tested prior to and following any repair or maintenance and before being subjected to core flux.
| | In accordance with IO CFR 50.9 I (b)(l), a copy of the proposed amendment is being forwarded to the state designee for the State of Florida. |
| | lf you have any questions, please contact us. |
| | Yours very truly, J. W. Williams, Jr. |
| | Group Vice President Nuclear Energy JWW/G JK/cab Attachments cc: Dr. J. Nelson Grace, Region II Harold F. Reis, Esquire Lyle E. Jerrett, Administrator Radiological Health Bc Rehabilitative Services |
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| ===5.2 REACTOR===
| | ATTACHMENT 1 T/S p.4.13-1 p.5.2-1 |
| REACTOR CORE 1.The reactor core contains approximately 71 metric tons of uranium in the form of slightly enriched uranium dioxide pellets.The pellets are encapsulated in Zircaloy-0 tubing to form fuel rods.The reactor core is made up of 157 fuel assemblies.
| |
| Each fuel assembly contains 200 fuel rods.2.The average enrichment of the initial core is a nominal 2.50 weight percent of U-235.Three fuel enrichments are used in the initial core.The highest enrichment is a nominal 3.10 weight percent of U-235.3.Reload fuel will be similar in design to the initial core.Burnable poison rods are in the form of rod clusters which are located in vacant rod cluster control guide tubes, are used for reactivity and/or power distribution control.5.There are 05 full-length RCC assemblies and 8 partial-length" RCC assemblies in the reactor core.The full-length RCC assemblies contain a 100 inch length of silver-indium-cadmium alloy clad with the stainless steel.The partial-length+
| |
| RCC assemblies contain a 36 inch length of silver-indium-cadmium alloy with the remainder of the stainless steel sheath filled with A1203.REACTOR COOLANT SYSTEM 1.The design of the Reactor Coolant System complies with the code requirements.
| |
| 2.All piping, components and supporting structures of the Reactor Coolant System are designed to Class I requirements and have been designed to withstand: | |
| a.The design seismic ground acceleration, 0.05g acting in the horizontal and 0.033g acting in the vertical planes simultaneously, with stress maintained within code allowable working stresses.b.The maximum potential seismic ground acceleration, 0.15g, acting in the horizontal and 0.10g acting in the vertical directions simultaneously with no loss of function.3.The nominal liquid volume of the Reactor Coolant System, at rated operating conditions, is 9088 cubic feet.+Any reference to part-length rods no longer applies after the part-length rods are removed from the reactor.
| |
| ATTACHMENT 2 No SI nificant Hazards Consideration Florida Power and Light Company (FPL)presents this evaluation of the hazards considerations involved with the proposed amendment, focusing on the three standards set forth in IO CFR 50.92(c)as quoted below: "The Commission may make a final determination, pursuant to the procedures in 50.9I, that a proposed amendment to an operating license for a facility licensed under 50.2l(b)or 50.22 or for a testing facility involves no significant hazards considerations, if operation of the facility in accordance with a proposed amendment would not: I.Involve a significant increase in the probability or consequences or 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." FPL submits that the activities associated with this amendment request do not meet any of the significant hazards considerations standards of IO CFR 50.92(c)and, accordingly, a no significant hazards consideration finding is justified.
| |
| In support of this determination, necessary.background information has been provided (Attachment 3).Discussion of each of the above significant safety hazards consideration standards follows.Evaluation The following evaluation demonstrates that the proposed amendment does not exceed any of the three significant hazards consideration standards.
| |
| I.Involve a si nificant increase in the robabilit or conse uences of an accident reviousl evaluated.
| |
| Page I of 3
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| The proposed Technical Specification change is an administrative change that will remove inconsistencies in the amount of special nuclear material that may be on site in the form of fission detectors.
| | 4.13 RADIOACTIVE MATERIALS SOURCES SURVEILLANCE Applies to leakage testing of by-product, source and special nuclear radioactive material sources. |
| The change also clarifies the required surveillance requirements for fission detectors.
| | O~b'ective: To assure that leakage from by-product, source and special nuclear radioactive material sources does not exceed allowable limits. |
| This change in itself cannot cause an accident nor can it result in additional consequences of an accident previously evaluated.
| | Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement State, as follows: |
| In fact, the additional fission detectors that precipitated the need for the T.S.change are being provided in accordance with NRC requirements to provide additional qualified instrumentation to monitor the reactor core during plant accidents.
| | : 1. Each sealed source, except fission detectors and startup sources subject to core flux or those exempted by Specification 3.11 containing radioactive material, other than Hydrogen 3, with a half-life greater than 30 days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months. |
| 2.Create the ossibilit of a new or different kind of accident from an accident reviousl evaluated.
| | : 2. The periodic leak test required does not apply to sealed sources that are stored and not being used. The sources excepted from this test shall be tested for leakage prior to any use or transfer to another user unless they have been leak tested within six months prior to the date of use or transfer. In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the transfer, sealed sources shall not be put into use until tested. |
| The proposed changes are administrative in nature.As discussed above the changes are being made to remove inconsistencies and provide clarification of the Technical Specifications.
| | : 3. Startup sources and fission detectors shall be leak tested prior to and following any repair or maintenance and before being subjected to core flux. |
| Therefore, this change in itself cannot create a new or different kind of accident.These changes are consistent with the Standard Technical Specifications promulgated by the NRC.3.Involve a si nificant reduction in a mar in of safet.The proposed administrative changes to the Technical Specifications were precipitated by the need to utilize additional fission detectors for reactor neutron flux monitoring.
| |
| This change will achieve consistency in the License and provide clarification of the intent of the surveillance requirements for fission detectors.
| |
| This change therefore does not involve a significant reduction in any margin of safety.48 FR l4870 dated April 6, l983 provided examples of amendments not likely to involve a significant hazards consideration.
| |
| This proposed change is considered to be most similar to example (I)in that it involves an administrative change, to achieve consistency and provide clarification of the present Technical Specifications.
| |
| Page2of 3 In summation, it has been shown that the Technical Specification change would not I.Involve a significant increase in the probability or consequences 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.Therefore, FPL has determined that, the proposed amendment involves no significant hazards considerations.
| |
| ATIACHMENT 3 BASIS FOR PROPOSED T.S.CHANGES INTRODUCTION:
| |
| As part of plant improvements required by the NRC pursuant to Reg.Guide l.97 Rev.3 and IO CFR 50 Appendix R, a new excore neutron flux monitoring system will be installed.
| |
| This system will employ the use of fission chambers mounted external to the core for neutron radiation detection.
| |
| Each detector will use enriched uranium in small quantities to provide the mechanism for neutron detection.
| |
| The combined quantity of this material for all required detectors is consistent with Operating License Section II.C., but will exceed that allowed by Technical Specification 5.2.1 In addition, to changes to T.S.5.2, administrative changes to T.S.4.I3 are necessary to clarify the surveillance requirements for fission detectors.
| |
| BACKGROUND In late 1973 the AEC (presently the NRC)began implementing changes in its.procedures for licensing the possession of byproduct, source, and special nuclear materials in connection with the operation of power reactors.The standard format for SAR's was amended to request information on an applicant's capabilities, facilities and procedures for handling and storage of this material.In addition, standard language for incorporation into the facility operating license and Technical Specifications was provided.On September l9, l974, after discussions with the AEC s Directorate of Licensing, FPL submitted proposed changes to the Turkey Point Facility Operating License.The purpose of the change was to amend Section II.C.of the license and provide two new Technical Specifications (3.I I and 4.I3)to ensure that byproduct, source and special nuclear material sources utilized at Turkey Point were maintained in accordance with the AEC's rules and regulations.
| |
| In support of this amendment request, FPL submitted revisions to the FSAR (dated 9/l7/74 and l2/23/74) describing the radioactive materials safety program at Turkey Point.The staff reviewed and approved the proposed Technical Specification changes since there was reasonable assurance that byproduct, source, and special nuclear material would be stored, used, and accounted for in a manner which met the applicable radiation protection provisions of IO CFR 20, 30, 40, and 70.As such the Operating License was amended on July IO, l975 to include (among other changes)the following Section II.C, which licensed FPL: "Pursuant to the Act and IO CFR Parts 30, 40 and.70 to receive, possess, and use at anytime any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;" This new section of the Operating License conformed with the AEC's standard license format as shown in an interoffice memo from the Directorate of Licensing to Branch Chiefs, Project Managers and Licensing Assistants dated I I/28/73.The intent of this section was to allow the use of the identified materials in amounts as required for reactor'operation.
| |
| Apparently by oversight, Technical Specification 5.2 was not amended to remove the restriction on the number of grams of enriched fissionable material allowed on-site as fission detectors.
| |
| Indeed, this specification should have been deleted since it is inconsistent with Operating License Section II.C.The other change to the Technical Specification is to clarify the intent of T.S.4.I3.The surveillance requirements specified for sealed source in use is to identify leakage that may have resulted from handling of the sealed source.Since the fission detectors, like startup sources, are not routinely handled the necessary surveillance intervals is not intended to be six months.This intent is clearly demonstrated in the NRC's Standard Technical Specifications 4.7.10 and 84.7.IO, where surveillance for startup sources and fission detectors are required to be tested prior to use and following repair or maintenance.
| |
| Therefore this change to the Technical Specification is considered purely, administrative since it merely clarifies the surveillance requirements for fission detectors.
| |
| Pa e2of 3
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| CONCLUSION As evidenced by the discussion above, the described changes are purely administrative. | | 5.2 REACTOR REACTOR CORE |
| As such, FPL concludes that: (I)that amendments do not involve a significant hazards consideration; (2)there is reasonable assurance that the health and safety of the public will not be endangered by the proposed changes and (3)these changes are in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.Pa e3of 3 I~ | | : 1. The reactor core contains approximately 71 metric tons of uranium in the form of slightly enriched uranium dioxide pellets. The pellets are encapsulated in Zircaloy - 0 tubing to form fuel rods. The reactor core is made up of 157 fuel assemblies. Each fuel assembly contains 200 fuel rods. |
| STATE OF FLORIDA COUNTY OF DADE J.W.Williams Jr.being first duly sworn, deposes and says: That he is a Grou Vice President of Florida Power&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.J.W.Williams, Jr.Subscribed and sworn to before me this~day of , I 9~.OTARY PUBLIC, in and for the County of Dade, State of Florida>>OilR""9!ill(<is.i: i.:,~.<<<ill!$5 ill: t,A~<<'.,~~'Oiiufb aHRI'F.>ethic | | : 2. The average enrichment of the initial core is a nominal 2.50 weight percent of U-235. Three fuel enrichments are used in the initial core. The highest enrichment is a nominal 3.10 weight percent of U-235. |
| !'y Commission expires:}} | | : 3. Reload fuel will be similar in design to the initial core. |
| | Burnable poison rods are in the form of rod clusters which are located in vacant rod cluster control guide tubes, are used for reactivity and/or power distribution control. |
| | : 5. There are 05 full-length RCC assemblies and 8 partial-length" RCC assemblies in the reactor core. The full-length RCC assemblies contain a 100 inch length of silver-indium-cadmium alloy clad with the stainless steel. The partial-length+ |
| | RCC assemblies contain a 36 inch length of silver-indium-cadmium alloy with the remainder of the stainless steel sheath filled with A1203. |
| | REACTOR COOLANT SYSTEM |
| | : 1. The design of the Reactor Coolant System complies with the code requirements. |
| | : 2. All piping, components and supporting structures of the Reactor Coolant System are designed to Class I requirements and have been designed to withstand: |
| | : a. The design seismic ground acceleration, 0.05g acting in the horizontal and 0.033g acting in the vertical planes simultaneously, with stress maintained within code allowable working stresses. |
| | : b. The maximum potential seismic ground acceleration, 0.15g, acting in the horizontal and 0.10g acting in the vertical directions simultaneously with no loss of function. |
| | : 3. The nominal liquid volume of the Reactor Coolant System, at rated operating conditions, is 9088 cubic feet. |
| | + Any reference to part-length rods no longer applies after the part-length rods are removed from the reactor. |
| | |
| | ATTACHMENT2 No SI nificant Hazards Consideration Florida Power and Light Company (FPL) presents this evaluation of the hazards considerations involved with the proposed amendment, focusing on the three standards set forth in IO CFR 50.92(c) as quoted below: |
| | "The Commission may make a final determination, pursuant to the procedures in 50.9I, that a proposed amendment to an operating license for a facility licensed under 50.2l(b) or 50.22 or for a testing facility involves no significant hazards considerations, if operation of the facility in accordance with a proposed amendment would not: |
| | I. Involve a significant increase in the probability or consequences or 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." |
| | FPL submits that the activities associated with this amendment request do not meet any of the significant hazards considerations standards of IO CFR 50.92(c) and, accordingly, a no significant hazards consideration finding is justified. In support of this determination, necessary .background information has been provided (Attachment 3). Discussion of each of the above significant safety hazards consideration standards follows. |
| | Evaluation The following evaluation demonstrates that the proposed amendment does not exceed any of the three significant hazards consideration standards. |
| | I. Involve a si nificant increase in the robabilit or conse uences of an accident reviousl evaluated. |
| | Page I of 3 |
| | |
| | The proposed Technical Specification change is an administrative change that will remove inconsistencies in the amount of special nuclear material that may be on site in the form of fission detectors. The change also clarifies the required surveillance requirements for fission detectors. This change in itself cannot cause an accident nor can it result in additional consequences of an accident previously evaluated. In fact, the additional fission detectors that precipitated the need for the T.S. change are being provided in accordance with NRC requirements to provide additional qualified instrumentation to monitor the reactor core during plant accidents. |
| | : 2. Create the ossibilit of a new or different kind of accident from an accident reviousl evaluated. |
| | The proposed changes are administrative in nature. As discussed above the changes are being made to remove inconsistencies and provide clarification of the Technical Specifications. Therefore, this change in itself cannot create a new or different kind of accident. These changes are consistent with the Standard Technical Specifications promulgated by the NRC. |
| | : 3. Involve a si nificant reduction in a mar in of safet . |
| | The proposed administrative changes to the Technical Specifications were precipitated by the need to utilize additional fission detectors for reactor neutron flux monitoring. |
| | This change will achieve consistency in the License and provide clarification of the intent of the surveillance requirements for fission detectors. This change therefore does not involve a significant reduction in any margin of safety. |
| | 48 FR l4870 dated April 6, l983 provided examples of amendments not likely to involve a significant hazards consideration. This proposed change is considered to be most similar to example (I) in that it involves an administrative change, to achieve consistency and provide clarification of the present Technical Specifications. |
| | Page2of 3 |
| | |
| | In summation, it has been shown that the Technical Specification change would not I. Involve a significant increase in the probability or consequences 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. |
| | Therefore, FPL has determined that, the proposed amendment involves no significant hazards considerations. |
| | |
| | ATIACHMENT3 BASIS FOR PROPOSED T.S. CHANGES INTRODUCTION: |
| | As part of plant improvements required by the NRC pursuant to Reg. Guide l.97 Rev. 3 and IO CFR 50 Appendix R, a new excore neutron flux monitoring system will be installed. This system will employ the use of fission chambers mounted external to the core for neutron radiation detection. Each detector will use enriched uranium in small quantities to provide the mechanism for neutron detection. The combined quantity of this material for all required detectors is consistent with Operating License Section II. C., but will exceed that allowed by Technical Specification 5.2. |
| | 1 In addition, to changes to T.S. 5.2, administrative changes to T.S. 4.I3 are necessary to clarify the surveillance requirements for fission detectors. |
| | BACKGROUND In late 1973 the AEC (presently the NRC) began implementing changes in its |
| | . procedures for licensing the possession of byproduct, source, and special nuclear materials in connection with the operation of power reactors. The standard format for SAR's was amended to request information on an applicant's capabilities, facilities and procedures for handling and storage of this material. In addition, standard language for incorporation into the facility operating license and Technical Specifications was provided. |
| | On September l9, l974, after discussions with the AEC s Directorate of Licensing, FPL submitted proposed changes to the Turkey Point Facility Operating License. |
| | The purpose of the change was to amend Section II.C. of the license and provide two new Technical Specifications (3.I I and 4.I3) to ensure that byproduct, source and special nuclear material sources utilized at Turkey Point were maintained in accordance with the AEC's rules and regulations. In support of this amendment request, FPL submitted revisions to the FSAR (dated 9/l7/74 and l2/23/74) |
| | |
| | describing the radioactive materials safety program at Turkey Point. The staff reviewed and approved the proposed Technical Specification changes since there was reasonable assurance that byproduct, source, and special nuclear material would be stored, used, and accounted for in a manner which met the applicable radiation protection provisions of IO CFR 20, 30, 40, and 70. As such the Operating License was amended on July IO, l975 to include (among other changes) the following Section II.C, which licensed FPL: |
| | "Pursuant to the Act and IO CFR Parts 30, 40 and.70 to receive, possess, and use at anytime any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;" |
| | This new section of the Operating License conformed with the AEC's standard license format as shown in an interoffice memo from the Directorate of Licensing to Branch Chiefs, Project Managers and Licensing Assistants dated I I/28/73. The intent of this section was to allow the use of the identified materials in amounts as required for reactor 'operation. Apparently by oversight, Technical Specification 5.2 was not amended to remove the restriction on the number of grams of enriched fissionable material allowed on-site as fission detectors. |
| | Indeed, this specification should have been deleted since it is inconsistent with Operating License Section II.C. |
| | The other change to the Technical Specification is to clarify the intent of T.S. |
| | 4.I3. The surveillance requirements specified for sealed source in use is to identify leakage that may have resulted from handling of the sealed source. Since the fission detectors, like startup sources, are not routinely handled the necessary surveillance intervals is not intended to be six months. This intent is clearly demonstrated in the NRC's Standard Technical Specifications 4.7.10 and 84.7.IO, where surveillance for startup sources and fission detectors are required to be tested prior to use and following repair or maintenance. Therefore this change to the Technical Specification is considered purely, administrative since it merely clarifies the surveillance requirements for fission detectors. |
| | Pa e2of 3 |
| | |
| | CONCLUSION As evidenced by the discussion above, the described changes are purely administrative. As such, FPL concludes that: (I) that amendments do not involve a significant hazards consideration; (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed changes and (3) these changes are in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public. |
| | Pa e3of 3 |
| | |
| | I~ |
| | STATE OF FLORIDA COUNTY OF DADE J. W. Williams Jr. being first duly sworn, deposes and says: |
| | That he is a Grou Vice President of Florida Power & 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. |
| | J. W. Williams, Jr. |
| | Subscribed and sworn to before me this |
| | ~day of , I 9~. |
| | OTARY PUBLIC, in and for the County of Dade, State of Florida |
| | >>OilR" "9!ill( <is.i: i.:, ~ |
| | < <<ill!$5 ill: t,A << |
| | ~ '., ~ ~ |
| | aHRI'F.>ethic 'Oiiufb |
| | !'y Commission expires:}} |
|
|---|
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
P. X I 4000, JUNO BEACH. F L 33408 FLORIDA POWER & LIGHT COMPANY March 7, 1985 L-85-IOO Office of Nuclear Reactor Regulation Attention: Mr. Hugh L. Thompson, Jr. Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Thompson:
Re: Turkey Point Units 3 8 4 Docket Nos. 50-250 6 50-25 I Proposed Amendment to Facility 0 ratin Licenses DPR 3 I and 4 I In accordance with IO CFR 50.90, Florida Power & Light Company (FPL) submits herewith three signed originals and forty copies of a request to amend Facility Operating License's DPR-3 I and 4!.
The purpose of this amendment is to remove inconsistencies within the license and provide. clarification regarding the surveillance of fission detectors.
The proposed modifications will involve Technical Specification changes as described below and as shown on the accompanying Technical Specification pages (Attachment I).
Pa e 4.13-I This page is revised to clearly indicate the leak testing surveillance intervals for fission detectors.
Pa es 5.2-l 8 5.2-2 The paragraph on page 5.2-2 discussing the amount of enriched fissionable material allowed on site for the purposes of monitoring neutron flux is being deleted to be consistent with the Operating License,Section II.C.
Pages 5.2- I and 5.2-2 have been consolidated as page 5.2- I.
These proposed changes have been reviewed and approved by the Turkey Point Plant Nuclear Safety Committee and the FPL Company Nuclear Review Board.
Attachment 2 provides an evaluation of the proposed action in light of the three standards contained in IO CFR 50.92 regarding the issue of no significant hazards. Attachment 3 provides the basis for the proposed modification.
In summary, FPL submits that the activities associated with the proposed amendment do not constitute a significant hazard to the public health and safety or to the environment and therefore that these amendments do not involve a significant hazards consideration. FPL respectfully requests that this application be processed and approved as'soon as possible. This change is required to support the installation of a new excore neutron flux monitoring system during the upcoming Unit 3 refueling outage.
MSO~Om~~7-PDR ADOCK P 05000250 PEOPLE SERVING PEOPLE P
Page 2 Office of Nuclear Reactor Regulations Mr. Hugh L. Thompson, Jr., Director In accordance with IO CFR l70.2 I, an application fee of $ I50.00 is attached.
In accordance with IO CFR 50.9 I (b)(l), a copy of the proposed amendment is being forwarded to the state designee for the State of Florida.
lf you have any questions, please contact us.
Yours very truly, J. W. Williams, Jr.
Group Vice President Nuclear Energy JWW/G JK/cab Attachments cc: Dr. J. Nelson Grace, Region II Harold F. Reis, Esquire Lyle E. Jerrett, Administrator Radiological Health Bc Rehabilitative Services
ATTACHMENT 1 T/S p.4.13-1 p.5.2-1
4.13 RADIOACTIVE MATERIALS SOURCES SURVEILLANCE Applies to leakage testing of by-product, source and special nuclear radioactive material sources.
O~b'ective: To assure that leakage from by-product, source and special nuclear radioactive material sources does not exceed allowable limits.
Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement State, as follows:
- 1. Each sealed source, except fission detectors and startup sources subject to core flux or those exempted by Specification 3.11 containing radioactive material, other than Hydrogen 3, with a half-life greater than 30 days and in any form other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months.
- 2. The periodic leak test required does not apply to sealed sources that are stored and not being used. The sources excepted from this test shall be tested for leakage prior to any use or transfer to another user unless they have been leak tested within six months prior to the date of use or transfer. In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the transfer, sealed sources shall not be put into use until tested.
- 3. Startup sources and fission detectors shall be leak tested prior to and following any repair or maintenance and before being subjected to core flux.
5.2 REACTOR REACTOR CORE
- 1. The reactor core contains approximately 71 metric tons of uranium in the form of slightly enriched uranium dioxide pellets. The pellets are encapsulated in Zircaloy - 0 tubing to form fuel rods. The reactor core is made up of 157 fuel assemblies. Each fuel assembly contains 200 fuel rods.
- 2. The average enrichment of the initial core is a nominal 2.50 weight percent of U-235. Three fuel enrichments are used in the initial core. The highest enrichment is a nominal 3.10 weight percent of U-235.
- 3. Reload fuel will be similar in design to the initial core.
Burnable poison rods are in the form of rod clusters which are located in vacant rod cluster control guide tubes, are used for reactivity and/or power distribution control.
- 5. There are 05 full-length RCC assemblies and 8 partial-length" RCC assemblies in the reactor core. The full-length RCC assemblies contain a 100 inch length of silver-indium-cadmium alloy clad with the stainless steel. The partial-length+
RCC assemblies contain a 36 inch length of silver-indium-cadmium alloy with the remainder of the stainless steel sheath filled with A1203.
REACTOR COOLANT SYSTEM
- 1. The design of the Reactor Coolant System complies with the code requirements.
- 2. All piping, components and supporting structures of the Reactor Coolant System are designed to Class I requirements and have been designed to withstand:
- a. The design seismic ground acceleration, 0.05g acting in the horizontal and 0.033g acting in the vertical planes simultaneously, with stress maintained within code allowable working stresses.
- b. The maximum potential seismic ground acceleration, 0.15g, acting in the horizontal and 0.10g acting in the vertical directions simultaneously with no loss of function.
- 3. The nominal liquid volume of the Reactor Coolant System, at rated operating conditions, is 9088 cubic feet.
+ Any reference to part-length rods no longer applies after the part-length rods are removed from the reactor.
ATTACHMENT2 No SI nificant Hazards Consideration Florida Power and Light Company (FPL) presents this evaluation of the hazards considerations involved with the proposed amendment, focusing on the three standards set forth in IO CFR 50.92(c) as quoted below:
"The Commission may make a final determination, pursuant to the procedures in 50.9I, that a proposed amendment to an operating license for a facility licensed under 50.2l(b) or 50.22 or for a testing facility involves no significant hazards considerations, if operation of the facility in accordance with a proposed amendment would not:
I. Involve a significant increase in the probability or consequences or 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."
FPL submits that the activities associated with this amendment request do not meet any of the significant hazards considerations standards of IO CFR 50.92(c) and, accordingly, a no significant hazards consideration finding is justified. In support of this determination, necessary .background information has been provided (Attachment 3). Discussion of each of the above significant safety hazards consideration standards follows.
Evaluation The following evaluation demonstrates that the proposed amendment does not exceed any of the three significant hazards consideration standards.
I. Involve a si nificant increase in the robabilit or conse uences of an accident reviousl evaluated.
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The proposed Technical Specification change is an administrative change that will remove inconsistencies in the amount of special nuclear material that may be on site in the form of fission detectors. The change also clarifies the required surveillance requirements for fission detectors. This change in itself cannot cause an accident nor can it result in additional consequences of an accident previously evaluated. In fact, the additional fission detectors that precipitated the need for the T.S. change are being provided in accordance with NRC requirements to provide additional qualified instrumentation to monitor the reactor core during plant accidents.
- 2. Create the ossibilit of a new or different kind of accident from an accident reviousl evaluated.
The proposed changes are administrative in nature. As discussed above the changes are being made to remove inconsistencies and provide clarification of the Technical Specifications. Therefore, this change in itself cannot create a new or different kind of accident. These changes are consistent with the Standard Technical Specifications promulgated by the NRC.
- 3. Involve a si nificant reduction in a mar in of safet .
The proposed administrative changes to the Technical Specifications were precipitated by the need to utilize additional fission detectors for reactor neutron flux monitoring.
This change will achieve consistency in the License and provide clarification of the intent of the surveillance requirements for fission detectors. This change therefore does not involve a significant reduction in any margin of safety.
48 FR l4870 dated April 6, l983 provided examples of amendments not likely to involve a significant hazards consideration. This proposed change is considered to be most similar to example (I) in that it involves an administrative change, to achieve consistency and provide clarification of the present Technical Specifications.
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In summation, it has been shown that the Technical Specification change would not I. Involve a significant increase in the probability or consequences 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.
Therefore, FPL has determined that, the proposed amendment involves no significant hazards considerations.
ATIACHMENT3 BASIS FOR PROPOSED T.S. CHANGES INTRODUCTION:
As part of plant improvements required by the NRC pursuant to Reg. Guide l.97 Rev. 3 and IO CFR 50 Appendix R, a new excore neutron flux monitoring system will be installed. This system will employ the use of fission chambers mounted external to the core for neutron radiation detection. Each detector will use enriched uranium in small quantities to provide the mechanism for neutron detection. The combined quantity of this material for all required detectors is consistent with Operating License Section II. C., but will exceed that allowed by Technical Specification 5.2.
1 In addition, to changes to T.S. 5.2, administrative changes to T.S. 4.I3 are necessary to clarify the surveillance requirements for fission detectors.
BACKGROUND In late 1973 the AEC (presently the NRC) began implementing changes in its
. procedures for licensing the possession of byproduct, source, and special nuclear materials in connection with the operation of power reactors. The standard format for SAR's was amended to request information on an applicant's capabilities, facilities and procedures for handling and storage of this material. In addition, standard language for incorporation into the facility operating license and Technical Specifications was provided.
On September l9, l974, after discussions with the AEC s Directorate of Licensing, FPL submitted proposed changes to the Turkey Point Facility Operating License.
The purpose of the change was to amend Section II.C. of the license and provide two new Technical Specifications (3.I I and 4.I3) to ensure that byproduct, source and special nuclear material sources utilized at Turkey Point were maintained in accordance with the AEC's rules and regulations. In support of this amendment request, FPL submitted revisions to the FSAR (dated 9/l7/74 and l2/23/74)
describing the radioactive materials safety program at Turkey Point. The staff reviewed and approved the proposed Technical Specification changes since there was reasonable assurance that byproduct, source, and special nuclear material would be stored, used, and accounted for in a manner which met the applicable radiation protection provisions of IO CFR 20, 30, 40, and 70. As such the Operating License was amended on July IO, l975 to include (among other changes) the following Section II.C, which licensed FPL:
"Pursuant to the Act and IO CFR Parts 30, 40 and.70 to receive, possess, and use at anytime any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;"
This new section of the Operating License conformed with the AEC's standard license format as shown in an interoffice memo from the Directorate of Licensing to Branch Chiefs, Project Managers and Licensing Assistants dated I I/28/73. The intent of this section was to allow the use of the identified materials in amounts as required for reactor 'operation. Apparently by oversight, Technical Specification 5.2 was not amended to remove the restriction on the number of grams of enriched fissionable material allowed on-site as fission detectors.
Indeed, this specification should have been deleted since it is inconsistent with Operating License Section II.C.
The other change to the Technical Specification is to clarify the intent of T.S.
4.I3. The surveillance requirements specified for sealed source in use is to identify leakage that may have resulted from handling of the sealed source. Since the fission detectors, like startup sources, are not routinely handled the necessary surveillance intervals is not intended to be six months. This intent is clearly demonstrated in the NRC's Standard Technical Specifications 4.7.10 and 84.7.IO, where surveillance for startup sources and fission detectors are required to be tested prior to use and following repair or maintenance. Therefore this change to the Technical Specification is considered purely, administrative since it merely clarifies the surveillance requirements for fission detectors.
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CONCLUSION As evidenced by the discussion above, the described changes are purely administrative. As such, FPL concludes that: (I) that amendments do not involve a significant hazards consideration; (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed changes and (3) these changes are in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
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STATE OF FLORIDA COUNTY OF DADE J. W. Williams Jr. being first duly sworn, deposes and says:
That he is a Grou Vice President of Florida Power & 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.
J. W. Williams, Jr.
Subscribed and sworn to before me this
~day of , I 9~.
OTARY PUBLIC, in and for the County of Dade, State of Florida
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