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{{#Wiki_filter:e' Dave Morey Southern Nuclear
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Dave Morey Vice President Southern Nuclear Operating Company i         Farley Project             P.O. Box 1295 Birmingham. Alabama 35201 A                                             . Tel 205.992.5131
Vice President Operating Company i
Farley Project P.O. Box 1295 Birmingham. Alabama 35201 A
. Tel 205.992.5131
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March 12, 1998 SOUTHE.RN c Energy to SernYourWorld" Docket Numbers:       50-348 50-364                                                                 10 CFR 50.90 U. S. Nuclear Regulatory Conunission ATTN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Request For Technical Specification Changes Conversion to the Imoroved Technical Specifications Ladies and Gentlemen:
March 12, 1998 SOUTHE.RN c
Energy to SernYourWorld" Docket Numbers:
50-348 50-364 10 CFR 50.90 U. S. Nuclear Regulatory Conunission ATTN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Request For Technical Specification Changes Conversion to the Imoroved Technical Specifications Ladies and Gentlemen:
In accordance with the provisions of 10 CFR 50.90, Southem Nuclear Operating Company (SNC) proposes to amend the Farley Nuclear Plant (FNP) Unit I and Unit 2 Technical Specifications (TS),
In accordance with the provisions of 10 CFR 50.90, Southem Nuclear Operating Company (SNC) proposes to amend the Farley Nuclear Plant (FNP) Unit I and Unit 2 Technical Specifications (TS),
Appendix A to Operating Licenses NPF-2 and NPF-8. This TS amendment request revises the existing TS for Farley Units I and 2 in their entirety. The amendment consists primarily of a conversion of the Farley yO             Current Technical Specifications (CTS), based on NUREG-0452, to the improved Technical Specifications (ITS) for Westinghouse plants based on NUREG-1431, Revision 1. Additional changes are reflected in 1
Appendix A to Operating Licenses NPF-2 and NPF-8. This TS amendment request revises the existing TS for Farley Units I and 2 in their entirety. The amendment consists primarily of a conversion of the Farley yO Current Technical Specifications (CTS), based on NUREG-0452, to the improved Technical Specifications (ITS) for Westinghouse plants based on NUREG-1431, Revision 1. Additional changes are reflected in Attachments 3 and 5. As part of this conversion, the two sets of CTS will be combined into a single set, 1
Attachments 3 and 5. As part of this conversion, the two sets of CTS will be combined into a single set, applicable to both operating units.
applicable to both operating units.
By letter dated December 1,1995, Sv%rn Nuclear Operating Company (SNC) provided notification of                 ,
By {{letter dated|date=December 1, 1995|text=letter dated December 1,1995}}, Sv%rn Nuclear Operating Company (SNC) provided notification of i
i the intent to implement ITS for FNr. The proposed license amendment request to convert the Farley CTS to the Farley ITS is provided in the volumes enclosed with this letter. The proposed amendment has been compared to the guidance of Nuclear Energy Institute (NEI) 96-06, " Improved Technical Specifications           !
the intent to implement ITS for FNr. The proposed license amendment request to convert the Farley CTS to the Farley ITS is provided in the volumes enclosed with this letter. The proposed amendment has been compared to the guidance of Nuclear Energy Institute (NEI) 96-06, " Improved Technical Specifications Conversion Guidance," dated August 1996. This NEl document was issued well after the start of the
Conversion Guidance," dated August 1996. This NEl document was issued well after the start of the               )'
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Farley conversion to the ITS and, therefore, the attached ITS material may differ slightly from the specific NEl 96-06 guidance. However, the intent of the guidance has been incorporated into the Farley ITS conversion documentation. In addition, SNC has performed reviews ofIndustry and NRC correspondence and incorporated related enhancements as well as addressing FNP-specific literal compliance concerns.
Farley conversion to the ITS and, therefore, the attached ITS material may differ slightly from the specific NEl 96-06 guidance. However, the intent of the guidance has been incorporated into the Farley ITS conversion documentation. In addition, SNC has performed reviews ofIndustry and NRC correspondence and incorporated related enhancements as well as addressing FNP-specific literal compliance concerns.
Due to the size and complexity of this license amendment request, numerous Attachments have been included to describe the organization and disposition of various items addressed during the conversion         l l process These Attachments are dneribed below:                                                               g Attachment 1, " improved Technict,I Specifications Conversion Reviewers Guide," describes the               jf organization of the enclosed submittal volumes and provides guidance for efficient review.                       ,
Due to the size and complexity of this license amendment request, numerous Attachments have been included to describe the organization and disposition of various items addressed during the conversion l
I Attachment 2, "An Overview of the Disposition of LCO's in the FNP ITS Conversion," provides a cross-             I reference comparison of all Parley CTS, Farley ITS, and STS (NUREG-1431, Rev.1) Technical k( j) ~.        Specifications.
process These Attachments are dneribed below:
g, " improved Technict,I Specifications Conversion Reviewers Guide," describes the jf organization of the enclosed submittal volumes and provides guidance for efficient review.
I, "An Overview of the Disposition of LCO's in the FNP ITS Conversion," provides a cross-I k( j) ~.
reference comparison of all Parley CTS, Farley ITS, and STS (NUREG-1431, Rev.1) Technical Specifications.
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c.1 U.S. Nuclear Regulatory Comnussion                                                                     Page 2 Mend =nent 3, "Farley CTS License AvaaaAnaat Requests incorporated into the ITS," provides a listing of all currently daractart license amendment requests that have been included in the ITS submittal package.
c.1 U.S. Nuclear Regulatory Comnussion Page 2 Mend =nent 3, "Farley CTS License AvaaaAnaat Requests incorporated into the ITS," provides a listing of all currently daractart license amendment requests that have been included in the ITS submittal package., " Generic O- :a= to NUREG-1431, Rev.1, Incorporated into the ITS," provides a listing of the generic Technical Specification Task Force (TSTF) changes incorporated into the Farley ITS submittal Package., " Changes identified as Beyond the Scope of an ITS Conversion," provides a listing of those changes incorporated into the Farley ITS submittal package which differ from both the CTS and the Improved Standard Technical Specification (ISTS) as written in NUREG-1431, Rev.1., " Summary of CTS Requirements Renwved from the TS and Placed in, or Currently 1.ocated
Attachment 4, " Generic O- :a= to NUREG-1431, Rev.1, Incorporated into the ITS," provides a listing of the generic Technical Specification Task Force (TSTF) changes incorporated into the Farley ITS submittal Package.
. in, Other Documents," provides a listing of the CTS requirements which will be relocated or removed from the CTS, the proposed document to which they will be initially relocated or moved, and the control mechanism that will apply to each relocated or moved item.
Attachment 5, " Changes identified as Beyond the Scope of an ITS Conversion," provides a listing of those changes incorporated into the Farley ITS submittal package which differ from both the CTS and the Improved Standard Technical Specification (ISTS) as written in NUREG-1431, Rev.1.
Attachment 6, " Summary of CTS Requirements Renwved from the TS and Placed in, or Currently 1.ocated
                    . in, Other Documents," provides a listing of the CTS requirements which will be relocated or removed from the CTS, the proposed document to which they will be initially relocated or moved, and the control mechanism that will apply to each relocated or moved item.
Implementation of the Farley ITS will require the performance of a number of new ITS surveillance requirements. SNC intends to treat these new requirenwnts as being " met" at the time ofimplementation, with the first performance of these new surveillance requirements scheduled to be completed within the required interval from the date ofimplementation.
Implementation of the Farley ITS will require the performance of a number of new ITS surveillance requirements. SNC intends to treat these new requirenwnts as being " met" at the time ofimplementation, with the first performance of these new surveillance requirements scheduled to be completed within the required interval from the date ofimplementation.
O U               Any revisions to the Farley Final Safety Ana!, sis Report (FSAR) required as a result of the conversion to the Farley ITS will be made in accordance with 10 CFR 50.71(c).
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Any revisions to the Farley Final Safety Ana!, sis Report (FSAR) required as a result of the conversion to the Farley ITS will be made in accordance with 10 CFR 50.71(c).
The planned implementation period is March 2000. 'Ihis imp!cmcatation period is timed to coincide with the Unit I steam generator replacement outage beginmng in April 2000. The Steam Generator Replacement (SGR) licensing package will be in the ITS format. Due to the time required for procedure revisions, the development of new programs, and training schedules for both licensed and non-licensed operators, and the desire for efficient implementation of both the ITS and SGR changes in parallel, SNC
The planned implementation period is March 2000. 'Ihis imp!cmcatation period is timed to coincide with the Unit I steam generator replacement outage beginmng in April 2000. The Steam Generator Replacement (SGR) licensing package will be in the ITS format. Due to the time required for procedure revisions, the development of new programs, and training schedules for both licensed and non-licensed operators, and the desire for efficient implementation of both the ITS and SGR changes in parallel, SNC
_ requires a full 6 months after the issuance of the Safety Evaluation to implement this proposed license amendment request at Farley. "Iherefore, SNC requests that the NRC review and approve the proposed ITS Conversion by September 30,1999.
_ requires a full 6 months after the issuance of the Safety Evaluation to implement this proposed license amendment request at Farley. "Iherefore, SNC requests that the NRC review and approve the proposed ITS Conversion by September 30,1999.
As denoted in 10 CFR 50.92(c), SNC has determined the proposed changes to the FNP TS do not involve a
As denoted in 10 CFR 50.92(c), SNC has determined the proposed changes to the FNP TS do not involve a
                    'significant hazards consideration. 'Ihe basis for this evaluation is provided in Enclosure 3 of the submittal volumes. SNC has also determined that the proposed changes will not significantly affect the qudity of the human environment._ A copy of the proposed changes has been sent to Dr. D. E. Williams, the Alabama State Designee, in acs4 dance with 10 CFR 50.91(b)(i).                                                       )
'significant hazards consideration. 'Ihe basis for this evaluation is provided in Enclosure 3 of the submittal volumes. SNC has also determined that the proposed changes will not significantly affect the qudity of the human environment._ A copy of the proposed changes has been sent to Dr. D. E. Williams, the Alabama State Designee, in acs4 dance with 10 CFR 50.91(b)(i).
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SNC requests a meeting in W==Magtaa. DC, at your earliest convenience to discuss the contents of this license amendment request, to establish a review schedule, and to establish unes of communication and the means of communicating requests for additional information and responses to those requests.
SNC requests a meeting in W==Magtaa. DC, at your earliest convenience to discuss the contents of this license amendment request, to establish a review schedule, and to establish unes of communication and the means of communicating requests for additional information and responses to those requests.
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L U.S. Nuclear Regulatory Commission                                                               Page 3 O:
L U.S. Nuclear Regulatory Commission Page 3 O:
Mr. D. N. Momy states that he is a Vice President of Southern Nuclear Operating Company and is '
Mr. D. N. Momy states that he is a Vice President of Southern Nuclear Operating Company and is '
authorized to execute this oath on behalf of Southern Nuclear Operating Company and that, to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.
authorized to execute this oath on behalf of Southern Nuclear Operating Company and that, to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.
Ifyou have any questions, please advise.
Ifyou have any questions, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY NN Dave Morey Swom to andsubscribedbef re me this&.Yy of NOA tt .                         I998                           l
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY NN Dave Morey Swom to andsubscribedbef re me this&.Yy of NOA tt.
              'nwh ' Notary Public U ~
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My Commission Expires:       #1.8mI<.L /. A/
Notary Public U ~
My Commission Expires:
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WAS/maf:itssub. doc Awh=ts (1-6)
WAS/maf:itssub. doc Awh=ts (1-6)
        - Enclosures - Conversion Documentation (10 Volumes) cc:   Mr. L. A. Reyes, Region II Administrator Mr. J.1. Zimmerman, NRR Project Manager Mr. T, M. Ross, Plant Sr. Resident Inspector Dr. D. E. Williamson, State Department of Public Health 1
- Enclosures - Conversion Documentation (10 Volumes) cc:
Mr. L. A. Reyes, Region II Administrator Mr. J.1. Zimmerman, NRR Project Manager Mr. T, M. Ross, Plant Sr. Resident Inspector Dr. D. E. Williamson, State Department of Public Health
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6 Farley Nuclear Plant ITS conversion Submittal O
''                                                          Farley Nuclear Plant ITS conversion Submittal O
Joseph M. Farley Nuclear Plant ImDr0ved Technical Specifications Conversion Reviewers Guide O
Attachment 1 Joseph M. Farley Nuclear Plant ImDr0ved Technical Specifications Conversion Reviewers Guide O
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  "                                                                                                Farley Nuclear Plant ITS conversion Submittal
Farley Nuclear Plant ITS conversion Submittal
/                                   Improved Technical Specifications Conversion Reviewers Guide V
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Improved Technical Specifications Conversion Reviewers Guide V
OVERVIEW i
OVERVIEW i
The Farley license amendment request for converting to a Farley-specific version of the generic Technical       ]
The Farley license amendment request for converting to a Farley-specific version of the generic Technical
]
Specifications (TS) contained in NUREG-1431, Rev.1, Standard Technical Specifications (STS),
Specifications (TS) contained in NUREG-1431, Rev.1, Standard Technical Specifications (STS),
Westinghouse Plants, is based on the format and presentation of the Improved Technical Specifications (ITS) conversion amendments already submitted by SNC plants Hatch and Vogtle, as well as generic                 3 guidance provided by the NRC and NEl.                                                                           l l
Westinghouse Plants, is based on the format and presentation of the Improved Technical Specifications (ITS) conversion amendments already submitted by SNC plants Hatch and Vogtle, as well as generic 3
The submittrJ package is divided into separate review sections. Each review section contains all the TS associated with a STS chapter (i.e., Electrical, Containment, RCS, etc.). The documentation included in each chapter secNn contains the information necessary to conduct a complete review of the conversion changes made to the Farley Current Technical Specifications (CTS) as well as the changes made to the corresponding STS to develop the Farley-specific version of the STS (the FNP ITS). The review packages           {
guidance provided by the NRC and NEl.
I are also formatted such that the documentation pertaining to irdividual TS may be separated from the parent chapter which facilitates the review process by allowing individual Specifications to be distributed separately if desired.
l The submittrJ package is divided into separate review sections. Each review section contains all the TS associated with a STS chapter (i.e., Electrical, Containment, RCS, etc.). The documentation included in each chapter secNn contains the information necessary to conduct a complete review of the conversion changes made to the Farley Current Technical Specifications (CTS) as well as the changes made to the corresponding STS to develop the Farley-specific version of the STS (the FNP ITS). The review packages
In order to facilitate the organization, preparation, and review of the chapter sections, each chapter section is divided into six enclosures. These enclosures are linked, providing a roadmap of the conversion from the     j CTS to the FNP-specific ITS. Therefore, typically the most efficient method for review of a chapter is to s
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lay out cach of the six enclosures side-by-side. This allows the reviewer to identify what changes are made
are also formatted such that the documentation pertaining to irdividual TS may be separated from the parent chapter which facilitates the review process by allowing individual Specifications to be distributed separately if desired.
/           to the CTS, why they are made, and why they are not a significant hazards concern. In parallel, the k           corresponding STS LCOs and Bases may be reviewed, including the changes required to make them FNP-specific and thejustifications for these changes. A description of each enclosure follows:                       l ENCLOSURE 1 Enclosure I consists of a markup of each of the FNP CTS that correspond with the applicable STS chapter (i.e, Electrical, Containment, RCS, etc.). In order to facilitate the review of the revisions to the CTS, the LCOs in Enclosure I are organized in CTS order. Each CTS is marked to show technical and organizational changes required to convert to the STS and the location of the CTS requirements in the corresponding FNP ITS (Enclosure 4). Due to the extensive format and editorial differences between the CTS and the STS, minor editorial and simple format changes may not be identified. Each significant change identified in Enclosure I is assigned a Discussion of Change (DOC) number and a no Significant llazards Evaluation (SHE) designator. The DOC for each numbered item is contained in Enclosure 2. The SilE designator assigned to each change corresponds to a generic or specific SHE contained in Enclosure
In order to facilitate the organization, preparation, and review of the chapter sections, each chapter section is divided into six enclosures. These enclosures are linked, providing a roadmap of the conversion from the j
CTS to the FNP-specific ITS. Therefore, typically the most efficient method for review of a chapter is to lay out cach of the six enclosures side-by-side. This allows the reviewer to identify what changes are made s
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to the CTS, why they are made, and why they are not a significant hazards concern. In parallel, the k
corresponding STS LCOs and Bases may be reviewed, including the changes required to make them FNP-specific and thejustifications for these changes. A description of each enclosure follows:
l ENCLOSURE 1 Enclosure I consists of a markup of each of the FNP CTS that correspond with the applicable STS chapter (i.e, Electrical, Containment, RCS, etc.). In order to facilitate the review of the revisions to the CTS, the LCOs in Enclosure I are organized in CTS order. Each CTS is marked to show technical and organizational changes required to convert to the STS and the location of the CTS requirements in the corresponding FNP ITS (Enclosure 4). Due to the extensive format and editorial differences between the CTS and the STS, minor editorial and simple format changes may not be identified. Each significant change identified in Enclosure I is assigned a Discussion of Change (DOC) number and a no Significant llazards Evaluation (SHE) designator. The DOC for each numbered item is contained in Enclosure 2. The SilE designator assigned to each change corresponds to a generic or specific SHE contained in Enclosure
: 3. Each SilE is fully described in Enclosure 3.
: 3. Each SilE is fully described in Enclosure 3.
A complete set of Unit ! CTS is included. Unit 2 CTS pages are included only when a difference exists between the Unit 2 and corresponding Unit I CTS that must be individuallyjustified. All changes marked on the Unit i CTS apply to the Unit 2 CTS unless a separate Unit 2 CTS page is included. As part of the front matter for Enclosure I in cach Chapter package, a listing and description of the differences between the current Unit I and Unit 2 TS is included.
A complete set of Unit ! CTS is included. Unit 2 CTS pages are included only when a difference exists between the Unit 2 and corresponding Unit I CTS that must be individuallyjustified. All changes marked on the Unit i CTS apply to the Unit 2 CTS unless a separate Unit 2 CTS page is included. As part of the front matter for Enclosure I in cach Chapter package, a listing and description of the differences between the current Unit I and Unit 2 TS is included.
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  ..                                                                                            Faley Nuclear Plant ITS conversion Submittal n                               Imoroved Technical Specifications Conversion Reviewers Guide (v)
Faley Nuclear Plant ITS conversion Submittal n
The CTS markup addresses the addition of new ITS LCOs in two ways. If the ncw LCO is derived from an existing CTS LCO, the markup of that CTS LCO addresses the new ITS LCO and the associated DOCS explain the addition of the ITS LCO. In this case, a copy of the new ITS LCO is not always included in Enclosure 1. If the ITS LCO is completely new to the CTS and unrelated to existing CTS LCOs, a copy of the new LCO is included at the end of the Enclosure 1 markup and the associated DOC evaluates the addition of that new LCO.
Imoroved Technical Specifications Conversion Reviewers Guide (v)
ENCLOSURE 2 Enclosure 2 contains a DOC for each marked-up change to the FNP CTS required to produce the FNP specific ITS. The DOC numbers are referenced directly from Enclosure 1 (CTS markup), and the associated SHEs are contained in Enclosure 3. Each of the DOCS and associated SHEs are applicable to both Unit I and 2 unless otherwise stated. Each technical change and the more complf::ated format and presentation changes to the CTS are discussed and justified specifically for FNP. In order to facilitate review, the DOCS in this enclosure are organized by individual TS and may be easily separated into individual TS review sections if desired. The DOCS for each LCO are labeled with the corresponding CTS number and name and the proposed FNP ITS specific number and name.
The CTS markup addresses the addition of new ITS LCOs in two ways. If the ncw LCO is derived from an existing CTS LCO, the markup of that CTS LCO addresses the new ITS LCO and the associated DOCS explain the addition of the ITS LCO. In this case, a copy of the new ITS LCO is not always included in. If the ITS LCO is completely new to the CTS and unrelated to existing CTS LCOs, a copy of the new LCO is included at the end of the Enclosure 1 markup and the associated DOC evaluates the addition of that new LCO.
ENCLOSURE 3 Enclosure 3 contains the collection of SilEs associated with all the CTS changes identified and discussed in
ENCLOSURE 2 contains a DOC for each marked-up change to the FNP CTS required to produce the FNP specific ITS. The DOC numbers are referenced directly from Enclosure 1 (CTS markup), and the associated SHEs are contained in Enclosure 3. Each of the DOCS and associated SHEs are applicable to both Unit I and 2 unless otherwise stated. Each technical change and the more complf::ated format and presentation changes to the CTS are discussed and justified specifically for FNP. In order to facilitate review, the DOCS in this enclosure are organized by individual TS and may be easily separated into individual TS review sections if desired. The DOCS for each LCO are labeled with the corresponding CTS number and name and the proposed FNP ITS specific number and name.
ENCLOSURE 3 contains the collection of SilEs associated with all the CTS changes identified and discussed in
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D the previous enclosures. The SIIEs contained in Enclosure 3 are presented on an STS chapter basis and are subdivided into individual LCO sections, as are each of the other Enclosures that make up the conversion document. The large majority of CTS changes are categorized or grouped such that a single
the previous enclosures. The SIIEs contained in Enclosure 3 are presented on an STS chapter basis and D
            " generic" SHE may be applied to each group of changes. For example, a single generic SHE may be applied to all changes that are classified as Administrative changes (i.e., moving requirements from one TS to another without introducing a technical change to the requirement) or changes classified as a Relocation (the movement of an entire TS outside of the license). The generic SHE categories identified within this enclosure conform to the applicable NRC and NE! guidance. All changes identified as less restrictive technical changes (i.e., extended allowed outage times or surveillance intervals, deletion ofindividual requirements, etc.) which are not associated with a generic SHE are individually evaluated for FNP. These individual esaluations ofless restrictive changes are also included in Enclosure 3. The SHE designators usai in Enclosure 3, and a brief description of each are listed below:
are subdivided into individual LCO sections, as are each of the other Enclosures that make up the conversion document. The large majority of CTS changes are categorized or grouped such that a single
" generic" SHE may be applied to each group of changes. For example, a single generic SHE may be applied to all changes that are classified as Administrative changes (i.e., moving requirements from one TS to another without introducing a technical change to the requirement) or changes classified as a Relocation (the movement of an entire TS outside of the license). The generic SHE categories identified within this enclosure conform to the applicable NRC and NE! guidance. All changes identified as less restrictive technical changes (i.e., extended allowed outage times or surveillance intervals, deletion ofindividual requirements, etc.) which are not associated with a generic SHE are individually evaluated for FNP. These individual esaluations ofless restrictive changes are also included in Enclosure 3. The SHE designators usai in Enclosure 3, and a brief description of each are listed below:
ADMINISTRATIVE ("A" labeled changes)
ADMINISTRATIVE ("A" labeled changes)
This generic category applies to changes that are editorial in nature, involve the movement of requirements within the CTS without affecting their technical content, simply reformat a requirement, or clarify the TS (such as deleting a footnote no longer applicable due to a technical change to a requirement). It also includes non-technical changes such as refonnatting and rewording the remaining requirements in order to conform with the fonnat and style of the STS. These changes are intended to make the TS more readily understandable to plant operators and other users. The application of the STS format and style will also assure consistency is achieved between TS.
This generic category applies to changes that are editorial in nature, involve the movement of requirements within the CTS without affecting their technical content, simply reformat a requirement, or clarify the TS (such as deleting a footnote no longer applicable due to a technical change to a requirement). It also includes non-technical changes such as refonnatting and rewording the remaining requirements in order to conform with the fonnat and style of the STS. These changes are intended to make the TS more readily understandable to plant operators and other users. The application of the STS format and style will also assure consistency is achieved between TS.
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  ..                                                                                          Farley Nuclear Plant ITS conversion Submittal
Farley Nuclear Plant ITS conversion Submittal
/                         Improved Technical Specifications Conversion Reviewers Guide C/
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Improved Technical Specifications Conversion Reviewers Guide C/
During this reformatting and rewording process, no technical changes (either actual or interpretational) were made to the TS unless they were identified and justified. However, some obvious admmistrative changes may not be specifically referenced to a discussion of change or SHE.
During this reformatting and rewording process, no technical changes (either actual or interpretational) were made to the TS unless they were identified and justified. However, some obvious admmistrative changes may not be specifically referenced to a discussion of change or SHE.
If no discussion of change or SHE is referenced for a change, it is considered administrative in nature and this Generic SHE applies. Changes to the CTS requirements categorized as Admmistrative are annotated with an "A" in the Enclosure I markup and Enclosure 2 DOC. Administrative changes are considered generic and each change identified as Administrative will not be specifically discussed in this SHE. This evaluation will be applicable to each of the changes identified with an "A"in the Enclosure 1 markup of the CTS and the associated Enclosure 2 DOC.
If no discussion of change or SHE is referenced for a change, it is considered administrative in nature and this Generic SHE applies. Changes to the CTS requirements categorized as Admmistrative are annotated with an "A" in the Enclosure I markup and Enclosure 2 DOC. Administrative changes are considered generic and each change identified as Administrative will not be specifically discussed in this SHE. This evaluation will be applicable to each of the changes identified with an "A"in the markup of the CTS and the associated Enclosure 2 DOC.
RELOCATION OF TECHNICAL SPECIFICATIONS ("R" labeled changes)
RELOCATION OF TECHNICAL SPECIFICATIONS ("R" labeled changes)
This generic category applies to changes that relocate CTS requirements that do not meet the criteria in the NRC Final Policy Statement on Technical Specification improvement for Nuclear Power Reactors (58FR39132, dated 7/22/93). This category of SHE may only be applied to entire TS that do not meet the NRC Policy Statement Criteria. Relocation of these CTS requirements allows the TS document to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. Therefore, CTS which do not meet the criteria in the NRC Final Policy Statement on Technical Specification Improvement for Nuclear Power Reactors (58 FR 39132, dated 7/22/93) have been proposed for relocation to other g
This generic category applies to changes that relocate CTS requirements that do not meet the criteria in the NRC Final Policy Statement on Technical Specification improvement for Nuclear Power Reactors (58FR39132, dated 7/22/93). This category of SHE may only be applied to entire TS that do not meet the NRC Policy Statement Criteria. Relocation of these CTS requirements allows the TS document to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. Therefore, CTS which do not meet the criteria in the NRC Final Policy Statement on Technical Specification Improvement for Nuclear Power Reactors (58 FR 39132, dated 7/22/93) have been proposed for relocation to other g
I     T     licensee controlled documents that are subject to the provisions of 10 CFR 50.59 or other applicable O           CFR. This will ensure that changes to these relocated TS requirements will be limited to those that do not involve an unreviewed safety question.
I T
licensee controlled documents that are subject to the provisions of 10 CFR 50.59 or other applicable O
CFR. This will ensure that changes to these relocated TS requirements will be limited to those that do not involve an unreviewed safety question.
The NRC policy statement addresses the scope and purpose of TS, in doing so, it sets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. These criteria are as follows:
The NRC policy statement addresses the scope and purpose of TS, in doing so, it sets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. These criteria are as follows:
Criterion 1: Installed instrumentation that is used to detect and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; Criterion 2: A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analyses that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; Criterion 3: A structure, system or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission barrier; Criterion 4: A structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to public health and safety.
Criterion 1: Installed instrumentation that is used to detect and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; Criterion 2: A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analyses that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; Criterion 3: A structure, system or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission barrier; Criterion 4: A structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to public health and safety.
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[                                                                                     Farley Nuclear Plant ITS conversion Submittal
[
/G                      Improved Technical Specifications Conversion Reviewers Guide
Farley Nuclear Plant ITS conversion Submittal G
(                                                                                                                     )
/
Changes to the CTS requirements categorized as Relocated are annotated with an "R" in the                   ,
Improved Technical Specifications Conversion Reviewers Guide
Enclosure I markup and Enclosure 2 DOC. Relocation changes are considered generic and each                 j relocated TS will not be specifically discussed in this SHE. A specific DOC for each CTS identified for relocation is provided in Enclosure 2. This evaluation will be applicable to each of the changes identified with an "R"in the Enclosure 1 markup of the CTS and the associated Enclosure 2 DOC.             j MORE RESTRICTIVE ("M" labeled change;0                                                                     1 This generic category consists of changes that modify the CTS to add new requirements or revise existing requirements to be more stringent. These changes are typically made to conform to applicable requirements in the STS, correct discrepancies, or remove ambiguities from the CTS.
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Changes to the CTS requirements categorized as Relocated are annotated with an "R" in the Enclosure I markup and Enclosure 2 DOC. Relocation changes are considered generic and each j
relocated TS will not be specifically discussed in this SHE. A specific DOC for each CTS identified for relocation is provided in Enclosure 2. This evaluation will be applicable to each of the changes identified with an "R"in the Enclosure 1 markup of the CTS and the associated Enclosure 2 DOC.
j MORE RESTRICTIVE ("M" labeled change;0 1
This generic category consists of changes that modify the CTS to add new requirements or revise existing requirements to be more stringent. These changes are typically made to conform to applicable requirements in the STS, correct discrepancies, or remove ambiguities from the CTS.
More restrictive changes are proposed only when such changes are consistent with:
More restrictive changes are proposed only when such changes are consistent with:
: 1) The FNP current licensing basis;
: 1) The FNP current licensing basis;
: 2) The applicable FNP safety analyses; and
: 2) The applicable FNP safety analyses; and
: 3) Good engineering practice such that the availability and reliability of the affected equipment is not reduced.
: 3) Good engineering practice such that the availability and reliability of the affected equipment is not reduced.
Changes to the CTS requirements categonzed as More Restrictive are annotated with an "M' in the h
Changes to the CTS requirements categonzed as More Restrictive are annotated with an "M' in the h markup and Enclosure 2 DOC. These changes are considered generic and each change U
U Enclosure 1 markup and Enclosure 2 DOC. These changes are considered generic and each change identified as More Restrictive will not be specifically discussed in this SHE. This : Muation will be applicable to each of the changes identified with an "M"in the Enclosure I markup of the CTS and             ;
identified as More Restrictive will not be specifically discussed in this SHE. This : Muation will be applicable to each of the changes identified with an "M"in the Enclosure I markup of the CTS and the associated Enclosure 2 DOC.
the associated Enclosure 2 DOC.                                                                             )
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REMOVAL OF REOUIREMENTS FROM RETAINED TS ("LA"labeleri chances)                                             l i
REMOVAL OF REOUIREMENTS FROM RETAINED TS ("LA"labeleri chances) i This generic category applies to changes that modify the CTS to achieve consistency with the style j
This generic category applies to changes that modify the CTS to achieve consistency with the style         j and format of the STS by removing some information and requirements from the CTS. This                       j category of change is considered to be less restrictive (no longer controlled by TS) and is referred to       j I
and format of the STS by removing some information and requirements from the CTS. This j
as Less Restrictive - Generic. The " partial relocation" ofinformation can not be addressed by the application of the enteria in the NRC Final Policy Statement on Technical Specification improvement for Nuclear Power Reactors, ne NRC Policy Statement criteria is only intended to apply to entire TS. This generic category is intended to apply to changes that remove some information that is typically descriptive in nature regarding the equipment, system (s), actiens or surveillances from a CTS that is retained in the TS. The information that is removed from the CTS is proposed for inclusion in the TS Bases, FSAR, or other licensee controlled documents as appropriate. The removal of this information from the CTS to licensee controlled documents is acceptable because the documents will be controlled through a process which utilizes 10 CFR 50.59 or other applicable CFR. Therefore, the information that has been moved continues to be maintained in an appropriately controlled manner. The proposed changes will not impact the actual information moved out of the CTS, but will reduce the level of regulatory control over this information.
category of change is considered to be less restrictive (no longer controlled by TS) and is referred to j
im                                                                                                                     1
I as Less Restrictive - Generic. The " partial relocation" ofinformation can not be addressed by the application of the enteria in the NRC Final Policy Statement on Technical Specification improvement for Nuclear Power Reactors, ne NRC Policy Statement criteria is only intended to apply to entire TS. This generic category is intended to apply to changes that remove some information that is typically descriptive in nature regarding the equipment, system (s), actiens or surveillances from a CTS that is retained in the TS. The information that is removed from the CTS is proposed for inclusion in the TS Bases, FSAR, or other licensee controlled documents as appropriate. The removal of this information from the CTS to licensee controlled documents is acceptable because the documents will be controlled through a process which utilizes 10 CFR 50.59 or other applicable CFR. Therefore, the information that has been moved continues to be maintained in an appropriately controlled manner. The proposed changes will not impact the actual information moved out of the CTS, but will reduce the level of regulatory control over this information.
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  -[                                                                                         Farley Nuclear Plant ITS conversion Submittal hO improved Technica! Specifications Conversion Reviewers Guide Changes to the CTS requirements that fall within this category (Less Restrictive - Generic) are annotated with an "LA" in the Enclosure I markup and Enclosure 2 DOC. These changes are considered generic and each change identified as Less Restrictive - Generic will not be specifically discussed in this SliE. This evaluation will be applicable to each of the changes identified with an "LA"in the Enclosure I markup of the CTS and the associated Enclosure 2 DOC.
-[
Farley Nuclear Plant ITS conversion Submittal h
improved Technica! Specifications Conversion Reviewers Guide O
Changes to the CTS requirements that fall within this category (Less Restrictive - Generic) are annotated with an "LA" in the Enclosure I markup and Enclosure 2 DOC. These changes are considered generic and each change identified as Less Restrictive - Generic will not be specifically discussed in this SliE. This evaluation will be applicable to each of the changes identified with an "LA"in the Enclosure I markup of the CTS and the associated Enclosure 2 DOC.
ALLOWANCE TO USE A SIMULATED OR ACTUAL ACTUATION SIGNAL ("LB" labeled changes)
ALLOWANCE TO USE A SIMULATED OR ACTUAL ACTUATION SIGNAL ("LB" labeled changes)
This generic category applies to those changes that provide the allowance to utilize a simulated or actual signal to verify the automatic actuation of specific components in the Surveillance test requirements of the TS. This type of change is considered less restrictive as it provides an alternate method to satisfy surveillance requirements that verify automatic equipment / system actuation. This change allows satisfactory automatic actuations (required equipment / system operation is verified) that occur due to an actual automatic actuation to fulfill the surveill,wce requirement. Operability is adequately demonstrated in either case as the affected equipment or system carmot discriminate between an actual or simulated (test) signal. Changes to the CTS requirements that fall within this category (Less Restrictive - Generic) are annotated with an "LB" in the Enclosure i markup and Enclosure 2 DOC. These changes are considered generic and each change identified as Less Restrictive - Generic will not be specifically discussed in this SHE. This evaluation will be applicable to each of the changes identified with an "LB" in the Enclosure I markup of the CTS and
This generic category applies to those changes that provide the allowance to utilize a simulated or actual signal to verify the automatic actuation of specific components in the Surveillance test requirements of the TS. This type of change is considered less restrictive as it provides an alternate method to satisfy surveillance requirements that verify automatic equipment / system actuation. This change allows satisfactory automatic actuations (required equipment / system operation is verified) that occur due to an actual automatic actuation to fulfill the surveill,wce requirement. Operability is adequately demonstrated in either case as the affected equipment or system carmot discriminate between an actual or simulated (test) signal. Changes to the CTS requirements that fall within this category (Less Restrictive - Generic) are annotated with an "LB" in the Enclosure i markup and DOC. These changes are considered generic and each change identified as Less Restrictive - Generic will not be specifically discussed in this SHE. This evaluation will be applicable to each of the changes identified with an "LB" in the Enclosure I markup of the CTS and (G
    )       the associated Enclosure 2 DOC.
)
(G LESS RESTRICTIVE ("L" labeled changes)
the associated Enclosure 2 DOC.
This category consists of technical changes which revise existing requirements such that more           f restoration time is provided, fewer compensatory measures are needed, or fewer or less restrictive surveillance requirements are required. This would also include requirements which are deleted from the TS (not relocated to other documents) and other technical changes that do not fit a generic category. Rese changes are evaluated individually and " specific" SHEs developed. Each " specific" SiiE for a less restrictive technical change will be individually numbered in each TS with the suffix "L" Technical changes to the CTS requirements categorized as "Less Restrictive - Specific" are annotated with the suflix "L" and an individual number in the Enclosure 1 markup and Enclosure 2       i DOC for each TS. In order to facilitate review, the less restrictive SHEs are organized by individual TS. The SHEs applicable to each TS may be separated into individual review packages if desired.
LESS RESTRICTIVE ("L" labeled changes)
ENCLOSURE 4 Enclosure 4 contains the markup of the generic STS LCOs from NUREG-1431, Revision 1. The LCOs in Enclosure 4 are organized in STS order. Each STS LCO is marked with all the changes required to make             j the FNF-specific ITS or to identify that the STS generic LCO is not applicable to FNP. Each change made         l to a generic STS LCO is identified with a number that corresponds to ajustification for difference (JD) in       i Enclosure 5, except in cases where an FNP number or nomenclature, consistent with the CTS, is simply substituted for the corresponding STS generic number or name.
This category consists of technical changes which revise existing requirements such that more f
restoration time is provided, fewer compensatory measures are needed, or fewer or less restrictive surveillance requirements are required. This would also include requirements which are deleted from the TS (not relocated to other documents) and other technical changes that do not fit a generic category. Rese changes are evaluated individually and " specific" SHEs developed. Each " specific" SiiE for a less restrictive technical change will be individually numbered in each TS with the suffix "L"
Technical changes to the CTS requirements categorized as "Less Restrictive - Specific" are annotated with the suflix "L" and an individual number in the Enclosure 1 markup and Enclosure 2 i
DOC for each TS. In order to facilitate review, the less restrictive SHEs are organized by individual TS. The SHEs applicable to each TS may be separated into individual review packages if desired.
ENCLOSURE 4 contains the markup of the generic STS LCOs from NUREG-1431, Revision 1. The LCOs in are organized in STS order. Each STS LCO is marked with all the changes required to make j
the FNF-specific ITS or to identify that the STS generic LCO is not applicable to FNP. Each change made to a generic STS LCO is identified with a number that corresponds to ajustification for difference (JD) in i, except in cases where an FNP number or nomenclature, consistent with the CTS, is simply substituted for the corresponding STS generic number or name.
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      ,,                                                                                              Farley Nuclear Plant
Farley Nuclear Plant ITS conversion Submittal
    .                                                                                                ITS conversion Submittal
(                                Improved Technical Specifications Conversion Reviewers Guide
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Improved Technical Specifications Conversion Reviewers Guide
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Bracketed information in the STS is confirmed to be applicable to FNP or replaced with information that is applicable to FNP or deleted as appropriate. In cases v.here previously NRC approved CTS information is used to replace the generic STS information in brackets, nojustification for altering the bracketed STS information is typically provided. The basis for all such changes to the STS is to maintain the current FNP licensing basis as specified in the CTS.
Bracketed information in the STS is confirmed to be applicable to FNP or replaced with information that is applicable to FNP or deleted as appropriate. In cases v.here previously NRC approved CTS information is used to replace the generic STS information in brackets, nojustification for altering the bracketed STS information is typically provided. The basis for all such changes to the STS is to maintain the current FNP licensing basis as specified in the CTS.
Line 159: Line 194:
He Industry /NEl revisions to the STS are marked-up and identified with the NEI tracking number (i.e.,
He Industry /NEl revisions to the STS are marked-up and identified with the NEI tracking number (i.e.,
TSTF-03, TSTF-19, etc). The NEI changes are treated as though they are part of the STS for the FNP conversion. Each NEl change package contains its own justification for change which is not repeated in this conversion documentation.
TSTF-03, TSTF-19, etc). The NEI changes are treated as though they are part of the STS for the FNP conversion. Each NEl change package contains its own justification for change which is not repeated in this conversion documentation.
ENCLOSURE 5 Enclosure 5 contains the JDs between the generic STS and the proposed FNP ITS. Each change identified and numbered in Enclosure 4 is justified within this Enclosure. The STS markup in Enclosure 4 also contains approved changes to the STS resulting from the NEl/NRC revision process. The Industry /NEl sponsored changes marked in this enclosure have been approved by the NRC unless othenvise noted in Attachment 3 and have also been determined to be applicable to FNP. Thejustifications for NEl changes are contained in the associated change package submitted to the NRC and are not repeated in this
ENCLOSURE 5 contains the JDs between the generic STS and the proposed FNP ITS. Each change identified and numbered in Enclosure 4 is justified within this Enclosure. The STS markup in Enclosure 4 also contains approved changes to the STS resulting from the NEl/NRC revision process. The Industry /NEl sponsored changes marked in this enclosure have been approved by the NRC unless othenvise noted in and have also been determined to be applicable to FNP. Thejustifications for NEl changes
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document. In order to facilitate review, the JDs in this enclosure are organized by individual TS and may be easily separated into individual TS review sections if desired. The JDs are labeled with the corresponding STS number and name and the proposed FNP ITS specific number and name if different               i than the STS.                                                                                                 l l
are contained in the associated change package submitted to the NRC and are not repeated in this document. In order to facilitate review, the JDs in this enclosure are organized by individual TS and may be easily separated into individual TS review sections if desired. The JDs are labeled with the corresponding STS number and name and the proposed FNP ITS specific number and name if different than the STS.
ENCLOSURE 6                                                                                                    l Enclosure 6 contains the generic STS Bases marked-up to indicate the changes required to make the FNP-specific ITS Bases. As control of the Bases content is the responsibility of the licensee, the changes to the generic STS Bases are not discussed individually as are the changes to the generic STS LCOs. Changes to       l the generic STS Bases are associated with one of several categories which provide a general description of the change. The categories of Bases changes are identified within the Enclosure 6 front matter. Listed         i below are brief explanations for the types of changes to the Bases. The explanations are keyed to alpha designators which are used to mark each FNP specific Bases change. In addition, the mark-ups in this enclosure show the NRC approved changes to the STS resulting from the NEl/NRC revision process. The           ,
ENCLOSURE 6 contains the generic STS Bases marked-up to indicate the changes required to make the FNP-specific ITS Bases. As control of the Bases content is the responsibility of the licensee, the changes to the generic STS Bases are not discussed individually as are the changes to the generic STS LCOs. Changes to the generic STS Bases are associated with one of several categories which provide a general description of the change. The categories of Bases changes are identified within the Enclosure 6 front matter. Listed below are brief explanations for the types of changes to the Bases. The explanations are keyed to alpha designators which are used to mark each FNP specific Bases change. In addition, the mark-ups in this enclosure show the NRC approved changes to the STS resulting from the NEl/NRC revision process. The Industry /NEl sponsored changes marked in this enclosure have been approved by the NRC unless otherwise noted in Attachment 3, and have also been determined to be applicable to FNP. He Industry /NEl revisions to the STS are marked-up and identified with the NEl tracking number (i.e., TSTF-03, TSTF-19, etc). The NEl changes are treated as though they are part of the STS for the FNP conversion. Each NEl change package contains its own justification for change which is not repeated in this conversion documentation. The FNP specific STS Bases in this enclosure will completely replace all the corresponding current FNP Bases. See the following page for an explanation of the categories of
Industry /NEl sponsored changes marked in this enclosure have been approved by the NRC unless otherwise noted in Attachment 3, and have also been determined to be applicable to FNP. He Industry /NEl revisions to the STS are marked-up and identified with the NEl tracking number (i.e., TSTF-03, TSTF-19, etc). The NEl changes are treated as though they are part of the STS for the FNP conversion. Each NEl change package contains its own justification for change which is not repeated in this conversion documentation. The FNP specific STS Bases in this enclosure will completely replace all the corresponding current FNP Bases. See the following page for an explanation of the categories of
(
(     )     changes used in the bases.
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changes used in the bases.
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    .,                                                                                Farley Nuclear Plant ITS conversion Submittal Imoroved Technical Specifications Conversion Reviewers Guide L
Farley Nuclear Plant ITS conversion Submittal Imoroved Technical Specifications Conversion Reviewers Guide L
KEY                   EXPLANATION FOR FNP SPECIFIC BASES CHANGES TSC-# Technical Specification Change - Tnis Bases change is due to a corresponding change made to the associated STS LCO and is explained in detail in the associated Enclosure 5 JD. The JD number used in Enclosure 5 is also referenced in the Bases markup (as TSC
KEY EXPLANATION FOR FNP SPECIFIC BASES CHANGES TSC-#
                    #) where applicable.
Technical Specification Change - Tnis Bases change is due to a corresponding change made to the associated STS LCO and is explained in detail in the associated Enclosure 5 JD. The JD number used in Enclosure 5 is also referenced in the Bases markup (as TSC
PSC   Plant Specific Change - The Bases information is revised to conform to FNP design, analysis, terminology, or operating practice. This change may result in a deletion or revision ofinformation contained in the STS Bases.
#) where applicable.
PSE   Plant Specific Enhancement - Additional information specific to FNP is provided to enhance the STS Bases information consistent with FNP design, analysis, terminology, or operating practice.
PSC Plant Specific Change - The Bases information is revised to conform to FNP design, analysis, terminology, or operating practice. This change may result in a deletion or revision ofinformation contained in the STS Bases.
E     Editorial - Changes made to the NUREG-1431 Bases to improve clarity and understanding or correct minor errors.
PSE Plant Specific Enhancement - Additional information specific to FNP is provided to enhance the STS Bases information consistent with FNP design, analysis, terminology, or operating practice.
D     Deletion - This STS Bases information is deleted. The information constitutes extra detail not required to support the TS requirements for Operability, Applicability, Actions, Completion Times, or Surveillances. The information is not required or not t                   readily verified for FNP, or is contained in other documents already referenced in the Bases.
E Editorial - Changes made to the NUREG-1431 Bases to improve clarity and understanding or correct minor errors.
D V                                                                                                              ,
D Deletion - This STS Bases information is deleted. The information constitutes extra detail not required to support the TS requirements for Operability, Applicability, Actions, Completion Times, or Surveillances. The information is not required or not t
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readily verified for FNP, or is contained in other documents already referenced in the Bases.
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    ,                                                                  Farley Nuclear Plant ITS corwersion Submittal l
Farley Nuclear Plant ITS corwersion Submittal l
l 1
1 Joseph M. Farley Nuclear Plant An Overview of the Disposition of LCO's in the FNP ITS Conversion O
Attachment 2                                                l 1
Joseph M. Farley Nuclear Plant An Overview of the Disposition of LCO's in the FNP ITS Conversion O
O l
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    ..                                                                                                  Far.:- wlear Plant ITF .anve.sion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev i Specifications (CTS)         Improved Technical         Standard Technical                 Notes Specifications         Specifications (STS)
Far.:-
(FNP ITS)                                                   (1) 1.0 USE AND APPLICATION 1.0 Definitions             1.1 Definitions           1.1 Definitions NA                           1.2 Logical               1.2 Logical               New ITS 1.2 Connectors                 Connectors NA                           1.3 Completion Times       1.3 Completion Times     New ITS 1.3 NA                           1.4 Frequency             1.4 Frequency             New ITS 1.4 2.0 SAFETY LIMITS (SLs) 2.1.1 Reactor Core SL       2.1.1 Reactor Core SL     2.1.1 Reactor Core SL 2.1.2 RCS Pressure           2.1.2 RCS Pressure         2.1.2 RCS Pressure SL                           SL                         SL 2.2.1 RTS Setpoints         3.3.1 RTS                 3.3.1 RTS                 CTS LSSS moved from 2.0 to Instrumentation section 3.3.
wlear Plant ITF.anve.sion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev i Specifications (CTS)
NA                           2.2 SL Violations         2.2 SL Violations         Information from these sections was contained in CTS 2.1.1 and 2.1.2.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
3.0 LCO AND SR APPLICABILITY 3.0.I                       LCO 3.0.1                 LCO 3.0.1 3.0.2                       LCO 3.0.2                 LCO 3,0.2 3.0.3                       LCO 3.0.3                 LCO 3.0.3 3.0.4                       LCO 3.0.4                 LCO 3.0.4 3.0.5                       NA                         NA                         CTS 3.0.5 was removed from the TS.
(FNP ITS)
(1) 1.0 USE AND APPLICATION 1.0 Definitions 1.1 Definitions 1.1 Definitions NA 1.2 Logical 1.2 Logical New ITS 1.2 Connectors Connectors NA 1.3 Completion Times 1.3 Completion Times New ITS 1.3 NA 1.4 Frequency 1.4 Frequency New ITS 1.4 2.0 SAFETY LIMITS (SLs) 2.1.1 Reactor Core SL 2.1.1 Reactor Core SL 2.1.1 Reactor Core SL 2.1.2 RCS Pressure 2.1.2 RCS Pressure 2.1.2 RCS Pressure SL SL SL 2.2.1 RTS Setpoints 3.3.1 RTS 3.3.1 RTS CTS LSSS moved from 2.0 to Instrumentation section 3.3.
NA 2.2 SL Violations 2.2 SL Violations Information from these sections was contained in CTS 2.1.1 and 2.1.2.
3.0 LCO AND SR APPLICABILITY 3.0.I LCO 3.0.1 LCO 3.0.1 3.0.2 LCO 3.0.2 LCO 3,0.2 3.0.3 LCO 3.0.3 LCO 3.0.3 3.0.4 LCO 3.0.4 LCO 3.0.4 3.0.5 NA NA CTS 3.0.5 was removed from the TS.
(1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
(1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
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Farley Nuclear Pl nt ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications         Specifications (STS)
Farley Nuclear Pl nt ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP ITS)                                                   (1)
Improved Technical Standard Technical Notes Specifications Specifications (STS)
NA                           LCO 3.0.5                   LCO 3.0.3                 New ITS 3.0.5.
(FNP ITS)
NA                           LCO 3.0.6                   LCO 3.0.6                 New ITS 3.0.6.
(1)
NA                           LCO 3.0.7                   LCO 3.0.7                 New ITS 3.0.7.
NA LCO 3.0.5 LCO 3.0.3 New ITS 3.0.5.
4.0.1                       SR 3.0.1                   SR 3.0.1 4.0.2                       SR 3.0.2                   SR 3.0.2 4.0.3                       SR 3.0.3                   SR 3.0.3 4.0.4                       SR 3.0.4                   SR 3.0.4 4.0.5                       NA                         NA                         CTS 4.0.5 retained in part as IST Program in ITS Section 5.0.
NA LCO 3.0.6 LCO 3.0.6 New ITS 3.0.6.
3.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1.1 SDM - Tavg         3.1.1 SDM                   3.1.1 SDM - Tavg >         FNP ITS 3.1.1                   f contains requirements            i
NA LCO 3.0.7 LCO 3.0.7 New ITS 3.0.7.
              > 200 F                                                 200 F for SDM at all temperatures.                   l
4.0.1 SR 3.0.1 SR 3.0.1 4.0.2 SR 3.0.2 SR 3.0.2 4.0.3 SR 3.0.3 SR 3.0.3 4.0.4 SR 3.0.4 SR 3.0.4 4.0.5 NA NA CTS 4.0.5 retained in part as IST Program in ITS Section 5.0.
                                                                                                                                  \
3.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1.1 SDM - Tavg 3.1.1 SDM 3.1.1 SDM - Tavg >
i 3/4.1.1.2 SDM - Tavg         NA                         3.1.2 SDM - Tavg s         Separate SDM LCOs s 200 F                                                 200 F                     are no longer necessary due to SDM limits being contained within the COLR.
FNP ITS 3.1.1 f
NA                           3.1.2 Core Reactivity       3.1.3 Core Reactivity     New LCO derived from existing CTS requirements.
> 200 F 200 F contains requirements i
3/4.1.1.3 MTC               3.1.3 MTC                   3.1.4 MTC 3/4.1.1.4 Minimum           3.4.2 Minimum               3.4.2 Minimum             CTS LCO moved to Temperature for             Temperature for             Temperature for           RCS Section (3.4).
for SDM at all temperatures.
Criticality                 Criticality                 Criticality b
\\
i 3/4.1.1.2 SDM - Tavg NA 3.1.2 SDM - Tavg s Separate SDM LCOs s 200 F 200 F are no longer necessary due to SDM limits being contained within the COLR.
NA 3.1.2 Core Reactivity 3.1.3 Core Reactivity New LCO derived from existing CTS requirements.
3/4.1.1.3 MTC 3.1.3 MTC 3.1.4 MTC 3/4.1.1.4 Minimum 3.4.2 Minimum 3.4.2 Minimum CTS LCO moved to Temperature for Temperature for Temperature for RCS Section (3.4).
Criticality Criticality Criticality b
(!) See the applicable Enclosure i CTS markup or isnelosure 4 STS markup for more detailed information.
(!) See the applicable Enclosure i CTS markup or isnelosure 4 STS markup for more detailed information.
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Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications         Specifications (STS)
Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP LTS)                                                   (1) 3/4.1.2.1 Boration           NA                         NA                         Relocated.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
(FNP LTS)
(1) 3/4.1.2.1 Boration NA NA Relocated.
Flow Paths -
Flow Paths -
Shutdown 3/4.1.2.2 Boration           NA                         NA                         Relocated.
Shutdown 3/4.1.2.2 Boration NA NA Relocated.
Flow Paths -
Flow Paths -
Operating 3/4.1.2.3 Charging           NA                         NA                         Relocated.
Operating 3/4.1.2.3 Charging NA NA Relocated.
Pump - Shutdown 3/4.1.2.4 Charging           NA                         NA                         Relocated.
Pump - Shutdown 3/4.1.2.4 Charging NA NA Relocated.
Pumps - Operating 3/4.1.2.5 Borated           NA                         NA                         Relocated.
Pumps - Operating 3/4.1.2.5 Borated NA NA Relocated.
Water Sources -
Water Sources -
g     Shutdown 3/4.1.2.6 Borated           NA                         NA                         Relocated.
Shutdown g
3/4.1.2.6 Borated NA NA Relocated.
Water Sources -
Water Sources -
Operating 3/4.1.3.1 Movable           3.1.4 Rod Group           3.1.5 Rod Group Control Assemblies -         Alignment Limits           Alignment Limits Group licight 3/4.1.3.2 Position           3.1.7 Rod Position         3.1.8 Rod Position Indication Systcms -         Indication                 Indication Operating i
Operating 3/4.1.3.1 Movable 3.1.4 Rod Group 3.1.5 Rod Group Control Assemblies -
                                                                                                                                ~
Alignment Limits Alignment Limits Group licight 3/4.1.3.2 Position 3.1.7 Rod Position 3.1.8 Rod Position Indication Systcms -
3/4.1.3.3 Position           NA                         NA                         Relocated.
Indication Indication Operating i
3/4.1.3.3 Position NA NA Relocated.
~
Indication Systems -
Indication Systems -
Shutdown 3/4.1.3.4 Rod Drop           NA                         NA                         LCO and Actions Time                                                                               removed from TS.
Shutdown 3/4.1.3.4 Rod Drop NA NA LCO and Actions Time removed from TS.
Surveillance requirement retained in FNP ITS 3.1.4.
Surveillance requirement retained in FNP ITS 3.1.4.
(1) See the applicable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed infonnation.
(1) See the applicable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed infonnation.
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  '.                                                                                                    Faricy Nuclear Plant ITS conversion Submittal i                         An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                 Notes Specifications       Specifications (STS)
Faricy Nuclear Plant ITS conversion Submittal i
(FNP ITS)                                                   (1) 3/4.1.3.5 Shutdown           3.1.5 Shutdown Bank       3.1.6 Shutdown Bank Rod Insertion Limit         insertion Limits           insertion Limits 3/4.1.3.6 Control Rod       3.1.6 Control Bank         3.1.7 Control Bank Insertion Limits             insertion Limits           Insertion Limits 3/4.10.2 Group               3.1.8 PHYSICS             3.1.9 PHYSICS             CTS 3/4.10.2 moved lleight, insertion and       TESTS Exception -         TESTS Exception -         into ITS Section 3.1.
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
Power Distribution           Mode 1                     Mode 1 Limits 3.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AFD                 3.2.3 AFD                 3.2.3B AFD (RAOC)
Improved Technical Standard Technical Notes Specifications Specifications (STS)
NA                           NA                         3.2.3A AFD (CAOC)         Not FNP methodology.
(FNP ITS)
3/4.2.2 Ileat Flux Hot       3.2.1 Heat Flux Hot       3.2.1.B Heat Flux Channel Factor               Channel Factor             Hot Channel Factor (F9(Z))                   (Fo(Z))(FQ Methodology)
(1) 3/4.1.3.5 Shutdown 3.1.5 Shutdown Bank 3.1.6 Shutdown Bank Rod Insertion Limit insertion Limits insertion Limits 3/4.1.3.6 Control Rod 3.1.6 Control Bank 3.1.7 Control Bank Insertion Limits insertion Limits Insertion Limits 3/4.10.2 Group 3.1.8 PHYSICS 3.1.9 PHYSICS CTS 3/4.10.2 moved lleight, insertion and TESTS Exception -
NA                           NA                         3.2.1.A Heat Flux         Not FNP Hot Channel Factor         methodology.
TESTS Exception -
(Fo(Z))(Fxy Methodology) 3/4.2.3 Nuclear             3.2.2 Nuclear             3.2.2 Nuclear Enthalpy Hot Channel         Enthalpy Rise Hot         Enthalpy Rise Hot Factor                       Channel Factor             Channel Factor 3/4.2.4 QPTR                 3.2.4 QPTR                 3.2.4 QPTR 3/4.2.5 DNB                 3.4.1 RCS Pressure,       3.4.1 RCS Pressure,       CTS LCO moved to Parameters                   Temperature, and           Temperature, and           the ITS RCS Section.
into ITS Section 3.1.
Flow DNB Limits           Flow DNB Limits o
Power Distribution Mode 1 Mode 1 Limits 3.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AFD 3.2.3 AFD 3.2.3B AFD (RAOC)
\
NA NA 3.2.3A AFD (CAOC)
Not FNP methodology.
3/4.2.2 Ileat Flux Hot 3.2.1 Heat Flux Hot 3.2.1.B Heat Flux Channel Factor Channel Factor Hot Channel Factor (F (Z))
(Fo(Z))(FQ 9
Methodology)
NA NA 3.2.1.A Heat Flux Not FNP Hot Channel Factor methodology.
(Fo(Z))(Fxy Methodology) 3/4.2.3 Nuclear 3.2.2 Nuclear 3.2.2 Nuclear Enthalpy Hot Channel Enthalpy Rise Hot Enthalpy Rise Hot Factor Channel Factor Channel Factor 3/4.2.4 QPTR 3.2.4 QPTR 3.2.4 QPTR 3/4.2.5 DNB 3.4.1 RCS Pressure, 3.4.1 RCS Pressure, CTS LCO moved to Parameters Temperature, and Temperature, and the ITS RCS Section.
Flow DNB Limits Flow DNB Limits o
\\
(1) See the applicable Enclosure ! CTS markup or Enclosure 4 STS markup for mcre detailed information.
(1) See the applicable Enclosure ! CTS markup or Enclosure 4 STS markup for mcre detailed information.
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Farley Nuclear Plant ITS conversion Submittal O
Farley Nuclear Plant ITS conversion Submittal O
  %J An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                 Notes Specifications         Specifications (STS)
An Overview of the Disposition of LCO's in the FNP ITS Conversion
(FNP ITS)                                                   (1) 3.3 INSTRUMENTATION 3/4.3.1 RTS                 3.3.1 RTS                 3.3.1 RTS 3/4.3.2 ESFAS               3.3.2 ESFAS               3.3.2 ESFAS 3/4.3.3.1 Radiation         NA                       NA                         CTS requirements Monitoring                                                                         moved to other ITS Instrumentation                                                                   LCOs (3.3.3, 3.3.6, 3.3.7, 3.3.8) or removed from the TS.
%J Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
3/4.3.3.2 Movable           NA                         NA                         Relocated.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
Incore Detcetors 3/4.3.3.8 Accident         3.3.3 Post Accident       3.3.3 Post Accident Monitoring                 Monitoring                 Monitoring g            Instrumentation             Instrumentation           Instrumentation 3/4.3.3.5 Remote             3.3.4 Remote               3.3.4 Remote Shutdown                     Shutdown System           Shutdown System Instrumentation 3/4.3.3.7 High Energy       NA                         NA                         Relocated.
(FNP ITS)
Lme Break Isolation Sensors 3/4.3.3.1I Waste Gas         NA                         NA                         Retained in part as Monitoring                                                                         ITS 5.5.12 Explosive Instrumentation                                                                   Gas and Radioactivity Monitoring Program.
(1) 3.3 INSTRUMENTATION 3/4.3.1 RTS 3.3.1 RTS 3.3.1 RTS 3/4.3.2 ESFAS 3.3.2 ESFAS 3.3.2 ESFAS 3/4.3.3.1 Radiation NA NA CTS requirements Monitoring moved to other ITS Instrumentation LCOs (3.3.3, 3.3.6, 3.3.7, 3.3.8) or removed from the TS.
3/4.3.4 Turbine             NA                         NA                         Relocated.
3/4.3.3.2 Movable NA NA Relocated.
Overspeed Protection NA                           3.3.5 Loss of Power       3.3.5 Loss of Power       Consists of CTS DG Start                   DG Start                   requirements Instrumentation           Instrumentation           previously in the ESFAS LCO plus one new alarm instrument.
Incore Detcetors 3/4.3.3.8 Accident 3.3.3 Post Accident 3.3.3 Post Accident Monitoring Monitoring Monitoring Instrumentation Instrumentation Instrumentation g
3/4.3.3.5 Remote 3.3.4 Remote 3.3.4 Remote Shutdown Shutdown System Shutdown System Instrumentation 3/4.3.3.7 High Energy NA NA Relocated.
Lme Break Isolation Sensors 3/4.3.3.1I Waste Gas NA NA Retained in part as Monitoring ITS 5.5.12 Explosive Instrumentation Gas and Radioactivity Monitoring Program.
3/4.3.4 Turbine NA NA Relocated.
Overspeed Protection NA 3.3.5 Loss of Power 3.3.5 Loss of Power Consists of CTS DG Start DG Start requirements Instrumentation Instrumentation previously in the ESFAS LCO plus one new alarm instrument.
(1) See the applicable Enclosure 1 CTS murkup or Enclosure 4 STS markup for more detailed infonnation.
(1) See the applicable Enclosure 1 CTS murkup or Enclosure 4 STS markup for more detailed infonnation.
A2 5 t-
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Farley Nuelear Plant
Farley Nuelear Plant ITS conversion Submittal
  ,.                                                                                                    ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion
(
(
Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications       Specifications (STS)
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP ITS)                                                 (1)
Improved Technical Standard Technical Notes Specifications Specifications (STS)
NA                           3.3.6 Containment         3.3.6 Containment         Consists of CTS Purge and Exhaust         Purge and Exhaust         requirements isolation                 Isolation                 previously in the Instrumentation           Instrumentation           ESFAS LCO as well as other LCOs (e.g.,
(FNP ITS)
(1)
NA 3.3.6 Containment 3.3.6 Containment Consists of CTS Purge and Exhaust Purge and Exhaust requirements isolation Isolation previously in the Instrumentation Instrumentation ESFAS LCO as well as other LCOs (e.g.,
Rad Monitors) which contained purge and exhaust isolation requirements. Puts all containment purge /
Rad Monitors) which contained purge and exhaust isolation requirements. Puts all containment purge /
exhaust valve isolation instrumentation in one LCO.
exhaust valve isolation instrumentation in one LCO.
NA                           3.3.7 CREFS               3.3.7 CREFS               Consists of CTS Actuation                 Actuation                 requirements from Instmmentation           Instrumentation           Rad Monitors as well as other LCOs which contained CREFS Actuation Instrument requirements. Puts all CREFS instrumentation in one LCO.
NA 3.3.7 CREFS 3.3.7 CREFS Consists of CTS Actuation Actuation requirements from Instmmentation Instrumentation Rad Monitors as well as other LCOs which contained CREFS Actuation Instrument requirements. Puts all CREFS instrumentation in one LCO.
NA                           3.3.8 Penetration         3.3.8 Fuel Building       FNP specific system Room Filtration (PRF)     Air Cleanup System         name (PRF). Consists System Actuation         Actuation                 of CTS requirements Instrumentation           Instrumentation           from Rad Monitors as well as other LCOs which contained PRF Actuation Instrument requirements. Puts all PRF instrumentation in one LCO.
NA 3.3.8 Penetration 3.3.8 Fuel Building FNP specific system Room Filtration (PRF)
NA                           NA                       3.3.9 Boron Dilution       Not installed at FNP.
Air Cleanup System name (PRF). Consists System Actuation Actuation of CTS requirements Instrumentation Instrumentation from Rad Monitors as well as other LCOs which contained PRF Actuation Instrument requirements. Puts all PRF instrumentation in one LCO.
NA NA 3.3.9 Boron Dilution Not installed at FNP.
Protection System (BDPS)
Protection System (BDPS)
O Y
OY (I) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
(I) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
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    ..                                                                                                      Farley Nuclear Plant ITS conversion Submittal
Farley Nuclear Plant ITS conversion Submittal
(                             An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev i Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications         Specifications (STS)
(
(FNP ITS)                                                   (1) 3.4 REACTOR COOLA.NT SYSTEM (RCS) 3/4.2.5 DNB                 3.4.1 RCS Pressure,       3.4.1 RCS Pressure,       CTS LCO moved into Parameters                 Temperature, and           Temperature, and           ITS RCS Section.
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev i Specifications (CTS)
Flow DNB Limits           Flow DNB Limits 3/4.1.1.4 Minimum           3.4.2 Minimum             3.4.2 Minimum             CTS LCO moved into Temperature for             Temperature for           Temperature for           ITS RCS Section.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
Criticality                 Criticality               Criticality 3/4.4.10.1 RCS               3.4.3 RCS Pressure         3.4.3 RCS Pressure Pressure / Temperature       and Temperature           and Temperature Limits                     Limits                     Limits 3/4.4.1.1 RCS Loops         3.4.4 RCS Loops -         3.4.4 RCS Loops -
(FNP ITS)
Startup and Power           Modes I and 2             Modes I and 2
(1) 3.4 REACTOR COOLA.NT SYSTEM (RCS) 3/4.2.5 DNB 3.4.1 RCS Pressure, 3.4.1 RCS Pressure, CTS LCO moved into Parameters Temperature, and Temperature, and ITS RCS Section.
Flow DNB Limits Flow DNB Limits 3/4.1.1.4 Minimum 3.4.2 Minimum 3.4.2 Minimum CTS LCO moved into Temperature for Temperature for Temperature for ITS RCS Section.
Criticality Criticality Criticality 3/4.4.10.1 RCS 3.4.3 RCS Pressure 3.4.3 RCS Pressure Pressure / Temperature and Temperature and Temperature Limits Limits Limits 3/4.4.1.1 RCS Loops 3.4.4 RCS Loops -
3.4.4 RCS Loops -
Startup and Power Modes I and 2 Modes I and 2
(]
(]
V Operation 3/4.4.1.2 RCS - Hot         3.4.5 RCS Loops -         3.4.5 RCS Loops -
Operation V
Standby                     Mode 3                     Mode 3 3/4.4.1.3 RCS - Hot         3.4.6 RCS Loops -         3.4.6 RCS Loops -
3/4.4.1.2 RCS - Hot 3.4.5 RCS Loops -
Shutdown                     Mode 4                     Mode 4 3/4.4.1.4 RCS - Cold         3.4.7 RCS Loops -         3.4.7 RCS Loops -         CTS LCO split into               j Shutdown                     Mode 5, Loops filled.     Mode 5, Loops filled.     two ITS LCOs.                     l i
3.4.5 RCS Loops -
3.4.8 RCS Loops -         3.4.8 RCS Loops -
Standby Mode 3 Mode 3 3/4.4.1.3 RCS - Hot 3.4.6 RCS Loops -
Mode 5, Loops Not         Mode 5, Loops Not                                           i Filled                     Filled 3/4.4.2 Safety Valves-       NA                         NA                         Relocated.
3.4.6 RCS Loops -
Shutdown 3/4.4.3 Safety Valves       3.4.10 Pressurizer         3.4.10 Pressurizer
Shutdown Mode 4 Mode 4 3/4.4.1.4 RCS - Cold 3.4.7 RCS Loops -
                - Operating                 Safety Valves             Safety Valves 3/4.4.4 Pressurizer         3.4.9 Pressurizer         3.4.9 Pressurizer a
3.4.7 RCS Loops -
'j (1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
CTS LCO split into j
Shutdown Mode 5, Loops filled.
Mode 5, Loops filled.
two ITS LCOs.
i 3.4.8 RCS Loops -
3.4.8 RCS Loops -
Mode 5, Loops Not Mode 5, Loops Not Filled Filled 3/4.4.2 Safety Valves-NA NA Relocated.
Shutdown 3/4.4.3 Safety Valves 3.4.10 Pressurizer 3.4.10 Pressurizer
- Operating Safety Valves Safety Valves 3/4.4.4 Pressurizer 3.4.9 Pressurizer 3.4.9 Pressurizer a
'j (1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
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  .                                                                                                    Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications         Specifications (STS)
Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP ITS)                                                   (1) 3/4.4.5 Relief Valves       3.4.11 Pressurizer         3.4.11 Pressurizer Power Operated Relief     Power Operated Rclief Valves                     Valves 3/4.4.6 Steam               NA                         NA                         CTS LCO and Generators                                                                         Actions removed and surveillance requirements retained in ITS Section 5.0 as a program.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
3/4.4.7.1 RCS               3.4.15 RCS Leakage         3.4.15 RCS Leakage Leakage Detection           Detection                 Detection Systems                     Instrumentation           Instrumentation 3/4.4.7.2 Operational       3.4.13 Operational         3.4.13 Operational         CTS LCO split into Leakage                     Leakage                   Leakage                   two ITS LCOs.
(FNP ITS)
3.4.14 RCS Pressure       3.4.14 RCS Pressure '
(1) 3/4.4.5 Relief Valves 3.4.11 Pressurizer 3.4.11 Pressurizer Power Operated Relief Power Operated Rclief Valves Valves 3/4.4.6 Steam NA NA CTS LCO and Generators Actions removed and surveillance requirements retained in ITS Section 5.0 as a program.
isolation Valve           Isolation Valve Leakage                   Leakage 3/4.4.10.3                   3.4.12 Low                 3.4.12 Low Overpressure                 Temperature               Temperature Protection Systems           Overpressure               Overpressure Pro'.ection (LTOP)         Protection (LTOP)
3/4.4.7.1 RCS 3.4.15 RCS Leakage 3.4.15 RCS Leakage Leakage Detection Detection Detection Systems Instrumentation Instrumentation 3/4.4.7.2 Operational 3.4.13 Operational 3.4.13 Operational CTS LCO split into Leakage Leakage Leakage two ITS LCOs.
System                     System 3/4,4.8 Chemist.y           NA                         NA                         Relocated.
3.4.14 RCS Pressure 3.4.14 RCS Pressure '
3/4.4.9 Specific             3.4.16 RCS Specific       3.4.16 RCS Specific Activity                     Activity                   Activity 3/4.10.2 Pressurizer         NA                         NA                         Relocated.
isolation Valve Isolation Valve Leakage Leakage 3/4.4.10.3 3.4.12 Low 3.4.12 Low Overpressure Temperature Temperature Protection Systems Overpressure Overpressure Pro'.ection (LTOP)
Protection (LTOP)
System System 3/4,4.8 Chemist.y NA NA Relocated.
3/4.4.9 Specific 3.4.16 RCS Specific 3.4.16 RCS Specific Activity Activity Activity 3/4.10.2 Pressurizer NA NA Relocated.
P/r Limits
P/r Limits
/~'%
/~'%
Line 295: Line 370:
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Farley Nuclear Plant
Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREC-1431, Rev 1 Specifications (CTS)
          ..                                                                                                    ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREC-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications         Specifications (STS)
Improved Technical Standard Technical Notes Specifications Specifications (STS)
(FNP ITS)                                                   (1) 3/4.4.11 RCS                 NA                         NA                         Addressed by existing Structural Integrity                                                               Inservice Test and Inspection Programs and new program added to ITS 5.0 to cover specific surveillances of this LCO.
(FNP ITS)
NA                           NA                         3.4.17 RCS Loop             Not installed at FNP.
(1) 3/4.4.11 RCS NA NA Addressed by existing Structural Integrity Inservice Test and Inspection Programs and new program added to ITS 5.0 to cover specific surveillances of this LCO.
NA NA 3.4.17 RCS Loop Not installed at FNP.
Isolation Valves
Isolation Valves
                                                                                                    ~
~
NA                           NA                         3.4.18 RCS isolated         No Loop isolation Loop Startup               valves at FNP.
NA NA 3.4.18 RCS isolated No Loop isolation Loop Startup valves at FNP.
3/4.10.4 RCS Loops           NA                         3.4.19 RCS Loops -         No longer used at Test Exception                                         Test Exception             FNP and deleted in FNPITS.
3/4.10.4 RCS Loops NA 3.4.19 RCS Loops -
3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3/4.5.1 Accumulators         3.5.1 Accumulators         3.5.1 Accumulators 3/4.5.2 ECCS                 3.5.2 ECCS -               3.5.2 ECCS -
No longer used at Test Exception Test Exception FNP and deleted in FNPITS.
Subsystems - Tavg 2         Operating                 Operating 350*F 3/4.5.2 ECCS                 3.5.3 ECCS -               3.5.3 ECCS -
3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3/4.5.1 Accumulators 3.5.1 Accumulators 3.5.1 Accumulators 3/4.5.2 ECCS 3.5.2 ECCS -
Subsystems - Tavg <         Shutdown                   Shutdown 350 F 3/4.5.5 RWST                 3.5.4 RWST                 3.5.4 RWST NA                           3.5.5 Seal injection       3.5.5 Seal injection       New LCO containing Flow                       Flow                       CTS requirements from RCS Operational Leakage.
3.5.2 ECCS -
O         (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS marl,up for more detailed information.
Subsystems - Tavg 2 Operating Operating 350*F 3/4.5.2 ECCS 3.5.3 ECCS -
3.5.3 ECCS -
Subsystems - Tavg <
Shutdown Shutdown 350 F 3/4.5.5 RWST 3.5.4 RWST 3.5.4 RWST NA 3.5.5 Seal injection 3.5.5 Seal injection New LCO containing Flow Flow CTS requirements from RCS Operational Leakage.
O (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS marl,up for more detailed information.
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  ..                                                                                                    Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion
Farley Nuclear Plant ITS conversion Submittal
(
(
Current Technical               FNP Specific         NUREG-1431 Rev 1 Specifications (CTS)       Improved Technical         Standard Technical                 Notes Specifications       Specifications (STS)
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431 Rev 1 Specifications (CTS)
(FNP ITS)                                                 (1) 3/4.5.6 ECCS                 3.5.6 ECCS                 NA                         FNP specific LCO for Recirculation Fluid           Recirculation Fluid                                 TSP in containment pil Control System           pl-1 Comrol System                                   instead of spray add tank system. This LCO is not part of the STS.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
3.6 CONTAINMENT SYSTEMS 3/4.6.1.1 Containment       3.6.1 Contaimnent         3.6.1 Containment integrity 3/4.6.1.2 Containment       NA                         NA                         Rese CTS leakage                                                                           requirements incorporated into other LCOs, programs, or removed from the TS.
(FNP ITS)
3/4.6.1.3 Cmtairunent       3.6.2 Containment Air     3.6.2 Containment Air Air Lecks                   Locks                     Locks i
(1) 3/4.5.6 ECCS 3.5.6 ECCS NA FNP specific LCO for Recirculation Fluid Recirculation Fluid TSP in containment pil Control System pl-1 Comrol System instead of spray add tank system. This LCO is not part of the STS.
3/4.6.1.4 Internal           3.6.4 Containment         3.6.4A Containment Pressure                     Pressure                   Pressure (Atmospheric, Dual, and Ice Condenser)                                         j NA                           NA                         3.6.4B Containment         Not part of the FNP Pressure                   design.
3.6 CONTAINMENT SYSTEMS 3/4.6.1.1 Containment 3.6.1 Contaimnent 3.6.1 Containment integrity 3/4.6.1.2 Containment NA NA Rese CTS leakage requirements incorporated into other LCOs, programs, or removed from the TS.
(Subatmospheric) 3/4.6.1.5 Air               3.6.5 Containment Air     3.6.5 A Containment Temperature                 Temperature               Air Temperature (Atmospheric and Dual)
3/4.6.1.3 Cmtairunent 3.6.2 Containment Air 3.6.2 Containment Air Air Lecks Locks Locks i
NA                           NA                         3.6.5B Containment         Not part of the FNP Air Temperature (Ice       design.
3/4.6.1.4 Internal 3.6.4 Containment 3.6.4A Containment Pressure Pressure Pressure (Atmospheric, Dual, and Ice Condenser) j NA NA 3.6.4B Containment Not part of the FNP Pressure design.
(Subatmospheric) 3/4.6.1.5 Air 3.6.5 Containment Air 3.6.5 A Containment Temperature Temperature Air Temperature (Atmospheric and Dual)
NA NA 3.6.5B Containment Not part of the FNP Air Temperature (Ice design.
Condenser)
Condenser)
~O                                                                                                                                 :
~O V
V                                                                                                                                 !
(I) Sec the applicable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed infonnation.
(I) Sec the applicable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed infonnation.
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s
s Farley Nuci:ar Plant ITS conversion Submittal
..                                                                                                  Farley Nuci:ar Plant ITS conversion Submittal
[J An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
[J An Overview of the Disposition of LCO's in the FNP ITS Conversion NUREG-1431, Rev 1 Current Technical              FNP Specific Specifications (CTS)       Improved Technical         Ltandard Technical                 Notes Specifications         Specifications (STS)
Improved Technical Ltandard Technical Notes Specifications Specifications (STS)
(FNP ITS)                                                 (1)
(FNP ITS)
NA                         NA                         3.6.5C Containment         Not part of the FNP             ]'
(1)
Air Temperature             design.
NA NA 3.6.5C Containment Not part of the FNP
(Subatmospheric) 3/4.6.1.6 Containment     NA                         NA                         Removed from the TS.
]
Structural Integrity                                                             Tendon surveillances retained in section 5.0 program.
Air Temperature design.
3/4.6.1.7 Containtnent     3.6.3 Containment         3.6.3 Containment           All containment Ventilation System         Isolation Valves           isolation Valves           isolation valve (Purge and Exhaust                                                                 requirements are Isolation Valves)                                                               addressed in one LCO.
(Subatmospheric) 3/4.6.1.6 Containment NA NA Removed from the TS.
3/4.6.3 Containment                                                                                                 l Isolation Valves                                                                                                   l G
Structural Integrity Tendon surveillances retained in section 5.0 program.
3/4 6 2.1 Contamment       3.6.6 Contamment           3.6.6A Containment         Two CTS LCOs are Spray System               Spray and Cooling         Spray and Cooling         combinei into one ITS System                     System (Atmospheric         LCO.
3/4.6.1.7 Containtnent 3.6.3 Containment 3.6.3 Containment All containment Ventilation System Isolation Valves isolation Valves isolation valve (Purge and Exhaust requirements are Isolation Valves) addressed in one LCO.
3/4.6.2.3 Containment                                 and Dual) (Credit Cooling System                                         Taken for lodine Removal by the Spray System)
3/4.6.3 Containment l
NA                         NA                         3.6.6B Containment         Not consistent with Spray and Cooling         appheable FNP System (Atmospheric       analysis (FNP credits and Dual)(Credit not       iodine removal by the Taken for lodine           Spray System).
Isolation Valves G
Removal by the Spray                                         .
3/4 6 2.1 Contamment 3.6.6 Contamment 3.6.6A Containment Two CTS LCOs are Spray System Spray and Cooling Spray and Cooling combinei into one ITS System System (Atmospheric LCO.
System)                                                      )
3/4.6.2.3 Containment and Dual) (Credit Cooling System Taken for lodine Removal by the Spray System)
NA                         NA                         3.6.6C Containment         Not part of the FNP Spray System (Ice         design.                           !
NA NA 3.6.6B Containment Not consistent with Spray and Cooling appheable FNP System (Atmospheric analysis (FNP credits and Dual)(Credit not iodine removal by the Taken for lodine Spray System).
Removal by the Spray System)
NA NA 3.6.6C Containment Not part of the FNP Spray System (Ice design.
Condenser)
Condenser)
NA                         NA                         3.6.6D Quench Spray       Not part of the FNP               l System                     design.
NA NA 3.6.6D Quench Spray Not part of the FNP System design.
p                                                                 (Subatmospheric)                                             ;
p (Subatmospheric)
Y)
Y)
(1) See the apphcable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed mformation.
(1) See the apphcable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed mformation.
l A2-Il i
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Farley Nuclear Plant ITS conversion Subnittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific           NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                 Notes Specifications         Specifications (STS)
Farley Nuclear Plant ITS conversion Subnittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP ITS)                                                   (1)
Improved Technical Standard Technical Notes Specifications Specifications (STS)
NA                           NA                         3.6.6E Recirculation       Not part of the FNP Spray System               design.
(FNP ITS)
(1)
NA NA 3.6.6E Recirculation Not part of the FNP Spray System design.
(Subatmospheric)
(Subatmospheric)
NA                           NA                         3.i7 Spray Additive       This system recently System                     removed from FNP and replaced with TSP inside containment (see CTS 3/4.5.6).
NA NA 3.i7 Spray Additive This system recently System removed from FNP and replaced with TSP inside containment (see CTS 3/4.5.6).
3/4.6.4 liydrogen           3.3.3 Post Accident         3.3.3 Post Accident       The requirements of Analyzers                   Monitoring                 Monitoring                 this LCO are moved
3/4.6.4 liydrogen 3.3.3 Post Accident 3.3.3 Post Accident The requirements of Analyzers Monitoring Monitoring this LCO are moved Instrumentation Instrumentation into the Post Accident Monitoring LCO consistent with the purpose of the p
"                                                                                                    into the Post Accident
instrumentation.
          ,                                  Instrumentation            Instrumentation
V 3/4.6.4.2 Electric 3.6.7 liydrogen 3.6.8 Hydrogen liydrogen Recombiners Recombiners Recombiners 3/4.6.4.411ydrogen 3.6.8 liydrogen 3.6.9 Hydrogen Maing System Mixing System Mixing System 3/4.6.4.3 Reactor 3.6.9 Reactor Cavity NA FhP specific system Cavity Hydrogen liydrogen Dilution and TS.
            !                                                                                        Monitoring LCO consistent with the purpose of the p                                                                                                   instrumentation.
Dilution System System NA NA 3.6.10 Hydrogen Not part of the FNP Ignition System (Ice design.
V               3/4.6.4.2 Electric           3.6.7 liydrogen             3.6.8 Hydrogen liydrogen                   Recombiners                 Recombiners Recombiners 3/4.6.4.411ydrogen           3.6.8 liydrogen             3.6.9 Hydrogen Maing System                 Mixing System               Mixing System 3/4.6.4.3 Reactor           3.6.9 Reactor Cavity       NA                         FhP specific system Cavity Hydrogen             liydrogen Dilution                                     and TS.
Dilution System             System NA                           NA                         3.6.10 Hydrogen           Not part of the FNP Ignition System (Ice       design.
Condenser)
Condenser)
NA                           NA                         3.6.1 I lodine Cleanup     Not part of the FNP System (Atmospheric       design.
NA NA 3.6.1 I lodine Cleanup Not part of the FNP System (Atmospheric design.
and Subatmospheric)
and Subatmospheric)
NA                           NA                         3.6.12 Vacuum Relief     Not part of the FNP Valves (Atmospheric       design, and Ice Condenser)
NA NA 3.6.12 Vacuum Relief Not part of the FNP Valves (Atmospheric
: design, and Ice Condenser)
(s.
(s.
(1) See the applicable Enclosure I (.TS markup or Enclosure 4 STS markup for more detailed information.
(1) See the applicable Enclosure I (.TS markup or Enclosure 4 STS markup for more detailed information.
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4
4 Farley Nuclear Plant ITS conversion Submittal 2
          -                                                                                                Farley Nuclear Plant ITS conversion Submittal 2
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific           NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                 Notes Specifications         Specifications (STS)
Improved Technical Standard Technical Notes Specifications Specifications (STS)
(FNP ITS)                                                   (1)
(FNP ITS)
NA                           NA                         3.6.13 Shield Building     Not pan of the FNP Air Cleanup System         design.                         j (Dual and Ice                                               l Condenser)
(1)
NA                           NA                         3.6.14 Air Return         Not part of the FNP System (Ice               design.
NA NA 3.6.13 Shield Building Not pan of the FNP Air Cleanup System design.
Condenser)                                                 I NA                           NA                         3.6.15 lee Bed (Ice       Not part of the FNP Condenser)               design.
j (Dual and Ice l
NA                           NA                         3.6.16 Ice Condenser     Not part of the FNP Doors (Ice Condenser)     design.                           1 NA                           NA                         3.6.17 Divider Barrier   Not part of the FNP               ,
Condenser)
O                                                                Integrity (Ice           design.                           {
NA NA 3.6.14 Air Return Not part of the FNP System (Ice design.
D                                                                 Condenser)
Condenser)
NA                           NA                         3.6.18 Containment       Not part of the FNP Recirculation Drains     design.
I NA NA 3.6.15 lee Bed (Ice Not part of the FNP Condenser) design.
NA NA 3.6.16 Ice Condenser Not part of the FNP Doors (Ice Condenser) design.
NA NA 3.6.17 Divider Barrier Not part of the FNP O
Integrity (Ice design.
{
D Condenser)
NA NA 3.6.18 Containment Not part of the FNP Recirculation Drains design.
(Ice Condenser)
(Ice Condenser)
NA                           NA                         3.6.19 Shield Building   Not part of the FNP (Dual and Ice             design.
NA NA 3.6.19 Shield Building Not part of the FNP (Dual and Ice design.
Condenser) 3.7 PLANT SYSTEMS 3/4 7.1.1 Turbine             3.7.1 Main Steam           3.7.1 Main Stexn Cycle Safety Valves           Safety Valves             Safety Valves 3/4.7.1.2 AFW                 3.7.5 AFW                 3.7.5 AFW 3/4.7.1.3 Condensate         3.7.6 Condensate         3.7.6 Condensate Storage Tank                 Storage Tank             Storage Tank 3/4.7.1.4 Activity           3.7.16 Secondary           3.7.18 Secondary Specific Activity         Specific Activity (1) See the applicabl: Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
Condenser) 3.7 PLANT SYSTEMS 3/4 7.1.1 Turbine 3.7.1 Main Steam 3.7.1 Main Stexn Cycle Safety Valves Safety Valves Safety Valves 3/4.7.1.2 AFW 3.7.5 AFW 3.7.5 AFW 3/4.7.1.3 Condensate 3.7.6 Condensate 3.7.6 Condensate Storage Tank Storage Tank Storage Tank 3/4.7.1.4 Activity 3.7.16 Secondary 3.7.18 Secondary Specific Activity Specific Activity (1) See the applicabl: Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
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Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                 Notes Specifications         Specifications (STS)
Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP ITS)                                                   (1) 3/4.7.1.5 Main Steam       3.7.2 Main Steam           3.7.2 Main Steam Line Isolation Valves       Isolation Valves           isolation Valves NA                         3.7.3 Main Feedwater       3.7.3 Main Feedwater       New LCO requirement Stop Valves and Main       Isolation Valves and       for FNP.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
Feedwater Regulation       Main Feedwater Valves and Associated     Regulation Valves and Bypass Valves             Associated Bypass Valves NA                           3.7.4 Atmospheric         3.7.4 Atmospheric         New LCO requirement ReliefValves               Dump Valves               for FNP.
(FNP ITS)
3/4.7.2 Steam               NA                         NA                         Relocated.
(1) 3/4.7.1.5 Main Steam 3.7.2 Main Steam 3.7.2 Main Steam Line Isolation Valves Isolation Valves isolation Valves NA 3.7.3 Main Feedwater 3.7.3 Main Feedwater New LCO requirement Stop Valves and Main Isolation Valves and for FNP.
Feedwater Regulation Main Feedwater Valves and Associated Regulation Valves and Bypass Valves Associated Bypass Valves NA 3.7.4 Atmospheric 3.7.4 Atmospheric New LCO requirement ReliefValves Dump Valves for FNP.
3/4.7.2 Steam NA NA Relocated.
Generator Pressurefremperature Limitation 4
Generator Pressurefremperature Limitation 4
3/4.7.3 Component           3.7.7 Component           3.7.7 Component Cooling Water               Cooling Water             Cooling Water 3/4.7.4 Service Water       3.7.8 Service Water       3.7.8 Service Water System                       System                     System 3/4.7.6.2 Ultimate           3.7.9 Ultimate Heat       3.7.9 Ultimate Heat Heat Sink - Pond             Sink                       Sink 3/4.7.7.1 Control           3.7.10 Control Room       3.7.10 Control Room Room Emergency               Emergency Filtration /     Emergency Filtration Filtration /                 Pressurization System     System (CREFS)
3/4.7.3 Component 3.7.7 Component 3.7.7 Component Cooling Water Cooling Water Cooling Water 3/4.7.4 Service Water 3.7.8 Service Water 3.7.8 Service Water System System System 3/4.7.6.2 Ultimate 3.7.9 Ultimate Heat 3.7.9 Ultimate Heat Heat Sink - Pond Sink Sink 3/4.7.7.1 Control 3.7.10 Control Room 3.7.10 Control Room Room Emergency Emergency Filtration /
Pressurization System       (CREFS)
Emergency Filtration Filtration /
(CREFS) 3/4.7.7.2 Control           3.7.11 Control Room       3.7.11 Control Room Room Air                     Air Conditioning           Emergency Air Conditioning System         System (CRACS)             Temperature Control (CRACS)                                                 System n
Pressurization System System (CREFS)
Pressurization System (CREFS)
(CREFS) 3/4.7.7.2 Control 3.7.11 Control Room 3.7.11 Control Room Room Air Air Conditioning Emergency Air Conditioning System System (CRACS)
Temperature Control (CRACS)
System n
(1) See the applicable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed information.
(1) See the applicable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed information.
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      -                                                                                                  Farley Nucle:r Plant ITS conversion Submittal f*h An Overview of the Disposition of LCO's in the FNP ITS Conversion
Farley Nucle:r Plant ITS conversion Submittal f*h
  ;;]
;;]
Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                 Notes Specifications         Specifications (STS)
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP ITS)                                                   (1)
Improved Technical Standard Technical Notes Specifications Specifications (STS)
NA                         NA                         3.7.12 ECCS Pump           STS LCO 3.7.13 more Room Exhaust Air           closely matches the Cleanup System             FNP design for this (PREACS)                   system.
(FNP ITS)
3/4.7.8 Penetration         3.7.12 Penetration         3.7.13 Fuel Building       STS LCO 3.7.13 Room Filtration             Room Filtration (PRF)     Air Cleanup System         addresses a system System                       System                     (FBACS)                   that performs two functions (penetration area / pump room cleanup (Modes 1-4) and fuel handling area cleanup during movement of irradiated fuel). This dual function system most closely matches k                                                                                             the FNP PRF system.
(1)
NA                           NA                         3.7.14 Penetration         STS LCO 3.7.13 more               !
NA NA 3.7.12 ECCS Pump STS LCO 3.7.13 more Room Exhaust Air closely matches the Cleanup System FNP design for this (PREACS) system.
Room Exhaust Air           closely matches the Cleanup System             FNP design for this (PREACS)                   system.                           l 3/4.7.9 Snubbers             NA                         NA                         Relocated.
3/4.7.8 Penetration 3.7.12 Penetration 3.7.13 Fuel Building STS LCO 3.7.13 Room Filtration Room Filtration (PRF)
I 3/4.7.10 Scaled             NA                         NA                         Relocated.
Air Cleanup System addresses a system System System (FBACS) that performs two functions (penetration area / pump room cleanup (Modes 1-4) and fuel handling area cleanup during movement of irradiated fuel). This dual function system most closely matches k
Source Contamination 3/4.7.13 Area               NA                         NA                         Relocated.
the FNP PRF system.
Temperature Monitoring (Unit 2 only) l !' p) .
NA NA 3.7.14 Penetration STS LCO 3.7.13 more Room Exhaust Air closely matches the Cleanup System FNP design for this (PREACS) system.
N s .-
3/4.7.9 Snubbers NA NA Relocated.
I 3/4.7.10 Scaled NA NA Relocated.
Source Contamination 3/4.7.13 Area NA NA Relocated.
Temperature Monitoring (Unit 2 only) l ' p).
!N s.-
(1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
(1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
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: c.                                                                                                   Farley Nuclear Plant ITS conversion Submittal ,
 
An Overview of the Disposition of LCO's in the FNP ITS Conversion l
c.
Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications       Specifications (STS)
Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP ITS)                                                   (1) 3/4.7.13 (Unit 1) Fuel     3.7.14 Fuel Storage       3.7.16 Fuel Storage         Unit I and 2 have Storage Pool Boron         Pool Boron                 Pool Boron                 ditTerent numbers due Concentration               Concentration             Concentration             to the additional Unit 2 CTS LCO 3/4.7.13 3/4.7.14 (Unit 2) Fuct                                                           for Area Temperature Storage Pool Boron                                                               Monitoring. The area Concentration                                                                     temperature monitoring LCO will not exist it. the FNP ITS.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
3/4.7.14 (Unit 1) Fuel     3.7.15 Spent Fuel         3.7.17 Spent Fuel         Unit I and 2 have Assembly Storage             Assembly Storage           Assembly Storage           difTerent numbers due to the additional Unit 3/4.7.15 (Unit 2) Fuel                                                             2 CTS LCO 3/4.7.13 Assembly Storage                                                                   for Area Temperature O                                                                                             Monitoring. The area d                                                                                             temperature monitoring LCO will not exist in the FNP ITS.
(FNP ITS)
3/4.9.11 Water Level         3.7.13 Fuel Storage       3.7.15 Fuel Storage       This CTS LCO moved Storage Pool                 Pool Water Level           Pool Water Level           from the Refueling Section of TS to the Plant System Section consistent with the STS.
(1) 3/4.7.13 (Unit 1) Fuel 3.7.14 Fuel Storage 3.7.16 Fuel Storage Unit I and 2 have Storage Pool Boron Pool Boron Pool Boron ditTerent numbers due Concentration Concentration Concentration to the additional Unit 2 CTS LCO 3/4.7.13 3/4.7.14 (Unit 2) Fuct for Area Temperature Storage Pool Boron Monitoring. The area Concentration temperature monitoring LCO will not exist it. the FNP ITS.
3.8 ELECTRICAL POWER SYSTEMS 3/4.8.1.1 AC Sources         3.8.1 AC Sources -         3.8.1 AC Sources
3/4.7.14 (Unit 1) Fuel 3.7.15 Spent Fuel 3.7.17 Spent Fuel Unit I and 2 have Assembly Storage Assembly Storage Assembly Storage difTerent numbers due to the additional Unit 3/4.7.15 (Unit 2) Fuel 2 CTS LCO 3/4.7.13 Assembly Storage for Area Temperature O
          - Operating                 Operating                 Operating 3/4.8.1.2 AC Sources         3.8.2 AC Sources -         3.8.2 AC Sources -
Monitoring. The area d
          - Shutdowr.                 Shutdown                   Shutdown I
temperature monitoring LCO will not exist in the FNP ITS.
G (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup lbr more detailed information.
3/4.9.11 Water Level 3.7.13 Fuel Storage 3.7.15 Fuel Storage This CTS LCO moved Storage Pool Pool Water Level Pool Water Level from the Refueling Section of TS to the Plant System Section consistent with the STS.
3.8 ELECTRICAL POWER SYSTEMS 3/4.8.1.1 AC Sources 3.8.1 AC Sources -
3.8.1 AC Sources
- Operating Operating Operating 3/4.8.1.2 AC Sources 3.8.2 AC Sources -
3.8.2 AC Sources -
- Shutdowr.
Shutdown Shutdown IG (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup lbr more detailed information.
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                    -                                                                                                                                                                                          Farley Nuclear Plant ITS conversion Submittal
Farley Nuclear Plant ITS conversion Submittal
' (G
' (G An Overview of the Disposition of LCO's in the FNP ITS Conversion
                      /                    An Overview of the Disposition of LCO's in the FNP ITS Conversion v                                                                                                                                                                                                                               .
/
Current Technical                                                                                                       FNP Specific           NUREG-1431, Rev 1 Specifications (CTS)                                                                         Improved Technical                                 Standard Technical             Notes Specifications             Specifications (STS)
v Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP ITS)                                       (1)
Improved Technical Standard Technical Notes Specifications Specifications (STS)
NA                                                                                       3.8.3 Diesel Fuel,                                       3.8.3 Diesel Fuel,     New LCO derived Lube Oil, and Starting                                   Lube Oil, and Starting from some existing TS Air                                                     Air                   requirements (3/4.8.1.1) and some new TS requirements             ,
(FNP ITS)
(lube oil and startmg           i l                                                                                                                                                                                                       air).                           l l                             3/4.8.2.1 AC                                                                             3.8.4 DC Sources -                                       3.8.4 DC Sources -     CTS LCOs are re-Distribution -                                                                           Operating                                               Operating             organized consistent Operating                                                                                                                                                               with the STS format 3.8.6 Battery Cell                                       3.8.6 Battery Cell     of these requirements.
(1)
3/4.8.2.3 Auxiliarv                                                                     Parameters                                               Parameters Building DC Distnbution -                                                                           3.8.7 inverters -                                         3.8.7 inverters -
NA 3.8.3 Diesel Fuel, 3.8.3 Diesel Fuel, New LCO derived Lube Oil, and Starting Lube Oil, and Starting from some existing TS Air Air requirements (3/4.8.1.1) and some new TS requirements (lube oil and startmg i
Operating                                                                               Operating                                                 Operating
l air).
      /
l l
l\
3/4.8.2.1 AC 3.8.4 DC Sources -
U                       Service Water                                                                           3.8.9 Distribution                                       3.8.9 Distribution Building DC                                                                             Systems - Operating                                       Systems - Operating Distribution -
3.8.4 DC Sources -
Operating 3/4.8.2.2 AC                                                                           3.8.5 DC Sources -                                       3.8.5 DC Sources -     CTS LCOs are re-Distribution -                                                                         Shutdown                                                 Shutdown               organized consistent Shutdown                                                                                                                                                                 with the STS format 3.8.8 Inverters -                                         3.8.8 Inverters -     of these requirements.
CTS LCOs are re-Distribution -
3/4.8.2.4 Auxiliary                                                                     Shutdown                                                 Shutdown Building DC Distribution -                                                                         3.8.10 Distribution                                       3.8.10 Distribution                                   ,
Operating Operating organized consistent Operating with the STS format 3.8.6 Battery Cell 3.8.6 Battery Cell of these requirements.
Shutdown                                                                               Systems - Shutdown                                       Systems - Shutdown                                     I t
3/4.8.2.3 Auxiliarv Parameters Parameters Building DC Distnbution -
3/4 8.3.1 Containment                                                                   NA                                                       NA                     Relocated.
3.8.7 inverters -
Penetration Conductor Overcurrent Protective Devices (Unit 2 only) 3/4.8.3.2 Motor                                                                         NA                                                       NA                     Relocated.
3.8.7 inverters -
Operating Operating Operating
/
l\\U Service Water 3.8.9 Distribution 3.8.9 Distribution Building DC Systems - Operating Systems - Operating Distribution -
Operating 3/4.8.2.2 AC 3.8.5 DC Sources -
3.8.5 DC Sources -
CTS LCOs are re-Distribution -
Shutdown Shutdown organized consistent Shutdown with the STS format 3.8.8 Inverters -
3.8.8 Inverters -
of these requirements.
3/4.8.2.4 Auxiliary Shutdown Shutdown Building DC Distribution -
3.8.10 Distribution 3.8.10 Distribution Shutdown Systems - Shutdown Systems - Shutdown I
3/4 8.3.1 Containment NA NA Relocated.
t Penetration Conductor Overcurrent Protective Devices (Unit 2 only) 3/4.8.3.2 Motor NA NA Relocated.
Operated Valves Thennal Overload
Operated Valves Thennal Overload
      ,o                       Protection Devices (v)                       (Unit 2 only)
,o Protection Devices (v)
(Unit 2 only)
(1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed information.
(1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed information.
A2 17
A2 17


        ..                                                                                                  Farley Nuclear Plant ITS conversion Submittal l
Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion l
An Overview of the Disposition of LCO's in the FNP ITS Conversion lV Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)       Improved Technical         Standard Technical                   Notes                   ,
lV Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
Specifications         Specifications (STS)                                         l l                                                   (FNP ITS)                                                   (1) 3.9 REFUELING OPERATIONS 3/4.9.1 Boron               3.9.1 Boron               3.9.1 Boron Concentration               Concentration             Concentration NA                         NA                         3.9.2 Unborated           This STS LCO is not Water Source               consistent with the Isolation Valves           FNP refueling Boron dilution analysis.
Improved Technical Standard Technical Notes Specifications Specifications (STS) l l
3/4.9.2                     3.9.2 Nuclear             3.9.3 Nuclear l               Instrumentation             Instrumentation           Instrumentation 3/4.9.3 Decay Time         NA                         NA                         Relocated 3/4.9.4 Containment         3.9.3 Containment         3.9.4 Containment         The CTS LCOs are Building Penetrations       Penetrations               Penetrations               combined into one
(FNP ITS)
,                                                                                                  Containment
(1) 3.9 REFUELING OPERATIONS 3/4.9.1 Boron 3.9.1 Boron 3.9.1 Boron Concentration Concentration Concentration NA NA 3.9.2 Unborated This STS LCO is not Water Source consistent with the Isolation Valves FNP refueling Boron dilution analysis.
,                3/4.9.9 Containment                                                               Penetration LCO l
3/4.9.2 3.9.2 Nuclear 3.9.3 Nuclear l
Purge and Exhaust                                                                 consistent with the isolation System                                                                   STS.
Instrumentation Instrumentation Instrumentation 3/4.9.3 Decay Time NA NA Relocated 3/4.9.4 Containment 3.9.3 Containment 3.9.4 Containment The CTS LCOs are Building Penetrations Penetrations Penetrations combined into one Containment 3/4.9.9 Containment Penetration LCO l
3/4.9.5                     NA                         NA                         Relocated.
Purge and Exhaust consistent with the isolation System STS.
Communications 3/4.9.6 Manipulator         NA                         NA                         Relocated.
3/4.9.5 NA NA Relocated.
Crane 3/4.9.7.1 Crane Travel     NA                         NA                         Relocated.
Communications 3/4.9.6 Manipulator NA NA Relocated.
                - Spent Fuel Storage Pool Building Bridge Crane 3/4.9.7.1 Crane Travel     NA                         NA                         Relocated.
Crane 3/4.9.7.1 Crane Travel NA NA Relocated.
                - Spent Fuel Storage Pool Spent Fuel Cask Crane 3/4.9.8.I RHR and           3.9.4 RHR and             3.9.5 RHR and Coolant Circulatien         Coolant Circulation -     Coolant Circulation -
- Spent Fuel Storage Pool Building Bridge Crane 3/4.9.7.1 Crane Travel NA NA Relocated.
All Water Levels.           High Water Level           High Water Level
- Spent Fuel Storage Pool Spent Fuel Cask Crane 3/4.9.8.I RHR and 3.9.4 RHR and 3.9.5 RHR and Coolant Circulatien Coolant Circulation -
(/n) w (1) See the apphcable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
Coolant Circulation -
(/n)
All Water Levels.
High Water Level High Water Level w
(1) See the apphcable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
A2-18
A2-18
                                                                                                                                    ?
?


            ..                                                                                                Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical       Standard Technical                   Notes Specifications         Specifications (STS)
Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP ITS)                                                 (1) 3/4.9.8.2 RHR - Low         3.9.5 RHR and             3.9.6 RHR and Water Level                 Coolant Circulation -     Coolant Circulation -
Improved Technical Standard Technical Notes Specifications Specifications (STS)
Low Water Level           Low Water Level 3/4.9.10.1 Water             3.9.6 Refueling Cavity     3.9.7 Refueling Cavity     CTS LCOs combined Level Reactor Vessel         Water Level               Water Level               into one LCO Fuel Assemblies                                                                   consistent with the STS.
(FNP ITS)
3/4.9.10.2 Water Level Reactor Vessel Control Rods 3/4.9.1 i Water Level -     3.7.13 Fuel Storage       3.7.15 Fuel Storage       This CTS LCO moved Storage Pool                 Pool Water Level           Pool Water Level           to Plant Systems Section consistent with O                                                                                             the STS.
(1) 3/4.9.8.2 RHR - Low 3.9.5 RHR and 3.9.6 RHR and Water Level Coolant Circulation -
3/4.9.12 Storage Pool       NA                         NA                         Relocated.
Coolant Circulation -
Ventilation (Fuel Storage) 3/4.9.13 Storage Pool       3.7.12 Penetration         3.7.13 Fuel Building     his CTS LCO moved Ventilation (Fuel           Room Filtration (PRF)     Air Cleanup System         to the Plant Systems Movement)                   System                     (FBACS)                   Section and combined with the Mode 1-4 LCO for the PRF system consistent with the closest corresponding STS LCO 3.7.13 FBACS.
Low Water Level Low Water Level 3/4.9.10.1 Water 3.9.6 Refueling Cavity 3.9.7 Refueling Cavity CTS LCOs combined Level Reactor Vessel Water Level Water Level into one LCO Fuel Assemblies consistent with the STS.
O       (1) See the applicable Enclosure ! CTS markup or Enclosure 4 STS markup for more detailed infonnation.
3/4.9.10.2 Water Level Reactor Vessel Control Rods 3/4.9.1 i Water Level -
3.7.13 Fuel Storage 3.7.15 Fuel Storage This CTS LCO moved Storage Pool Pool Water Level Pool Water Level to Plant Systems Section consistent with O
the STS.
3/4.9.12 Storage Pool NA NA Relocated.
Ventilation (Fuel Storage) 3/4.9.13 Storage Pool 3.7.12 Penetration 3.7.13 Fuel Building his CTS LCO moved Ventilation (Fuel Room Filtration (PRF)
Air Cleanup System to the Plant Systems Movement)
System (FBACS)
Section and combined with the Mode 1-4 LCO for the PRF system consistent with the closest corresponding STS LCO 3.7.13 FBACS.
O (1) See the applicable Enclosure ! CTS markup or Enclosure 4 STS markup for more detailed infonnation.
A2-19
A2-19


  ..                                                                                                    Farley Nuclear Plant ITS conversion Submittal
Farley Nuclear Plant ITS conversion Submittal
(                         An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                 Notes Sp ecifications       Specifications (STS)
(
(FNP ITS)                                                   (1)
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
CTS 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 Shutdown           NA                         NA                         This CTS LCO is Margin                                                                             deleted consistent with TSTF changes to the STS.
Improved Technical Standard Technical Notes Sp ecifications Specifications (STS)
3/4.10.2 Group               NA                         NA                         This CTS LCO is lleight, lasertion and                                                             deleted consistent with Po;<er Distribution                                                               TSTF changes to the Limits                                                                             STS.
(FNP ITS)
3/4.10.3 Physics             3.1.8 Physics Tests       3.1.10 Physics Tests       This CTS LCO is Tests                       Exceptions - Mode 2       Exceptions - Mode 2       moved to the reactivity control section of the TS consistent with the STS.
(1)
s 3/4.10.4 Reactor             NA                         3.4.19 RCS Loops           This CTS test Coolant Loops.                                         Test Exception             exception is no longer used at FNP and has been eliminated from the FNP ITS.
CTS 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 Shutdown NA NA This CTS LCO is Margin deleted consistent with TSTF changes to the STS.
3/4.10.5 Position           NA                         NA                         Relocated.
3/4.10.2 Group NA NA This CTS LCO is lleight, lasertion and deleted consistent with Po;<er Distribution TSTF changes to the Limits STS.
3/4.10.3 Physics 3.1.8 Physics Tests 3.1.10 Physics Tests This CTS LCO is Tests Exceptions - Mode 2 Exceptions - Mode 2 moved to the reactivity control section of the TS consistent with the STS.
s 3/4.10.4 Reactor NA 3.4.19 RCS Loops This CTS test Coolant Loops.
Test Exception exception is no longer used at FNP and has been eliminated from the FNP ITS.
3/4.10.5 Position NA NA Relocated.
Indicating System -
Indicating System -
Shutdown (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed infonnation.
Shutdown (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed infonnation.
A2-20
A2-20


  ..                                                                                              Farley Nuclear Plant ITS conversion Submittal
Farley Nuclear Plant ITS conversion Submittal
'O                   An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications       Specifications (STS)
'O An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
(FNP ITS)                                                   (1)
Improved Technical Standard Technical Notes Specifications Specifications (STS)
CTS 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.4 Liquid           NA                         NA                         'Ihis LCO retained in Holdup Tanks                                                                       part within the Explosive Gas and I
(FNP ITS)
(1)
CTS 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.4 Liquid NA NA
'Ihis LCO retained in Holdup Tanks part within the Explosive Gas and I
Storage Tank Radioactivity Monitoring Program in Section 5.0 of the FNP ITS. Other elements of the program will b':
Storage Tank Radioactivity Monitoring Program in Section 5.0 of the FNP ITS. Other elements of the program will b':
placed in the TRM.
placed in the TRM.
3/4.11.2.5 Waste Gas         NA                         NA                         This LCO retained in             !
3/4.11.2.5 Waste Gas NA NA This LCO retained in I
I Monitoring                                                                         part within the
Monitoring part within the
/7                                                                                         Explosive Gas and V                                                                                         Storage Tank Radioactivity Monitoring Program in Section 5.0 of the FNP ITS. Other elements of the program will be placed in the TRM.
/7 Explosive Gas and V
3/4.11.2.6 Gas               NA                         NA                         This LCO retained in Storage Tanks                                                                     part within the Explosive Gas and Storage Tank Radioactivity Monitoring Program in Section 5.0 of the FNP ITS. Other elements of the program will be placed in the TRM CT V
Storage Tank Radioactivity Monitoring Program in Section 5.0 of the FNP ITS. Other elements of the program will be placed in the TRM.
3/4.11.2.6 Gas NA NA This LCO retained in Storage Tanks part within the Explosive Gas and Storage Tank Radioactivity Monitoring Program in Section 5.0 of the FNP ITS. Other elements of the program will be placed in the TRM CT V
(1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed information.
(1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed information.
A2 21
A2 21


    ..                                                                                                    Farley Nuclear Plant ITS conversion Submittal
Farley Nuclear Plant ITS conversion Submittal
  /^                         An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev i Specifications (CTS)       Improved Technical         Standard Technical                   Notes Specifications         Specifications (STS)
/^
(FNP ITS)                                                   (1)
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev i Specifications (CTS)
CTS 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING No LCOs are                 NA                         NA                         All CTS LCOs in this contained in this CTS                                                             section were deleted section.                                                                           by presious amendments. The ITS conversion deletes the remaining blank pages in this section.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
4.0 DESIGN FEATURES 5.1 Site                   4.1 Site Location         4.1 Site Location         Text description only.
(FNP ITS)
5.1.1 Exclusion Area       NA                         NA                         Figure removed from the TS.
(1)
C\
CTS 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING No LCOs are NA NA All CTS LCOs in this contained in this CTS section were deleted section.
V             5.1.2 Low Population         NA                         NA                         Figure removed from Zone                                                                               the TS.
by presious amendments. The ITS conversion deletes the remaining blank pages in this section.
5.1.3 Site Boundary         NA                         NA                         Figure removed from for Gaseous Emuents                                                               the TS.
4.0 DESIGN FEATURES 5.1 Site 4.1 Site Location 4.1 Site Location Text description only.
5.1.4 Site Boundary         NA                         NA                         Figure removed from for Liquid Emuents                                                                 the TS, 5.2 Containment             NA                         NA                         Section removed from the TS.
5.1.1 Exclusion Area NA NA Figure removed from the TS.
5.3 Reactor Core             4.2 Reactor Core           4.2 Reactor Core 5.3.1 Fuel Assemblies       4.2.1 Fuel Assemblies     4.2.1 Fuel Assemblies 5.3.2 Control Rod           4.2.2 Control Rod         4.2.2 Control Rod Assemblies                   Assemblies                 Assemblies 5.4 RCS                     NA                         NA                         Section removed from the TS.
C\\
5.5 Meteorological           NA                         NA                         Section removed from
V 5.1.2 Low Population NA NA Figure removed from Zone the TS.
.I             Tower Location                                                                     the TS.
5.1.3 Site Boundary NA NA Figure removed from for Gaseous Emuents the TS.
5.1.4 Site Boundary NA NA Figure removed from for Liquid Emuents the TS, 5.2 Containment NA NA Section removed from the TS.
5.3 Reactor Core 4.2 Reactor Core 4.2 Reactor Core 5.3.1 Fuel Assemblies 4.2.1 Fuel Assemblies 4.2.1 Fuel Assemblies 5.3.2 Control Rod 4.2.2 Control Rod 4.2.2 Control Rod Assemblies Assemblies Assemblies 5.4 RCS NA NA Section removed from the TS.
5.5 Meteorological NA NA Section removed from
.I Tower Location the TS.
A (1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
A (1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
A2-22
A2-22


      -*                                                                                                      Fuley Nuclear Plant ITS conversion Submittal (O
Fuley Nuclear Plant ITS conversion Submittal (O
  %/
An Overview of the Disposition of LCO's in the FNP ITS Conversion
          )                        An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev i Specifications (CTS)         Improved Technical         Standard Technical                 Notes Specifications         Specifications (STS)
)
(FNP ITS)                                                   (1) 5.6 Fuel Storage           4.3 Fuel Storage           4.3 Fuel Storage 5.6.1 Criticality           4.3.1 Criticality         4.3.1 Criticality 5.6.2 Drainage             4.3.2 Drainage             4.3.2 Drainage 5.6.3 Capacity             4.3.3 Capacity             4.3.3 Capacity 5.7 Component Cyclic       NA                         NA                         Moved to or Transient Limit                                                                 Administrative Controls Section as a program.
%/
5.0 ADMINISTRATIVE CONTROLS 6.1 Responsibility           5.1 Responsibility         5.1 Responsibility
Current Technical FNP Specific NUREG-1431, Rev i Specifications (CTS)
  /
Improved Technical Standard Technical Notes Specifications Specifications (STS)
(/               6.2 Organization             5.2 Organization           5.2 Organization 6.2.1 Offsite and           5.2.1 Onsite and           5.2.1 Onsite and Onsite Organization         Offsite Organization       Offsite Organization 6.2.2 Facility Staff         5.2.2 Unit Staff           5.2.2 Unit Staff 6.2.3 Safety Audit and       NA                         NA                         Moved out ofTS into Engineering Review                                                                 QA Program.
(FNP ITS)
Group 6.2.4 Shift Technical       5.2.2.g                   5.2.2.g                   Moved to an untitled Advisor                                                                           paragraph under Unit Staff.
(1) 5.6 Fuel Storage 4.3 Fuel Storage 4.3 Fuel Storage 5.6.1 Criticality 4.3.1 Criticality 4.3.1 Criticality 5.6.2 Drainage 4.3.2 Drainage 4.3.2 Drainage 5.6.3 Capacity 4.3.3 Capacity 4.3.3 Capacity 5.7 Component Cyclic NA NA Moved to or Transient Limit Administrative Controls Section as a program.
6.3 Facility Staff           5 3 Unit Staff             5.3 Unit StafT Qualifications               Qualifications             Qualifications 6.4 Training                 NA                         NA                         Removed from the TS and contained in the FSAR.
5.0 ADMINISTRATIVE CONTROLS 6.1 Responsibility 5.1 Responsibility 5.1 Responsibility
  /%.\
/
(/
6.2 Organization 5.2 Organization 5.2 Organization 6.2.1 Offsite and 5.2.1 Onsite and 5.2.1 Onsite and Onsite Organization Offsite Organization Offsite Organization 6.2.2 Facility Staff 5.2.2 Unit Staff 5.2.2 Unit Staff 6.2.3 Safety Audit and NA NA Moved out ofTS into Engineering Review QA Program.
Group 6.2.4 Shift Technical 5.2.2.g 5.2.2.g Moved to an untitled Advisor paragraph under Unit Staff.
6.3 Facility Staff 5 3 Unit Staff 5.3 Unit StafT Qualifications Qualifications Qualifications 6.4 Training NA NA Removed from the TS and contained in the FSAR.
/%.
ll
ll
() .
\\
().
(1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed infonnation.
(1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed infonnation.
A2-23
A2-23


  ,.                                                                                                    Farley Nuc! car Plant ITS conversion Submittal O                             An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical             FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)       Improved Technical         Standard Technical                   Notes Specifications         Specifications (STS)
Farley Nuc! car Plant ITS conversion Submittal O
(FNP ITS)                                                 (1) 6.5 Review and Audit       NA                         NA                         Removed from the TS and placed in the QA Program.
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
6.6 Reportable Event       NA                         NA                         Removed from the TS.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
Action 6.7 Safety Limit           NA                         NA                         Removed from the TS.
(FNP ITS)
Vmlation 6.8 Procedures and         5.4 Procedures             5.4 Procedures Programs 5.5 Programs and           5.5 Programs and Manuals                   Manuals 6.13 Offsite Dose           5.5.1 Offsite Dose         5.5.1 Offsite Dose Calculation Manual         Calculation Manual         Calculation Manual 6.8.3.a Primary             5.5.2 Primary Coolant     5.5.2 Primary Coolant Coolant Sources             Sources Outside           Sources Outside Outside Containment         Containment               Containment 6.8.3.b In Plant           NA                         NA                         Removed from the TS Radiation Monitoring                                                             to the FSAR.
(1) 6.5 Review and Audit NA NA Removed from the TS and placed in the QA Program.
6.8.3.c Secondary           5.5.10 Secondary           5.5.10 Secondary Water Chemistry             Water Chemistry           Water Chemistry 6.8.3.d Post Accident       5.5.3 Post Accident       5.5 3 Post Accident Sampling                   Sampling                   Sampling 6.8.3.e Radioactive         5.5.4 Radioactive         5.5.4 Radioactive Efiluent Controls           Effluent Controls         Effluent Controls Program                     Program                   Program 6.8.3.f Radiological       NA                         NA                       Removed from the TS Environmental                                                                   to the ODCM.
6.6 Reportable Event NA NA Removed from the TS.
Action 6.7 Safety Limit NA NA Removed from the TS.
Vmlation 6.8 Procedures and 5.4 Procedures 5.4 Procedures Programs 5.5 Programs and 5.5 Programs and Manuals Manuals 6.13 Offsite Dose 5.5.1 Offsite Dose 5.5.1 Offsite Dose Calculation Manual Calculation Manual Calculation Manual 6.8.3.a Primary 5.5.2 Primary Coolant 5.5.2 Primary Coolant Coolant Sources Sources Outside Sources Outside Outside Containment Containment Containment 6.8.3.b In Plant NA NA Removed from the TS Radiation Monitoring to the FSAR.
6.8.3.c Secondary 5.5.10 Secondary 5.5.10 Secondary Water Chemistry Water Chemistry Water Chemistry 6.8.3.d Post Accident 5.5.3 Post Accident 5.5 3 Post Accident Sampling Sampling Sampling 6.8.3.e Radioactive 5.5.4 Radioactive 5.5.4 Radioactive Efiluent Controls Effluent Controls Effluent Controls Program Program Program 6.8.3.f Radiological NA NA Removed from the TS Environmental to the ODCM.
Monitoring Program O
Monitoring Program O
V (1) See the apphcable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed infonnation.
V (1) See the apphcable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed infonnation.
A2-24
A2-24


      .~s
.~s Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
    ,,                                                                                                        Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications         Specifications (STS)
Improved Technical Standard Technical Notes Specifications Specifications (STS)
(FNP ITS)                                                   (1) 6.8.3.g Solid               NA                         NA                         Removed from the TS Radioactive Wastes                                                                 to the FSAR.
(FNP ITS)
Control Program NA                         5.5.5 Component             5.5.5 Component           Moved from the Cyclic or Transient         Cyclic or Transient       Design Features Limit                       Limit                     section of the CTS.
(1) 6.8.3.g Solid NA NA Removed from the TS Radioactive Wastes to the FSAR.
NA                         5.5.6 Pre-Stressed         5.5.6 Pre-Stressed         Moved from the Concrete Containment       Concrete Containment       Containment Tendon Surveillance         Tendon Surveillance       Structural Integrity Program                     Program                   LCO in Section 3.6.
Control Program NA 5.5.5 Component 5.5.5 Component Moved from the Cyclic or Transient Cyclic or Transient Design Features Limit Limit section of the CTS.
NA                         5.5.7 Reactor Coolant       5.5.7 Reactor Coolant     Moved from the RCS Pump Flywheel               Pump Flywheel             Structural Integrity inspection Program         inspection Program         LCO in section 3.4.
NA 5.5.6 Pre-Stressed 5.5.6 Pre-Stressed Moved from the Concrete Containment Concrete Containment Containment Tendon Surveillance Tendon Surveillance Structural Integrity Program Program LCO in Section 3.6.
NA                           5.5.R Inservice Testing     5.5.8 Inservice Testing   Moved from CTS Program                     Program                   4.0.5.
NA 5.5.7 Reactor Coolant 5.5.7 Reactor Coolant Moved from the RCS Pump Flywheel Pump Flywheel Structural Integrity inspection Program inspection Program LCO in section 3.4.
NA                           5.5.9 SG Tube               5.5.9 SG Tube             Mosed from the SG Surveillance Program       Surveillance Program       LCO in section 3.4.
NA 5.5.R Inservice Testing 5.5.8 Inservice Testing Moved from CTS Program Program 4.0.5.
6.8.3.c Secondary           5.5.10 Secondary           5.5.10 Secondary Water Chemistry             Water Chemistry             Water Chemistry NA                           5.5.11 Ventilation         5.5.1i Ventilation         Moved from various Filter Testing Program     Filter Testing Program     ventilation system LCOs in the CTS.
NA 5.5.9 SG Tube 5.5.9 SG Tube Mosed from the SG Surveillance Program Surveillance Program LCO in section 3.4.
NA                           5.5.12 Explosive Gas       5.5.12 Explosive Gas       Moved from related and Storage Tank           and Storage Tank           LCOs in the CTS.
6.8.3.c Secondary 5.5.10 Secondary 5.5.10 Secondary Water Chemistry Water Chemistry Water Chemistry NA 5.5.11 Ventilation 5.5.1i Ventilation Moved from various Filter Testing Program Filter Testing Program ventilation system LCOs in the CTS.
Radioactivity               Radioactivity Monitoring Program         Monitoring Program NA                           5.5.13 Diesel Fuel Oil     5.5.13 Diesel Fuel Oil     Moved from CTS Testing Program           Testing Program             requirements in Electrical Section of the CTS.
NA 5.5.12 Explosive Gas 5.5.12 Explosive Gas Moved from related and Storage Tank and Storage Tank LCOs in the CTS.
bv (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed information.                 ;
Radioactivity Radioactivity Monitoring Program Monitoring Program NA 5.5.13 Diesel Fuel Oil 5.5.13 Diesel Fuel Oil Moved from CTS Testing Program Testing Program requirements in Electrical Section of the CTS.
bv (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed information.
l A2-25 i
l A2-25 i


    .                                                                                                Farley Nuclear Plant ITS conversion Submittal
Farley Nuclear Plant ITS conversion Submittal
,t                       An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific -       NUREG-1431, Rev i Specifications (CTS)         Improved Technical         Standard Technical -                 Notes Specifications         Specifications (STS)
,t An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific -
(FNP E S)                                                 (1)
NUREG-1431, Rev i Specifications (CTS)
NA                           5.5.14 Technical           5.5.14 Technical           New Program Specification Bases       Specification Bases       introduced in the STS.
Improved Technical Standard Technical -
Control Program           Control Program NA                           5.5.15 Safety Function     5.5.15 Safety Function     New Program Determination             Determination             introduced in the STS.
Notes Specifications Specifications (STS)
Program                   Program NA                           5.5.16 Main Steamline     NA                         FNP Specific Inspection Program                                   requirements moved from the RCS Structural Integrity LCO in Section 3.4.
(FNP E S)
6.16 Containment             5.5.17 Containment         NA                         FNP specific Leakage Rate Testing         Leakage Rate Testing                                 requirements resulting Program                     Program                                               from adoption of 10CFR50 App. J Option B.
(1)
6.9 Reporting               5.6 Reporting             5.6 Reporting Requirements                 Requirements               Requirements 6.9.1.1-3 Startup           NA                         NA                         Deleted.
NA 5.5.14 Technical 5.5.14 Technical New Program Specification Bases Specification Bases introduced in the STS.
Report 6.9.1.4 Annual               NA                         NA                       Section title deleted.
Control Program Control Program NA 5.5.15 Safety Function 5.5.15 Safety Function New Program Determination Determination introduced in the STS.
Reports 6.9.1.5.a (untitled)         5.6.1 Occupational         5.6.1 Occupational Radiation Exposure         Radiation Exposure Report                     Report 6 9 l.6-7 Annual             5.6.2 Annual               5.6.2 Annual Radiological                 Radiological               Radiological Environmental               Environmental             Environmental Operating Report-           Operating Report           Operating Report 6.9.1.8-9 Annual             5.6.3 Radioactive         5.6.3 Radioactive o       Radioactive Efiluent         Efiluent Release           Efiluent Release Release Report               Report                     Report (I) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed infonnation.
Program Program NA 5.5.16 Main Steamline NA FNP Specific Inspection Program requirements moved from the RCS Structural Integrity LCO in Section 3.4.
6.16 Containment 5.5.17 Containment NA FNP specific Leakage Rate Testing Leakage Rate Testing requirements resulting Program Program from adoption of 10CFR50 App. J Option B.
6.9 Reporting 5.6 Reporting 5.6 Reporting Requirements Requirements Requirements 6.9.1.1-3 Startup NA NA Deleted.
Report 6.9.1.4 Annual NA NA Section title deleted.
Reports 6.9.1.5.a (untitled) 5.6.1 Occupational 5.6.1 Occupational Radiation Exposure Radiation Exposure Report Report 6 9 l.6-7 Annual 5.6.2 Annual 5.6.2 Annual Radiological Radiological Radiological Environmental Environmental Environmental Operating Report-Operating Report Operating Report 6.9.1.8-9 Annual 5.6.3 Radioactive 5.6.3 Radioactive o
Radioactive Efiluent Efiluent Release Efiluent Release Release Report Report Report (I) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed infonnation.
A2-26
A2-26


  .M                                                                                                 Farley Nuclear Plant ITS conversion Submittal r
.M Farley Nuclear Plant ITS conversion Submittal r
/                         An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev 1 Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications         Specifications (STS)
/
(FNP ITS)                                                 (1) 6.9.1.10 Monthly             5.6.4 Monthly             5.6.4 Monthly Operating Report             Operating Reports         Operating Reports 6.9.1.11 Core               5.6.5 Core Operating       5.6.5 Core Operating Operating Limits             Limits Report             Limits Report Report 6.9.1.12 Annual             5.6.7 Emergency           5.6.7 Emergency Diesel Generator             Diesel Generator           Diesel Generator Reliability Data             Failure Report             Failure Report Report 6.9.1.13 Annual             NA                         NA                         Deleted Reactor Coolant System Specific Activity Report k           6.9.1.14 Annual             NA                         NA                         Deleted Scaled Source Leakage Report 6.9.1.15 Pressure           5.6.6 RCS Pressure         5.6.6 RCS Pressure Temperature Limits           Temperature Limits         Temperature Limits Report                       Report                     Report NA                           5.6.8 Post Accident       5.6.8 Post Accident       New report introduced Monitoring Report         Monitoring Report         by the STS.
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)
NA                           5.6.9 Tendon               5.6.9 Tendon               New report introduced Surveillance Report       Surveillance Report       by the STS.
Improved Technical Standard Technical Notes Specifications Specifications (STS)
NA                           5.6.10 Steam               5.6.10 Steam               Moved from the CTS Generator Tube             Generator Tube             SG LCO in the RCS Inspection Report         inspection Report         section of the CTS.
(FNP ITS)
NA                           5.6.11 Alternate AC       5.6.11 Alternate AC       Based on existing (AAC) Source Out of       (AAC) Source Out of       CTS requirements Service Report             Service Report             6.8.1.j for AAC.
(1) 6.9.1.10 Monthly 5.6.4 Monthly 5.6.4 Monthly Operating Report Operating Reports Operating Reports 6.9.1.11 Core 5.6.5 Core Operating 5.6.5 Core Operating Operating Limits Limits Report Limits Report Report 6.9.1.12 Annual 5.6.7 Emergency 5.6.7 Emergency Diesel Generator Diesel Generator Diesel Generator Reliability Data Failure Report Failure Report Report 6.9.1.13 Annual NA NA Deleted Reactor Coolant System Specific Activity Report k
6.9.2 Special Reports        NA                        NA                        Deleted.
6.9.1.14 Annual NA NA Deleted Scaled Source Leakage Report 6.9.1.15 Pressure 5.6.6 RCS Pressure 5.6.6 RCS Pressure Temperature Limits Temperature Limits Temperature Limits Report Report Report NA 5.6.8 Post Accident 5.6.8 Post Accident New report introduced Monitoring Report Monitoring Report by the STS.
NA 5.6.9 Tendon 5.6.9 Tendon New report introduced Surveillance Report Surveillance Report by the STS.
NA 5.6.10 Steam 5.6.10 Steam Moved from the CTS Generator Tube Generator Tube SG LCO in the RCS Inspection Report inspection Report section of the CTS.
NA 5.6.11 Alternate AC 5.6.11 Alternate AC Based on existing (AAC) Source Out of (AAC) Source Out of CTS requirements Service Report Service Report 6.8.1.j for AAC.
']
']
6.9.2 Special Reports NA NA Deleted.
v (1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
v (1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.
A2 27
A2 27


1
1
  ,W
,W
  .h                                                                                               Farley Nuclear Plant ITS conversion Submittal p.
.h Farley Nuclear Plant ITS conversion Submittal p.
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical               FNP Specific         NUREG-1431, Rev i Specifications (CTS)         Improved Technical         Standard Technical                   Notes Specifications         Specifications (STS)
An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev i Specifications (CTS)
(FNP ITS)                                                   (1) 6.10 Record Retention       NA                         NA                         Removed from the TS             '
Improved Technical Standard Technical Notes Specifications Specifications (STS)
and placed in the QA Program.
(FNP ITS)
6.11 Radiation               NA                         NA                         Removed from the TS.
(1) 6.10 Record Retention NA NA Removed from the TS and placed in the QA Program.
Protection Program 6.12 High Radiation         5.7 High Radiation         5.7 High Radiation Area                         Area                       Area 6.13 Process Control         NA                         NA                         Removed from the TS Program                                                                             and placed in the FSAR.
6.11 Radiation NA NA Removed from the TS.
6.14 Offsite Dose           5.5.1 ODCM                 5.5.1 ODCM Calculation Manual (ODCM) 6.15 Major Changes           NA                         NA                         The information To Radioactive Waste                                                               contained in this Treatment Systems                                                                   section was deleted by a previous amendment. The empty section is deleted in the ITS conversion.
Protection Program 6.12 High Radiation 5.7 High Radiation 5.7 High Radiation Area Area Area 6.13 Process Control NA NA Removed from the TS Program and placed in the FSAR.
6.16 Containment             5.5.17 Contaimnent         NA                         FNP specific Leakage Rate Testing         Leakage Rate Testing                                   requirements resulting Program                     Program                                               from adoption of 10CFR50 App. J Option B.
6.14 Offsite Dose 5.5.1 ODCM 5.5.1 ODCM Calculation Manual (ODCM) 6.15 Major Changes NA NA The information To Radioactive Waste contained in this Treatment Systems section was deleted by a previous amendment. The empty section is deleted in the ITS conversion.
6.16 Containment 5.5.17 Contaimnent NA FNP specific Leakage Rate Testing Leakage Rate Testing requirements resulting Program Program from adoption of 10CFR50 App. J Option B.
O V
O V
(1) See the applicable Enclosure l CTS markup or Enclosure 4 STS markup for more detailed information.
(1) See the applicable Enclosure l CTS markup or Enclosure 4 STS markup for more detailed information.
A2 28
A2 28


s
s Farley Nuc! car Plant ITS conversion Submittal O
**                                                        Farley Nuc! car Plant
Joseph M. Farley Nuclear Plant Farley CTS License Amendment Requests Incorporated into the ITS O
.                                                          ITS conversion Submittal O
Attachment 3 Joseph M. Farley Nuclear Plant Farley CTS License Amendment Requests Incorporated into the ITS O
O
O


4 Farley Nuc! car Plant ITS conversion Submittal Farley CTS License Amendment Requests incorporated into the ITS License Amendment Request         Affected ITS Specifications       Affected CTS Pages (Title and Letter Date)
4 Farley Nuc! car Plant ITS conversion Submittal Farley CTS License Amendment Requests incorporated into the ITS License Amendment Request Affected ITS Specifications Affected CTS Pages (Title and Letter Date)
Facility Operating Licenses and   1.0, 2.0, 3.2, 3.3, 3.4, 3.5, 3.6, 1-6,2-5 through 2-7, 3/4 2-15, Technical Specifications Change   4.0, 5.0                           3/43-25,3/43-27,3/43-28,3/4 Request for Power Uprating,                                           4-12b (Unit 2 only),3/4 7-9,5-6, February 14,1997                                                     5-8,6-19a,6-24, B 3/4 2-5, B 3/4 4-3b (Unit 2 only), B 3/4 5-5, B 3/4 6-2, and B 3/4 7-1 Technical Specification           3.3, 3.5                           3/43-2,3/43-6,3/43-14,3/45-ComplianceIssues Amendments,                                         3 and 3/4 5-7 May 27,1997 Control Room, Penetration         3.3, 3.9                           3/43-39,3/43-40,3/47-16,3/4 Room, and Containment Purge                                           7-17,3/4 7-17a,3/4 7-18,3/4 7-Filtration systems and Radiation                                     19,3/4 9-14 through 3/4 9-18, B Monitoring Instmmentation, June                                       3/4 7-4, B 3/4 7-4a, B 3/4 9-3 30,1997                                                                                                   (
Facility Operating Licenses and 1.0, 2.0, 3.2, 3.3, 3.4, 3.5, 3.6, 1-6,2-5 through 2-7, 3/4 2-15, Technical Specifications Change 4.0, 5.0 3/43-25,3/43-27,3/43-28,3/4 Request for Power Uprating, 4-12b (Unit 2 only),3/4 7-9,5-6, February 14,1997 5-8,6-19a,6-24, B 3/4 2-5, B 3/4 4-3b (Unit 2 only), B 3/4 5-5, B 3/4 6-2, and B 3/4 7-1 Technical Specification 3.3, 3.5 3/43-2,3/43-6,3/43-14,3/45-ComplianceIssues Amendments, 3 and 3/4 5-7 May 27,1997 Control Room, Penetration 3.3, 3.9 3/43-39,3/43-40,3/47-16,3/4 Room, and Containment Purge 7-17,3/4 7-17a,3/4 7-18,3/4 7-Filtration systems and Radiation 19,3/4 9-14 through 3/4 9-18, B Monitoring Instmmentation, June 3/4 7-4, B 3/4 7-4a, B 3/4 9-3 30,1997
Pressure Temperature Limits       1.0, 3.4, 5.0                     1-5,3/44-27,3/44-29,3/44-30, O     Report, July 23,1997                                                 6-20,6-20a, B 3/4 4-6 through B     )
(
d                                                                           3/4 4-10, B 3/4 4-10a, and B 3/4 4-11 through B 3/4 4-14 Auxiliary Building & Service       3.8                               3/4 8-9(a) and 3/4 8-13 Water Building Battery Surveillances, December 30, 1997 Intermediate Range Neutron Flux   2.0, 3.1, 3.3                     2-5,3/410-3, and B 2-4 Reactor Trip Setpoint, December 31,1997 Pressure Temperature Limits       3.4, 5.0                           3/4 4-3,3/4 4-4a,3/4 4-32, B 3/4 Report February 12,1998                                               4-1, and B 3/4 4-8 Response to Request for           5.0                                 6-19a Additional Information Related to Power Uprate Facility Operating Licenses and Technical Specifications change Request, February, 12,1998 (3
Pressure Temperature Limits 1.0, 3.4, 5.0 1-5,3/44-27,3/44-29,3/44-30, O
~C#                                                       A3-1
Report, July 23,1997 6-20,6-20a, B 3/4 4-6 through B
)
d 3/4 4-10, B 3/4 4-10a, and B 3/4 4-11 through B 3/4 4-14 Auxiliary Building & Service 3.8 3/4 8-9(a) and 3/4 8-13 Water Building Battery Surveillances, December 30, 1997 Intermediate Range Neutron Flux 2.0, 3.1, 3.3 2-5,3/410-3, and B 2-4 Reactor Trip Setpoint, December 31,1997 Pressure Temperature Limits 3.4, 5.0 3/4 4-3,3/4 4-4a,3/4 4-32, B 3/4 Report February 12,1998 4-1, and B 3/4 4-8 Response to Request for 5.0 6-19a Additional Information Related to Power Uprate Facility Operating Licenses and Technical Specifications change Request, February, 12,1998 (3
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Farley Nuclear Plant ITS conversion Submittal O
Farley Nuclear Plant ITS conversion Submittal O
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Attachment 4 Joseph M. Farley Nuclear Plant i
Joseph M. Farley Nuclear Plant i
Generic Changes to NUREG-1431, Rev.1. Incorporated into the ITS O
Generic Changes to NUREG-1431, Rev.1. Incorporated into the ITS O
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1 Farley Nuclear Plant ITS conversion Subasttal Generic Changes to NUREG 1431, Rey,1, incorporated into the ITS FNP ITS Chapter TSTF's incorporated Comments 1.0 None 2.0 TSTF-5 3.0 TSTF-6, TSTF-8, TSTF-12, TSTF-71,TSTF 104,TSTF-122, TSTF-165, TSTF-166 3.1 TSTF-9, TSTF-12, TSTF-13, TSTF-14, TSTF-15, TSTF-89, TSTF-108 TSTF-110,TSTF-136, TSTF-141. TSTF.142 3.2 TSTF-95. TSTF-97, TSTF-98, TSTF-99, TSTF-109. TSTF-110, TSTF-136 3.3 TSTF-161 TSTF-169 O
.                                                                      Farley Nuclear Plant ITS conversion Subasttal Generic Changes to NUREG 1431, Rey,1, incorporated into the ITS FNP ITS Chapter             TSTF's incorporated                 Comments 1.0             None 2.0             TSTF-5 3.0             TSTF-6, TSTF-8, TSTF-12, TSTF-71,TSTF 104,TSTF-122, TSTF-165, TSTF-166 3.1             TSTF-9, TSTF-12, TSTF-13, TSTF-14, TSTF-15, TSTF-89, TSTF-108 TSTF-110,TSTF-136, TSTF-141. TSTF.142 3.2             TSTF-95. TSTF-97, TSTF-98, TSTF-99, TSTF-109. TSTF-110, TSTF-136 3.3             TSTF-161 TSTF-169 O             3.4             TSTF-28,TSTF-54 TSTF-60,     TSTF's 26,93,94, and 108 not TSTF-61, TSTF-114, TSTF-     incorporated.
3.4 TSTF-28,TSTF-54 TSTF-60, TSTF's 26,93,94, and 108 not TSTF-61, TSTF-114, TSTF-incorporated.
136, TSTF-153, TSTF-162 3.5             TSTF-90, TSTF-153 3.6             TSTF-17, TSTF-30. TSTF-45,   TSTF-52 under NRC TSTF-46, TSTF 52             consideration.
136, TSTF-153, TSTF-162 3.5 TSTF-90, TSTF-153 3.6 TSTF-17, TSTF-30. TSTF-45, TSTF-52 under NRC TSTF-46, TSTF 52 consideration.
3.7             TSTF-100, TSTF-101, TSTF-     TSTF-70 not incorporated.
3.7 TSTF-100, TSTF-101, TSTF-TSTF-70 not incorporated.
139. TSTF-140. TSTF-174 3.8             TSTF-8, TSTF-38 3.9             TSTF-20, TSTF-96, TSTF-197   TSTF-136 not incorporated.
139. TSTF-140. TSTF-174 3.8 TSTF-8, TSTF-38 3.9 TSTF-20, TSTF-96, TSTF-197 TSTF-136 not incorporated.
4.0             None i
4.0 None i
5.0             TSTF-118 TSTF-152             TSTF-106 not incorporated.           l A4-1
5.0 TSTF-118 TSTF-152 TSTF-106 not incorporated.
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Farley Nuclear Plant
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Farley Nuclear Plant ITS conversion Submittal O                                                                                   l 1
ITS conversion Submittal O
Attachment 5 Joseph M. Farley Nuclear Plant Channes Identified as Beyond the Scope of an ITS Conversion O
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Joseph M. Farley Nuclear Plant Channes Identified as Beyond the Scope of an ITS Conversion O
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Farley Nuclear Plant ITS conversion Submittal T                       Changes Identified as Beyond the Scope of an ITS Conversion CTS     DOC       ITS           JD                           Summary of Change Reference Number   Reference     Number 3.2 POWER DISTRIBUTION LIMITS C
Farley Nuclear Plant ITS conversion Submittal T
3/4.2.2   2 A,     3.2.1           1     The STS terms Fo*(2) and Fn (Z) in LCO 3.2.1 are deleted I l-A                           and the tenns Fo(Z), " steady state" limit, and " transient" limi are used. While these terms are not used in the Farley CTS, they are consistent with the methodology which represents the current Farley licensing basis.
Changes Identified as Beyond the Scope of an ITS Conversion CTS DOC ITS JD Summary of Change Reference Number Reference Number 3.2 POWER DISTRIBUTION LIMITS C
3/4.2.4   4a-A     3.2.4           1     The STS wording in Required Action A.! to " reduce" thermal power is revised to " limit" thermal power to allow entry into the LCO applicability during startup when QPTR may be in excess of 1.02 due to transient core conditions which are usually self-correcting.
3/4.2.2 2 A, 3.2.1 1
3/4.2.4   la M     3.2.4           la     The Applicability of LCO 3.2.4 is revised to be consistent with the Applicability for the AFD LCO to eliminate subtle difTerences between the two LCO Applicabilities which were previously the same.
The STS terms Fo*(2) and Fn (Z) in LCO 3.2.1 are deleted I l-A and the tenns Fo(Z), " steady state" limit, and " transient" limi are used. While these terms are not used in the Farley CTS, they are consistent with the methodology which represents the current Farley licensing basis.
3/4.2.4   3-L,     3.2.4       2,3,4,5,   The Required Actions, Completion Times, and Surveillance 6-L                   and 6   Notes are revised to clarify the requirements of LCO 3.2.4, ensure that references to the reduced power level of A.1 in subsequent Actions reflect the lowest power limit, ensure that equilibrium conditions are met prior to performing surveillances, and ensure that the LCO is not exited prematurely. These changes are based on TSTF-241.
3/4.2.4 4a-A 3.2.4 1
The STS wording in Required Action A.! to " reduce" thermal power is revised to " limit" thermal power to allow entry into the LCO applicability during startup when QPTR may be in excess of 1.02 due to transient core conditions which are usually self-correcting.
3/4.2.4 la M 3.2.4 la The Applicability of LCO 3.2.4 is revised to be consistent with the Applicability for the AFD LCO to eliminate subtle difTerences between the two LCO Applicabilities which were previously the same.
3/4.2.4 3-L, 3.2.4 2,3,4,5, The Required Actions, Completion Times, and Surveillance 6-L and 6 Notes are revised to clarify the requirements of LCO 3.2.4, ensure that references to the reduced power level of A.1 in subsequent Actions reflect the lowest power limit, ensure that equilibrium conditions are met prior to performing surveillances, and ensure that the LCO is not exited prematurely. These changes are based on TSTF-241.
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Farley Nuclear Plant ITS conversion Submittal (O,                     Changes identified as Beyond the Scope of an ITS Conversion v
Farley Nuclear Plant ITS conversion Submittal (O,
CTS     DOC       ITS           JD                           Summary of Change Reference Number Reference     Number 3.3 INSTRUMENTATION 3/4.3.2   39-L   3.3.2           13   The STS footnote (i) (FNP ITS footnote (d)) to ESFAS Table 3.3.2-1 is revised consistent with the FNP main steam system design. He mtent of the STS footnote is to provide an exception to the Mode of Applicability for the main steam line isolation function when all of the main steam lines are isolated. The note is revised to reflect the fact that this can be accomplished by a single MSIV in each line. The STS note was written for plant designs which only include a single MSIV per line instead of the two MSIVs per line incorporated in the FNP design.
Changes identified as Beyond the Scope of an ITS Conversion v
3/4.3.2   28 L   3.3.2           19   The STS footnote (j) (FNP ITS footnote (g)) to ESFAS Table 3.3.2-1 is revised consistent with the FNP main feedwater system design. The intent of the STS footnote is to proside an exception to the Mode of Applicability for the turbine trip and feedwater line isolation functions when all of the main O
CTS DOC ITS JD Summary of Change Reference Number Reference Number 3.3 INSTRUMENTATION 3/4.3.2 39-L 3.3.2 13 The STS footnote (i) (FNP ITS footnote (d)) to ESFAS Table 3.3.2-1 is revised consistent with the FNP main steam system design. He mtent of the STS footnote is to provide an exception to the Mode of Applicability for the main steam line isolation function when all of the main steam lines are isolated. The note is revised to reflect the fact that this can be accomplished by a single MSIV in each line. The STS note was written for plant designs which only include a single MSIV per line instead of the two MSIVs per line incorporated in the FNP design.
V feedwater lines are isolated. He note is revised to reflect the fact that this can be accomplished by a single Main i
3/4.3.2 28 L 3.3.2 19 The STS footnote (j) (FNP ITS footnote (g)) to ESFAS Table 3.3.2-1 is revised consistent with the FNP main feedwater system design. The intent of the STS footnote is to proside an exception to the Mode of Applicability for the turbine trip and feedwater line isolation functions when all of the main O
Feedwater Stop Valve or the combination of a MFRV and its associated MFRV bypass in each line. The STS note is revised to take credit for either method ofisolation, consistent with the FNP design.
feedwater lines are isolated. He note is revised to reflect the i
3/4.3.3.5 10a-M   3.3.4           4     A new Condition C is added to FNP ITS LCO 3.3.4 to address actions associated with the source range neutron flux       ,
V fact that this can be accomplished by a single Main Feedwater Stop Valve or the combination of a MFRV and its associated MFRV bypass in each line. The STS note is revised to take credit for either method ofisolation, consistent with the FNP design.
monitor. This monitor is not included in the FNP CTS. The           I monitor provides visual indication only and is not depended         l upon for any actuation signal or to monitor the operation of any component necessary to maintain the unit in Mode 3.
3/4.3.3.5 10a-M 3.3.4 4
A new Condition C is added to FNP ITS LCO 3.3.4 to address actions associated with the source range neutron flux monitor. This monitor is not included in the FNP CTS. The monitor provides visual indication only and is not depended upon for any actuation signal or to monitor the operation of any component necessary to maintain the unit in Mode 3.
Therefore, shutdown actions are not appropriate and the new condition provides appropriate actions.
Therefore, shutdown actions are not appropriate and the new condition provides appropriate actions.
3/4.3.2 35-M,     3.3.5       1, 2, 3, 4 STS LCO 3.3.5 is revised to accommodate the addition of a 61-M                   and 8   degraded grid alarm function. This function does not exist in the CTS. This is in compliance with a previous commitment to the NRC to include this function in the ITS conversion.
3/4.3.2 35-M, 3.3.5 1, 2, 3, 4 STS LCO 3.3.5 is revised to accommodate the addition of a 61-M and 8 degraded grid alarm function. This function does not exist in the CTS. This is in compliance with a previous commitment to the NRC to include this function in the ITS conversion.
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Farley Nuc! car Plant ITS conversion Submittal Changes Identified as Beyond the Scope of an ITS Conversion CTS       DOC       ITS           JD                           Summary of Change Reference   Number   Reference     Number 3.4 REACTOR COOLANT SYSTEM (RCS) 3/4.10.4     1-L     3.4.17         1     The RCS Loop Test Exception LCO is deleted from both the CTS and FNP ITS. This test exception is no longer used at FNP.
Farley Nuc! car Plant ITS conversion Submittal Changes Identified as Beyond the Scope of an ITS Conversion CTS DOC ITS JD Summary of Change Reference Number Reference Number 3.4 REACTOR COOLANT SYSTEM (RCS) 3/4.10.4 1-L 3.4.17 1
3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3/4.5.3   4a-L     3.5.3           2     A new Action is added to the ECCS-Shutdown LCO. The new Action provides an allowed outage time of 72 hours for the required ECCS centrifugal charging subsystem to be inoperable provided the remaining operable ECCS components are capable of providing 100% of the ECCS flow, equivalent to a single operable ECCS subsystem. At FNP, the requirement to ensure that only one centrifugal charging pump is operable for overpressurization concerns is   i not applicable until the temperature of one or more of the RCS cold legs is less than or equal to 180 degrees F.           ,
The RCS Loop Test Exception LCO is deleted from both the CTS and FNP ITS. This test exception is no longer used at FNP.
Therefore, in MODE 4, two or more centrifugal charging         l O-   .
3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3/4.5.3 4a-L 3.5.3 2
pumps may be available and an Action similar to that in STS 3.5.2 (ECCS-Operating) may be applied in FNP ITS 3.5.3 l
A new Action is added to the ECCS-Shutdown LCO. The new Action provides an allowed outage time of 72 hours for the required ECCS centrifugal charging subsystem to be inoperable provided the remaining operable ECCS components are capable of providing 100% of the ECCS flow, equivalent to a single operable ECCS subsystem. At FNP, the requirement to ensure that only one centrifugal charging pump is operable for overpressurization concerns is i
(ECCS-Shutdown).                                               )
not applicable until the temperature of one or more of the RCS cold legs is less than or equal to 180 degrees F.
3/4.4.7.2.e 4-M and   3.5.5           1     The RCP seal injection flow requirements are revised from 1 LA                           verification of a single operating point to verification of a   j range of values on an operating curve (graph). Establishing a reference differential pressure allows a more precise and repeatable verification of seal injection flow and proper     )
Therefore, in MODE 4, two or more centrifugal charging O-pumps may be available and an Action similar to that in STS 3.5.2 (ECCS-Operating) may be applied in FNP ITS 3.5.3 (ECCS-Shutdown).
throttle valve position. In the conversion to ITS, this change I in the measurement of the seal injection flow is addressed by use of a graph from which the appropriate flow can be determined based on the delta between the RCS pressure and the charging discharge header pressure. He points on the graph are based on FNP-specific safety analysis assumptions which provide the relationship between seal injection flow, RCS pressure, and charging discharge header pressure over a range of values for each of these parameters. His method of determining the seal injection flow limit was approved by the NRC for Vogtle.
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3/4.4.7.2.e 4-M and 3.5.5 1
l
The RCP seal injection flow requirements are revised from 1 LA verification of a single operating point to verification of a j
range of values on an operating curve (graph). Establishing a reference differential pressure allows a more precise and repeatable verification of seal injection flow and proper
)
throttle valve position. In the conversion to ITS, this change I
in the measurement of the seal injection flow is addressed by use of a graph from which the appropriate flow can be determined based on the delta between the RCS pressure and the charging discharge header pressure. He points on the graph are based on FNP-specific safety analysis assumptions which provide the relationship between seal injection flow, RCS pressure, and charging discharge header pressure over a range of values for each of these parameters. His method of determining the seal injection flow limit was approved by the NRC for Vogtle.
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4 Farley Nuclear Plant ITS conversion Submittal Changes Identified as Beyond the Scope of an ITS Conversion CTS     DOC       ITS             JD                           Summary of Change Reference Number   Reference     Number 3.7 PLANT SYSTEMS 3/4.7.1.1 4-L and   3.7.1         2 and 6   The CTS time allowed to reduce the power range neutron 4a-L                               flux setpoint to within the required limit is extended and made applicable in Mode 1 only. The additional time to reduce setpoints allows for a more controlled evolution. The restriction to Mode I for this Action is consistent with the applicable FNP specific safety analysis and climinates the unnecessary requirement to apply this Action in Mode 2 or 3.
4 Farley Nuclear Plant ITS conversion Submittal Changes Identified as Beyond the Scope of an ITS Conversion CTS DOC ITS JD Summary of Change Reference Number Reference Number 3.7 PLANT SYSTEMS 3/4.7.1.1 4-L and 3.7.1 2 and 6 The CTS time allowed to reduce the power range neutron 4a-L flux setpoint to within the required limit is extended and made applicable in Mode 1 only. The additional time to reduce setpoints allows for a more controlled evolution. The restriction to Mode I for this Action is consistent with the applicable FNP specific safety analysis and climinates the unnecessary requirement to apply this Action in Mode 2 or 3.
This CTS Action and Completion Time are FNP specific and not part of the STS 3/4.7.1.5   4-L     3.7.2         i and 3   The CTS Actions for an inoperable MSIV are revised to take credit for the redundant MSIVs (Train A and B)in each steam line at FNP. The STS and the CTS are written for the standard PWR plant design ofone MSIV per steam line.
This CTS Action and Completion Time are FNP specific and not part of the STS 3/4.7.1.5 4-L 3.7.2 i and 3 The CTS Actions for an inoperable MSIV are revised to take credit for the redundant MSIVs (Train A and B)in each steam line at FNP. The STS and the CTS are written for the standard PWR plant design ofone MSIV per steam line.
These Actions are also revised to be consistent with the Vogtle Plant Technical Specifications which also take credit for two MSIVs in cach steam line and which have been approved by the NRC.
These Actions are also revised to be consistent with the Vogtle Plant Technical Specifications which also take credit for two MSIVs in cach steam line and which have been approved by the NRC.
f           3/4.7.4   11-L     3.7.8             3     An Action has been added to the SW LCO that accounts for the redundant automatic turbine building isolation valves in each FNP SW train. One isolation valve in each train may be inoperable and the turbine building isolation function is not lost (one train of turbine building isolation valves remain operable in each train of SW). This FNP specific design was not previously accounted for in the CTS and is not part of the STS. The proposed change eliminates the potential for an unnecessary shutdown per LCO 3.0.3 with a single inoperable turbine building isolation valve in each SW train.
f 3/4.7.4 11-L 3.7.8 3
An Action has been added to the SW LCO that accounts for the redundant automatic turbine building isolation valves in each FNP SW train. One isolation valve in each train may be inoperable and the turbine building isolation function is not lost (one train of turbine building isolation valves remain operable in each train of SW). This FNP specific design was not previously accounted for in the CTS and is not part of the STS. The proposed change eliminates the potential for an unnecessary shutdown per LCO 3.0.3 with a single inoperable turbine building isolation valve in each SW train.
O A5 4
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Fr.rley Nuclear Pent ITS conversion Submittal
Fr.rley Nuclear Pent ITS conversion Submittal
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Changes identified as Beyond the Scope of an ITS Conversion CTS     DOC         ITS           JD                           Summary of Change Reference Number   Reference       Number 3.8 ELECTRICAL POWER SYSTEMS DG Test   16-LA       Table           32   The DG accelerated Test Table is deleted from both the CTS Schedule             3.8.1-1                 and STS. This deletion is consistent with previous NRC page                                       guidance applicable to plants after implementing the 3/4 8-6a                                     maintenance rule.
Changes identified as Beyond the Scope of an ITS Conversion CTS DOC ITS JD Summary of Change Reference Number Reference Number 3.8 ELECTRICAL POWER SYSTEMS DG Test 16-LA Table 32 The DG accelerated Test Table is deleted from both the CTS Schedule 3.8.1-1 and STS. This deletion is consistent with previous NRC page guidance applicable to plants after implementing the 3/4 8-6a maintenance rule.
4.8.1.2 8-L, 9-L SR 3.8.2.1       1, 2, 3 The AC Sources - Shutdown surveillance is revised to more and                     and 4   accurately and completely state the required surveillances.
4.8.1.2 8-L, 9-L SR 3.8.2.1 1, 2, 3 The AC Sources - Shutdown surveillance is revised to more and and 4 accurately and completely state the required surveillances.
10-A                             This includes additional exceptions for surveillances which verify SI signal response and automatic load sequencing (not required during shutdown). Additional clarifications have also been added to the STS surveillance to state what is actually required to be performed.
10-A This includes additional exceptions for surveillances which verify SI signal response and automatic load sequencing (not required during shutdown). Additional clarifications have also been added to the STS surveillance to state what is actually required to be performed.
3/4.8.2.5   5-L     3.8.4 and     2 and 3 The Actions for an inoperable Service Water intake Structure 3.8.9                 (SWIS) Battery and Distribution System are revised to more accurately reflect the specific FNP design. The SWIS batteries and distribution system provide power to the SW d(3                                                 System and do not impact any other ESF system. The Actions for an inoperable train of SWIS batteries or Distribution System are revised from a two hour shutdown requirement to declare the associated train of SW inoperable.
3/4.8.2.5 5-L 3.8.4 and 2 and 3 The Actions for an inoperable Service Water intake Structure 3.8.9 (SWIS) Battery and Distribution System are revised to more accurately reflect the specific FNP design. The SWIS batteries and distribution system provide power to the SW d(3 System and do not impact any other ESF system. The Actions for an inoperable train of SWIS batteries or Distribution System are revised from a two hour shutdown requirement to declare the associated train of SW inoperable.
3.9 REFUELING OPERATIONS 3/4 9.2   9-M       3.9.2           3   The Actions of the Nuclear Instrumentation LCO are revised by the addition of a specific Action for loss of the audible count rate. This new Action is applicable for plants which credit the audible count rate in the refueling boron dilution accident analysis. TSTF-23 has been submitted for NRC approval to incorporate this change in the STS.
3.9 REFUELING OPERATIONS 3/4 9.2 9-M 3.9.2 3
5.0 ADMINISTRATIVE CONTROLS 6.1.2     2-L       5.1.2           la   The specific title for the control room command function is replaced with a more generic description to avoid technical specification changes in the future and to be consistent with the Vogtle Plant technical specifications.
The Actions of the Nuclear Instrumentation LCO are revised by the addition of a specific Action for loss of the audible count rate. This new Action is applicable for plants which credit the audible count rate in the refueling boron dilution accident analysis. TSTF-23 has been submitted for NRC approval to incorporate this change in the STS.
6.3.1   12a-A       5.3.1           7   The specific title of the Health Physics Supervisor is replaced
5.0 ADMINISTRATIVE CONTROLS 6.1.2 2-L 5.1.2 la The specific title for the control room command function is replaced with a more generic description to avoid technical specification changes in the future and to be consistent with the Vogtle Plant technical specifications.
.,m                                               with a more generic description to avoid technical specification changes in the future.
6.3.1 12a-A 5.3.1 7
The specific title of the Health Physics Supervisor is replaced
.,m with a more generic description to avoid technical specification changes in the future.
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a Farley Nuclear Plant ITS conversion Submittal Changes identified as Beyond the Scope of an ITS Conversion CTS     DOC       ITS           JD                         Summary of Change Reference Number Reference     Number                                         /
a Farley Nuclear Plant ITS conversion Submittal Changes identified as Beyond the Scope of an ITS Conversion CTS DOC ITS JD Summary of Change Reference Number Reference Number
4.4.11.2   3-L     5.5.7           11     The inspection frequency for the RCP Flywheel is revised consistent with the NRC approved WCAP-14535A," Topical Report on RCP Flywheel Inspection Elimination", November, 1996. Note: the 10 year inspection frequency was approved generically for RCPs with flywheels constructed of a certain material (FNP RCPs utilize an approved flywheel material).
/
6.9.1.12 60-L     5.6.7           23     The EDG Failure Report is revised consistent with the latest FNP commitments for DG failure tracking and reporting.
4.4.11.2 3-L 5.5.7 11 The inspection frequency for the RCP Flywheel is revised consistent with the NRC approved WCAP-14535A," Topical Report on RCP Flywheel Inspection Elimination", November, 1996. Note: the 10 year inspection frequency was approved generically for RCPs with flywheels constructed of a certain material (FNP RCPs utilize an approved flywheel material).
6.12.1.c 77-L   5.7.1.c           -    The Specific Health Physics Supervisor title is revised with a more genene description of the position to avoid technical specification changes in the future.
6.9.1.12 60-L 5.6.7 23 The EDG Failure Report is revised consistent with the latest FNP commitments for DG failure tracking and reporting.
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The Specific Health Physics Supervisor title is revised with a 6.12.1.c 77-L 5.7.1.c more genene description of the position to avoid technical specification changes in the future.
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Farley Nuclear Plant ITS conversion Submittal O
Farley Nuclear Plant ITS conversion Submittal O
Attachment 6 Joseph M. Farley Nuclear Plant Summary of CTS Requirements Removed from the TS and Placed in, or Currently Located in, Other Documents J
Joseph M. Farley Nuclear Plant Summary of CTS Requirements Removed from the TS and Placed in, or Currently Located in, Other Documents J
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Farley Nuclear Plant lis Conversion Summary of CTS Requirements Removed From the TS sad Placed in, or Currently Located in, Other Documents ITS       DOC #               Description of CTS Requirement                     Document               Control a
Farley Nuclear Plant lis Conversion Summary of CTS Requirements Removed From the TS sad Placed in, or Currently Located in, Other Documents ITS DOC #
Section 1.0 USE AND APPLICATION 1.0         6-LA       1.6 Containment Integrity definition (except             LCO 3.6.1           5.5.14 Bases item "d" as described in DOC 6-LA).                         Bases         Control Program 1.0       19-LA       1.22 Process Control Program definition.                   FSAR               10CFR50.59 1.0       32-LA       Table 1.1,140 F Mode 6 temperature                           TRM               10CFR50.59 limitation.
Description of CTS Requirement Document Control Section a
3.0 LCO AND SR APPLICABILITY 3.0       16-LA       4.0.5 ASME Inservice inspection (ISI)                   ISI Program         10CFR50.55a requirements.
1.0 USE AND APPLICATION 1.0 6-LA 1.6 Containment Integrity definition (except LCO 3.6.1 5.5.14 Bases item "d" as described in DOC 6-LA).
3.1 REACTIVITY CONTROL SYSTEMS 3.1         1-LA       3/4.1.1.1 Shutdown Margin requirements for                   TRM               10CFR50.59 Mode I and Mode 2 with ka 21.
Bases Control Program 1.0 19-LA 1.22 Process Control Program definition.
3.I         I l-LA     4.1.1.1.1.e items 1-6 providing guidance for             SR 3.1.1.1           5.5.14 Bases the performance of the surveillance                         bases         Control Program requirement 3.1         15-LA       4.1.1.1.2 Reference to the " factors stated in           SR 3.1.2.1           5.5.14 Bases 4.1.! 1.1 e, above"(items 1-6).                             bases         Control Program 3.1         2-LA       3/4.1.1.2 Actions describing a flow rate and             LCO 3.1.1           5.5.14 Bases boron concentration required to be used to                   bases         Control Program restore the SDM to within limit.
FSAR 10CFR50.59 1.0 32-LA Table 1.1,140 F Mode 6 temperature TRM 10CFR50.59 limitation.
3.1         5-LA       4.1.1.2.b Descriptive information (6 items)               SR 3.1.1.1         5.5.14 Bases providing guidance for the performance of the               bases         Control Program surveillance requirement.
3.0 LCO AND SR APPLICABILITY 3.0 16-LA 4.0.5 ASME Inservice inspection (ISI)
3.1         4-LA       3/4.1.1.3 Information modifying the required             LCO 3.1.3           5.5.14 Bases actions.                                                 Action A.1       Control Program bases N
ISI Program 10CFR50.55a requirements.
          ' 'the "lX designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.
3.1 REACTIVITY CONTROL SYSTEMS 3.1 1-LA 3/4.1.1.1 Shutdown Margin requirements for TRM 10CFR50.59 Mode I and Mode 2 with ka 21.
3.I I l-LA 4.1.1.1.1.e items 1-6 providing guidance for SR 3.1.1.1 5.5.14 Bases the performance of the surveillance bases Control Program requirement 3.1 15-LA 4.1.1.1.2 Reference to the " factors stated in SR 3.1.2.1 5.5.14 Bases 4.1.! 1.1 e, above"(items 1-6).
bases Control Program 3.1 2-LA 3/4.1.1.2 Actions describing a flow rate and LCO 3.1.1 5.5.14 Bases boron concentration required to be used to bases Control Program restore the SDM to within limit.
3.1 5-LA 4.1.1.2.b Descriptive information (6 items)
SR 3.1.1.1 5.5.14 Bases providing guidance for the performance of the bases Control Program surveillance requirement.
3.1 4-LA 3/4.1.1.3 Information modifying the required LCO 3.1.3 5.5.14 Bases actions.
Action A.1 Control Program bases N
' 'the "lX designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.
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Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS       DOC #               Description of CTS Requirement                     Document                 Control a
Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #
Section 3.1         5-LA       3/4.1.1.3 Action Statement a.3 required the               10CFR50.72           10CFR50.72 and preparation and submission of a special                         and               10CFR50.73 report to the NRC within 10 days if the MTC               10CFR50.73 is more positive than the beginning oflife limit.
Description of CTS Requirement Document Control Section a
3.1         1-R       3/4.1.2.1 Boration Systems Flow Paths -                       TRM               10CFR50.59 Shutdown 3.1         1-R       3/4.1.2.2 Boration Systems Flow Paths -                       TRM               10CFR50.59 Operating 3.I         l-R       3/4.1.2.3 Charging Pump - Shutdown                             TRM               10CFR50.59 31           1-R       3/4.1.2.4 Charging Pumps - Operating                           TRM               10CFR50.59 3.1         1-R       3/4.1.2.5 Borated Water Sources - Shutdown                     TRM               10CFR50.59 3.1         1-R       3/4.1.2.6 Borated Water Sources - Operating                   TRM               10CFR50.59 b           3.1         5-LA       3/4.1.3 l Action Statement d.2 specific                     LCO 3.1.4             5.5.14 Bases guidance as to how the rod alignment may be                 Action B.1         Control Program restored to within the limits.                                 bases 3.1         7-LA       3/4.1.3.1 Table 3.1-1 lists the accident                   LCO 3.1.4             5.5.14 Bases analyses that must be evaluated in CTS                   Action B.2.6         Control Program Action Statement d.3.a.                                       bases 3.1       2-LA       3/4.1.3.2 LCO and Actions descriptive details               LCO 3.1.7             5.5.14 Bases regarding the operability of the digital rod                   bases           Control Program position indication system.
3.1 5-LA 3/4.1.1.3 Action Statement a.3 required the 10CFR50.72 10CFR50.72 and preparation and submission of a special and 10CFR50.73 report to the NRC within 10 days if the MTC 10CFR50.73 is more positive than the beginning oflife limit.
3.1         1-R       3/4.1.3.3 Position Indication System -                         TRM               10CFR50.59 Shutdown 3.I       2-LA       3/4.1.3.4 LCO requirement specifying the rod               SR 3.1.4.3             5.5.14 Bases position in steps that corresponds to the fully               bases           Control Program withdrawn position and the associated asterisked note.
3.1 1-R 3/4.1.2.1 Boration Systems Flow Paths -
3.1         7-LA       4.1.3.4.b Surveillance Requirement specifies                   TRM               10CFR50.59 a post maintenance test requirement for rod drop time.
TRM 10CFR50.59 Shutdown 3.1 1-R 3/4.1.2.2 Boration Systems Flow Paths -
TRM 10CFR50.59 Operating 3.I l-R 3/4.1.2.3 Charging Pump - Shutdown TRM 10CFR50.59 31 1-R 3/4.1.2.4 Charging Pumps - Operating TRM 10CFR50.59 3.1 1-R 3/4.1.2.5 Borated Water Sources - Shutdown TRM 10CFR50.59 3.1 1-R 3/4.1.2.6 Borated Water Sources - Operating TRM 10CFR50.59 b
3.1 5-LA 3/4.1.3 l Action Statement d.2 specific LCO 3.1.4 5.5.14 Bases guidance as to how the rod alignment may be Action B.1 Control Program restored to within the limits.
bases 3.1 7-LA 3/4.1.3.1 Table 3.1-1 lists the accident LCO 3.1.4 5.5.14 Bases analyses that must be evaluated in CTS Action B.2.6 Control Program Action Statement d.3.a.
bases 3.1 2-LA 3/4.1.3.2 LCO and Actions descriptive details LCO 3.1.7 5.5.14 Bases regarding the operability of the digital rod bases Control Program position indication system.
3.1 1-R 3/4.1.3.3 Position Indication System -
TRM 10CFR50.59 Shutdown 3.I 2-LA 3/4.1.3.4 LCO requirement specifying the rod SR 3.1.4.3 5.5.14 Bases position in steps that corresponds to the fully bases Control Program withdrawn position and the associated asterisked note.
3.1 7-LA 4.1.3.4.b Surveillance Requirement specifies TRM 10CFR50.59 a post maintenance test requirement for rod drop time.
* The "1.A" designation indicates that part of a 13 is removed and the "R" designation indicates an entire TS is removed.
* The "1.A" designation indicates that part of a 13 is removed and the "R" designation indicates an entire TS is removed.
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Fc.rley Nuclear Plant ITS Conversion
Fc.rley Nuclear Plant ITS Conversion
(                                       Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS       DOC #               Description of CTS Requirement                     Document               Control a
(
Section 3.2 POWER DISTRIBUTION LIMITS 3.2         7-LA       4.2.2.2 Descriptive surveillance details.             LCO 3.2.1 SR           5.5.14 Bases and Action         Control Program bases 3.2         8-LA       4.2.2.2.d Fq(Z) relationships and specific                   COLR               5.6.5 COLR.
Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #
Description of CTS Requirement Document Control Section a
3.2 POWER DISTRIBUTION LIMITS 3.2 7-LA 4.2.2.2 Descriptive surveillance details.
LCO 3.2.1 SR 5.5.14 Bases and Action Control Program bases 3.2 8-LA 4.2.2.2.d Fq(Z) relationships and specific COLR 5.6.5 COLR.
values.
values.
3.2         9-LA       4.2.3.1 Descriptive material regarding how                 LCO 3.2.2           5.5.14 Bases this surveillance is performed (using movable               bases           Control Program incore detectors to obtain a power distribution map).
3.2 9-LA 4.2.3.1 Descriptive material regarding how LCO 3.2.2 5.5.14 Bases this surveillance is performed (using movable bases Control Program incore detectors to obtain a power distribution map).
32         I l-LA     4.2.3.2 Info nation to calculate the required             SR 3.2.2.1           5.5.14 Bases F% (4% measurement uncertainty)                             bases           Control Program 32         12-LA       4.2.4.2 Detail describing how the surveillance           SR 3.2.4.2           5.5.14 Bases O                                     may be met                                                   bases           Control Program U                                                         3.3 INSTRUMENTATION 3.3         2-LA       2.2.1 Safety Limit statement for the RTS                 LCO 3.3.1             5.5.14 Bases instrumentation operability details (interlock               bases           Control Program and setpoint setting requirements).
32 I l-LA 4.2.3.2 Info nation to calculate the required SR 3.2.2.1 5.5.14 Bases F% (4% measurement uncertainty) bases Control Program 32 12-LA 4.2.4.2 Detail describing how the surveillance SR 3.2.4.2 5.5.14 Bases O
3.3         5-LA       Table 2.2 1 Descriptive information                       LCO 3.3.1             5.5.14 Bases pertaining to various trip setpoints and                     bases           Control Program allowable values.
may be met bases Control Program U
3.3       15c-LA       4.3.1.3 Detailed explanation of the RTS                 SR 3.3.1.14           5.5.14 Bases Response Time Testing requirements.                         bases           Control Program 3.3       36-LA       Table 3.3-1 Function 12 A and B. Loss of                 LCO 3.3.1             5.5.14 Bases Flow trip, design description information.                   bases           Control Program 33-       44-LA       Table 3.3-1 Charmels To Trip colunm                     FSAR 7.2 and         10CFR50.59 and information desenbing the RTS design                     LCO 3.3.1             5.5.14 Bases features.                                                   bases           Control Program 33         83 LA       Table 4.3-1 Manual Reactor Trip function                 SR 3.3.1.12           5.5.14 Bases surveillance notes which provide test                       bases           Control Program
3.3 INSTRUMENTATION 3.3 2-LA 2.2.1 Safety Limit statement for the RTS LCO 3.3.1 5.5.14 Bases instrumentation operability details (interlock bases Control Program and setpoint setting requirements).
_g i                                     requirement details.
3.3 5-LA Table 2.2 1 Descriptive information LCO 3.3.1 5.5.14 Bases pertaining to various trip setpoints and bases Control Program allowable values.
          * 'Ihe "lA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
3.3 15c-LA 4.3.1.3 Detailed explanation of the RTS SR 3.3.1.14 5.5.14 Bases Response Time Testing requirements.
bases Control Program 3.3 36-LA Table 3.3-1 Function 12 A and B. Loss of LCO 3.3.1 5.5.14 Bases Flow trip, design description information.
bases Control Program 33-44-LA Table 3.3-1 Charmels To Trip colunm FSAR 7.2 and 10CFR50.59 and information desenbing the RTS design LCO 3.3.1 5.5.14 Bases features.
bases Control Program 33 83 LA Table 4.3-1 Manual Reactor Trip function SR 3.3.1.12 5.5.14 Bases surveillance notes which provide test bases Control Program
_g i
requirement details.
* 'Ihe "lA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
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Farley Nucicar Plant ITS Conversion O                                     Summary of CTS Requirements Removed From the TS V                                     and Placed in, or Currently Located in, Other Documents ITS         DOC #               Description of CTS Requirement                     Document                 Control a
Farley Nucicar Plant ITS Conversion O
Section 3.3       93 LA       Table 4.3-1 Note 9 applicable to the CFT for             SR 3.3.1.13           5.5.14 Bases the turbine trip RTS functions contains                     bases           Control Program descriptive detail regarding the performance of the required surveillance.
Summary of CTS Requirements Removed From the TS V
1 33         97-LA       Table 4.3-1 Note 8 modifying the CFT                     SR 3.3.1.11           5.5.14 Bases requirement for the RTS interlocks contains                 bases           Control Program     ,
and Placed in, or Currently Located in, Other Documents ITS DOC #
descriptive information applicable to the                                                       I required testing.
Description of CTS Requirement Document Control Section a
3.3       99-LA       Table 4.3-1 Surveillance Notes 14 and 15                 SR 3.3.1.4           5.5.14 Bases which describe the testing required by this                 bases           Control Program     ;
3.3 93 LA Table 4.3-1 Note 9 applicable to the CFT for SR 3.3.1.13 5.5.14 Bases the turbine trip RTS functions contains bases Control Program descriptive detail regarding the performance of the required surveillance.
CFT contain details of the undervoltage and shunt trip mechanism tests that are required for the RTDs-33         104-LA       Table 4.3-1 Note 13 assigned to the RTS                 SR 3.3.1.4             5.5.14 Bases reactor trip bypass breaker function contains               bases           Control Program D                                   specific information regarding what is tested
1 33 97-LA Table 4.3-1 Note 8 modifying the CFT SR 3.3.1.11 5.5.14 Bases requirement for the RTS interlocks contains bases Control Program descriptive information applicable to the I
(                                   on the bypass breakers (local manual shunt trip and local manual undervoltage trip).
required testing.
3.3       105-LA       Table 4.3-1 Note 1 I for the reactor trip               SR 3.3.1.12           5.5.14 Bases bypass breaker function contains a                           bases           Control Program desenpiion of the bypass breaker testing required.
3.3 99-LA Table 4.3-1 Surveillance Notes 14 and 15 SR 3.3.1.4 5.5.14 Bases which describe the testing required by this bases Control Program CFT contain details of the undervoltage and shunt trip mechanism tests that are required for the RTDs-33 104-LA Table 4.3-1 Note 13 assigned to the RTS SR 3.3.1.4 5.5.14 Bases reactor trip bypass breaker function contains bases Control Program D
3.3         2-LA       3/4.3.2 ESFA5 LCO statement operability                 LCO 3.3.2             5.5.14 Bases details (trip setpoint setting requirements).               bases           Control Program 3.3       4c LA       4.3.2.3 Detailed description of the Staggered           SR 3.3.2.9           5.5.14 Bases Test requirement for ESF Response Time                       bases           Control Program Testing.
specific information regarding what is tested
3.3         12-LA     Table 3.3 3 ESFAS Channels To Trip                       FSAR 7.3 and         10CFR50.59 and column descriptive design information.                   LCO 3.3.2             5.5.14 Bases     j bases           Control Program 3.3         29-LA       Table 3.3-3, ESFAS Function 6.b, details                 LCO 3.3.2             5.5.14 Bases describing the SG water level low-low                         bases           Control Program auxiliary feedwater initiation ftmedons.
(
on the bypass breakers (local manual shunt trip and local manual undervoltage trip).
3.3 105-LA Table 4.3-1 Note 1 I for the reactor trip SR 3.3.1.12 5.5.14 Bases bypass breaker function contains a bases Control Program desenpiion of the bypass breaker testing required.
3.3 2-LA 3/4.3.2 ESFA5 LCO statement operability LCO 3.3.2 5.5.14 Bases details (trip setpoint setting requirements).
bases Control Program 3.3 4c LA 4.3.2.3 Detailed description of the Staggered SR 3.3.2.9 5.5.14 Bases Test requirement for ESF Response Time bases Control Program Testing.
3.3 12-LA Table 3.3 3 ESFAS Channels To Trip FSAR 7.3 and 10CFR50.59 and column descriptive design information.
LCO 3.3.2 5.5.14 Bases j
bases Control Program 3.3 29-LA Table 3.3-3, ESFAS Function 6.b, details LCO 3.3.2 5.5.14 Bases describing the SG water level low-low bases Control Program auxiliary feedwater initiation ftmedons.
O
O
* 1he "lA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
* 1he "lA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
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Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, O'.her Documents N
Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, O'.her Documents N
ITS     DOC #                                                   Description of CTS Requirement Document                           Control Section         a                                                                           .'
ITS DOC #
Description of CTS Requirement Document Control Section a
I l
I l
3.3     33-LA         Table 3.3-3, ESFAS Functions 6.d and 6.e,                               l.C O 3.3.2                     5.5.14 Bases auxiliary feedwater auto start on Si and trip                             bases                     Control Program of main feedwater pump functions descriptive j
3.3 33-LA Table 3.3-3, ESFAS Functions 6.d and 6.e, l.C O 3.3.2 5.5.14 Bases auxiliary feedwater auto start on Si and trip bases Control Program of main feedwater pump functions descriptive j
information regarding the specific auxiliary i                                                          feedwater pumps that are started.
information regarding the specific auxiliary feedwater pumps that are started.
l                                   3.3     67-LA           Table 3.3-1 SG water level high high turbine                           LCO 3.3.2                       5.5.14 Bases trip feedwater isolation function setpoint                                 bases                     Control Program l                                                           descriptive detail regarding the narrow range instrument span on each SG.                                                                                             !
i l
33     68 LA           Table 3.3-4 SG water level low low auxiliary                           LCO 3.3.2                       5.5.14 Bases     l feedwater pump start function setpoint                                     bases                     Control Program     j descriptive detail regarding the narrow range instrument span on each SG.
3.3 67-LA Table 3.3-1 SG water level high high turbine LCO 3.3.2 5.5.14 Bases trip feedwater isolation function setpoint bases Control Program l
3.3     70-LA           Table 3.3-4
descriptive detail regarding the narrow range instrument span on each SG.
* footnote to the CTS loss of                               LCO 3.3.5,                     5.5.14 Bases     l power (LOP) functions which references the                                 LOP                       Control Program appropriate relay setting sheet for additional                         Instruments.
33 68 LA Table 3.3-4 SG water level low low auxiliary LCO 3.3.2 5.5.14 Bases l
                      .I                                                                                                             channel calibration requirements calibration l                                                                                                                                 surveillance bases 3.3     87 LA         Table 4.3-2 Note 6 modifying the muthly                                   SR 3.3.2.2                     5.5.14 Bases l                                                           ESFAS CFT for the auxiliary feedwater                                     bases                     Control Program
feedwater pump start function setpoint bases Control Program j
!'                                                          automatic actuation logic function provides an exception to the requirement to perform actuation logic testing on the trip of all main feedwater pumps function.
descriptive detail regarding the narrow range instrument span on each SG.
33     94-LA         Table 4 3-2 Note I requirement .a perform                                 SR 3.3.2.6                     5.5.14 Bases manual actuation surveillances during                                     bases                     Control Program shutdowns.
3.3 70-LA Table 3.3-4
3.3     96-LA         Table 4.3-2 Note 4 detailed description of                               SR 3.3.5.1                     5.5.14 Bases functional test surveillance requirements.                                 bases                     Control Program l
* footnote to the CTS loss of LCO 3.3.5, 5.5.14 Bases l
power (LOP) functions which references the LOP Control Program appropriate relay setting sheet for additional Instruments.
.I calibration requirements channel calibration l
surveillance bases 3.3 87 LA Table 4.3-2 Note 6 modifying the muthly SR 3.3.2.2 5.5.14 Bases l
ESFAS CFT for the auxiliary feedwater bases Control Program automatic actuation logic function provides an exception to the requirement to perform actuation logic testing on the trip of all main feedwater pumps function.
33 94-LA Table 4 3-2 Note I requirement.a perform SR 3.3.2.6 5.5.14 Bases manual actuation surveillances during bases Control Program shutdowns.
3.3 96-LA Table 4.3-2 Note 4 detailed description of SR 3.3.5.1 5.5.14 Bases functional test surveillance requirements.
bases Control Program l
v
v
* The "LA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
* The "LA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
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Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents
Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #
!                                  ITS                         DOC #                                           Description of CTS Requirement       Document         Control a
Description of CTS Requirement Document Control Section a
Section 3.3                             5-LA                             3/4.3.3.1 Actions "a" and "b" for Radiation       TRM         10CFR50.59 l                                                                                                   Monitors that are removed from the TS (fuel storage pool area monitor R5 (CTS Taule 3.3-6 item 1.a) and the noble gas efflucci monitors, R-29B, R60A-C, R60D, RISB&C, (CTS Table 3.3-6 items 2 d.i-iv).
3.3 5-LA 3/4.3.3.1 Actions "a" and "b" for Radiation TRM 10CFR50.59 l
3.3                           9-LA                             3/4.3.3.1 Radiation Monitor requirements for       TRM         10CFR50.59 l                                                                                                   the Fuel storage pool area monitor R5 (CTS l                                                                                                   Table 3.3-6 item 1.a) and the noble gas effluent monitors R-298, R60A-C, R60D, i                                                                                                   RISB&C, (CTS Table 3.3-6 items 2.d.i-iv) including setpoints, applicable Modes,                                               ,
Monitors that are removed from the TS (fuel storage pool area monitor R5 (CTS Taule 3.3-6 item 1.a) and the noble gas efflucci monitors, R-29B, R60A-C, R60D, RISB&C, (CTS Table 3.3-6 items 2 d.i-iv).
minimum charmel requirements, measurement                                           l l                                                                                                   range, Actions, and surveillance requirements.
3.3 9-LA 3/4.3.3.1 Radiation Monitor requirements for TRM 10CFR50.59 l
33                           22-LA                               3/4.3.3 i Action 27a applicable to the noble       TRM         10CFR50.59 gas efiluent momtors R298, R60A, B, C. &
the Fuel storage pool area monitor R5 (CTS l
R60D, RISB&C (CTS Table 3.3-6 items 2.d.i-iv).                                                                           !
Table 3.3-6 item 1.a) and the noble gas effluent monitors R-298, R60A-C, R60D, i
3.3                                 1-R                           3/4.3.3.2 Movable incore Detectors                 TRM         10CFR50.59           i 3.3                               l-R                           3/4.3.3.7 liigh Energy Line Break Isolation       TRM         10CFR50.59           :
RISB&C, (CTS Table 3.3-6 items 2.d.i-iv) including setpoints, applicable Modes, minimum charmel requirements, measurement l
Sensors                                                                             I 3.3                           20 LA                               3/4.3.3.8 # footnote to the reactor vessel level LCO 3.3.3     5.5.14 Bases indicating system on Table 3.3.-l 1 describes     bases     Control Program a channel oflevel indication and defines what is required for an operable channel.                                                 i 33                           30 LA                               4.6.4.1 Surveillance details regarding the       SR 3.3.3.2   5.5.14 Bases makeup of the sample gases used for               bases     Control Program calibration of the hydrogen analyzers.
l range, Actions, and surveillance requirements.
33                               1-LA                             3/4.3 3.1l Waste Gas Monitoring                   TRM       5.5.12 Explosive Instrumentation which contains requirements                       Gas and for instrumentation to monitor oxygen and                     Radioactivity hydrogen gas content in the waste gas system.                   Monitoring Program and 10CFR50.59 k
33 22-LA 3/4.3.3 i Action 27a applicable to the noble TRM 10CFR50.59 gas efiluent momtors R298, R60A, B, C. &
R60D, RISB&C (CTS Table 3.3-6 items 2.d.i-iv).
3.3 1-R 3/4.3.3.2 Movable incore Detectors TRM 10CFR50.59 i
3.3 l-R 3/4.3.3.7 liigh Energy Line Break Isolation TRM 10CFR50.59 Sensors I
3.3 20 LA 3/4.3.3.8 # footnote to the reactor vessel level LCO 3.3.3 5.5.14 Bases indicating system on Table 3.3.-l 1 describes bases Control Program a channel oflevel indication and defines what is required for an operable channel.
i 33 30 LA 4.6.4.1 Surveillance details regarding the SR 3.3.3.2 5.5.14 Bases makeup of the sample gases used for bases Control Program calibration of the hydrogen analyzers.
33 1-LA 3/4.3 3.1l Waste Gas Monitoring TRM 5.5.12 Explosive Instrumentation which contains requirements Gas and for instrumentation to monitor oxygen and Radioactivity hydrogen gas content in the waste gas system.
Monitoring Program and 10CFR50.59 k
* 1hc "1X designauon mdicates that pan of a 'l S is removed and the "R" designation indicates an entire TS is removed.
* 1hc "1X designauon mdicates that pan of a 'l S is removed and the "R" designation indicates an entire TS is removed.
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Section 3.3           1-R       3/4.3.4 Turbine Overspeed Protection                         TRM               10CFR50.59 3.4 REACTOR COOLANT SYSTEM (RCS) 34         10-LA       Table 3.2-1 *** footnote contains the                     LCO 3.4.1           5.5.14 Bases measurement uncertainties associated with the                 bases           Control Program calculations used to determine the minimum RCS flow specified in the TS.
Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #
34           3-LA       3/4.1.1.4 Applicability
Description of CTS Requirement Document Control Section a
* footnote referencing           LCO 3.4.2             5.5.14 Bases special test exception 310 3                                 bases           Control Program 3.4         5-LA       4.4.1.1 The surveillance requirement to verify           SR 3.4.4.1           5.5.14 Bases the circulation of reactor coolant in order to               bases           Control Program verify an operable RCS loop.
3.3 1-R 3/4.3.4 Turbine Overspeed Protection TRM 10CFR50.59 3.4 REACTOR COOLANT SYSTEM (RCS) 34 10-LA Table 3.2-1 *** footnote contains the LCO 3.4.1 5.5.14 Bases measurement uncertainties associated with the bases Control Program calculations used to determine the minimum RCS flow specified in the TS.
3.4         2-LA       3.4.1.2 Descriptive list of RCS loops in the             LCO 3.4.5             5.5.14 Bases LCO statement.                                               bases           Control Program 3.4         3-LA       3.4.1.2 Action statement b specific actions               LCO 3.4.5           5.5.14 Bases regarding how to de-energize the control rod                 bases           Control Program drive mechanisms (open the reactor trip breakers or shut down the rod drive motor / generator sets) 34           7 LA       4.4.1.2.2 and 4 4.1.2.3 Surveillance details             LCO 3.4.5             5.5.14 Bases "and circulating reactor coolant" and "shall                 bases           Control Program be determined operable" 3.4         2-LA       3/4.4.1.3 LCO list describing the RCS and                 LCO 3.4.6             5.5.14 Bases RHR loops available to meet the LCO                         bases           Control Program requirement.
34 3-LA 3/4.1.1.4 Applicability
3.4         7-LA       4.4.1.3.2 and 4.4.1.3.3 Surveillance details             LCO 3.4.6           5.5.14 Bases "and circulating reactor coolant" and "shall                 bases           Control Program be determined operable" 3.4         4 LA       4.4.1.4 Surveillance detc.ils "and circulating         LCO 3.4.7 and         5.5.14 Bases reactor coolant"                                         LCO 3.4.8         Control Program bases 3.4           1-R       3/4.4.2 Safety Valves Shutdown                               TRM               10CFR50.59
* footnote referencing LCO 3.4.2 5.5.14 Bases special test exception 310 3 bases Control Program 3.4 5-LA 4.4.1.1 The surveillance requirement to verify SR 3.4.4.1 5.5.14 Bases the circulation of reactor coolant in order to bases Control Program verify an operable RCS loop.
3.4 2-LA 3.4.1.2 Descriptive list of RCS loops in the LCO 3.4.5 5.5.14 Bases LCO statement.
bases Control Program 3.4 3-LA 3.4.1.2 Action statement b specific actions LCO 3.4.5 5.5.14 Bases regarding how to de-energize the control rod bases Control Program drive mechanisms (open the reactor trip breakers or shut down the rod drive motor / generator sets) 34 7 LA 4.4.1.2.2 and 4 4.1.2.3 Surveillance details LCO 3.4.5 5.5.14 Bases "and circulating reactor coolant" and "shall bases Control Program be determined operable" 3.4 2-LA 3/4.4.1.3 LCO list describing the RCS and LCO 3.4.6 5.5.14 Bases RHR loops available to meet the LCO bases Control Program requirement.
3.4 7-LA 4.4.1.3.2 and 4.4.1.3.3 Surveillance details LCO 3.4.6 5.5.14 Bases "and circulating reactor coolant" and "shall bases Control Program be determined operable" 3.4 4 LA 4.4.1.4 Surveillance detc.ils "and circulating LCO 3.4.7 and 5.5.14 Bases reactor coolant" LCO 3.4.8 Control Program bases 3.4 1-R 3/4.4.2 Safety Valves Shutdown TRM 10CFR50.59
's
's
        * 'the "l.A" designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.
* 'the "l.A" designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.
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Farley Nuclear Plant ITS Conversion 4
q                                       Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents U
q Summary of CTS Requirements Removed From the TS U
ITS       DOC #               Description of CTS Requirement                     Document               Control a
and Placed in, or Currently Located in, Other Documents ITS DOC #
Section 3.4         5-LA       3/4.4.3
Description of CTS Requirement Document Control Section a
* footnote specifying that the lift               LCO 3.4.10             5.5.14 Bases setting pressure shall correspond to ambient                   bases           Control Program conditions of the valve at nominal operating temperature and pressure.
3.4 5-LA 3/4.4.3
3.4         4-LA       4.4.4.2 and 4.4.4.3 Details regarding how the               LCO 3.4.9           5.5.14 Bases surveillance requirements are to be met.                       bases           Control Program 34         2-LA       4.4.6.0 Reference to the requirements of                     10 CFR             10 CFR 50.55a Specification 4.0 $ (Inservice Inspection                     50.55a Program) 3.4         1-LA       3.4.7.1 LCO statement details (the radiation             LCO 3.4.15             5.5.14 Bases monitor instrument designations R-11 and R-                   bases           Control Program 12).
* footnote specifying that the lift LCO 3.4.10 5.5.14 Bases setting pressure shall correspond to ambient bases Control Program conditions of the valve at nominal operating temperature and pressure.
3.4         14-LA       Table 3.4-1 Containing a list of the RCS                     TRM               10CFR50.59 PlVs.
3.4 4-LA 4.4.4.2 and 4.4.4.3 Details regarding how the LCO 3.4.9 5.5.14 Bases surveillance requirements are to be met.
O V            3.4         15 LA       4.4.7.2.2 References to the requirements of Specification 4.0.5 (Inservice inspection 10 CFR 50.55a 10 CFR 50.55a Program).
bases Control Program 34 2-LA 4.4.6.0 Reference to the requirements of 10 CFR 10 CFR 50.55a Specification 4.0 $ (Inservice Inspection 50.55a Program) 3.4 1-LA 3.4.7.1 LCO statement details (the radiation LCO 3.4.15 5.5.14 Bases monitor instrument designations R-11 and R-bases Control Program 12).
3.4         19-LA       4.4.7.2.2.b Requirement for post maintenance                 TRM               10CFR50.59 testing on RCS PlVs.
3.4 14-LA Table 3.4-1 Containing a list of the RCS TRM 10CFR50.59 PlVs.
3.4         26-LA       4.4.7.2.2 # footnote with specific procedural             SR 3.4.14.1           5.5.14 Bases guidance for performing the RCS PlV                           bases           Control Program leakage measurement surveillance.
OV 3.4 15 LA 4.4.7.2.2 References to the requirements of 10 CFR 10 CFR 50.55a Specification 4.0.5 (Inservice inspection 50.55a Program).
34           1R       3/4.4 8 Chemistry                                             TRM               10CFR50.59 3.4         1-LA       3/4.4.10 LCO statement exception to the                   LCO 3.4.3             5.5.14 Bases pressurizer, and descriptive information                     bases           Control Program concerning the applicability in the LCO statement.
3.4 19-LA 4.4.7.2.2.b Requirement for post maintenance TRM 10CFR50.59 testing on RCS PlVs.
3.4         4-LA       3/4.4.10 Action statement description of the               LCO 3.4.3             5.5.14 Bases required engineering evaluation.                             bases           Control Program O
3.4 26-LA 4.4.7.2.2 # footnote with specific procedural SR 3.4.14.1 5.5.14 Bases guidance for performing the RCS PlV bases Control Program leakage measurement surveillance.
U        '
34 1R 3/4.4 8 Chemistry TRM 10CFR50.59 3.4 1-LA 3/4.4.10 LCO statement exception to the LCO 3.4.3 5.5.14 Bases pressurizer, and descriptive information bases Control Program concerning the applicability in the LCO statement.
1he "lA" designation indicates llun part of a TS is removed and the "R" designation indicates an entire TS is removed.
3.4 4-LA 3/4.4.10 Action statement description of the LCO 3.4.3 5.5.14 Bases required engineering evaluation.
bases Control Program OU 1he "lA" designation indicates llun part of a TS is removed and the "R" designation indicates an entire TS is removed.
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Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS       DOC #               Description of CTS Requirement                     Document               Control a
Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #
Section 3.4         6-LA       4.4.10.1.2 Requires reactor vessel material               10CFR50,               10CFR50, surveillance specimens to be removed and                 Appendix 11           Appendix 11 cxamined to determine changes in material propenies as required by 10CFR50, Appendix 11, 3.4           1-R       3/4.4.10.2 Pressurizer                                       TRM               10CFR50.59 3.4         8-LA       4.4.10.3.1.a - Specific RiiR relief valve ID             SR 3.4.12.3           5.5.14 Bases numbers.                                                     bases           Control Program 3.4         12-LA       4.1.2.3.2 (from the Reactivity Control                   SR 3.4.12.1           5.5.14 Bases Systems Chapter) Contains specific means by                 bases           Control Program which a charging pump is rendered incapable ofinjecting into the RCS (motor circuit breakers are removed from their electrical power supply circuits).
Description of CTS Requirement Document Control Section a
3.4 6-LA 4.4.10.1.2 Requires reactor vessel material
: 10CFR50, 10CFR50, surveillance specimens to be removed and Appendix 11 Appendix 11 cxamined to determine changes in material propenies as required by 10CFR50, Appendix 11, 3.4 1-R 3/4.4.10.2 Pressurizer TRM 10CFR50.59 3.4 8-LA 4.4.10.3.1.a - Specific RiiR relief valve ID SR 3.4.12.3 5.5.14 Bases numbers.
bases Control Program 3.4 12-LA 4.1.2.3.2 (from the Reactivity Control SR 3.4.12.1 5.5.14 Bases Systems Chapter) Contains specific means by bases Control Program which a charging pump is rendered incapable ofinjecting into the RCS (motor circuit breakers are removed from their electrical power supply circuits).
(
(
3.4         1-LA       3/4.4.11 Structural Integrity LCO, Actions, Applicability, and surveillance requirements 10CFR 50.55a (ISI) and 10CFR 50.55a (ISI) and 5.5.8 for ASME Code Class I,2, and 3                           5.5.8 (IST)               (IST) components to be maintained in accordance                                                       ,
3.4 1-LA 3/4.4.11 Structural Integrity LCO, Actions, 10CFR 50.55a 10CFR 50.55a Applicability, and surveillance requirements (ISI) and (ISI) and 5.5.8 for ASME Code Class I,2, and 3 5.5.8 (IST)
l with the Insersice Test and Inspection Programs.
(IST) components to be maintained in accordance with the Insersice Test and Inspection Programs.
1 3.4           l-R       3/4.4.12 Reactor Vesselliead Vents                           TRM               10CFR50.59 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3.5         8 LA       4.5.1.1.b Explanation regarding the RWST                   SR 3.5.1.4           5.5.14 Bases boron concentration being within the                         bases           Control Program accumulator boron concentration limits.
1 3.4 l-R 3/4.4.12 Reactor Vesselliead Vents TRM 10CFR50.59 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3.5 8 LA 4.5.1.1.b Explanation regarding the RWST SR 3.5.1.4 5.5.14 Bases boron concentration being within the bases Control Program accumulator boron concentration limits.
3.5       10-LA       4.5.1.1.c Specific details of how power is                 SR 3.5.1.5           5.5.14 Bases removed from valve operators.                                 bases           Control Program 35         2-LA       3.5 2 LCO statement containing descriptive                 LCO 3.5.2           5.5.14 Bases information regarding the operability                         bases           Control Program requirements for the ECCS subsystems.
3.5 10-LA 4.5.1.1.c Specific details of how power is SR 3.5.1.5 5.5.14 Bases removed from valve operators.
3.5         5 LA       3/4.5.2 Action statement "b" for reporting               10CFR50.73               10CFR ECCS actuations is effectively addressed by               (a)(2)(iv)         50.73(a)(2)(iv)
bases Control Program 35 2-LA 3.5 2 LCO statement containing descriptive LCO 3.5.2 5.5.14 Bases information regarding the operability bases Control Program requirements for the ECCS subsystems.
O                                   existing regulations.
3.5 5 LA 3/4.5.2 Action statement "b" for reporting 10CFR50.73 10CFR ECCS actuations is effectively addressed by (a)(2)(iv) 50.73(a)(2)(iv)
O existing regulations.
* The "tA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
* The "tA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
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Summary of CTS Requirements Removed From the TS
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Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS       DOC #               Description of CTS Requirement                       Document                 Control a
and Placed in, or Currently Located in, Other Documents ITS DOC #
Section 3.5       6 LA       4.5.2.a - Surveillance requirement detail                   SR 3.5.2.1           5.5.14 Bases regarding how power is removed from the                         bases           Control Program valves (locked open disconnect device).
Description of CTS Requirement Document Control Section a
3.5         7 LA       4.5.2.c Surveillance requirement for a visual                 TRM               10CFR50.59 inspection of containment prior to establishing containment integrity and after each containment entry.
3.5 6 LA 4.5.2.a - Surveillance requirement detail SR 3.5.2.1 5.5.14 Bases regarding how power is removed from the bases Control Program valves (locked open disconnect device).
3.5       10-LA       4.5.2.e.1 Surveillance requirement to verify                   TRM               10CFR50.59 the ECCS throttle valves mechanical position stop after each valve stroke and maintenance.
3.5 7 LA 4.5.2.c Surveillance requirement for a visual TRM 10CFR50.59 inspection of containment prior to establishing containment integrity and after each containment entry.
3.5       12-LA       4.5.2.f.I and 2 Surveillance details "during               LCO 3.5.2             5.5.14 Bases     j shutdown", the specific actuating signal (SI),             surveillance         Control Program     j 1
3.5 10-LA 4.5.2.e.1 Surveillance requirement to verify TRM 10CFR50.59 the ECCS throttle valves mechanical position stop after each valve stroke and maintenance.
and the specific pumps involved in the testing.               bases 3.5         14-LA       4.5.2.g.1 and 2 Specific requirements                       SR 3.5.2.3           5.5.14 Bases regarding pump testing on recirculation flow                   bases           Control Program ON                                   and die required psid values.
3.5 12-LA 4.5.2.f.I and 2 Surveillance details "during LCO 3.5.2 5.5.14 Bases j
35         15 LA       4.5 2 h Post valve stroke surveillance                     SR 3.5.2.6           5.5.14 Bases requirement and details regarding the                       bases and         Control Program mechamcal stop position verification for the                   TRM             and 10CFR50.59 RHR valves.
shutdown", the specific actuating signal (SI),
3.5       16-LA       4.5.2.i Post maintenance ECCS flow balance                   TRM and           10CFR50.59 and     j test requirement after any modifications that               LCO 3.5.2             5.5.14 Bases alter the subsystem flow characteristics and                   bases           Control Program associated required flows.
surveillance Control Program j
35         2-LA       3.5.3 LCO statement containing descriptive                 LCO 3.5.2             5.5.14 Bases information regarding the operability                         bases           Control Program requirements for the ECCS subsystems.
and the specific pumps involved in the testing.
3.5         4-LA       3/4.5.3 Action "a" description of the charging             LCO 3.5.2             5.5.14 Bases subsystem (pump and flow path).                               bases           Control Program 3.5         7-LA       3/4.5.3 Action "b" description of the charging             LCO 3.5.2             5.5.14 Bases subsystem (pump and heat exchanger),                           bases           Control Program i
bases 1
O       '
3.5 14-LA 4.5.2.g.1 and 2 Specific requirements SR 3.5.2.3 5.5.14 Bases regarding pump testing on recirculation flow bases Control Program ON and die required psid values.
The "1.A" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
35 15 LA 4.5 2 h Post valve stroke surveillance SR 3.5.2.6 5.5.14 Bases requirement and details regarding the bases and Control Program mechamcal stop position verification for the TRM and 10CFR50.59 RHR valves.
A6-10                                                                 j i
3.5 16-LA 4.5.2.i Post maintenance ECCS flow balance TRM and 10CFR50.59 and j
l
test requirement after any modifications that LCO 3.5.2 5.5.14 Bases alter the subsystem flow characteristics and bases Control Program associated required flows.
35 2-LA 3.5.3 LCO statement containing descriptive LCO 3.5.2 5.5.14 Bases information regarding the operability bases Control Program requirements for the ECCS subsystems.
3.5 4-LA 3/4.5.3 Action "a" description of the charging LCO 3.5.2 5.5.14 Bases subsystem (pump and flow path).
bases Control Program 3.5 7-LA 3/4.5.3 Action "b" description of the charging LCO 3.5.2 5.5.14 Bases subsystem (pump and heat exchanger),
bases Control Program i
O The "1.A" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
A6-10 j
i l


a J
a J
4   +
4
Farley Nuclear Plant ITS Conversion p                                     Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents Q
+
ITS         DOC #               Description of CTS Requirement                     Document                 Control a
Farley Nuclear Plant ITS Conversion p
Section                                                                                                                      j 3.5         8-LA       3/4.5.3 Action "b" description of maintaining             LCO 3.5.3             5.5.14 Bases the RCS Tavg < 350 F by the use of                       Action bases         Control Program alternate heat removal methods.
Summary of CTS Requirements Removed From the TS Q
3.5         10-LA       3/4.5.3 Action statement "c" for reporting               10CFR50.73           10CFR50.73 (a)
and Placed in, or Currently Located in, Other Documents ITS DOC #
ECCS actuations is effectively addressed by               (a)(2)(iv)               (2)(iv) existing regulations.
Description of CTS Requirement Document Control j
35         12-LA       4.5 3.2 Surveillance requirement detail                   SR 3.5.3.2           5.5.14 Bases regardmg how power is removed from the                       bases           Control Program valves (locked open disconnect device).
Section a
3.5         l-LA       3/4.5.6 LCO statement details describing                   LCO 3.5.6             5.5.14 Bases recirculation pH control system operability,                 bases           Control Program 3.5         1-LA       3.4.7.2.e, The details of the LCO for RCS                 LCO 3.5.5             5.5.14 Bases Operational leakage, and associated                           bases           Control Program surveillance 4.4.7.2. l .c are moved into the STS LCO 3.5.5, Seal injection Flow, SR O                                   3.5.5.1, and the associated bases.
3.5 8-LA 3/4.5.3 Action "b" description of maintaining LCO 3.5.3 5.5.14 Bases the RCS Tavg < 350 F by the use of Action bases Control Program alternate heat removal methods.
3.6 CONTAINMENT SYSTEMS 3.6         6-LA       3/4.6.1
3.5 10-LA 3/4.5.3 Action statement "c" for reporting 10CFR50.73 10CFR50.73 (a)
* footnote requirement to verify the               LCO 3.6.1             5.5.14 Bases status of the equipment hatch.                               bases           Control Program 3.6         9 LA       SR 3.6.1.2 Requires that containment                     Containment         5.5.6 Pre-stressed structural integrity be venfied in accordance               Tendon                 Concrete with the Containment Tendon Surveillance                 Surveillance           Containment Program.                                                   Program                 Tendon Surveillance Program 3.6         1-LA       3.6.1.3 LCO statement descriptive text                     LCO 3.6.2             5.5.14 Bases regarding the status of the airlock doors and                 bases           Control Program the exception to allow entry and exit through the air lock.
ECCS actuations is effectively addressed by (a)(2)(iv)
3.6         2-LA       4.6.1.5.I Desenptive details regarding the                 LCO 3.6.2             5.5.14 Bases average air temperature required to be                       bases           Control Program venfied in 4.6.15.2.
(2)(iv) existing regulations.
b o        ' The "lA" designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.
35 12-LA 4.5 3.2 Surveillance requirement detail SR 3.5.3.2 5.5.14 Bases regardmg how power is removed from the bases Control Program valves (locked open disconnect device).
3.5 l-LA 3/4.5.6 LCO statement details describing LCO 3.5.6 5.5.14 Bases recirculation pH control system operability, bases Control Program 3.5 1-LA 3.4.7.2.e, The details of the LCO for RCS LCO 3.5.5 5.5.14 Bases Operational leakage, and associated bases Control Program surveillance 4.4.7.2. l.c are moved into the STS LCO 3.5.5, Seal injection Flow, SR O
3.5.5.1, and the associated bases.
3.6 CONTAINMENT SYSTEMS 3.6 6-LA 3/4.6.1
* footnote requirement to verify the LCO 3.6.1 5.5.14 Bases status of the equipment hatch.
bases Control Program 3.6 9 LA SR 3.6.1.2 Requires that containment Containment 5.5.6 Pre-stressed structural integrity be venfied in accordance Tendon Concrete with the Containment Tendon Surveillance Surveillance Containment Program.
Program Tendon Surveillance Program 3.6 1-LA 3.6.1.3 LCO statement descriptive text LCO 3.6.2 5.5.14 Bases regarding the status of the airlock doors and bases Control Program the exception to allow entry and exit through the air lock.
3.6 2-LA 4.6.1.5.I Desenptive details regarding the LCO 3.6.2 5.5.14 Bases average air temperature required to be bases Control Program venfied in 4.6.15.2.
bo The "lA" designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.
A6-l l
A6-l l


Farley Nuclear Plant ITS Conversion 4
Farley Nuclear Plant ITS Conversion 4
Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents
Summary of CTS Requirements Removed From the TS
(
(
ITS       DOC #               Description of CTS Requirement                     Document                 Control Section 3.6         1-LA       3/4.6.1,6 LCO, Applicabihty, Actions, and               Containment         5.5.6 Pre-stressed surveillance requirements.                                 Tendon               Concrete Surveillance           Containment Program               Tendon Surveillance Program 3.6       3-LA       3/4.6.1.7.b LCO provision regarding the 8                 LCO 3.6.3             5.5.14 Bases inch mini-purge supply and exhaust isolation                 bases           Control Program valves.
and Placed in, or Currently Located in, Other Documents ITS DOC #
3.6       9 LA       3/4.6.1.7
Description of CTS Requirement Document Control Section 3.6 1-LA 3/4.6.1,6 LCO, Applicabihty, Actions, and Containment 5.5.6 Pre-stressed surveillance requirements.
* footnote to LCO which describes               LCO 3.6.3             5.5.14 Bases the applicability of the LCO to the 48 inch                 bases           Control Program purge and exhaust valves and purge and exhaust leakage.
Tendon Concrete Surveillance Containment Program Tendon Surveillance Program 3.6 3-LA 3/4.6.1.7.b LCO provision regarding the 8 LCO 3.6.3 5.5.14 Bases inch mini-purge supply and exhaust isolation bases Control Program valves.
3.6       10-LA       3/4.6.1.7 Action "c" and associated                         TRM               10CFR50.59 surveillance (4.6.1.7.3.b) for containment purge supply or exhaust leakage in excess of G                                     0.05 la for each valve.
3.6 9 LA 3/4.6.1.7
36         15-LA       4.6.1.7.4 Requirements for replacing resilient               TRM               10CFR50.59 seals in containment purge and exhaust valves and requirement to compare current leakage with previous leakage to detect excess valve degradation.
* footnote to LCO which describes LCO 3.6.3 5.5.14 Bases the applicability of the LCO to the 48 inch bases Control Program purge and exhaust valves and purge and exhaust leakage.
3.6       2-LA       3/4.6.2.1 Operability description in the LCO             LCO 3.6.6             5.5.14 Bases statement,                                                   bases           Control Program 3.6       5 LA       4.6.2.1.b Surveillance details regarding the             SR 3.6.6.4           5.5.14 Bases method of testing and required discharge                     bases           Control Program pressure.
3.6 10-LA 3/4.6.1.7 Action "c" and associated TRM 10CFR50.59 surveillance (4.6.1.7.3.b) for containment purge supply or exhaust leakage in excess of G
36         8-LA       4 6 2.1.c and d Surveillance details regarding         LCO 3.6.6 SR           5.5.14 Bases the specific actuation signal and specific                   bases           Control Program method for venfying each containment spray nozzle is unobstructed.
0.05 la for each valve.
3.6       2-LA       3/4.6.2.3 LCO statement describing the                   LCO 3.6.6             5.5.14 Bases number of fans in each group                                 bases           Control Program O
36 15-LA 4.6.1.7.4 Requirements for replacing resilient TRM 10CFR50.59 seals in containment purge and exhaust valves and requirement to compare current leakage with previous leakage to detect excess valve degradation.
U
3.6 2-LA 3/4.6.2.1 Operability description in the LCO LCO 3.6.6 5.5.14 Bases statement, bases Control Program 3.6 5 LA 4.6.2.1.b Surveillance details regarding the SR 3.6.6.4 5.5.14 Bases method of testing and required discharge bases Control Program pressure.
36 8-LA 4 6 2.1.c and d Surveillance details regarding LCO 3.6.6 SR 5.5.14 Bases the specific actuation signal and specific bases Control Program method for venfying each containment spray nozzle is unobstructed.
3.6 2-LA 3/4.6.2.3 LCO statement describing the LCO 3.6.6 5.5.14 Bases number of fans in each group bases Control Program OU
* The "lX designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed A6-12
* The "lX designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed A6-12
* Farley Nuclear Plant ITS Conversion A                                    Summary of CTS Requirements Removed From the TS Q                                  and Placed in, or Currently Located in, Other Documents Document                Control ITS        DOC #            Description of CTS Requirement a
Section 36        6-LA      4.6.2.3.a. and b Surveillance details regarding    LCO 3.6.6 SR          5.5.14 Bases where each fan group is started and the                  bases          Control Program specific automatic actuation signal.
3.6        1-LA      3/4.6.3 List of containment isolation valves in          TRM              10CFR50.59 Table 3.6 1.
3.6      11 LA      4.6.3.1 Post maintenance testing requirements            TRM              10CFR50.59 for containment isolation valves.
36        13 LA    4.6 3.2.a and b Surveillance details regarding      SR 3 6.3.6            5.5.14 Baues the specific actuation signal tested                    bases          Control Program 3.6        19-LA    Table 3.6-1 " footnote regarding                    SR 3.6.3.2            5.5.14 Bases containment isolation valves which may be                bases          Control Program open with the power removed for overpressure protection requirements.
3.6        4 LA      4.6.4.2.b.1 Channel calibration requirement              TRM              10CFR50.59 Q                                  for the hydrogen recombiners.
36        5 LA      4.6.4.2.a and 4.6.4.2.b 2 and 3 Surveillance        LCO 3.6.7 SR          5.5.14 Bases details desenbmg specific requirements for              bases          Control Program hydrogen recombiner testing.
3.6        4-LA      4.6.4.3.a.1 Surveillance details regarding            SR 3.6.9.1          5.5.14 Bases where the hydrogen dilution system is started.          bases          Control Program 3.6        5-LA      4.6.4.4.a - Surveillance details regarding            SR 3.6.8.1          5.5.14 Bases where the systens is started (control room).            bases          Control Program 3.7 PLANT SYSTEMS 3,7        9 LA      Table 3.7-3 Main Steam Safety Valve orifice          LCO 3.7.1            5.5.14 Bases size.                                                    bases          Control Program 3.7        10-LA    Table 3.7-3
* footnote regarding the                  SR 3.7.1.1          5.5.14 Bases requirement for ambient conditions for the lift          bases          Control Program  ;
setting pressure of the main steam safety valves.
.                3.7        2 LA      3/4.7.1.2 LCO information describing the              LCO 3.7.5            5.5.14 Bases AFW system operabihty requirements,                      bases          Control Pryram    1
            ' lhe "lX designalmn indicates that gun of u TS n remmed and the "R" designatmn irdicates an entire TS u muoved.
A6-13                                                            i 1


8 Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS       DOC #               Description of CTS Requirement                     Document                   Control a
Farley Nuclear Plant ITS Conversion A
Section 3,7       9 LA       4.7.1.2.2.a.3 Surveillance specific valve                 SR 3.7.5.1               5.5.14 Bases position guidance.                                           bases               Control Program 3.7         14-LA       4.7.1.2.2.b, c.1, c.2 AFW valves and pumps             LCO 3.7.5 SR               5.5.14 Bases specific auto start signals.                                 bases               Control Program
Summary of CTS Requirements Removed From the TS Q
            .i .7       15-LA       4.7.1.2.2.c Requirement that the 18 month               LCO 3.7.5 SR               5.5.14 Bases surveillance be performed "during shutdown"                   bases               Control Program 37         17-LA       4.7.12.2.c 3 Specific turbine-driven AFW                 SR 3.7.5.5               5.5.14 Bases pump steam admission valve ID numbers.                       bases               Control Program 3.7         l-R       3/4.7.2 Steam Ger.erator                                     TRM                   10CFR50.59 Pressure / Temperature Limitation 3.7         6-LA       4.7.3.b Surveillance requirement to be                   SR 3.7.7.2               5.5.14 Bases perfonned during shutdown and specific                       bases               Control Program automatic valve actuation signal.
and Placed in, or Currently Located in, Other Documents ITS DOC #
3.7         2-LA       3/4.7.4 LCO description of operable SW                   LCO 3.7.8                 5.5.14 Bases
Description of CTS Requirement Document Control Section a
'                                  loop.                                                         bases               Control Program 3.7         6-LA       4.7.4.b Surveillance requirement to be                   SR 3.7.8.2               5.5.14 Bases performed during shutdown'and specific                       bases               Control Program automatic valve actuation signal.
36 6-LA 4.6.2.3.a. and b Surveillance details regarding LCO 3.6.6 SR 5.5.14 Bases where each fan group is started and the bases Control Program specific automatic actuation signal.
3.7         12-LA       4.7.4.c FNP specific surveillance to verify               SR 3.7.8.4               5.5.14 Bases SW buried piping integrity. Descriptive term                 bases               Control Program
3.6 1-LA 3/4.6.3 List of containment isolation valves in TRM 10CFR50.59 Table 3.6 1.
                                    " leak tight" 3.7         3 LA       4.7.6.2.2-4 Ultimate Heat Sink spillway                     TRM                   10CFR50.59 channel and ground water seepage maintenance requirements.
3.6 11 LA 4.6.3.1 Post maintenance testing requirements TRM 10CFR50.59 for containment isolation valves.
3.7         4-LA       4.7.7.1.a - Surveillance description of                   SR 3.7.10.1               5.5.14 Bases CREFS flow path.                                             bases               Control Program 3.7         8-LA       4.7.7.1.b, c, d.1, e, f Surveillances and                 Ventilation         5.5.11 Ventilation associated footnotes for the CREFS system.                 Filter Test               Filter Test Program               Program and SR 3.7.10.2 The "lA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
36 13 LA 4.6 3.2.a and b Surveillance details regarding SR 3 6.3.6 5.5.14 Baues the specific actuation signal tested bases Control Program 3.6 19-LA Table 3.6-1 " footnote regarding SR 3.6.3.2 5.5.14 Bases containment isolation valves which may be bases Control Program open with the power removed for overpressure protection requirements.
3.6 4 LA 4.6.4.2.b.1 Channel calibration requirement TRM 10CFR50.59 Q
for the hydrogen recombiners.
36 5 LA 4.6.4.2.a and 4.6.4.2.b 2 and 3 Surveillance LCO 3.6.7 SR 5.5.14 Bases details desenbmg specific requirements for bases Control Program hydrogen recombiner testing.
3.6 4-LA 4.6.4.3.a.1 Surveillance details regarding SR 3.6.9.1 5.5.14 Bases where the hydrogen dilution system is started.
bases Control Program 3.6 5-LA 4.6.4.4.a - Surveillance details regarding SR 3.6.8.1 5.5.14 Bases where the systens is started (control room).
bases Control Program 3.7 PLANT SYSTEMS 3,7 9 LA Table 3.7-3 Main Steam Safety Valve orifice LCO 3.7.1 5.5.14 Bases size.
bases Control Program 3.7 10-LA Table 3.7-3
* footnote regarding the SR 3.7.1.1 5.5.14 Bases requirement for ambient conditions for the lift bases Control Program setting pressure of the main steam safety valves.
3.7 2 LA 3/4.7.1.2 LCO information describing the LCO 3.7.5 5.5.14 Bases AFW system operabihty requirements, bases Control Pryram 1
' lhe "lX designalmn indicates that gun of u TS n remmed and the "R" designatmn irdicates an entire TS u muoved.
A6-13 i
1
 
8 Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #
Description of CTS Requirement Document Control Section a
3,7 9 LA 4.7.1.2.2.a.3 Surveillance specific valve SR 3.7.5.1 5.5.14 Bases position guidance.
bases Control Program 3.7 14-LA 4.7.1.2.2.b, c.1, c.2 AFW valves and pumps LCO 3.7.5 SR 5.5.14 Bases specific auto start signals.
bases Control Program
.i.7 15-LA 4.7.1.2.2.c Requirement that the 18 month LCO 3.7.5 SR 5.5.14 Bases surveillance be performed "during shutdown" bases Control Program 37 17-LA 4.7.12.2.c 3 Specific turbine-driven AFW SR 3.7.5.5 5.5.14 Bases pump steam admission valve ID numbers.
bases Control Program 3.7 l-R 3/4.7.2 Steam Ger.erator TRM 10CFR50.59 Pressure / Temperature Limitation 3.7 6-LA 4.7.3.b Surveillance requirement to be SR 3.7.7.2 5.5.14 Bases perfonned during shutdown and specific bases Control Program automatic valve actuation signal.
3.7 2-LA 3/4.7.4 LCO description of operable SW LCO 3.7.8 5.5.14 Bases loop.
bases Control Program 3.7 6-LA 4.7.4.b Surveillance requirement to be SR 3.7.8.2 5.5.14 Bases performed during shutdown'and specific bases Control Program automatic valve actuation signal.
3.7 12-LA 4.7.4.c FNP specific surveillance to verify SR 3.7.8.4 5.5.14 Bases SW buried piping integrity. Descriptive term bases Control Program
" leak tight" 3.7 3 LA 4.7.6.2.2-4 Ultimate Heat Sink spillway TRM 10CFR50.59 channel and ground water seepage maintenance requirements.
3.7 4-LA 4.7.7.1.a - Surveillance description of SR 3.7.10.1 5.5.14 Bases CREFS flow path.
bases Control Program 3.7 8-LA 4.7.7.1.b, c, d.1, e, f Surveillances and Ventilation 5.5.11 Ventilation associated footnotes for the CREFS system.
Filter Test Filter Test Program Program and SR 3.7.10.2 The "lA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
A6-14
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Farley Nuclear Plant ITS Conversion
Farley Nuclear Plant ITS Conversion
/                                         Summary of CTS Requirements Removed From the TS Q                                       and Placed in, or Currently Located in, Other Documents ITS         DOC 4               Description of CTS Requirement                     Decument               Control a
/
Section 3.7         10-LA       4.7.7.1.d.2 Surveillance description of                   SR 3.7.10.3           5.5.14 Bases specific CREFS actuation signal.                             bases           Control Program 3.7         4-LA       4.7.8.a - Surveillance details regarding where           SR 3.7.12.2           5.5.14 Bases the PRF system is started and the required                   bases           Control Program flow path.
Summary of CTS Requirements Removed From the TS Q
3.7         5-LA       4.7.8.b, c, d.1, d.3, e, f Surveillances and             Ventilation       5.5.11 Ventilation associated
and Placed in, or Currently Located in, Other Documents ITS DOC 4 Description of CTS Requirement Decument Control Section a
* footnotes for the PRF system.                 Filter Test           Filter Test Program           Program and SR 3.7.12.3 3.7         7 LA       4.7.8.d.2 Surveillance details regarding the             SR 3.7.12.4           5.5.14 Bases specific PRF actuation signal                                 bases           Control Program 3.7         3 LA       3/4.9.13 LCO statement describing the                     LCO 3.7.12           5.5.14 Bases operability requirements for the PRF when in                 bases           Control Program the fuel handling accident mode of operation.
3.7 10-LA 4.7.7.1.d.2 Surveillance description of SR 3.7.10.3 5.5.14 Bases specific CREFS actuation signal.
O h              3.7         1-R       3/4.7.9 Snubbers                                             TRM               10CFR50.59 3.7         l-R       3/4.7.10 Scaled Source Contamination                         TRM               10CFR50.59 3.7           l-R       3/4.7.13 (Unit 2) Area Temperature                           TRM               10CFR50.59 Monitoring 3.8 ELECTRICAL POWER SYSTEMS 3.8         2-LA       3/4.8.1.1 LCO description of DG set.                     LCO 3.8.1             5.5.14 Bases bases           Control Program 38         16-LA       4.8. l.12.a - Accelerated testing surveillance           Replaced by           10CFR50.65 requirements for the DGs contained in Table             Maintenance 4.8-1 (deleted).                                               Rule compliance 38         20-LA       4.8.1.1.2.a.4 Surveillance details regarding           SR 3.8.1.2 and         5.5.14 Bases DG synchronous speed (RPMs) and output                   SR 3.8.1.6         Control Program breaker closing permissive (57 Ih).                           bases 3.8         23-LA       4.8.1.1.2.a.6 Surveillance details regarding             LCO 3.8.1             5.5.14 Bases the required alignment of a DG to the                         bases           Control Program 7
bases Control Program 3.7 4-LA 4.7.8.a - Surveillance details regarding where SR 3.7.12.2 5.5.14 Bases the PRF system is started and the required bases Control Program flow path.
i                                     associated emergency bus.
3.7 5-LA 4.7.8.b, c, d.1, d.3, e, f Surveillances and Ventilation 5.5.11 Ventilation associated
          * 'Ihe "t.A" designation indicates that part of'a TS is removed and the "R" designation indicates an entire TS is removed. l A6-15
* footnotes for the PRF system.
Filter Test Filter Test Program Program and SR 3.7.12.3 3.7 7 LA 4.7.8.d.2 Surveillance details regarding the SR 3.7.12.4 5.5.14 Bases specific PRF actuation signal bases Control Program 3.7 3 LA 3/4.9.13 LCO statement describing the LCO 3.7.12 5.5.14 Bases operability requirements for the PRF when in bases Control Program the fuel handling accident mode of operation.
Oh 3.7 1-R 3/4.7.9 Snubbers TRM 10CFR50.59 3.7 l-R 3/4.7.10 Scaled Source Contamination TRM 10CFR50.59 3.7 l-R 3/4.7.13 (Unit 2) Area Temperature TRM 10CFR50.59 Monitoring 3.8 ELECTRICAL POWER SYSTEMS 3.8 2-LA 3/4.8.1.1 LCO description of DG set.
LCO 3.8.1 5.5.14 Bases bases Control Program 38 16-LA 4.8. l.12.a - Accelerated testing surveillance Replaced by 10CFR50.65 requirements for the DGs contained in Table Maintenance 4.8-1 (deleted).
Rule compliance 38 20-LA 4.8.1.1.2.a.4 Surveillance details regarding SR 3.8.1.2 and 5.5.14 Bases DG synchronous speed (RPMs) and output SR 3.8.1.6 Control Program breaker closing permissive (57 Ih).
bases 3.8 23-LA 4.8.1.1.2.a.6 Surveillance details regarding LCO 3.8.1 5.5.14 Bases the required alignment of a DG to the bases Control Program 7
i associated emergency bus.
* 'Ihe "t.A" designation indicates that part of'a TS is removed and the "R" designation indicates an entire TS is removed.
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Farley Nuclear Plant ITS Conversion
Farley Nuclear Plant ITS Conversion
  /                                     Summary of CTS Requirements Removed From the TS
/
(                                     and Placed in, or Currently Located in, Other Documents ITS         DOC #             Description of CTS Requirement                       Document               Control a
Summary of CTS Requirements Removed From the TS
Section 3.8         25-LA       4.8.1.1.2.c.) Surveillance requirement to                   TRM               10CFR50.59 inspect and maintain DG in accordance wn.
(
and Placed in, or Currently Located in, Other Documents ITS DOC #
Description of CTS Requirement Document Control Section a
3.8 25-LA 4.8.1.1.2.c.) Surveillance requirement to TRM 10CFR50.59 inspect and maintain DG in accordance wn.
procedur;s prepared in conjunction with manufacturers' recommendation.
procedur;s prepared in conjunction with manufacturers' recommendation.
3.8         32-LA > 4.8.1.1.2.c.5 Surveillance details regarding                 SR 3.8.1.12           5.5.14 Bases the required steady state voltage and                         bases           Control Program frequency.
3.8 32-LA > 4.8.1.1.2.c.5 Surveillance details regarding SR 3.8.1.12 5.5.14 Bases the required steady state voltage and bases Control Program frequency.
3.8         36-LA     4.8.l.l.2 c.6 Surveillance verifications that               LCO 3.8.1           5.5.14 Bases auto-connected for.ds do not exceed DG                         bases           Control Program ratings.
3.8 36-LA 4.8.l.l.2 c.6 Surveillance verifications that LCO 3.8.1 5.5.14 Bases auto-connected for.ds do not exceed DG bases Control Program ratings.
3.8         39-LA     4.8.1.1.2.c.10 Surveillance verification that                 TRM               10CFR50.59 DG lockout features prevent DG stan when rcquired.
3.8 39-LA 4.8.1.1.2.c.10 Surveillance verification that TRM 10CFR50.59 DG lockout features prevent DG stan when rcquired.
38         44-LA       4.8.1.1.2.c 11 Surveillance details regarding             SR 3.8.1.8           5.5.14 Bases       i specific KW rating of single largest load.                   bases           Control Program u) 38         41-LA     4.8.1.1.2.d Surveillance details regarding               SR 3.8.1.19           5.5.14 Bases required performance after any modifications                 bases           Control Program which could afTect the DG interdependence.
38 44-LA 4.8.1.1.2.c 11 Surveillance details regarding SR 3.8.1.8 5.5.14 Bases specific KW rating of single largest load.
3.8         43-LA     4.8.1.1.2.e Surveillance details regarding               SR 3.8.1.18           5.5.14 Bases verification of DG breaker and ESF breaker                   bases           Control Program positions and fuse status and " footnote allowance for this test to be performed on either unit for shared DGs.
bases Control Program u) 38 41-LA 4.8.1.1.2.d Surveillance details regarding SR 3.8.1.19 5.5.14 Bases required performance after any modifications bases Control Program which could afTect the DG interdependence.
3.8         3-LA       3/4.8.1.2 Specific DG ID numbers in the                   LCO 3.8.2           5.5.14 Bases LCO requirement for one operable DG.                         bases           Control Program 3.8         3-LA       3/4.8.2.1 Specific information regarding how               LCO 3.8.7           5.5.14 Bases inverters are connected.                                     bases           Control Program 3.8         4-LA       3/4.8.2.1 LCO requirement for H and J                     FSAR SB0           10CFR50.59 and 4160kV buses.                                             discussion (J         5.5.14 Bases bus) and LCO         Control Program 3.8.1/2 bases (H bus) yy k)
3.8 43-LA 4.8.1.1.2.e Surveillance details regarding SR 3.8.1.18 5.5.14 Bases verification of DG breaker and ESF breaker bases Control Program positions and fuse status and " footnote allowance for this test to be performed on either unit for shared DGs.
3.8 3-LA 3/4.8.1.2 Specific DG ID numbers in the LCO 3.8.2 5.5.14 Bases LCO requirement for one operable DG.
bases Control Program 3.8 3-LA 3/4.8.2.1 Specific information regarding how LCO 3.8.7 5.5.14 Bases inverters are connected.
bases Control Program 3.8 4-LA 3/4.8.2.1 LCO requirement for H and J FSAR SB0 10CFR50.59 and 4160kV buses.
discussion (J 5.5.14 Bases bus) and LCO Control Program 3.8.1/2 bases (H bus) yy k)
* The "LA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
* The "LA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
A6-16                                                               i l
A6-16 i
l
l l


Farley Nuclear Plant ITS Conversion p                                       Summary of CTS Requirements Removed From the TS
Farley Nuclear Plant ITS Conversion p
\                                     and Placed in, or Currently Located in, Other Documents ITS         DOC #             Description of CTS Requirement                     Document               Control a
Summary of CTS Requirements Removed From the TS
Section 3.8         5-LA       3/4.8.2.1 LCO list of required AC buses.                 LCO 3.8.9           5.5.14 Bases bases           Control Program 3.8         2-LA       3/4.8.3.2 Specific LCO and Action                         LCO 3.8.4           5.5.14 Bases requirements regarding the battery ID and                   bases           Control Program supporting chargers.
\\
3.8       3-LA       3/4.8.3.2 Specific DC busses listed in tiu               LCO 3.8.9           5.5.14 Bases LCO.                                                         bases           Control Program 3.8         5-LA       3/4.8.3.2 LCO and Action description of an               LCO 3.8.9           5.5.14 Bases operable bus (energized).                                     bases           Control Program 3.8         7-LA       4.8.2.3.2.b.2 Surveillance description of                 SR 3.8.4.2           5.5.14 Bases
and Placed in, or Currently Located in, Other Documents ITS DOC #
                                    " excessive" visible corrosion.                               bases           Control Program 3.8         9-LA       4.8.2.3.2.b.3 Surveillance specifics of exact             SR 3.8.6.3           5.5.14 Bases number of battery cells checked (10),                         bases           Control Program 3.8         17-LA     4.8.2.3.2.e Surveillance description of                   SR 3.8.4.8           5.5.14 Bases battery degradation.                                         bases           Control Program 3.8       22-LA       Table 4.8-2 Note (a) specific electrolyte                 LCO 3.8.6             5.5.14 Bases temperature used for correcting specific                     bases           Control Program gravity.                                                                                         )
Description of CTS Requirement Document Control Section a
38         2-LA       3/4.8.2.5 LCO description of the specific                 LCO 3.8.4           5.5.14 Bases CTS battery banks and the required chargers                 bases           Control Program for each battery.
3.8 5-LA 3/4.8.2.1 LCO list of required AC buses.
3.8         3-LA       3/4.8.2.5 LCO description of specific 125V               LCO 3.8.9           5.5.14 Bases DC busses.                                                   bases           Control Program 3.8         8-LA     4.8.2.5.2.b.2 Surveillance description of                 SR 3.8.4.2           5.5.14 Bases
LCO 3.8.9 5.5.14 Bases bases Control Program 3.8 2-LA 3/4.8.3.2 Specific LCO and Action LCO 3.8.4 5.5.14 Bases requirements regarding the battery ID and bases Control Program supporting chargers.
                                    " excessive" visible corrosion.                               bases           Control Program 3.8         10-LA     4.8.2.5.2.b.3 Surveillance specifics of exact             SR 3.8.6.3           5.5.14 Bases number of battery cells checked (10).                         bases           Control Program 3.8         17-LA     4.8.2.5.2.e Surveillance description of                   SR 3.8.4.8           5.5.14 Bases battery degradation,                                         bases           Control Program O
3.8 3-LA 3/4.8.3.2 Specific DC busses listed in tiu LCO 3.8.9 5.5.14 Bases LCO.
bases Control Program 3.8 5-LA 3/4.8.3.2 LCO and Action description of an LCO 3.8.9 5.5.14 Bases operable bus (energized).
bases Control Program 3.8 7-LA 4.8.2.3.2.b.2 Surveillance description of SR 3.8.4.2 5.5.14 Bases
" excessive" visible corrosion.
bases Control Program 3.8 9-LA 4.8.2.3.2.b.3 Surveillance specifics of exact SR 3.8.6.3 5.5.14 Bases number of battery cells checked (10),
bases Control Program 3.8 17-LA 4.8.2.3.2.e Surveillance description of SR 3.8.4.8 5.5.14 Bases battery degradation.
bases Control Program 3.8 22-LA Table 4.8-2 Note (a) specific electrolyte LCO 3.8.6 5.5.14 Bases temperature used for correcting specific bases Control Program gravity.
)
38 2-LA 3/4.8.2.5 LCO description of the specific LCO 3.8.4 5.5.14 Bases CTS battery banks and the required chargers bases Control Program for each battery.
3.8 3-LA 3/4.8.2.5 LCO description of specific 125V LCO 3.8.9 5.5.14 Bases DC busses.
bases Control Program 3.8 8-LA 4.8.2.5.2.b.2 Surveillance description of SR 3.8.4.2 5.5.14 Bases
" excessive" visible corrosion.
bases Control Program 3.8 10-LA 4.8.2.5.2.b.3 Surveillance specifics of exact SR 3.8.6.3 5.5.14 Bases number of battery cells checked (10).
bases Control Program 3.8 17-LA 4.8.2.5.2.e Surveillance description of SR 3.8.4.8 5.5.14 Bases battery degradation, bases Control Program O
V
V
* The "!A" designation mdicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
* The "!A" designation mdicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
Line 907: Line 1,199:


Faricy Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS
Faricy Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS
    )                                     and Placed in, or Currently Located in, Other Documents ITS       DOC #             Description of CTS Requirement                     Document                 Control a
)
Section 3.8         lR       3/4.8.3.1 Containment Penetration Conductor                 TRM               10CFR50.59 Overcurrent Protective Devices (Unit 2).
and Placed in, or Currently Located in, Other Documents ITS DOC #
3.8           l-R       3/4.8.3.2 Motor Operated Valves Thermal                     TRM               10CFR50.59 Overload Protection Devices (Unit 2).
Description of CTS Requirement Document Control Section a
3.9 REFUELING OPERATIONS 3.9         2-LA       3/4.9.1 LCO and surveillance descriptive                 LCO 3.9.1           5.5.14 Bases information regarding the portions of the RCS               bases           Control Program and refueling canal affected.
3.8 lR 3/4.8.3.1 Containment Penetration Conductor TRM 10CFR50.59 Overcurrent Protective Devices (Unit 2).
34         5 LA       3/4 9 I The boron concentration required by                 COLR               5.6.5 COLR this LCO will be contained in the Core Operating Limits Report (COLR) 3.9         8 LA       3/4.9.1 Actions specifying the makeup flow               LCO 3.9.1           5.5.14 Bases rate and boron concentration are replaced                   bases           Control Program with more general STS bases guidance.
3.8 l-R 3/4.8.3.2 Motor Operated Valves Thermal TRM 10CFR50.59 Overload Protection Devices (Unit 2).
3.9         2-LA       3/4.9.2 LCO description of flux monitor                   LCO 3.9.1           5.5.14 Bases display visual operability.                                   bases           Control Program 3.9         lR         3/4.9.3 Decay Time                                           TRM               10CFR50.59 3.9         l-R       3/4.9.5 Communications                                       TRM               10CFR50.59 3.9         l-R       3/4.9.6 Manipulator Crane                                     TRM               10CFR50.59 3.9         l-R       3/4.9.7.1 Crane Travel - Spent Fuel Storage                   TRM               10CFR50.59 Pool Building Bridge Crane 39           l-R       ~3/4.9 7.2 Spent Fuel Cask Crane                             TRM               10CFR50.59 3.9       5 LA       3/4.9.8.1 Action "b" explanation of the                   LCO 3.9.4           5.5.14 Bases reason for the I hour out of 8 hour exception                 bases           Control Program to the requirement to have RHR in operation.
3.9 REFUELING OPERATIONS 3.9 2-LA 3/4.9.1 LCO and surveillance descriptive LCO 3.9.1 5.5.14 Bases information regarding the portions of the RCS bases Control Program and refueling canal affected.
3.9       4-LA       3/4.9.8.2 Action "a" provision to perform the             LCO 3.9.5           5.5.14 Bases Action "as soon as possible"is effectively             Actions bases         Control Program replaced with the STS bases description of this Action.
34 5 LA 3/4 9 I The boron concentration required by COLR 5.6.5 COLR this LCO will be contained in the Core Operating Limits Report (COLR) 3.9 8 LA 3/4.9.1 Actions specifying the makeup flow LCO 3.9.1 5.5.14 Bases rate and boron concentration are replaced bases Control Program with more general STS bases guidance.
3.9 2-LA 3/4.9.2 LCO description of flux monitor LCO 3.9.1 5.5.14 Bases display visual operability.
bases Control Program 3.9 lR 3/4.9.3 Decay Time TRM 10CFR50.59 3.9 l-R 3/4.9.5 Communications TRM 10CFR50.59 3.9 l-R 3/4.9.6 Manipulator Crane TRM 10CFR50.59 3.9 l-R 3/4.9.7.1 Crane Travel - Spent Fuel Storage TRM 10CFR50.59 Pool Building Bridge Crane 39 l-R
~3/4.9 7.2 Spent Fuel Cask Crane TRM 10CFR50.59 3.9 5 LA 3/4.9.8.1 Action "b" explanation of the LCO 3.9.4 5.5.14 Bases reason for the I hour out of 8 hour exception bases Control Program to the requirement to have RHR in operation.
3.9 4-LA 3/4.9.8.2 Action "a" provision to perform the LCO 3.9.5 5.5.14 Bases Action "as soon as possible"is effectively Actions bases Control Program replaced with the STS bases description of this Action.
* 1he "!X designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed A6-18
* 1he "!X designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed A6-18


Farley Nuclear Pimt ITS Conversion Summary of CTS Requirements Removed From the TS O           ITS        DOC #
Farley Nuclear Pimt ITS Conversion Summary of CTS Requirements Removed From the TS O
and Placed in, or Currently Located in, Other Documents Description of CTS Requirement                     Document -               Control Section 39         6 LA       4.9.9 Description of specific actuating                   SR 3.9.3.2           5.5.14 Bases signals.                                                     bases           Control Program 3.9           l-R       3/4.9.12 Storage Pool Ventilation (Fuel                     TRM               10CFR50.59 Storage)
and Placed in, or Currently Located in, Other Documents ITS DOC #
CTS 3/4.10 TEST EXCEPTIONS AND 3/4.11 RADIOACTIVE EFFLUENTS 3.10           1-R       3/4.10.5 Position Indication System -                       TRM               10CFR50.59 Shutdown 3.11         1-LA       3/4.11.1.4 Liquid Holdup Tanks                         Explosive Gas         5.5.12 Explosive and Storage         Gas and Storage Tank                   Tank Radioactivity         Radioactivity Monitoring           Monitoring Program and           Program and TRM               10CFR 50.59
Description of CTS Requirement Document -
: 3. I I       l-LA       3/4.11.2.5 Waste Gas Monitoring                       Explosive Gas         5.5.12 Explosive and Storage         Gas and Storage Tank                   Tank Radioactivity         Radioactivity   )
Control Section 39 6 LA 4.9.9 Description of specific actuating SR 3.9.3.2 5.5.14 Bases signals.
I Monitoring             Monitoring Program and           Program and TRM               10CFR 50.59 3 II         l-LA       3/411.2.6 Gas Storage Tanks                           Explosive Gas         5.5.12 Explosive and Storage         Gas and Storage Tank                   Tank Radioactivity         Radioactivity Monitoring             Monitoring Program and           Program and TRM               10CFR 50.59 I
bases Control Program 3.9 l-R 3/4.9.12 Storage Pool Ventilation (Fuel TRM 10CFR50.59 Storage)
CTS 3/4.10 TEST EXCEPTIONS AND 3/4.11 RADIOACTIVE EFFLUENTS 3.10 1-R 3/4.10.5 Position Indication System -
TRM 10CFR50.59 Shutdown 3.11 1-LA 3/4.11.1.4 Liquid Holdup Tanks Explosive Gas 5.5.12 Explosive and Storage Gas and Storage Tank Tank Radioactivity Radioactivity Monitoring Monitoring Program and Program and TRM 10CFR 50.59
: 3. I I l-LA 3/4.11.2.5 Waste Gas Monitoring Explosive Gas 5.5.12 Explosive and Storage Gas and Storage Tank Tank Radioactivity Radioactivity
)
Monitoring Monitoring Program and Program and TRM 10CFR 50.59 3 II l-LA 3/411.2.6 Gas Storage Tanks Explosive Gas 5.5.12 Explosive and Storage Gas and Storage Tank Tank Radioactivity Radioactivity Monitoring Monitoring Program and Program and TRM 10CFR 50.59 I
* The "lA" designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.
* The "lA" designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.
A6-19
A6-19


Farley Nuclear Plant ITS Conversion c                                       Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS       DOC #               Description of CTS Requirement                       Document                 Control a
Farley Nuclear Plant ITS Conversion c
Section 4.0 DESIGN FEATURES 4.0         1-LA         Exclusion Area, Figure 5.1-1, Low                         FSAR 2.1             10CFR50.59 Population Zone, Figure 5. l-2. Site Boundary for Gaseous Efiluents, Figure 5.1-3, and the Site Boundary For Liquid Effluents Figure 5 l-4 4.0         2-LA         5.2 Containment - design information.                   FSAR 3.8 and           10CFR50.59 Table 6.2-1 4.0         3-LA       5.4 RCS - design information.                             FSAR 5.0,             10CFR50.59 Table 5.1-1, and 5.2 4.0         4 LA       5.5 Meteorological Tower Location, Figure                 FSAR 2.3.3,           10CFR50.59 5.5-1                                                   Figures 2.3-27 and 2.4-1 4.0         11-LA       5.7 Component Cyclic or Transient Limit,                   New FSAR           FNP ITS 5.5.5, Table 5.7-1. New Table required to identify               Table 5.2-2a         Component and the TS limits.                                                                       Cyclic or Transient Limit Program, and 10CFR50.59 5.0 ADMINISTRATIVE CONTROLS 50         5-LA       6.2.2.a References to shift crew composition               10CFR 50.54         10CFR 50.54 (k) shown in Table 6.2-1 replaced with specifics             (k)(1) and (m)           (1) and (m) not addressed in 10CFR 50.54 (k)(1) and (m).
Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #
5.0         9-LA       6.2.2.d Requirement for an SRO to supervise                   10 CFR           10 CFR 50.54(m) all Core Alterations.                                     50.54(m) (2)               (2) (iv).
Description of CTS Requirement Document Control Section a
(iv) 5.0         11-LA       6.2.2.g Requirement that shift supervisors               10 CFR 50.54         10 CFR 50.54 (k) hold a senior reactor operator license and that         (k)(1) and (m)         (1) and (m)and reactor operators hold a reactor operator               and section 13           10CFR 50.59 license.                                                   of the FSAR
4.0 DESIGN FEATURES 4.0 1-LA Exclusion Area, Figure 5.1-1, Low FSAR 2.1 10CFR50.59 Population Zone, Figure 5. l-2. Site Boundary for Gaseous Efiluents, Figure 5.1-3, and the Site Boundary For Liquid Effluents Figure 5 l-4 4.0 2-LA 5.2 Containment - design information.
FSAR 3.8 and 10CFR50.59 Table 6.2-1 4.0 3-LA 5.4 RCS - design information.
FSAR 5.0, 10CFR50.59 Table 5.1-1, and 5.2 4.0 4 LA 5.5 Meteorological Tower Location, Figure FSAR 2.3.3, 10CFR50.59 5.5-1 Figures 2.3-27 and 2.4-1 4.0 11-LA 5.7 Component Cyclic or Transient Limit, New FSAR FNP ITS 5.5.5, Table 5.7-1. New Table required to identify Table 5.2-2a Component and the TS limits.
Cyclic or Transient Limit Program, and 10CFR50.59 5.0 ADMINISTRATIVE CONTROLS 50 5-LA 6.2.2.a References to shift crew composition 10CFR 50.54 10CFR 50.54 (k) shown in Table 6.2-1 replaced with specifics (k)(1) and (m)
(1) and (m) not addressed in 10CFR 50.54 (k)(1) and (m).
5.0 9-LA 6.2.2.d Requirement for an SRO to supervise 10 CFR 10 CFR 50.54(m) all Core Alterations.
50.54(m) (2)
(2) (iv).
(iv) 5.0 11-LA 6.2.2.g Requirement that shift supervisors 10 CFR 50.54 10 CFR 50.54 (k) hold a senior reactor operator license and that (k)(1) and (m)
(1) and (m)and reactor operators hold a reactor operator and section 13 10CFR 50.59 license.
of the FSAR
* lhe "lX designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
* lhe "lX designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
A6-20
A6-20


Farley Nuclear Plant   .
Farley Nuclear Plant ITS Conversion j
ITS Conversion   j I
I Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #
Summary of CTS Requirements Removed From the TS
Description of CTS Requirement Document Control Section a
'                                      and Placed in, or Currently Located in, Other Documents ITS         DOC #               Description of CTS Requirement                     Document                 Control a
5.0 13 LA Table 6.2-1 Minimum Shifl Crew 10 CFR 50.54 10 CFR 50.54 (k)
Section 5.0       13 LA       Table 6.2-1 Minimum Shifl Crew                           10 CFR 50.54         10 CFR 50.54 (k)
Composition.
Composition.                                           (k)(1) and (m)           (1) and (m) 5.0       15-LA       6.2.3 Safety Audit and Engineering Review                   Quality         10 CFR 50.54(a)
(k)(1) and (m)
Group (SAERG).                                             Assurance Progmm 5.0       16-LA       6.4 Training (entire section).                         FSAR Chapter             10CFR50.59 13.2 Training Program 50         17-LA       6.5 Review and Audit (entire section).                     Quality         10 CFR 50.54(a)
(1) and (m) 5.0 15-LA 6.2.3 Safety Audit and Engineering Review Quality 10 CFR 50.54(a)
Assurance Program 5.0       18-LA       6.6 Reportable Event Action (entire section).           10 CFR 50.72           10 CFR 50.72 and 10 CFR             and 10 CFR 50.73                 50.73 50         19-LA       6.7 Safety Limit Violation (entire section).             10CFR 50.36,           10CFR 50.36, 10CFR 50.72,           10CFR 50.72, and 10CFR         and 10CFR 50.73 50.73 5.0         20-LA       6.8.1 Requirements for written procedures for             Regulatory       Regulatory Guide the following: 6.8.1.b, refueling operations,           Guide 1.33,10           1.33,10 CFR 6.8. l .c, surveillance and test activities of         CFR 50.54(p),       50.54(p),10 CFR safety related equipment,6.8.1.d Security                   10 CFR           50.54(q) and 10 Plan implementation, and 6.8. I .e Emergency             50.54(q) and       CFR 50 Appendix Plan implementation.                                       10 CFR 50                   E Appendix E 50         22-LA       6.8.1 g Requirement for written procedures                   FSAR               10CFR50.59 for the process control program.                                               10CFR Part 20, 61, and 71 5.0         25-LA       6.8.1.j(i) Procedures be established.                   FSAR section         10CFR50.59 and implemented and maintained for the station                 8.3.1.1.7.3         10 CFR 50.65 blackout Alternate AC (AAC) Source                             and Reliability Program to derme the testing,                 Maintenance maintenance, and parts procurement                     Rule (10 CFR                               l requirements necessary to maintam the AAC                   50.65)                               ]
Group (SAERG).
[._s                               as a Class IE component.
Assurance Progmm 5.0 16-LA 6.4 Training (entire section).
FSAR Chapter 10CFR50.59 13.2 Training Program 50 17-LA 6.5 Review and Audit (entire section).
Quality 10 CFR 50.54(a)
Assurance Program 5.0 18-LA 6.6 Reportable Event Action (entire section).
10 CFR 50.72 10 CFR 50.72 and 10 CFR and 10 CFR 50.73 50.73 50 19-LA 6.7 Safety Limit Violation (entire section).
10CFR 50.36, 10CFR 50.36, 10CFR 50.72, 10CFR 50.72, and 10CFR and 10CFR 50.73 50.73 5.0 20-LA 6.8.1 Requirements for written procedures for Regulatory Regulatory Guide the following: 6.8.1.b, refueling operations, Guide 1.33,10 1.33,10 CFR 6.8. l.c, surveillance and test activities of CFR 50.54(p),
50.54(p),10 CFR safety related equipment,6.8.1.d Security 10 CFR 50.54(q) and 10 Plan implementation, and 6.8. I.e Emergency 50.54(q) and CFR 50 Appendix Plan implementation.
10 CFR 50 E
Appendix E 50 22-LA 6.8.1 g Requirement for written procedures FSAR 10CFR50.59 for the process control program.
10CFR Part 20, 61, and 71 5.0 25-LA 6.8.1.j(i) Procedures be established.
FSAR section 10CFR50.59 and implemented and maintained for the station 8.3.1.1.7.3 10 CFR 50.65 blackout Alternate AC (AAC) Source and Reliability Program to derme the testing, Maintenance maintenance, and parts procurement Rule (10 CFR requirements necessary to maintam the AAC 50.65)
]
[._s as a Class IE component.
* The "lX designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
* The "lX designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.
A6-21
A6-21
                                                                                                                                        )
)
* Farley Nu: lear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents Q
 
ITS         DOC #             Description of CTS Requirement                     Document                   Control a
Farley Nu: lear Plant ITS Conversion Summary of CTS Requirements Removed From the TS Q
Section 5.0       27-LA       6.8.2 Requirements for the procedure and                   Quality           10CFR 50.54(a) policy review process, including changes                 Assurance made to the procedures and policies.                       Program 5.0       29-LA       6.8.3.b in-Plant Radiation Monitonng                       FSAR               10CFR50.59 Program 5.0       34-LA       6.8.3.f Radiological Environmental                         ODCM                     10CFR50, Monitoring Program                                                               Appendix 1, 10CFR50.34a and 10CFR50.36.a 5.0       22 LA       6.8.3.g Solid Radioactive Wastes Control                   FSAR             10CFR Part 20, Program, Process Control Program (PCP).                                       61, and 71 and 10CFR50.59 50         68-LA       610 Record Retention (entire section)                     Quality           10CFR 50.54(a) p                                                                                                       Assurance Program 5.0         69-LA       6.11 Radiation Protection Program to                       10 CFR                     10 CFR       {
and Placed in, or Currently Located in, Other Documents ITS DOC #
maintain procedures in accordance with                   20.1101(b)           20.1101(b) and       j 10CFR20.                                               and 10 CFR                   10 CFR       l 20.I101(c)             20.I101(c) 5.0         71-LA       '" footnote to CTS 6.12 specifying radiation               10 CFR           10 CFR 20.1602 measurement procedure.                                     20.1602 5.0         73-LA       6.13 Process Control Program (PCP)                         FSAR             10CFR50.59 and 10 CFR Part 20, 61, and 71 A
Description of CTS Requirement Document Control Section a
V
5.0 27-LA 6.8.2 Requirements for the procedure and Quality 10CFR 50.54(a) policy review process, including changes Assurance made to the procedures and policies.
Program 5.0 29-LA 6.8.3.b in-Plant Radiation Monitonng FSAR 10CFR50.59 Program 5.0 34-LA 6.8.3.f Radiological Environmental ODCM
: 10CFR50, Monitoring Program Appendix 1, 10CFR50.34a and 10CFR50.36.a 5.0 22 LA 6.8.3.g Solid Radioactive Wastes Control FSAR 10CFR Part 20, Program, Process Control Program (PCP).
61, and 71 and 10CFR50.59 50 68-LA 610 Record Retention (entire section)
Quality 10CFR 50.54(a) p Assurance Program 5.0 69-LA 6.11 Radiation Protection Program to 10 CFR 10 CFR
{
maintain procedures in accordance with 20.1101(b) 20.1101(b) and j
10CFR20.
and 10 CFR 10 CFR 20.I101(c) 20.I101(c) 5.0 71-LA
'" footnote to CTS 6.12 specifying radiation 10 CFR 10 CFR 20.1602 measurement procedure.
20.1602 5.0 73-LA 6.13 Process Control Program (PCP)
FSAR 10CFR50.59 and 10 CFR Part 20, 61, and 71 AV
* The "lA" designatwn tndientes that pun of a TS is removed and the "R" designation indicates an entire TS is removed A6-22
* The "lA" designatwn tndientes that pun of a TS is removed and the "R" designation indicates an entire TS is removed A6-22


I JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 IMPROVED TECHNICAL SPECIFICATION (TS) CONVERSION CHAPTER 1.0 - USE AND APPLICATION CONTENTS O   e    ENCLOSURE 1 MARKUP OF CURRENT FARLEY TS e   ENCLOSURE 2 DISCUSSION OF CHANGES TO CURRENT FARLEY TS e    ENCLOSURE 3 SIGNIFICANT HAZARDS EVALUATIONS FOR       ,
I JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 IMPROVED TECHNICAL SPECIFICATION (TS) CONVERSION CHAPTER 1.0 - USE AND APPLICATION CONTENTS O
CHANGES TO THE CURRENT FARLEY TS         j
ENCLOSURE 1 MARKUP OF CURRENT FARLEY TS e
    . ENCLOSURE 4 MARKUP OF NUREG-1431, Rev.1 - LCOs       j l
ENCLOSURE 2 DISCUSSION OF CHANGES TO CURRENT FARLEY e
e    ENCLOSURE 5 JUSTIFICATIONS FOR DIFFERENCES FROM NUREG-1431, Rev.1
TS ENCLOSURE 3 SIGNIFICANT HAZARDS EVALUATIONS FOR e
CHANGES TO THE CURRENT FARLEY TS j
ENCLOSURE 4 MARKUP OF NUREG-1431, Rev.1 - LCOs j
ENCLOSURE 5 JUSTIFICATIONS FOR DIFFERENCES FROM e
NUREG-1431, Rev.1
.__}}
.__}}

Latest revision as of 10:22, 3 December 2024

Application for Amends to Licenses NPF-2 & NPF-8 to Revise Existing TS in Entirety.Amend Consists Primarily of Conversion of Current TS to Improved Ts,Per NUREG-1431,rev 1.Vols 1-10 Contain Listed Attachments
ML20216F705
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 03/12/1998
From: Dennis Morey
SOUTHERN NUCLEAR OPERATING CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20216F708 List:
References
RTR-NUREG-1431 NUDOCS 9803190030
Download: ML20216F705 (77)
v • d • e


Text

e' Dave Morey Southern Nuclear

+,

Vice President Operating Company i

Farley Project P.O. Box 1295 Birmingham. Alabama 35201 A

. Tel 205.992.5131

(

March 12, 1998 SOUTHE.RN c

Energy to SernYourWorld" Docket Numbers:

50-348 50-364 10 CFR 50.90 U. S. Nuclear Regulatory Conunission ATTN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Request For Technical Specification Changes Conversion to the Imoroved Technical Specifications Ladies and Gentlemen:

In accordance with the provisions of 10 CFR 50.90, Southem Nuclear Operating Company (SNC) proposes to amend the Farley Nuclear Plant (FNP) Unit I and Unit 2 Technical Specifications (TS),

Appendix A to Operating Licenses NPF-2 and NPF-8. This TS amendment request revises the existing TS for Farley Units I and 2 in their entirety. The amendment consists primarily of a conversion of the Farley yO Current Technical Specifications (CTS), based on NUREG-0452, to the improved Technical Specifications (ITS) for Westinghouse plants based on NUREG-1431, Revision 1. Additional changes are reflected in Attachments 3 and 5. As part of this conversion, the two sets of CTS will be combined into a single set, 1

applicable to both operating units.

By letter dated December 1,1995, Sv%rn Nuclear Operating Company (SNC) provided notification of i

the intent to implement ITS for FNr. The proposed license amendment request to convert the Farley CTS to the Farley ITS is provided in the volumes enclosed with this letter. The proposed amendment has been compared to the guidance of Nuclear Energy Institute (NEI) 96-06, " Improved Technical Specifications Conversion Guidance," dated August 1996. This NEl document was issued well after the start of the

)

Farley conversion to the ITS and, therefore, the attached ITS material may differ slightly from the specific NEl 96-06 guidance. However, the intent of the guidance has been incorporated into the Farley ITS conversion documentation. In addition, SNC has performed reviews ofIndustry and NRC correspondence and incorporated related enhancements as well as addressing FNP-specific literal compliance concerns.

Due to the size and complexity of this license amendment request, numerous Attachments have been included to describe the organization and disposition of various items addressed during the conversion l

process These Attachments are dneribed below:

g, " improved Technict,I Specifications Conversion Reviewers Guide," describes the jf organization of the enclosed submittal volumes and provides guidance for efficient review.

I, "An Overview of the Disposition of LCO's in the FNP ITS Conversion," provides a cross-I k( j) ~.

reference comparison of all Parley CTS, Farley ITS, and STS (NUREG-1431, Rev.1) Technical Specifications.

g$

W

  • ' "f h!k!hu1RMiiiEii1 9903190030Mbik2 I 7

PDR ADOCK 05000348, P

PDR _

.,e 4

c.1 U.S. Nuclear Regulatory Comnussion Page 2 Mend =nent 3, "Farley CTS License AvaaaAnaat Requests incorporated into the ITS," provides a listing of all currently daractart license amendment requests that have been included in the ITS submittal package., " Generic O- :a= to NUREG-1431, Rev.1, Incorporated into the ITS," provides a listing of the generic Technical Specification Task Force (TSTF) changes incorporated into the Farley ITS submittal Package., " Changes identified as Beyond the Scope of an ITS Conversion," provides a listing of those changes incorporated into the Farley ITS submittal package which differ from both the CTS and the Improved Standard Technical Specification (ISTS) as written in NUREG-1431, Rev.1., " Summary of CTS Requirements Renwved from the TS and Placed in, or Currently 1.ocated

. in, Other Documents," provides a listing of the CTS requirements which will be relocated or removed from the CTS, the proposed document to which they will be initially relocated or moved, and the control mechanism that will apply to each relocated or moved item.

Implementation of the Farley ITS will require the performance of a number of new ITS surveillance requirements. SNC intends to treat these new requirenwnts as being " met" at the time ofimplementation, with the first performance of these new surveillance requirements scheduled to be completed within the required interval from the date ofimplementation.

O U

Any revisions to the Farley Final Safety Ana!, sis Report (FSAR) required as a result of the conversion to the Farley ITS will be made in accordance with 10 CFR 50.71(c).

The planned implementation period is March 2000. 'Ihis imp!cmcatation period is timed to coincide with the Unit I steam generator replacement outage beginmng in April 2000. The Steam Generator Replacement (SGR) licensing package will be in the ITS format. Due to the time required for procedure revisions, the development of new programs, and training schedules for both licensed and non-licensed operators, and the desire for efficient implementation of both the ITS and SGR changes in parallel, SNC

_ requires a full 6 months after the issuance of the Safety Evaluation to implement this proposed license amendment request at Farley. "Iherefore, SNC requests that the NRC review and approve the proposed ITS Conversion by September 30,1999.

As denoted in 10 CFR 50.92(c), SNC has determined the proposed changes to the FNP TS do not involve a

'significant hazards consideration. 'Ihe basis for this evaluation is provided in Enclosure 3 of the submittal volumes. SNC has also determined that the proposed changes will not significantly affect the qudity of the human environment._ A copy of the proposed changes has been sent to Dr. D. E. Williams, the Alabama State Designee, in acs4 dance with 10 CFR 50.91(b)(i).

)

SNC requests a meeting in W==Magtaa. DC, at your earliest convenience to discuss the contents of this license amendment request, to establish a review schedule, and to establish unes of communication and the means of communicating requests for additional information and responses to those requests.

. jn.

)

n.6

_?

.. y 4

L U.S. Nuclear Regulatory Commission Page 3 O:

Mr. D. N. Momy states that he is a Vice President of Southern Nuclear Operating Company and is '

authorized to execute this oath on behalf of Southern Nuclear Operating Company and that, to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.

Ifyou have any questions, please advise.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY NN Dave Morey Swom to andsubscribedbef re me this&.Yy of NOA tt.

I998 l

'nwh I. % r ~

Notary Public U ~

My Commission Expires:

  1. 1.8mI<.L /. A/

O

(

WAS/maf:itssub. doc Awh=ts (1-6)

- Enclosures - Conversion Documentation (10 Volumes) cc:

Mr. L. A. Reyes, Region II Administrator Mr. J.1. Zimmerman, NRR Project Manager Mr. T, M. Ross, Plant Sr. Resident Inspector Dr. D. E. Williamson, State Department of Public Health

. I3 L/

,s>

6 Farley Nuclear Plant ITS conversion Submittal O

Joseph M. Farley Nuclear Plant ImDr0ved Technical Specifications Conversion Reviewers Guide O

O

Farley Nuclear Plant ITS conversion Submittal

/

Improved Technical Specifications Conversion Reviewers Guide V

OVERVIEW i

The Farley license amendment request for converting to a Farley-specific version of the generic Technical

]

Specifications (TS) contained in NUREG-1431, Rev.1, Standard Technical Specifications (STS),

Westinghouse Plants, is based on the format and presentation of the Improved Technical Specifications (ITS) conversion amendments already submitted by SNC plants Hatch and Vogtle, as well as generic 3

guidance provided by the NRC and NEl.

l The submittrJ package is divided into separate review sections. Each review section contains all the TS associated with a STS chapter (i.e., Electrical, Containment, RCS, etc.). The documentation included in each chapter secNn contains the information necessary to conduct a complete review of the conversion changes made to the Farley Current Technical Specifications (CTS) as well as the changes made to the corresponding STS to develop the Farley-specific version of the STS (the FNP ITS). The review packages

{

are also formatted such that the documentation pertaining to irdividual TS may be separated from the parent chapter which facilitates the review process by allowing individual Specifications to be distributed separately if desired.

In order to facilitate the organization, preparation, and review of the chapter sections, each chapter section is divided into six enclosures. These enclosures are linked, providing a roadmap of the conversion from the j

CTS to the FNP-specific ITS. Therefore, typically the most efficient method for review of a chapter is to lay out cach of the six enclosures side-by-side. This allows the reviewer to identify what changes are made s

/

to the CTS, why they are made, and why they are not a significant hazards concern. In parallel, the k

corresponding STS LCOs and Bases may be reviewed, including the changes required to make them FNP-specific and thejustifications for these changes. A description of each enclosure follows:

l ENCLOSURE 1 Enclosure I consists of a markup of each of the FNP CTS that correspond with the applicable STS chapter (i.e, Electrical, Containment, RCS, etc.). In order to facilitate the review of the revisions to the CTS, the LCOs in Enclosure I are organized in CTS order. Each CTS is marked to show technical and organizational changes required to convert to the STS and the location of the CTS requirements in the corresponding FNP ITS (Enclosure 4). Due to the extensive format and editorial differences between the CTS and the STS, minor editorial and simple format changes may not be identified. Each significant change identified in Enclosure I is assigned a Discussion of Change (DOC) number and a no Significant llazards Evaluation (SHE) designator. The DOC for each numbered item is contained in Enclosure 2. The SilE designator assigned to each change corresponds to a generic or specific SHE contained in Enclosure

3. Each SilE is fully described in Enclosure 3.

A complete set of Unit ! CTS is included. Unit 2 CTS pages are included only when a difference exists between the Unit 2 and corresponding Unit I CTS that must be individuallyjustified. All changes marked on the Unit i CTS apply to the Unit 2 CTS unless a separate Unit 2 CTS page is included. As part of the front matter for Enclosure I in cach Chapter package, a listing and description of the differences between the current Unit I and Unit 2 TS is included.

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Faley Nuclear Plant ITS conversion Submittal n

Imoroved Technical Specifications Conversion Reviewers Guide (v)

The CTS markup addresses the addition of new ITS LCOs in two ways. If the ncw LCO is derived from an existing CTS LCO, the markup of that CTS LCO addresses the new ITS LCO and the associated DOCS explain the addition of the ITS LCO. In this case, a copy of the new ITS LCO is not always included in. If the ITS LCO is completely new to the CTS and unrelated to existing CTS LCOs, a copy of the new LCO is included at the end of the Enclosure 1 markup and the associated DOC evaluates the addition of that new LCO.

ENCLOSURE 2 contains a DOC for each marked-up change to the FNP CTS required to produce the FNP specific ITS. The DOC numbers are referenced directly from Enclosure 1 (CTS markup), and the associated SHEs are contained in Enclosure 3. Each of the DOCS and associated SHEs are applicable to both Unit I and 2 unless otherwise stated. Each technical change and the more complf::ated format and presentation changes to the CTS are discussed and justified specifically for FNP. In order to facilitate review, the DOCS in this enclosure are organized by individual TS and may be easily separated into individual TS review sections if desired. The DOCS for each LCO are labeled with the corresponding CTS number and name and the proposed FNP ITS specific number and name.

ENCLOSURE 3 contains the collection of SilEs associated with all the CTS changes identified and discussed in

[)

the previous enclosures. The SIIEs contained in Enclosure 3 are presented on an STS chapter basis and D

are subdivided into individual LCO sections, as are each of the other Enclosures that make up the conversion document. The large majority of CTS changes are categorized or grouped such that a single

" generic" SHE may be applied to each group of changes. For example, a single generic SHE may be applied to all changes that are classified as Administrative changes (i.e., moving requirements from one TS to another without introducing a technical change to the requirement) or changes classified as a Relocation (the movement of an entire TS outside of the license). The generic SHE categories identified within this enclosure conform to the applicable NRC and NE! guidance. All changes identified as less restrictive technical changes (i.e., extended allowed outage times or surveillance intervals, deletion ofindividual requirements, etc.) which are not associated with a generic SHE are individually evaluated for FNP. These individual esaluations ofless restrictive changes are also included in Enclosure 3. The SHE designators usai in Enclosure 3, and a brief description of each are listed below:

ADMINISTRATIVE ("A" labeled changes)

This generic category applies to changes that are editorial in nature, involve the movement of requirements within the CTS without affecting their technical content, simply reformat a requirement, or clarify the TS (such as deleting a footnote no longer applicable due to a technical change to a requirement). It also includes non-technical changes such as refonnatting and rewording the remaining requirements in order to conform with the fonnat and style of the STS. These changes are intended to make the TS more readily understandable to plant operators and other users. The application of the STS format and style will also assure consistency is achieved between TS.

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Farley Nuclear Plant ITS conversion Submittal

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Improved Technical Specifications Conversion Reviewers Guide C/

During this reformatting and rewording process, no technical changes (either actual or interpretational) were made to the TS unless they were identified and justified. However, some obvious admmistrative changes may not be specifically referenced to a discussion of change or SHE.

If no discussion of change or SHE is referenced for a change, it is considered administrative in nature and this Generic SHE applies. Changes to the CTS requirements categorized as Admmistrative are annotated with an "A" in the Enclosure I markup and Enclosure 2 DOC. Administrative changes are considered generic and each change identified as Administrative will not be specifically discussed in this SHE. This evaluation will be applicable to each of the changes identified with an "A"in the markup of the CTS and the associated Enclosure 2 DOC.

RELOCATION OF TECHNICAL SPECIFICATIONS ("R" labeled changes)

This generic category applies to changes that relocate CTS requirements that do not meet the criteria in the NRC Final Policy Statement on Technical Specification improvement for Nuclear Power Reactors (58FR39132, dated 7/22/93). This category of SHE may only be applied to entire TS that do not meet the NRC Policy Statement Criteria. Relocation of these CTS requirements allows the TS document to be reserved only for those conditions or limitations upon reactor operation which are necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety thereby focusing the scope of the TS. Therefore, CTS which do not meet the criteria in the NRC Final Policy Statement on Technical Specification Improvement for Nuclear Power Reactors (58 FR 39132, dated 7/22/93) have been proposed for relocation to other g

I T

licensee controlled documents that are subject to the provisions of 10 CFR 50.59 or other applicable O

CFR. This will ensure that changes to these relocated TS requirements will be limited to those that do not involve an unreviewed safety question.

The NRC policy statement addresses the scope and purpose of TS, in doing so, it sets forth a specific set of objective criteria for determining which regulatory requirements and operating restrictions should be included in the TS. These criteria are as follows:

Criterion 1: Installed instrumentation that is used to detect and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary; Criterion 2: A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analyses that either assumes the failure of or presents a challenge to the integrity of a fission product barrier; Criterion 3: A structure, system or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission barrier; Criterion 4: A structure, system, or component which operating experience or probabilistic safety assessment has shown to be significant to public health and safety.

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Farley Nuclear Plant ITS conversion Submittal G

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Improved Technical Specifications Conversion Reviewers Guide

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Changes to the CTS requirements categorized as Relocated are annotated with an "R" in the Enclosure I markup and Enclosure 2 DOC. Relocation changes are considered generic and each j

relocated TS will not be specifically discussed in this SHE. A specific DOC for each CTS identified for relocation is provided in Enclosure 2. This evaluation will be applicable to each of the changes identified with an "R"in the Enclosure 1 markup of the CTS and the associated Enclosure 2 DOC.

j MORE RESTRICTIVE ("M" labeled change;0 1

This generic category consists of changes that modify the CTS to add new requirements or revise existing requirements to be more stringent. These changes are typically made to conform to applicable requirements in the STS, correct discrepancies, or remove ambiguities from the CTS.

More restrictive changes are proposed only when such changes are consistent with:

1) The FNP current licensing basis;
2) The applicable FNP safety analyses; and
3) Good engineering practice such that the availability and reliability of the affected equipment is not reduced.

Changes to the CTS requirements categonzed as More Restrictive are annotated with an "M' in the h markup and Enclosure 2 DOC. These changes are considered generic and each change U

identified as More Restrictive will not be specifically discussed in this SHE. This : Muation will be applicable to each of the changes identified with an "M"in the Enclosure I markup of the CTS and the associated Enclosure 2 DOC.

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REMOVAL OF REOUIREMENTS FROM RETAINED TS ("LA"labeleri chances) i This generic category applies to changes that modify the CTS to achieve consistency with the style j

and format of the STS by removing some information and requirements from the CTS. This j

category of change is considered to be less restrictive (no longer controlled by TS) and is referred to j

I as Less Restrictive - Generic. The " partial relocation" ofinformation can not be addressed by the application of the enteria in the NRC Final Policy Statement on Technical Specification improvement for Nuclear Power Reactors, ne NRC Policy Statement criteria is only intended to apply to entire TS. This generic category is intended to apply to changes that remove some information that is typically descriptive in nature regarding the equipment, system (s), actiens or surveillances from a CTS that is retained in the TS. The information that is removed from the CTS is proposed for inclusion in the TS Bases, FSAR, or other licensee controlled documents as appropriate. The removal of this information from the CTS to licensee controlled documents is acceptable because the documents will be controlled through a process which utilizes 10 CFR 50.59 or other applicable CFR. Therefore, the information that has been moved continues to be maintained in an appropriately controlled manner. The proposed changes will not impact the actual information moved out of the CTS, but will reduce the level of regulatory control over this information.

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A l-4 i

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Farley Nuclear Plant ITS conversion Submittal h

improved Technica! Specifications Conversion Reviewers Guide O

Changes to the CTS requirements that fall within this category (Less Restrictive - Generic) are annotated with an "LA" in the Enclosure I markup and Enclosure 2 DOC. These changes are considered generic and each change identified as Less Restrictive - Generic will not be specifically discussed in this SliE. This evaluation will be applicable to each of the changes identified with an "LA"in the Enclosure I markup of the CTS and the associated Enclosure 2 DOC.

ALLOWANCE TO USE A SIMULATED OR ACTUAL ACTUATION SIGNAL ("LB" labeled changes)

This generic category applies to those changes that provide the allowance to utilize a simulated or actual signal to verify the automatic actuation of specific components in the Surveillance test requirements of the TS. This type of change is considered less restrictive as it provides an alternate method to satisfy surveillance requirements that verify automatic equipment / system actuation. This change allows satisfactory automatic actuations (required equipment / system operation is verified) that occur due to an actual automatic actuation to fulfill the surveill,wce requirement. Operability is adequately demonstrated in either case as the affected equipment or system carmot discriminate between an actual or simulated (test) signal. Changes to the CTS requirements that fall within this category (Less Restrictive - Generic) are annotated with an "LB" in the Enclosure i markup and DOC. These changes are considered generic and each change identified as Less Restrictive - Generic will not be specifically discussed in this SHE. This evaluation will be applicable to each of the changes identified with an "LB" in the Enclosure I markup of the CTS and (G

)

the associated Enclosure 2 DOC.

LESS RESTRICTIVE ("L" labeled changes)

This category consists of technical changes which revise existing requirements such that more f

restoration time is provided, fewer compensatory measures are needed, or fewer or less restrictive surveillance requirements are required. This would also include requirements which are deleted from the TS (not relocated to other documents) and other technical changes that do not fit a generic category. Rese changes are evaluated individually and " specific" SHEs developed. Each " specific" SiiE for a less restrictive technical change will be individually numbered in each TS with the suffix "L"

Technical changes to the CTS requirements categorized as "Less Restrictive - Specific" are annotated with the suflix "L" and an individual number in the Enclosure 1 markup and Enclosure 2 i

DOC for each TS. In order to facilitate review, the less restrictive SHEs are organized by individual TS. The SHEs applicable to each TS may be separated into individual review packages if desired.

ENCLOSURE 4 contains the markup of the generic STS LCOs from NUREG-1431, Revision 1. The LCOs in are organized in STS order. Each STS LCO is marked with all the changes required to make j

the FNF-specific ITS or to identify that the STS generic LCO is not applicable to FNP. Each change made to a generic STS LCO is identified with a number that corresponds to ajustification for difference (JD) in i, except in cases where an FNP number or nomenclature, consistent with the CTS, is simply substituted for the corresponding STS generic number or name.

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Farley Nuclear Plant ITS conversion Submittal

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(

Improved Technical Specifications Conversion Reviewers Guide

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Bracketed information in the STS is confirmed to be applicable to FNP or replaced with information that is applicable to FNP or deleted as appropriate. In cases v.here previously NRC approved CTS information is used to replace the generic STS information in brackets, nojustification for altering the bracketed STS information is typically provided. The basis for all such changes to the STS is to maintain the current FNP licensing basis as specified in the CTS.

In addition, the markups in Enclosure 4 show the NRC approved changes to the STS resulting from the Nuclear Energy Institute (NEI)/NRC revision process. He Industry /NEl sponsored changes marked in this enclosure have been approved by the NRC and have also been determined to be applicable to FNP.

He Industry /NEl revisions to the STS are marked-up and identified with the NEI tracking number (i.e.,

TSTF-03, TSTF-19, etc). The NEI changes are treated as though they are part of the STS for the FNP conversion. Each NEl change package contains its own justification for change which is not repeated in this conversion documentation.

ENCLOSURE 5 contains the JDs between the generic STS and the proposed FNP ITS. Each change identified and numbered in Enclosure 4 is justified within this Enclosure. The STS markup in Enclosure 4 also contains approved changes to the STS resulting from the NEl/NRC revision process. The Industry /NEl sponsored changes marked in this enclosure have been approved by the NRC unless othenvise noted in and have also been determined to be applicable to FNP. Thejustifications for NEl changes

(.y-}

are contained in the associated change package submitted to the NRC and are not repeated in this document. In order to facilitate review, the JDs in this enclosure are organized by individual TS and may be easily separated into individual TS review sections if desired. The JDs are labeled with the corresponding STS number and name and the proposed FNP ITS specific number and name if different than the STS.

ENCLOSURE 6 contains the generic STS Bases marked-up to indicate the changes required to make the FNP-specific ITS Bases. As control of the Bases content is the responsibility of the licensee, the changes to the generic STS Bases are not discussed individually as are the changes to the generic STS LCOs. Changes to the generic STS Bases are associated with one of several categories which provide a general description of the change. The categories of Bases changes are identified within the Enclosure 6 front matter. Listed below are brief explanations for the types of changes to the Bases. The explanations are keyed to alpha designators which are used to mark each FNP specific Bases change. In addition, the mark-ups in this enclosure show the NRC approved changes to the STS resulting from the NEl/NRC revision process. The Industry /NEl sponsored changes marked in this enclosure have been approved by the NRC unless otherwise noted in Attachment 3, and have also been determined to be applicable to FNP. He Industry /NEl revisions to the STS are marked-up and identified with the NEl tracking number (i.e., TSTF-03, TSTF-19, etc). The NEl changes are treated as though they are part of the STS for the FNP conversion. Each NEl change package contains its own justification for change which is not repeated in this conversion documentation. The FNP specific STS Bases in this enclosure will completely replace all the corresponding current FNP Bases. See the following page for an explanation of the categories of

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changes used in the bases.

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Farley Nuclear Plant ITS conversion Submittal Imoroved Technical Specifications Conversion Reviewers Guide L

KEY EXPLANATION FOR FNP SPECIFIC BASES CHANGES TSC-#

Technical Specification Change - Tnis Bases change is due to a corresponding change made to the associated STS LCO and is explained in detail in the associated Enclosure 5 JD. The JD number used in Enclosure 5 is also referenced in the Bases markup (as TSC

  1. ) where applicable.

PSC Plant Specific Change - The Bases information is revised to conform to FNP design, analysis, terminology, or operating practice. This change may result in a deletion or revision ofinformation contained in the STS Bases.

PSE Plant Specific Enhancement - Additional information specific to FNP is provided to enhance the STS Bases information consistent with FNP design, analysis, terminology, or operating practice.

E Editorial - Changes made to the NUREG-1431 Bases to improve clarity and understanding or correct minor errors.

D Deletion - This STS Bases information is deleted. The information constitutes extra detail not required to support the TS requirements for Operability, Applicability, Actions, Completion Times, or Surveillances. The information is not required or not t

readily verified for FNP, or is contained in other documents already referenced in the Bases.

DV Al 7

Farley Nuclear Plant ITS corwersion Submittal l

1 Joseph M. Farley Nuclear Plant An Overview of the Disposition of LCO's in the FNP ITS Conversion O

O l

Far.:-

wlear Plant ITF.anve.sion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev i Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 1.0 USE AND APPLICATION 1.0 Definitions 1.1 Definitions 1.1 Definitions NA 1.2 Logical 1.2 Logical New ITS 1.2 Connectors Connectors NA 1.3 Completion Times 1.3 Completion Times New ITS 1.3 NA 1.4 Frequency 1.4 Frequency New ITS 1.4 2.0 SAFETY LIMITS (SLs) 2.1.1 Reactor Core SL 2.1.1 Reactor Core SL 2.1.1 Reactor Core SL 2.1.2 RCS Pressure 2.1.2 RCS Pressure 2.1.2 RCS Pressure SL SL SL 2.2.1 RTS Setpoints 3.3.1 RTS 3.3.1 RTS CTS LSSS moved from 2.0 to Instrumentation section 3.3.

NA 2.2 SL Violations 2.2 SL Violations Information from these sections was contained in CTS 2.1.1 and 2.1.2.

3.0 LCO AND SR APPLICABILITY 3.0.I LCO 3.0.1 LCO 3.0.1 3.0.2 LCO 3.0.2 LCO 3,0.2 3.0.3 LCO 3.0.3 LCO 3.0.3 3.0.4 LCO 3.0.4 LCO 3.0.4 3.0.5 NA NA CTS 3.0.5 was removed from the TS.

(1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.

A21

Farley Nuclear Pl nt ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1)

NA LCO 3.0.5 LCO 3.0.3 New ITS 3.0.5.

NA LCO 3.0.6 LCO 3.0.6 New ITS 3.0.6.

NA LCO 3.0.7 LCO 3.0.7 New ITS 3.0.7.

4.0.1 SR 3.0.1 SR 3.0.1 4.0.2 SR 3.0.2 SR 3.0.2 4.0.3 SR 3.0.3 SR 3.0.3 4.0.4 SR 3.0.4 SR 3.0.4 4.0.5 NA NA CTS 4.0.5 retained in part as IST Program in ITS Section 5.0.

3.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1.1 SDM - Tavg 3.1.1 SDM 3.1.1 SDM - Tavg >

FNP ITS 3.1.1 f

> 200 F 200 F contains requirements i

for SDM at all temperatures.

\\

i 3/4.1.1.2 SDM - Tavg NA 3.1.2 SDM - Tavg s Separate SDM LCOs s 200 F 200 F are no longer necessary due to SDM limits being contained within the COLR.

NA 3.1.2 Core Reactivity 3.1.3 Core Reactivity New LCO derived from existing CTS requirements.

3/4.1.1.3 MTC 3.1.3 MTC 3.1.4 MTC 3/4.1.1.4 Minimum 3.4.2 Minimum 3.4.2 Minimum CTS LCO moved to Temperature for Temperature for Temperature for RCS Section (3.4).

Criticality Criticality Criticality b

(!) See the applicable Enclosure i CTS markup or isnelosure 4 STS markup for more detailed information.

A2-2

Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP LTS)

(1) 3/4.1.2.1 Boration NA NA Relocated.

Flow Paths -

Shutdown 3/4.1.2.2 Boration NA NA Relocated.

Flow Paths -

Operating 3/4.1.2.3 Charging NA NA Relocated.

Pump - Shutdown 3/4.1.2.4 Charging NA NA Relocated.

Pumps - Operating 3/4.1.2.5 Borated NA NA Relocated.

Water Sources -

Shutdown g

3/4.1.2.6 Borated NA NA Relocated.

Water Sources -

Operating 3/4.1.3.1 Movable 3.1.4 Rod Group 3.1.5 Rod Group Control Assemblies -

Alignment Limits Alignment Limits Group licight 3/4.1.3.2 Position 3.1.7 Rod Position 3.1.8 Rod Position Indication Systcms -

Indication Indication Operating i

3/4.1.3.3 Position NA NA Relocated.

~

Indication Systems -

Shutdown 3/4.1.3.4 Rod Drop NA NA LCO and Actions Time removed from TS.

Surveillance requirement retained in FNP ITS 3.1.4.

(1) See the applicable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed infonnation.

A2-3

Faricy Nuclear Plant ITS conversion Submittal i

An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 3/4.1.3.5 Shutdown 3.1.5 Shutdown Bank 3.1.6 Shutdown Bank Rod Insertion Limit insertion Limits insertion Limits 3/4.1.3.6 Control Rod 3.1.6 Control Bank 3.1.7 Control Bank Insertion Limits insertion Limits Insertion Limits 3/4.10.2 Group 3.1.8 PHYSICS 3.1.9 PHYSICS CTS 3/4.10.2 moved lleight, insertion and TESTS Exception -

TESTS Exception -

into ITS Section 3.1.

Power Distribution Mode 1 Mode 1 Limits 3.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AFD 3.2.3 AFD 3.2.3B AFD (RAOC)

NA NA 3.2.3A AFD (CAOC)

Not FNP methodology.

3/4.2.2 Ileat Flux Hot 3.2.1 Heat Flux Hot 3.2.1.B Heat Flux Channel Factor Channel Factor Hot Channel Factor (F (Z))

(Fo(Z))(FQ 9

Methodology)

NA NA 3.2.1.A Heat Flux Not FNP Hot Channel Factor methodology.

(Fo(Z))(Fxy Methodology) 3/4.2.3 Nuclear 3.2.2 Nuclear 3.2.2 Nuclear Enthalpy Hot Channel Enthalpy Rise Hot Enthalpy Rise Hot Factor Channel Factor Channel Factor 3/4.2.4 QPTR 3.2.4 QPTR 3.2.4 QPTR 3/4.2.5 DNB 3.4.1 RCS Pressure, 3.4.1 RCS Pressure, CTS LCO moved to Parameters Temperature, and Temperature, and the ITS RCS Section.

Flow DNB Limits Flow DNB Limits o

\\

(1) See the applicable Enclosure ! CTS markup or Enclosure 4 STS markup for mcre detailed information.

A2-4

Farley Nuclear Plant ITS conversion Submittal O

An Overview of the Disposition of LCO's in the FNP ITS Conversion

%J Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 3.3 INSTRUMENTATION 3/4.3.1 RTS 3.3.1 RTS 3.3.1 RTS 3/4.3.2 ESFAS 3.3.2 ESFAS 3.3.2 ESFAS 3/4.3.3.1 Radiation NA NA CTS requirements Monitoring moved to other ITS Instrumentation LCOs (3.3.3, 3.3.6, 3.3.7, 3.3.8) or removed from the TS.

3/4.3.3.2 Movable NA NA Relocated.

Incore Detcetors 3/4.3.3.8 Accident 3.3.3 Post Accident 3.3.3 Post Accident Monitoring Monitoring Monitoring Instrumentation Instrumentation Instrumentation g

3/4.3.3.5 Remote 3.3.4 Remote 3.3.4 Remote Shutdown Shutdown System Shutdown System Instrumentation 3/4.3.3.7 High Energy NA NA Relocated.

Lme Break Isolation Sensors 3/4.3.3.1I Waste Gas NA NA Retained in part as Monitoring ITS 5.5.12 Explosive Instrumentation Gas and Radioactivity Monitoring Program.

3/4.3.4 Turbine NA NA Relocated.

Overspeed Protection NA 3.3.5 Loss of Power 3.3.5 Loss of Power Consists of CTS DG Start DG Start requirements Instrumentation Instrumentation previously in the ESFAS LCO plus one new alarm instrument.

(1) See the applicable Enclosure 1 CTS murkup or Enclosure 4 STS markup for more detailed infonnation.

A2 5 t-

Farley Nuelear Plant ITS conversion Submittal

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An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1)

NA 3.3.6 Containment 3.3.6 Containment Consists of CTS Purge and Exhaust Purge and Exhaust requirements isolation Isolation previously in the Instrumentation Instrumentation ESFAS LCO as well as other LCOs (e.g.,

Rad Monitors) which contained purge and exhaust isolation requirements. Puts all containment purge /

exhaust valve isolation instrumentation in one LCO.

NA 3.3.7 CREFS 3.3.7 CREFS Consists of CTS Actuation Actuation requirements from Instmmentation Instrumentation Rad Monitors as well as other LCOs which contained CREFS Actuation Instrument requirements. Puts all CREFS instrumentation in one LCO.

NA 3.3.8 Penetration 3.3.8 Fuel Building FNP specific system Room Filtration (PRF)

Air Cleanup System name (PRF). Consists System Actuation Actuation of CTS requirements Instrumentation Instrumentation from Rad Monitors as well as other LCOs which contained PRF Actuation Instrument requirements. Puts all PRF instrumentation in one LCO.

NA NA 3.3.9 Boron Dilution Not installed at FNP.

Protection System (BDPS)

OY (I) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.

A2-6

Farley Nuclear Plant ITS conversion Submittal

(

An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev i Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 3.4 REACTOR COOLA.NT SYSTEM (RCS) 3/4.2.5 DNB 3.4.1 RCS Pressure, 3.4.1 RCS Pressure, CTS LCO moved into Parameters Temperature, and Temperature, and ITS RCS Section.

Flow DNB Limits Flow DNB Limits 3/4.1.1.4 Minimum 3.4.2 Minimum 3.4.2 Minimum CTS LCO moved into Temperature for Temperature for Temperature for ITS RCS Section.

Criticality Criticality Criticality 3/4.4.10.1 RCS 3.4.3 RCS Pressure 3.4.3 RCS Pressure Pressure / Temperature and Temperature and Temperature Limits Limits Limits 3/4.4.1.1 RCS Loops 3.4.4 RCS Loops -

3.4.4 RCS Loops -

Startup and Power Modes I and 2 Modes I and 2

(]

Operation V

3/4.4.1.2 RCS - Hot 3.4.5 RCS Loops -

3.4.5 RCS Loops -

Standby Mode 3 Mode 3 3/4.4.1.3 RCS - Hot 3.4.6 RCS Loops -

3.4.6 RCS Loops -

Shutdown Mode 4 Mode 4 3/4.4.1.4 RCS - Cold 3.4.7 RCS Loops -

3.4.7 RCS Loops -

CTS LCO split into j

Shutdown Mode 5, Loops filled.

Mode 5, Loops filled.

two ITS LCOs.

i 3.4.8 RCS Loops -

3.4.8 RCS Loops -

Mode 5, Loops Not Mode 5, Loops Not Filled Filled 3/4.4.2 Safety Valves-NA NA Relocated.

Shutdown 3/4.4.3 Safety Valves 3.4.10 Pressurizer 3.4.10 Pressurizer

- Operating Safety Valves Safety Valves 3/4.4.4 Pressurizer 3.4.9 Pressurizer 3.4.9 Pressurizer a

'j (1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.

A2-7

Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 3/4.4.5 Relief Valves 3.4.11 Pressurizer 3.4.11 Pressurizer Power Operated Relief Power Operated Rclief Valves Valves 3/4.4.6 Steam NA NA CTS LCO and Generators Actions removed and surveillance requirements retained in ITS Section 5.0 as a program.

3/4.4.7.1 RCS 3.4.15 RCS Leakage 3.4.15 RCS Leakage Leakage Detection Detection Detection Systems Instrumentation Instrumentation 3/4.4.7.2 Operational 3.4.13 Operational 3.4.13 Operational CTS LCO split into Leakage Leakage Leakage two ITS LCOs.

3.4.14 RCS Pressure 3.4.14 RCS Pressure '

isolation Valve Isolation Valve Leakage Leakage 3/4.4.10.3 3.4.12 Low 3.4.12 Low Overpressure Temperature Temperature Protection Systems Overpressure Overpressure Pro'.ection (LTOP)

Protection (LTOP)

System System 3/4,4.8 Chemist.y NA NA Relocated.

3/4.4.9 Specific 3.4.16 RCS Specific 3.4.16 RCS Specific Activity Activity Activity 3/4.10.2 Pressurizer NA NA Relocated.

P/r Limits

/~'%

(1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.

A2-8

Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREC-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 3/4.4.11 RCS NA NA Addressed by existing Structural Integrity Inservice Test and Inspection Programs and new program added to ITS 5.0 to cover specific surveillances of this LCO.

NA NA 3.4.17 RCS Loop Not installed at FNP.

Isolation Valves

~

NA NA 3.4.18 RCS isolated No Loop isolation Loop Startup valves at FNP.

3/4.10.4 RCS Loops NA 3.4.19 RCS Loops -

No longer used at Test Exception Test Exception FNP and deleted in FNPITS.

3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3/4.5.1 Accumulators 3.5.1 Accumulators 3.5.1 Accumulators 3/4.5.2 ECCS 3.5.2 ECCS -

3.5.2 ECCS -

Subsystems - Tavg 2 Operating Operating 350*F 3/4.5.2 ECCS 3.5.3 ECCS -

3.5.3 ECCS -

Subsystems - Tavg <

Shutdown Shutdown 350 F 3/4.5.5 RWST 3.5.4 RWST 3.5.4 RWST NA 3.5.5 Seal injection 3.5.5 Seal injection New LCO containing Flow Flow CTS requirements from RCS Operational Leakage.

O (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS marl,up for more detailed information.

A2-9

Farley Nuclear Plant ITS conversion Submittal

(

An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431 Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 3/4.5.6 ECCS 3.5.6 ECCS NA FNP specific LCO for Recirculation Fluid Recirculation Fluid TSP in containment pil Control System pl-1 Comrol System instead of spray add tank system. This LCO is not part of the STS.

3.6 CONTAINMENT SYSTEMS 3/4.6.1.1 Containment 3.6.1 Contaimnent 3.6.1 Containment integrity 3/4.6.1.2 Containment NA NA Rese CTS leakage requirements incorporated into other LCOs, programs, or removed from the TS.

3/4.6.1.3 Cmtairunent 3.6.2 Containment Air 3.6.2 Containment Air Air Lecks Locks Locks i

3/4.6.1.4 Internal 3.6.4 Containment 3.6.4A Containment Pressure Pressure Pressure (Atmospheric, Dual, and Ice Condenser) j NA NA 3.6.4B Containment Not part of the FNP Pressure design.

(Subatmospheric) 3/4.6.1.5 Air 3.6.5 Containment Air 3.6.5 A Containment Temperature Temperature Air Temperature (Atmospheric and Dual)

NA NA 3.6.5B Containment Not part of the FNP Air Temperature (Ice design.

Condenser)

~O V

(I) Sec the applicable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed infonnation.

A2-10

s Farley Nuci:ar Plant ITS conversion Submittal

[J An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Ltandard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1)

NA NA 3.6.5C Containment Not part of the FNP

]

Air Temperature design.

(Subatmospheric) 3/4.6.1.6 Containment NA NA Removed from the TS.

Structural Integrity Tendon surveillances retained in section 5.0 program.

3/4.6.1.7 Containtnent 3.6.3 Containment 3.6.3 Containment All containment Ventilation System Isolation Valves isolation Valves isolation valve (Purge and Exhaust requirements are Isolation Valves) addressed in one LCO.

3/4.6.3 Containment l

Isolation Valves G

3/4 6 2.1 Contamment 3.6.6 Contamment 3.6.6A Containment Two CTS LCOs are Spray System Spray and Cooling Spray and Cooling combinei into one ITS System System (Atmospheric LCO.

3/4.6.2.3 Containment and Dual) (Credit Cooling System Taken for lodine Removal by the Spray System)

NA NA 3.6.6B Containment Not consistent with Spray and Cooling appheable FNP System (Atmospheric analysis (FNP credits and Dual)(Credit not iodine removal by the Taken for lodine Spray System).

Removal by the Spray System)

NA NA 3.6.6C Containment Not part of the FNP Spray System (Ice design.

Condenser)

NA NA 3.6.6D Quench Spray Not part of the FNP System design.

p (Subatmospheric)

Y)

(1) See the apphcable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed mformation.

A2-Il i

Farley Nuclear Plant ITS conversion Subnittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1)

NA NA 3.6.6E Recirculation Not part of the FNP Spray System design.

(Subatmospheric)

NA NA 3.i7 Spray Additive This system recently System removed from FNP and replaced with TSP inside containment (see CTS 3/4.5.6).

3/4.6.4 liydrogen 3.3.3 Post Accident 3.3.3 Post Accident The requirements of Analyzers Monitoring Monitoring this LCO are moved Instrumentation Instrumentation into the Post Accident Monitoring LCO consistent with the purpose of the p

instrumentation.

V 3/4.6.4.2 Electric 3.6.7 liydrogen 3.6.8 Hydrogen liydrogen Recombiners Recombiners Recombiners 3/4.6.4.411ydrogen 3.6.8 liydrogen 3.6.9 Hydrogen Maing System Mixing System Mixing System 3/4.6.4.3 Reactor 3.6.9 Reactor Cavity NA FhP specific system Cavity Hydrogen liydrogen Dilution and TS.

Dilution System System NA NA 3.6.10 Hydrogen Not part of the FNP Ignition System (Ice design.

Condenser)

NA NA 3.6.1 I lodine Cleanup Not part of the FNP System (Atmospheric design.

and Subatmospheric)

NA NA 3.6.12 Vacuum Relief Not part of the FNP Valves (Atmospheric

design, and Ice Condenser)

(s.

(1) See the applicable Enclosure I (.TS markup or Enclosure 4 STS markup for more detailed information.

A2-12

4 Farley Nuclear Plant ITS conversion Submittal 2

An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1)

NA NA 3.6.13 Shield Building Not pan of the FNP Air Cleanup System design.

j (Dual and Ice l

Condenser)

NA NA 3.6.14 Air Return Not part of the FNP System (Ice design.

Condenser)

I NA NA 3.6.15 lee Bed (Ice Not part of the FNP Condenser) design.

NA NA 3.6.16 Ice Condenser Not part of the FNP Doors (Ice Condenser) design.

NA NA 3.6.17 Divider Barrier Not part of the FNP O

Integrity (Ice design.

{

D Condenser)

NA NA 3.6.18 Containment Not part of the FNP Recirculation Drains design.

(Ice Condenser)

NA NA 3.6.19 Shield Building Not part of the FNP (Dual and Ice design.

Condenser) 3.7 PLANT SYSTEMS 3/4 7.1.1 Turbine 3.7.1 Main Steam 3.7.1 Main Stexn Cycle Safety Valves Safety Valves Safety Valves 3/4.7.1.2 AFW 3.7.5 AFW 3.7.5 AFW 3/4.7.1.3 Condensate 3.7.6 Condensate 3.7.6 Condensate Storage Tank Storage Tank Storage Tank 3/4.7.1.4 Activity 3.7.16 Secondary 3.7.18 Secondary Specific Activity Specific Activity (1) See the applicabl: Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.

A2-13

. l.

Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 3/4.7.1.5 Main Steam 3.7.2 Main Steam 3.7.2 Main Steam Line Isolation Valves Isolation Valves isolation Valves NA 3.7.3 Main Feedwater 3.7.3 Main Feedwater New LCO requirement Stop Valves and Main Isolation Valves and for FNP.

Feedwater Regulation Main Feedwater Valves and Associated Regulation Valves and Bypass Valves Associated Bypass Valves NA 3.7.4 Atmospheric 3.7.4 Atmospheric New LCO requirement ReliefValves Dump Valves for FNP.

3/4.7.2 Steam NA NA Relocated.

Generator Pressurefremperature Limitation 4

3/4.7.3 Component 3.7.7 Component 3.7.7 Component Cooling Water Cooling Water Cooling Water 3/4.7.4 Service Water 3.7.8 Service Water 3.7.8 Service Water System System System 3/4.7.6.2 Ultimate 3.7.9 Ultimate Heat 3.7.9 Ultimate Heat Heat Sink - Pond Sink Sink 3/4.7.7.1 Control 3.7.10 Control Room 3.7.10 Control Room Room Emergency Emergency Filtration /

Emergency Filtration Filtration /

Pressurization System System (CREFS)

Pressurization System (CREFS)

(CREFS) 3/4.7.7.2 Control 3.7.11 Control Room 3.7.11 Control Room Room Air Air Conditioning Emergency Air Conditioning System System (CRACS)

Temperature Control (CRACS)

System n

(1) See the applicable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed information.

A2-14

Farley Nucle:r Plant ITS conversion Submittal f*h

]

An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1)

NA NA 3.7.12 ECCS Pump STS LCO 3.7.13 more Room Exhaust Air closely matches the Cleanup System FNP design for this (PREACS) system.

3/4.7.8 Penetration 3.7.12 Penetration 3.7.13 Fuel Building STS LCO 3.7.13 Room Filtration Room Filtration (PRF)

Air Cleanup System addresses a system System System (FBACS) that performs two functions (penetration area / pump room cleanup (Modes 1-4) and fuel handling area cleanup during movement of irradiated fuel). This dual function system most closely matches k

the FNP PRF system.

NA NA 3.7.14 Penetration STS LCO 3.7.13 more Room Exhaust Air closely matches the Cleanup System FNP design for this (PREACS) system.

3/4.7.9 Snubbers NA NA Relocated.

I 3/4.7.10 Scaled NA NA Relocated.

Source Contamination 3/4.7.13 Area NA NA Relocated.

Temperature Monitoring (Unit 2 only) l ' p).

!N s.-

(1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.

A2-15

c.

Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 3/4.7.13 (Unit 1) Fuel 3.7.14 Fuel Storage 3.7.16 Fuel Storage Unit I and 2 have Storage Pool Boron Pool Boron Pool Boron ditTerent numbers due Concentration Concentration Concentration to the additional Unit 2 CTS LCO 3/4.7.13 3/4.7.14 (Unit 2) Fuct for Area Temperature Storage Pool Boron Monitoring. The area Concentration temperature monitoring LCO will not exist it. the FNP ITS.

3/4.7.14 (Unit 1) Fuel 3.7.15 Spent Fuel 3.7.17 Spent Fuel Unit I and 2 have Assembly Storage Assembly Storage Assembly Storage difTerent numbers due to the additional Unit 3/4.7.15 (Unit 2) Fuel 2 CTS LCO 3/4.7.13 Assembly Storage for Area Temperature O

Monitoring. The area d

temperature monitoring LCO will not exist in the FNP ITS.

3/4.9.11 Water Level 3.7.13 Fuel Storage 3.7.15 Fuel Storage This CTS LCO moved Storage Pool Pool Water Level Pool Water Level from the Refueling Section of TS to the Plant System Section consistent with the STS.

3.8 ELECTRICAL POWER SYSTEMS 3/4.8.1.1 AC Sources 3.8.1 AC Sources -

3.8.1 AC Sources

- Operating Operating Operating 3/4.8.1.2 AC Sources 3.8.2 AC Sources -

3.8.2 AC Sources -

- Shutdowr.

Shutdown Shutdown IG (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup lbr more detailed information.

A2-16

Farley Nuclear Plant ITS conversion Submittal

' (G An Overview of the Disposition of LCO's in the FNP ITS Conversion

/

v Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1)

NA 3.8.3 Diesel Fuel, 3.8.3 Diesel Fuel, New LCO derived Lube Oil, and Starting Lube Oil, and Starting from some existing TS Air Air requirements (3/4.8.1.1) and some new TS requirements (lube oil and startmg i

l air).

l l

3/4.8.2.1 AC 3.8.4 DC Sources -

3.8.4 DC Sources -

CTS LCOs are re-Distribution -

Operating Operating organized consistent Operating with the STS format 3.8.6 Battery Cell 3.8.6 Battery Cell of these requirements.

3/4.8.2.3 Auxiliarv Parameters Parameters Building DC Distnbution -

3.8.7 inverters -

3.8.7 inverters -

Operating Operating Operating

/

l\\U Service Water 3.8.9 Distribution 3.8.9 Distribution Building DC Systems - Operating Systems - Operating Distribution -

Operating 3/4.8.2.2 AC 3.8.5 DC Sources -

3.8.5 DC Sources -

CTS LCOs are re-Distribution -

Shutdown Shutdown organized consistent Shutdown with the STS format 3.8.8 Inverters -

3.8.8 Inverters -

of these requirements.

3/4.8.2.4 Auxiliary Shutdown Shutdown Building DC Distribution -

3.8.10 Distribution 3.8.10 Distribution Shutdown Systems - Shutdown Systems - Shutdown I

3/4 8.3.1 Containment NA NA Relocated.

t Penetration Conductor Overcurrent Protective Devices (Unit 2 only) 3/4.8.3.2 Motor NA NA Relocated.

Operated Valves Thennal Overload

,o Protection Devices (v)

(Unit 2 only)

(1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed information.

A2 17

Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion l

lV Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS) l l

(FNP ITS)

(1) 3.9 REFUELING OPERATIONS 3/4.9.1 Boron 3.9.1 Boron 3.9.1 Boron Concentration Concentration Concentration NA NA 3.9.2 Unborated This STS LCO is not Water Source consistent with the Isolation Valves FNP refueling Boron dilution analysis.

3/4.9.2 3.9.2 Nuclear 3.9.3 Nuclear l

Instrumentation Instrumentation Instrumentation 3/4.9.3 Decay Time NA NA Relocated 3/4.9.4 Containment 3.9.3 Containment 3.9.4 Containment The CTS LCOs are Building Penetrations Penetrations Penetrations combined into one Containment 3/4.9.9 Containment Penetration LCO l

Purge and Exhaust consistent with the isolation System STS.

3/4.9.5 NA NA Relocated.

Communications 3/4.9.6 Manipulator NA NA Relocated.

Crane 3/4.9.7.1 Crane Travel NA NA Relocated.

- Spent Fuel Storage Pool Building Bridge Crane 3/4.9.7.1 Crane Travel NA NA Relocated.

- Spent Fuel Storage Pool Spent Fuel Cask Crane 3/4.9.8.I RHR and 3.9.4 RHR and 3.9.5 RHR and Coolant Circulatien Coolant Circulation -

Coolant Circulation -

(/n)

All Water Levels.

High Water Level High Water Level w

(1) See the apphcable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.

A2-18

?

Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 3/4.9.8.2 RHR - Low 3.9.5 RHR and 3.9.6 RHR and Water Level Coolant Circulation -

Coolant Circulation -

Low Water Level Low Water Level 3/4.9.10.1 Water 3.9.6 Refueling Cavity 3.9.7 Refueling Cavity CTS LCOs combined Level Reactor Vessel Water Level Water Level into one LCO Fuel Assemblies consistent with the STS.

3/4.9.10.2 Water Level Reactor Vessel Control Rods 3/4.9.1 i Water Level -

3.7.13 Fuel Storage 3.7.15 Fuel Storage This CTS LCO moved Storage Pool Pool Water Level Pool Water Level to Plant Systems Section consistent with O

the STS.

3/4.9.12 Storage Pool NA NA Relocated.

Ventilation (Fuel Storage) 3/4.9.13 Storage Pool 3.7.12 Penetration 3.7.13 Fuel Building his CTS LCO moved Ventilation (Fuel Room Filtration (PRF)

Air Cleanup System to the Plant Systems Movement)

System (FBACS)

Section and combined with the Mode 1-4 LCO for the PRF system consistent with the closest corresponding STS LCO 3.7.13 FBACS.

O (1) See the applicable Enclosure ! CTS markup or Enclosure 4 STS markup for more detailed infonnation.

A2-19

Farley Nuclear Plant ITS conversion Submittal

(

An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Sp ecifications Specifications (STS)

(FNP ITS)

(1)

CTS 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 Shutdown NA NA This CTS LCO is Margin deleted consistent with TSTF changes to the STS.

3/4.10.2 Group NA NA This CTS LCO is lleight, lasertion and deleted consistent with Po;<er Distribution TSTF changes to the Limits STS.

3/4.10.3 Physics 3.1.8 Physics Tests 3.1.10 Physics Tests This CTS LCO is Tests Exceptions - Mode 2 Exceptions - Mode 2 moved to the reactivity control section of the TS consistent with the STS.

s 3/4.10.4 Reactor NA 3.4.19 RCS Loops This CTS test Coolant Loops.

Test Exception exception is no longer used at FNP and has been eliminated from the FNP ITS.

3/4.10.5 Position NA NA Relocated.

Indicating System -

Shutdown (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed infonnation.

A2-20

Farley Nuclear Plant ITS conversion Submittal

'O An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1)

CTS 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.4 Liquid NA NA

'Ihis LCO retained in Holdup Tanks part within the Explosive Gas and I

Storage Tank Radioactivity Monitoring Program in Section 5.0 of the FNP ITS. Other elements of the program will b':

placed in the TRM.

3/4.11.2.5 Waste Gas NA NA This LCO retained in I

Monitoring part within the

/7 Explosive Gas and V

Storage Tank Radioactivity Monitoring Program in Section 5.0 of the FNP ITS. Other elements of the program will be placed in the TRM.

3/4.11.2.6 Gas NA NA This LCO retained in Storage Tanks part within the Explosive Gas and Storage Tank Radioactivity Monitoring Program in Section 5.0 of the FNP ITS. Other elements of the program will be placed in the TRM CT V

(1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed information.

A2 21

Farley Nuclear Plant ITS conversion Submittal

/^

An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev i Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1)

CTS 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING No LCOs are NA NA All CTS LCOs in this contained in this CTS section were deleted section.

by presious amendments. The ITS conversion deletes the remaining blank pages in this section.

4.0 DESIGN FEATURES 5.1 Site 4.1 Site Location 4.1 Site Location Text description only.

5.1.1 Exclusion Area NA NA Figure removed from the TS.

C\\

V 5.1.2 Low Population NA NA Figure removed from Zone the TS.

5.1.3 Site Boundary NA NA Figure removed from for Gaseous Emuents the TS.

5.1.4 Site Boundary NA NA Figure removed from for Liquid Emuents the TS, 5.2 Containment NA NA Section removed from the TS.

5.3 Reactor Core 4.2 Reactor Core 4.2 Reactor Core 5.3.1 Fuel Assemblies 4.2.1 Fuel Assemblies 4.2.1 Fuel Assemblies 5.3.2 Control Rod 4.2.2 Control Rod 4.2.2 Control Rod Assemblies Assemblies Assemblies 5.4 RCS NA NA Section removed from the TS.

5.5 Meteorological NA NA Section removed from

.I Tower Location the TS.

A (1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.

A2-22

Fuley Nuclear Plant ITS conversion Submittal (O

An Overview of the Disposition of LCO's in the FNP ITS Conversion

)

%/

Current Technical FNP Specific NUREG-1431, Rev i Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 5.6 Fuel Storage 4.3 Fuel Storage 4.3 Fuel Storage 5.6.1 Criticality 4.3.1 Criticality 4.3.1 Criticality 5.6.2 Drainage 4.3.2 Drainage 4.3.2 Drainage 5.6.3 Capacity 4.3.3 Capacity 4.3.3 Capacity 5.7 Component Cyclic NA NA Moved to or Transient Limit Administrative Controls Section as a program.

5.0 ADMINISTRATIVE CONTROLS 6.1 Responsibility 5.1 Responsibility 5.1 Responsibility

/

(/

6.2 Organization 5.2 Organization 5.2 Organization 6.2.1 Offsite and 5.2.1 Onsite and 5.2.1 Onsite and Onsite Organization Offsite Organization Offsite Organization 6.2.2 Facility Staff 5.2.2 Unit Staff 5.2.2 Unit Staff 6.2.3 Safety Audit and NA NA Moved out ofTS into Engineering Review QA Program.

Group 6.2.4 Shift Technical 5.2.2.g 5.2.2.g Moved to an untitled Advisor paragraph under Unit Staff.

6.3 Facility Staff 5 3 Unit Staff 5.3 Unit StafT Qualifications Qualifications Qualifications 6.4 Training NA NA Removed from the TS and contained in the FSAR.

/%.

ll

\\

().

(1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed infonnation.

A2-23

Farley Nuc! car Plant ITS conversion Submittal O

An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 6.5 Review and Audit NA NA Removed from the TS and placed in the QA Program.

6.6 Reportable Event NA NA Removed from the TS.

Action 6.7 Safety Limit NA NA Removed from the TS.

Vmlation 6.8 Procedures and 5.4 Procedures 5.4 Procedures Programs 5.5 Programs and 5.5 Programs and Manuals Manuals 6.13 Offsite Dose 5.5.1 Offsite Dose 5.5.1 Offsite Dose Calculation Manual Calculation Manual Calculation Manual 6.8.3.a Primary 5.5.2 Primary Coolant 5.5.2 Primary Coolant Coolant Sources Sources Outside Sources Outside Outside Containment Containment Containment 6.8.3.b In Plant NA NA Removed from the TS Radiation Monitoring to the FSAR.

6.8.3.c Secondary 5.5.10 Secondary 5.5.10 Secondary Water Chemistry Water Chemistry Water Chemistry 6.8.3.d Post Accident 5.5.3 Post Accident 5.5 3 Post Accident Sampling Sampling Sampling 6.8.3.e Radioactive 5.5.4 Radioactive 5.5.4 Radioactive Efiluent Controls Effluent Controls Effluent Controls Program Program Program 6.8.3.f Radiological NA NA Removed from the TS Environmental to the ODCM.

Monitoring Program O

V (1) See the apphcable Enclosure i CTS markup or Enclosure 4 STS markup for more detailed infonnation.

A2-24

.~s Farley Nuclear Plant ITS conversion Submittal An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 6.8.3.g Solid NA NA Removed from the TS Radioactive Wastes to the FSAR.

Control Program NA 5.5.5 Component 5.5.5 Component Moved from the Cyclic or Transient Cyclic or Transient Design Features Limit Limit section of the CTS.

NA 5.5.6 Pre-Stressed 5.5.6 Pre-Stressed Moved from the Concrete Containment Concrete Containment Containment Tendon Surveillance Tendon Surveillance Structural Integrity Program Program LCO in Section 3.6.

NA 5.5.7 Reactor Coolant 5.5.7 Reactor Coolant Moved from the RCS Pump Flywheel Pump Flywheel Structural Integrity inspection Program inspection Program LCO in section 3.4.

NA 5.5.R Inservice Testing 5.5.8 Inservice Testing Moved from CTS Program Program 4.0.5.

NA 5.5.9 SG Tube 5.5.9 SG Tube Mosed from the SG Surveillance Program Surveillance Program LCO in section 3.4.

6.8.3.c Secondary 5.5.10 Secondary 5.5.10 Secondary Water Chemistry Water Chemistry Water Chemistry NA 5.5.11 Ventilation 5.5.1i Ventilation Moved from various Filter Testing Program Filter Testing Program ventilation system LCOs in the CTS.

NA 5.5.12 Explosive Gas 5.5.12 Explosive Gas Moved from related and Storage Tank and Storage Tank LCOs in the CTS.

Radioactivity Radioactivity Monitoring Program Monitoring Program NA 5.5.13 Diesel Fuel Oil 5.5.13 Diesel Fuel Oil Moved from CTS Testing Program Testing Program requirements in Electrical Section of the CTS.

bv (1) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed information.

l A2-25 i

Farley Nuclear Plant ITS conversion Submittal

,t An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific -

NUREG-1431, Rev i Specifications (CTS)

Improved Technical Standard Technical -

Notes Specifications Specifications (STS)

(FNP E S)

(1)

NA 5.5.14 Technical 5.5.14 Technical New Program Specification Bases Specification Bases introduced in the STS.

Control Program Control Program NA 5.5.15 Safety Function 5.5.15 Safety Function New Program Determination Determination introduced in the STS.

Program Program NA 5.5.16 Main Steamline NA FNP Specific Inspection Program requirements moved from the RCS Structural Integrity LCO in Section 3.4.

6.16 Containment 5.5.17 Containment NA FNP specific Leakage Rate Testing Leakage Rate Testing requirements resulting Program Program from adoption of 10CFR50 App. J Option B.

6.9 Reporting 5.6 Reporting 5.6 Reporting Requirements Requirements Requirements 6.9.1.1-3 Startup NA NA Deleted.

Report 6.9.1.4 Annual NA NA Section title deleted.

Reports 6.9.1.5.a (untitled) 5.6.1 Occupational 5.6.1 Occupational Radiation Exposure Radiation Exposure Report Report 6 9 l.6-7 Annual 5.6.2 Annual 5.6.2 Annual Radiological Radiological Radiological Environmental Environmental Environmental Operating Report-Operating Report Operating Report 6.9.1.8-9 Annual 5.6.3 Radioactive 5.6.3 Radioactive o

Radioactive Efiluent Efiluent Release Efiluent Release Release Report Report Report (I) See the applicable Enclosure I CTS markup or Enclosure 4 STS markup for more detailed infonnation.

A2-26

.M Farley Nuclear Plant ITS conversion Submittal r

/

An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev 1 Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 6.9.1.10 Monthly 5.6.4 Monthly 5.6.4 Monthly Operating Report Operating Reports Operating Reports 6.9.1.11 Core 5.6.5 Core Operating 5.6.5 Core Operating Operating Limits Limits Report Limits Report Report 6.9.1.12 Annual 5.6.7 Emergency 5.6.7 Emergency Diesel Generator Diesel Generator Diesel Generator Reliability Data Failure Report Failure Report Report 6.9.1.13 Annual NA NA Deleted Reactor Coolant System Specific Activity Report k

6.9.1.14 Annual NA NA Deleted Scaled Source Leakage Report 6.9.1.15 Pressure 5.6.6 RCS Pressure 5.6.6 RCS Pressure Temperature Limits Temperature Limits Temperature Limits Report Report Report NA 5.6.8 Post Accident 5.6.8 Post Accident New report introduced Monitoring Report Monitoring Report by the STS.

NA 5.6.9 Tendon 5.6.9 Tendon New report introduced Surveillance Report Surveillance Report by the STS.

NA 5.6.10 Steam 5.6.10 Steam Moved from the CTS Generator Tube Generator Tube SG LCO in the RCS Inspection Report inspection Report section of the CTS.

NA 5.6.11 Alternate AC 5.6.11 Alternate AC Based on existing (AAC) Source Out of (AAC) Source Out of CTS requirements Service Report Service Report 6.8.1.j for AAC.

']

6.9.2 Special Reports NA NA Deleted.

v (1) See the applicable Enclosure 1 CTS markup or Enclosure 4 STS markup for more detailed information.

A2 27

1

,W

.h Farley Nuclear Plant ITS conversion Submittal p.

An Overview of the Disposition of LCO's in the FNP ITS Conversion Current Technical FNP Specific NUREG-1431, Rev i Specifications (CTS)

Improved Technical Standard Technical Notes Specifications Specifications (STS)

(FNP ITS)

(1) 6.10 Record Retention NA NA Removed from the TS and placed in the QA Program.

6.11 Radiation NA NA Removed from the TS.

Protection Program 6.12 High Radiation 5.7 High Radiation 5.7 High Radiation Area Area Area 6.13 Process Control NA NA Removed from the TS Program and placed in the FSAR.

6.14 Offsite Dose 5.5.1 ODCM 5.5.1 ODCM Calculation Manual (ODCM) 6.15 Major Changes NA NA The information To Radioactive Waste contained in this Treatment Systems section was deleted by a previous amendment. The empty section is deleted in the ITS conversion.

6.16 Containment 5.5.17 Contaimnent NA FNP specific Leakage Rate Testing Leakage Rate Testing requirements resulting Program Program from adoption of 10CFR50 App. J Option B.

O V

(1) See the applicable Enclosure l CTS markup or Enclosure 4 STS markup for more detailed information.

A2 28

s Farley Nuc! car Plant ITS conversion Submittal O

Joseph M. Farley Nuclear Plant Farley CTS License Amendment Requests Incorporated into the ITS O

O

4 Farley Nuc! car Plant ITS conversion Submittal Farley CTS License Amendment Requests incorporated into the ITS License Amendment Request Affected ITS Specifications Affected CTS Pages (Title and Letter Date)

Facility Operating Licenses and 1.0, 2.0, 3.2, 3.3, 3.4, 3.5, 3.6, 1-6,2-5 through 2-7, 3/4 2-15, Technical Specifications Change 4.0, 5.0 3/43-25,3/43-27,3/43-28,3/4 Request for Power Uprating, 4-12b (Unit 2 only),3/4 7-9,5-6, February 14,1997 5-8,6-19a,6-24, B 3/4 2-5, B 3/4 4-3b (Unit 2 only), B 3/4 5-5, B 3/4 6-2, and B 3/4 7-1 Technical Specification 3.3, 3.5 3/43-2,3/43-6,3/43-14,3/45-ComplianceIssues Amendments, 3 and 3/4 5-7 May 27,1997 Control Room, Penetration 3.3, 3.9 3/43-39,3/43-40,3/47-16,3/4 Room, and Containment Purge 7-17,3/4 7-17a,3/4 7-18,3/4 7-Filtration systems and Radiation 19,3/4 9-14 through 3/4 9-18, B Monitoring Instmmentation, June 3/4 7-4, B 3/4 7-4a, B 3/4 9-3 30,1997

(

Pressure Temperature Limits 1.0, 3.4, 5.0 1-5,3/44-27,3/44-29,3/44-30, O

Report, July 23,1997 6-20,6-20a, B 3/4 4-6 through B

)

d 3/4 4-10, B 3/4 4-10a, and B 3/4 4-11 through B 3/4 4-14 Auxiliary Building & Service 3.8 3/4 8-9(a) and 3/4 8-13 Water Building Battery Surveillances, December 30, 1997 Intermediate Range Neutron Flux 2.0, 3.1, 3.3 2-5,3/410-3, and B 2-4 Reactor Trip Setpoint, December 31,1997 Pressure Temperature Limits 3.4, 5.0 3/4 4-3,3/4 4-4a,3/4 4-32, B 3/4 Report February 12,1998 4-1, and B 3/4 4-8 Response to Request for 5.0 6-19a Additional Information Related to Power Uprate Facility Operating Licenses and Technical Specifications change Request, February, 12,1998 (3

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A3-1

]

Farley Nuclear Plant ITS conversion Submittal O

i l

l

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I i

Joseph M. Farley Nuclear Plant i

Generic Changes to NUREG-1431, Rev.1. Incorporated into the ITS O

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J

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1 Farley Nuclear Plant ITS conversion Subasttal Generic Changes to NUREG 1431, Rey,1, incorporated into the ITS FNP ITS Chapter TSTF's incorporated Comments 1.0 None 2.0 TSTF-5 3.0 TSTF-6, TSTF-8, TSTF-12, TSTF-71,TSTF 104,TSTF-122, TSTF-165, TSTF-166 3.1 TSTF-9, TSTF-12, TSTF-13, TSTF-14, TSTF-15, TSTF-89, TSTF-108 TSTF-110,TSTF-136, TSTF-141. TSTF.142 3.2 TSTF-95. TSTF-97, TSTF-98, TSTF-99, TSTF-109. TSTF-110, TSTF-136 3.3 TSTF-161 TSTF-169 O

3.4 TSTF-28,TSTF-54 TSTF-60, TSTF's 26,93,94, and 108 not TSTF-61, TSTF-114, TSTF-incorporated.

136, TSTF-153, TSTF-162 3.5 TSTF-90, TSTF-153 3.6 TSTF-17, TSTF-30. TSTF-45, TSTF-52 under NRC TSTF-46, TSTF 52 consideration.

3.7 TSTF-100, TSTF-101, TSTF-TSTF-70 not incorporated.

139. TSTF-140. TSTF-174 3.8 TSTF-8, TSTF-38 3.9 TSTF-20, TSTF-96, TSTF-197 TSTF-136 not incorporated.

4.0 None i

5.0 TSTF-118 TSTF-152 TSTF-106 not incorporated.

A4-1

e e

Farley Nuclear Plant

+

ITS conversion Submittal O

l 1

Joseph M. Farley Nuclear Plant Channes Identified as Beyond the Scope of an ITS Conversion O

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Farley Nuclear Plant ITS conversion Submittal T

Changes Identified as Beyond the Scope of an ITS Conversion CTS DOC ITS JD Summary of Change Reference Number Reference Number 3.2 POWER DISTRIBUTION LIMITS C

3/4.2.2 2 A, 3.2.1 1

The STS terms Fo*(2) and Fn (Z) in LCO 3.2.1 are deleted I l-A and the tenns Fo(Z), " steady state" limit, and " transient" limi are used. While these terms are not used in the Farley CTS, they are consistent with the methodology which represents the current Farley licensing basis.

3/4.2.4 4a-A 3.2.4 1

The STS wording in Required Action A.! to " reduce" thermal power is revised to " limit" thermal power to allow entry into the LCO applicability during startup when QPTR may be in excess of 1.02 due to transient core conditions which are usually self-correcting.

3/4.2.4 la M 3.2.4 la The Applicability of LCO 3.2.4 is revised to be consistent with the Applicability for the AFD LCO to eliminate subtle difTerences between the two LCO Applicabilities which were previously the same.

3/4.2.4 3-L, 3.2.4 2,3,4,5, The Required Actions, Completion Times, and Surveillance 6-L and 6 Notes are revised to clarify the requirements of LCO 3.2.4, ensure that references to the reduced power level of A.1 in subsequent Actions reflect the lowest power limit, ensure that equilibrium conditions are met prior to performing surveillances, and ensure that the LCO is not exited prematurely. These changes are based on TSTF-241.

gG A51

____________________________j

Farley Nuclear Plant ITS conversion Submittal (O,

Changes identified as Beyond the Scope of an ITS Conversion v

CTS DOC ITS JD Summary of Change Reference Number Reference Number 3.3 INSTRUMENTATION 3/4.3.2 39-L 3.3.2 13 The STS footnote (i) (FNP ITS footnote (d)) to ESFAS Table 3.3.2-1 is revised consistent with the FNP main steam system design. He mtent of the STS footnote is to provide an exception to the Mode of Applicability for the main steam line isolation function when all of the main steam lines are isolated. The note is revised to reflect the fact that this can be accomplished by a single MSIV in each line. The STS note was written for plant designs which only include a single MSIV per line instead of the two MSIVs per line incorporated in the FNP design.

3/4.3.2 28 L 3.3.2 19 The STS footnote (j) (FNP ITS footnote (g)) to ESFAS Table 3.3.2-1 is revised consistent with the FNP main feedwater system design. The intent of the STS footnote is to proside an exception to the Mode of Applicability for the turbine trip and feedwater line isolation functions when all of the main O

feedwater lines are isolated. He note is revised to reflect the i

V fact that this can be accomplished by a single Main Feedwater Stop Valve or the combination of a MFRV and its associated MFRV bypass in each line. The STS note is revised to take credit for either method ofisolation, consistent with the FNP design.

3/4.3.3.5 10a-M 3.3.4 4

A new Condition C is added to FNP ITS LCO 3.3.4 to address actions associated with the source range neutron flux monitor. This monitor is not included in the FNP CTS. The monitor provides visual indication only and is not depended upon for any actuation signal or to monitor the operation of any component necessary to maintain the unit in Mode 3.

Therefore, shutdown actions are not appropriate and the new condition provides appropriate actions.

3/4.3.2 35-M, 3.3.5 1, 2, 3, 4 STS LCO 3.3.5 is revised to accommodate the addition of a 61-M and 8 degraded grid alarm function. This function does not exist in the CTS. This is in compliance with a previous commitment to the NRC to include this function in the ITS conversion.

O k

A5-2

Farley Nuc! car Plant ITS conversion Submittal Changes Identified as Beyond the Scope of an ITS Conversion CTS DOC ITS JD Summary of Change Reference Number Reference Number 3.4 REACTOR COOLANT SYSTEM (RCS) 3/4.10.4 1-L 3.4.17 1

The RCS Loop Test Exception LCO is deleted from both the CTS and FNP ITS. This test exception is no longer used at FNP.

3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3/4.5.3 4a-L 3.5.3 2

A new Action is added to the ECCS-Shutdown LCO. The new Action provides an allowed outage time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the required ECCS centrifugal charging subsystem to be inoperable provided the remaining operable ECCS components are capable of providing 100% of the ECCS flow, equivalent to a single operable ECCS subsystem. At FNP, the requirement to ensure that only one centrifugal charging pump is operable for overpressurization concerns is i

not applicable until the temperature of one or more of the RCS cold legs is less than or equal to 180 degrees F.

Therefore, in MODE 4, two or more centrifugal charging O-pumps may be available and an Action similar to that in STS 3.5.2 (ECCS-Operating) may be applied in FNP ITS 3.5.3 (ECCS-Shutdown).

)

3/4.4.7.2.e 4-M and 3.5.5 1

The RCP seal injection flow requirements are revised from 1 LA verification of a single operating point to verification of a j

range of values on an operating curve (graph). Establishing a reference differential pressure allows a more precise and repeatable verification of seal injection flow and proper

)

throttle valve position. In the conversion to ITS, this change I

in the measurement of the seal injection flow is addressed by use of a graph from which the appropriate flow can be determined based on the delta between the RCS pressure and the charging discharge header pressure. He points on the graph are based on FNP-specific safety analysis assumptions which provide the relationship between seal injection flow, RCS pressure, and charging discharge header pressure over a range of values for each of these parameters. His method of determining the seal injection flow limit was approved by the NRC for Vogtle.

O A5-3

4 Farley Nuclear Plant ITS conversion Submittal Changes Identified as Beyond the Scope of an ITS Conversion CTS DOC ITS JD Summary of Change Reference Number Reference Number 3.7 PLANT SYSTEMS 3/4.7.1.1 4-L and 3.7.1 2 and 6 The CTS time allowed to reduce the power range neutron 4a-L flux setpoint to within the required limit is extended and made applicable in Mode 1 only. The additional time to reduce setpoints allows for a more controlled evolution. The restriction to Mode I for this Action is consistent with the applicable FNP specific safety analysis and climinates the unnecessary requirement to apply this Action in Mode 2 or 3.

This CTS Action and Completion Time are FNP specific and not part of the STS 3/4.7.1.5 4-L 3.7.2 i and 3 The CTS Actions for an inoperable MSIV are revised to take credit for the redundant MSIVs (Train A and B)in each steam line at FNP. The STS and the CTS are written for the standard PWR plant design ofone MSIV per steam line.

These Actions are also revised to be consistent with the Vogtle Plant Technical Specifications which also take credit for two MSIVs in cach steam line and which have been approved by the NRC.

f 3/4.7.4 11-L 3.7.8 3

An Action has been added to the SW LCO that accounts for the redundant automatic turbine building isolation valves in each FNP SW train. One isolation valve in each train may be inoperable and the turbine building isolation function is not lost (one train of turbine building isolation valves remain operable in each train of SW). This FNP specific design was not previously accounted for in the CTS and is not part of the STS. The proposed change eliminates the potential for an unnecessary shutdown per LCO 3.0.3 with a single inoperable turbine building isolation valve in each SW train.

O A5 4

Fr.rley Nuclear Pent ITS conversion Submittal

[%

Changes identified as Beyond the Scope of an ITS Conversion CTS DOC ITS JD Summary of Change Reference Number Reference Number 3.8 ELECTRICAL POWER SYSTEMS DG Test 16-LA Table 32 The DG accelerated Test Table is deleted from both the CTS Schedule 3.8.1-1 and STS. This deletion is consistent with previous NRC page guidance applicable to plants after implementing the 3/4 8-6a maintenance rule.

4.8.1.2 8-L, 9-L SR 3.8.2.1 1, 2, 3 The AC Sources - Shutdown surveillance is revised to more and and 4 accurately and completely state the required surveillances.

10-A This includes additional exceptions for surveillances which verify SI signal response and automatic load sequencing (not required during shutdown). Additional clarifications have also been added to the STS surveillance to state what is actually required to be performed.

3/4.8.2.5 5-L 3.8.4 and 2 and 3 The Actions for an inoperable Service Water intake Structure 3.8.9 (SWIS) Battery and Distribution System are revised to more accurately reflect the specific FNP design. The SWIS batteries and distribution system provide power to the SW d(3 System and do not impact any other ESF system. The Actions for an inoperable train of SWIS batteries or Distribution System are revised from a two hour shutdown requirement to declare the associated train of SW inoperable.

3.9 REFUELING OPERATIONS 3/4 9.2 9-M 3.9.2 3

The Actions of the Nuclear Instrumentation LCO are revised by the addition of a specific Action for loss of the audible count rate. This new Action is applicable for plants which credit the audible count rate in the refueling boron dilution accident analysis. TSTF-23 has been submitted for NRC approval to incorporate this change in the STS.

5.0 ADMINISTRATIVE CONTROLS 6.1.2 2-L 5.1.2 la The specific title for the control room command function is replaced with a more generic description to avoid technical specification changes in the future and to be consistent with the Vogtle Plant technical specifications.

6.3.1 12a-A 5.3.1 7

The specific title of the Health Physics Supervisor is replaced

.,m with a more generic description to avoid technical specification changes in the future.

A5-5

a Farley Nuclear Plant ITS conversion Submittal Changes identified as Beyond the Scope of an ITS Conversion CTS DOC ITS JD Summary of Change Reference Number Reference Number

/

4.4.11.2 3-L 5.5.7 11 The inspection frequency for the RCP Flywheel is revised consistent with the NRC approved WCAP-14535A," Topical Report on RCP Flywheel Inspection Elimination", November, 1996. Note: the 10 year inspection frequency was approved generically for RCPs with flywheels constructed of a certain material (FNP RCPs utilize an approved flywheel material).

6.9.1.12 60-L 5.6.7 23 The EDG Failure Report is revised consistent with the latest FNP commitments for DG failure tracking and reporting.

The Specific Health Physics Supervisor title is revised with a 6.12.1.c 77-L 5.7.1.c more genene description of the position to avoid technical specification changes in the future.

OV

~b A5-6

Farley Nuclear Plant ITS conversion Submittal O

Joseph M. Farley Nuclear Plant Summary of CTS Requirements Removed from the TS and Placed in, or Currently Located in, Other Documents J

O O

Farley Nuclear Plant lis Conversion Summary of CTS Requirements Removed From the TS sad Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

1.0 USE AND APPLICATION 1.0 6-LA 1.6 Containment Integrity definition (except LCO 3.6.1 5.5.14 Bases item "d" as described in DOC 6-LA).

Bases Control Program 1.0 19-LA 1.22 Process Control Program definition.

FSAR 10CFR50.59 1.0 32-LA Table 1.1,140 F Mode 6 temperature TRM 10CFR50.59 limitation.

3.0 LCO AND SR APPLICABILITY 3.0 16-LA 4.0.5 ASME Inservice inspection (ISI)

ISI Program 10CFR50.55a requirements.

3.1 REACTIVITY CONTROL SYSTEMS 3.1 1-LA 3/4.1.1.1 Shutdown Margin requirements for TRM 10CFR50.59 Mode I and Mode 2 with ka 21.

3.I I l-LA 4.1.1.1.1.e items 1-6 providing guidance for SR 3.1.1.1 5.5.14 Bases the performance of the surveillance bases Control Program requirement 3.1 15-LA 4.1.1.1.2 Reference to the " factors stated in SR 3.1.2.1 5.5.14 Bases 4.1.! 1.1 e, above"(items 1-6).

bases Control Program 3.1 2-LA 3/4.1.1.2 Actions describing a flow rate and LCO 3.1.1 5.5.14 Bases boron concentration required to be used to bases Control Program restore the SDM to within limit.

3.1 5-LA 4.1.1.2.b Descriptive information (6 items)

SR 3.1.1.1 5.5.14 Bases providing guidance for the performance of the bases Control Program surveillance requirement.

3.1 4-LA 3/4.1.1.3 Information modifying the required LCO 3.1.3 5.5.14 Bases actions.

Action A.1 Control Program bases N

' 'the "lX designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-1

Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3.1 5-LA 3/4.1.1.3 Action Statement a.3 required the 10CFR50.72 10CFR50.72 and preparation and submission of a special and 10CFR50.73 report to the NRC within 10 days if the MTC 10CFR50.73 is more positive than the beginning oflife limit.

3.1 1-R 3/4.1.2.1 Boration Systems Flow Paths -

TRM 10CFR50.59 Shutdown 3.1 1-R 3/4.1.2.2 Boration Systems Flow Paths -

TRM 10CFR50.59 Operating 3.I l-R 3/4.1.2.3 Charging Pump - Shutdown TRM 10CFR50.59 31 1-R 3/4.1.2.4 Charging Pumps - Operating TRM 10CFR50.59 3.1 1-R 3/4.1.2.5 Borated Water Sources - Shutdown TRM 10CFR50.59 3.1 1-R 3/4.1.2.6 Borated Water Sources - Operating TRM 10CFR50.59 b

3.1 5-LA 3/4.1.3 l Action Statement d.2 specific LCO 3.1.4 5.5.14 Bases guidance as to how the rod alignment may be Action B.1 Control Program restored to within the limits.

bases 3.1 7-LA 3/4.1.3.1 Table 3.1-1 lists the accident LCO 3.1.4 5.5.14 Bases analyses that must be evaluated in CTS Action B.2.6 Control Program Action Statement d.3.a.

bases 3.1 2-LA 3/4.1.3.2 LCO and Actions descriptive details LCO 3.1.7 5.5.14 Bases regarding the operability of the digital rod bases Control Program position indication system.

3.1 1-R 3/4.1.3.3 Position Indication System -

TRM 10CFR50.59 Shutdown 3.I 2-LA 3/4.1.3.4 LCO requirement specifying the rod SR 3.1.4.3 5.5.14 Bases position in steps that corresponds to the fully bases Control Program withdrawn position and the associated asterisked note.

3.1 7-LA 4.1.3.4.b Surveillance Requirement specifies TRM 10CFR50.59 a post maintenance test requirement for rod drop time.

  • The "1.A" designation indicates that part of a 13 is removed and the "R" designation indicates an entire TS is removed.

A6-2

Fc.rley Nuclear Plant ITS Conversion

(

Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3.2 POWER DISTRIBUTION LIMITS 3.2 7-LA 4.2.2.2 Descriptive surveillance details.

LCO 3.2.1 SR 5.5.14 Bases and Action Control Program bases 3.2 8-LA 4.2.2.2.d Fq(Z) relationships and specific COLR 5.6.5 COLR.

values.

3.2 9-LA 4.2.3.1 Descriptive material regarding how LCO 3.2.2 5.5.14 Bases this surveillance is performed (using movable bases Control Program incore detectors to obtain a power distribution map).

32 I l-LA 4.2.3.2 Info nation to calculate the required SR 3.2.2.1 5.5.14 Bases F% (4% measurement uncertainty) bases Control Program 32 12-LA 4.2.4.2 Detail describing how the surveillance SR 3.2.4.2 5.5.14 Bases O

may be met bases Control Program U

3.3 INSTRUMENTATION 3.3 2-LA 2.2.1 Safety Limit statement for the RTS LCO 3.3.1 5.5.14 Bases instrumentation operability details (interlock bases Control Program and setpoint setting requirements).

3.3 5-LA Table 2.2 1 Descriptive information LCO 3.3.1 5.5.14 Bases pertaining to various trip setpoints and bases Control Program allowable values.

3.3 15c-LA 4.3.1.3 Detailed explanation of the RTS SR 3.3.1.14 5.5.14 Bases Response Time Testing requirements.

bases Control Program 3.3 36-LA Table 3.3-1 Function 12 A and B. Loss of LCO 3.3.1 5.5.14 Bases Flow trip, design description information.

bases Control Program 33-44-LA Table 3.3-1 Charmels To Trip colunm FSAR 7.2 and 10CFR50.59 and information desenbing the RTS design LCO 3.3.1 5.5.14 Bases features.

bases Control Program 33 83 LA Table 4.3-1 Manual Reactor Trip function SR 3.3.1.12 5.5.14 Bases surveillance notes which provide test bases Control Program

_g i

requirement details.

  • 'Ihe "lA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.

A6 3

\\

Farley Nucicar Plant ITS Conversion O

Summary of CTS Requirements Removed From the TS V

and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3.3 93 LA Table 4.3-1 Note 9 applicable to the CFT for SR 3.3.1.13 5.5.14 Bases the turbine trip RTS functions contains bases Control Program descriptive detail regarding the performance of the required surveillance.

1 33 97-LA Table 4.3-1 Note 8 modifying the CFT SR 3.3.1.11 5.5.14 Bases requirement for the RTS interlocks contains bases Control Program descriptive information applicable to the I

required testing.

3.3 99-LA Table 4.3-1 Surveillance Notes 14 and 15 SR 3.3.1.4 5.5.14 Bases which describe the testing required by this bases Control Program CFT contain details of the undervoltage and shunt trip mechanism tests that are required for the RTDs-33 104-LA Table 4.3-1 Note 13 assigned to the RTS SR 3.3.1.4 5.5.14 Bases reactor trip bypass breaker function contains bases Control Program D

specific information regarding what is tested

(

on the bypass breakers (local manual shunt trip and local manual undervoltage trip).

3.3 105-LA Table 4.3-1 Note 1 I for the reactor trip SR 3.3.1.12 5.5.14 Bases bypass breaker function contains a bases Control Program desenpiion of the bypass breaker testing required.

3.3 2-LA 3/4.3.2 ESFA5 LCO statement operability LCO 3.3.2 5.5.14 Bases details (trip setpoint setting requirements).

bases Control Program 3.3 4c LA 4.3.2.3 Detailed description of the Staggered SR 3.3.2.9 5.5.14 Bases Test requirement for ESF Response Time bases Control Program Testing.

3.3 12-LA Table 3.3 3 ESFAS Channels To Trip FSAR 7.3 and 10CFR50.59 and column descriptive design information.

LCO 3.3.2 5.5.14 Bases j

bases Control Program 3.3 29-LA Table 3.3-3, ESFAS Function 6.b, details LCO 3.3.2 5.5.14 Bases describing the SG water level low-low bases Control Program auxiliary feedwater initiation ftmedons.

O

  • 1he "lA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-4

Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, O'.her Documents N

ITS DOC #

Description of CTS Requirement Document Control Section a

I l

3.3 33-LA Table 3.3-3, ESFAS Functions 6.d and 6.e, l.C O 3.3.2 5.5.14 Bases auxiliary feedwater auto start on Si and trip bases Control Program of main feedwater pump functions descriptive j

information regarding the specific auxiliary feedwater pumps that are started.

i l

3.3 67-LA Table 3.3-1 SG water level high high turbine LCO 3.3.2 5.5.14 Bases trip feedwater isolation function setpoint bases Control Program l

descriptive detail regarding the narrow range instrument span on each SG.

33 68 LA Table 3.3-4 SG water level low low auxiliary LCO 3.3.2 5.5.14 Bases l

feedwater pump start function setpoint bases Control Program j

descriptive detail regarding the narrow range instrument span on each SG.

3.3 70-LA Table 3.3-4

power (LOP) functions which references the LOP Control Program appropriate relay setting sheet for additional Instruments.

.I calibration requirements channel calibration l

surveillance bases 3.3 87 LA Table 4.3-2 Note 6 modifying the muthly SR 3.3.2.2 5.5.14 Bases l

ESFAS CFT for the auxiliary feedwater bases Control Program automatic actuation logic function provides an exception to the requirement to perform actuation logic testing on the trip of all main feedwater pumps function.

33 94-LA Table 4 3-2 Note I requirement.a perform SR 3.3.2.6 5.5.14 Bases manual actuation surveillances during bases Control Program shutdowns.

3.3 96-LA Table 4.3-2 Note 4 detailed description of SR 3.3.5.1 5.5.14 Bases functional test surveillance requirements.

bases Control Program l

v

  • The "LA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-5

^

Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3.3 5-LA 3/4.3.3.1 Actions "a" and "b" for Radiation TRM 10CFR50.59 l

Monitors that are removed from the TS (fuel storage pool area monitor R5 (CTS Taule 3.3-6 item 1.a) and the noble gas efflucci monitors, R-29B, R60A-C, R60D, RISB&C, (CTS Table 3.3-6 items 2 d.i-iv).

3.3 9-LA 3/4.3.3.1 Radiation Monitor requirements for TRM 10CFR50.59 l

the Fuel storage pool area monitor R5 (CTS l

Table 3.3-6 item 1.a) and the noble gas effluent monitors R-298, R60A-C, R60D, i

RISB&C, (CTS Table 3.3-6 items 2.d.i-iv) including setpoints, applicable Modes, minimum charmel requirements, measurement l

l range, Actions, and surveillance requirements.

33 22-LA 3/4.3.3 i Action 27a applicable to the noble TRM 10CFR50.59 gas efiluent momtors R298, R60A, B, C. &

R60D, RISB&C (CTS Table 3.3-6 items 2.d.i-iv).

3.3 1-R 3/4.3.3.2 Movable incore Detectors TRM 10CFR50.59 i

3.3 l-R 3/4.3.3.7 liigh Energy Line Break Isolation TRM 10CFR50.59 Sensors I

3.3 20 LA 3/4.3.3.8 # footnote to the reactor vessel level LCO 3.3.3 5.5.14 Bases indicating system on Table 3.3.-l 1 describes bases Control Program a channel oflevel indication and defines what is required for an operable channel.

i 33 30 LA 4.6.4.1 Surveillance details regarding the SR 3.3.3.2 5.5.14 Bases makeup of the sample gases used for bases Control Program calibration of the hydrogen analyzers.

33 1-LA 3/4.3 3.1l Waste Gas Monitoring TRM 5.5.12 Explosive Instrumentation which contains requirements Gas and for instrumentation to monitor oxygen and Radioactivity hydrogen gas content in the waste gas system.

Monitoring Program and 10CFR50.59 k

  • 1hc "1X designauon mdicates that pan of a 'l S is removed and the "R" designation indicates an entire TS is removed.

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Description of CTS Requirement Document Control Section a

3.3 1-R 3/4.3.4 Turbine Overspeed Protection TRM 10CFR50.59 3.4 REACTOR COOLANT SYSTEM (RCS) 34 10-LA Table 3.2-1 *** footnote contains the LCO 3.4.1 5.5.14 Bases measurement uncertainties associated with the bases Control Program calculations used to determine the minimum RCS flow specified in the TS.

34 3-LA 3/4.1.1.4 Applicability

  • footnote referencing LCO 3.4.2 5.5.14 Bases special test exception 310 3 bases Control Program 3.4 5-LA 4.4.1.1 The surveillance requirement to verify SR 3.4.4.1 5.5.14 Bases the circulation of reactor coolant in order to bases Control Program verify an operable RCS loop.

3.4 2-LA 3.4.1.2 Descriptive list of RCS loops in the LCO 3.4.5 5.5.14 Bases LCO statement.

bases Control Program 3.4 3-LA 3.4.1.2 Action statement b specific actions LCO 3.4.5 5.5.14 Bases regarding how to de-energize the control rod bases Control Program drive mechanisms (open the reactor trip breakers or shut down the rod drive motor / generator sets) 34 7 LA 4.4.1.2.2 and 4 4.1.2.3 Surveillance details LCO 3.4.5 5.5.14 Bases "and circulating reactor coolant" and "shall bases Control Program be determined operable" 3.4 2-LA 3/4.4.1.3 LCO list describing the RCS and LCO 3.4.6 5.5.14 Bases RHR loops available to meet the LCO bases Control Program requirement.

3.4 7-LA 4.4.1.3.2 and 4.4.1.3.3 Surveillance details LCO 3.4.6 5.5.14 Bases "and circulating reactor coolant" and "shall bases Control Program be determined operable" 3.4 4 LA 4.4.1.4 Surveillance detc.ils "and circulating LCO 3.4.7 and 5.5.14 Bases reactor coolant" LCO 3.4.8 Control Program bases 3.4 1-R 3/4.4.2 Safety Valves Shutdown TRM 10CFR50.59

's

  • 'the "l.A" designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.

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Farley Nuclear Plant ITS Conversion 4

q Summary of CTS Requirements Removed From the TS U

and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3.4 5-LA 3/4.4.3

  • footnote specifying that the lift LCO 3.4.10 5.5.14 Bases setting pressure shall correspond to ambient bases Control Program conditions of the valve at nominal operating temperature and pressure.

3.4 4-LA 4.4.4.2 and 4.4.4.3 Details regarding how the LCO 3.4.9 5.5.14 Bases surveillance requirements are to be met.

bases Control Program 34 2-LA 4.4.6.0 Reference to the requirements of 10 CFR 10 CFR 50.55a Specification 4.0 $ (Inservice Inspection 50.55a Program) 3.4 1-LA 3.4.7.1 LCO statement details (the radiation LCO 3.4.15 5.5.14 Bases monitor instrument designations R-11 and R-bases Control Program 12).

3.4 14-LA Table 3.4-1 Containing a list of the RCS TRM 10CFR50.59 PlVs.

OV 3.4 15 LA 4.4.7.2.2 References to the requirements of 10 CFR 10 CFR 50.55a Specification 4.0.5 (Inservice inspection 50.55a Program).

3.4 19-LA 4.4.7.2.2.b Requirement for post maintenance TRM 10CFR50.59 testing on RCS PlVs.

3.4 26-LA 4.4.7.2.2 # footnote with specific procedural SR 3.4.14.1 5.5.14 Bases guidance for performing the RCS PlV bases Control Program leakage measurement surveillance.

34 1R 3/4.4 8 Chemistry TRM 10CFR50.59 3.4 1-LA 3/4.4.10 LCO statement exception to the LCO 3.4.3 5.5.14 Bases pressurizer, and descriptive information bases Control Program concerning the applicability in the LCO statement.

3.4 4-LA 3/4.4.10 Action statement description of the LCO 3.4.3 5.5.14 Bases required engineering evaluation.

bases Control Program OU 1he "lA" designation indicates llun part of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-8

Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3.4 6-LA 4.4.10.1.2 Requires reactor vessel material

10CFR50, 10CFR50, surveillance specimens to be removed and Appendix 11 Appendix 11 cxamined to determine changes in material propenies as required by 10CFR50, Appendix 11, 3.4 1-R 3/4.4.10.2 Pressurizer TRM 10CFR50.59 3.4 8-LA 4.4.10.3.1.a - Specific RiiR relief valve ID SR 3.4.12.3 5.5.14 Bases numbers.

bases Control Program 3.4 12-LA 4.1.2.3.2 (from the Reactivity Control SR 3.4.12.1 5.5.14 Bases Systems Chapter) Contains specific means by bases Control Program which a charging pump is rendered incapable ofinjecting into the RCS (motor circuit breakers are removed from their electrical power supply circuits).

(

3.4 1-LA 3/4.4.11 Structural Integrity LCO, Actions, 10CFR 50.55a 10CFR 50.55a Applicability, and surveillance requirements (ISI) and (ISI) and 5.5.8 for ASME Code Class I,2, and 3 5.5.8 (IST)

(IST) components to be maintained in accordance with the Insersice Test and Inspection Programs.

1 3.4 l-R 3/4.4.12 Reactor Vesselliead Vents TRM 10CFR50.59 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3.5 8 LA 4.5.1.1.b Explanation regarding the RWST SR 3.5.1.4 5.5.14 Bases boron concentration being within the bases Control Program accumulator boron concentration limits.

3.5 10-LA 4.5.1.1.c Specific details of how power is SR 3.5.1.5 5.5.14 Bases removed from valve operators.

bases Control Program 35 2-LA 3.5 2 LCO statement containing descriptive LCO 3.5.2 5.5.14 Bases information regarding the operability bases Control Program requirements for the ECCS subsystems.

3.5 5 LA 3/4.5.2 Action statement "b" for reporting 10CFR50.73 10CFR ECCS actuations is effectively addressed by (a)(2)(iv) 50.73(a)(2)(iv)

O existing regulations.

  • The "tA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-9

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Farley Nuclear Plant ITS Conversion r

Summary of CTS Requirements Removed From the TS

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and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3.5 6 LA 4.5.2.a - Surveillance requirement detail SR 3.5.2.1 5.5.14 Bases regarding how power is removed from the bases Control Program valves (locked open disconnect device).

3.5 7 LA 4.5.2.c Surveillance requirement for a visual TRM 10CFR50.59 inspection of containment prior to establishing containment integrity and after each containment entry.

3.5 10-LA 4.5.2.e.1 Surveillance requirement to verify TRM 10CFR50.59 the ECCS throttle valves mechanical position stop after each valve stroke and maintenance.

3.5 12-LA 4.5.2.f.I and 2 Surveillance details "during LCO 3.5.2 5.5.14 Bases j

shutdown", the specific actuating signal (SI),

surveillance Control Program j

and the specific pumps involved in the testing.

bases 1

3.5 14-LA 4.5.2.g.1 and 2 Specific requirements SR 3.5.2.3 5.5.14 Bases regarding pump testing on recirculation flow bases Control Program ON and die required psid values.

35 15 LA 4.5 2 h Post valve stroke surveillance SR 3.5.2.6 5.5.14 Bases requirement and details regarding the bases and Control Program mechamcal stop position verification for the TRM and 10CFR50.59 RHR valves.

3.5 16-LA 4.5.2.i Post maintenance ECCS flow balance TRM and 10CFR50.59 and j

test requirement after any modifications that LCO 3.5.2 5.5.14 Bases alter the subsystem flow characteristics and bases Control Program associated required flows.

35 2-LA 3.5.3 LCO statement containing descriptive LCO 3.5.2 5.5.14 Bases information regarding the operability bases Control Program requirements for the ECCS subsystems.

3.5 4-LA 3/4.5.3 Action "a" description of the charging LCO 3.5.2 5.5.14 Bases subsystem (pump and flow path).

bases Control Program 3.5 7-LA 3/4.5.3 Action "b" description of the charging LCO 3.5.2 5.5.14 Bases subsystem (pump and heat exchanger),

bases Control Program i

O The "1.A" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-10 j

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Farley Nuclear Plant ITS Conversion p

Summary of CTS Requirements Removed From the TS Q

and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control j

Section a

3.5 8-LA 3/4.5.3 Action "b" description of maintaining LCO 3.5.3 5.5.14 Bases the RCS Tavg < 350 F by the use of Action bases Control Program alternate heat removal methods.

3.5 10-LA 3/4.5.3 Action statement "c" for reporting 10CFR50.73 10CFR50.73 (a)

ECCS actuations is effectively addressed by (a)(2)(iv)

(2)(iv) existing regulations.

35 12-LA 4.5 3.2 Surveillance requirement detail SR 3.5.3.2 5.5.14 Bases regardmg how power is removed from the bases Control Program valves (locked open disconnect device).

3.5 l-LA 3/4.5.6 LCO statement details describing LCO 3.5.6 5.5.14 Bases recirculation pH control system operability, bases Control Program 3.5 1-LA 3.4.7.2.e, The details of the LCO for RCS LCO 3.5.5 5.5.14 Bases Operational leakage, and associated bases Control Program surveillance 4.4.7.2. l.c are moved into the STS LCO 3.5.5, Seal injection Flow, SR O

3.5.5.1, and the associated bases.

3.6 CONTAINMENT SYSTEMS 3.6 6-LA 3/4.6.1

  • footnote requirement to verify the LCO 3.6.1 5.5.14 Bases status of the equipment hatch.

bases Control Program 3.6 9 LA SR 3.6.1.2 Requires that containment Containment 5.5.6 Pre-stressed structural integrity be venfied in accordance Tendon Concrete with the Containment Tendon Surveillance Surveillance Containment Program.

Program Tendon Surveillance Program 3.6 1-LA 3.6.1.3 LCO statement descriptive text LCO 3.6.2 5.5.14 Bases regarding the status of the airlock doors and bases Control Program the exception to allow entry and exit through the air lock.

3.6 2-LA 4.6.1.5.I Desenptive details regarding the LCO 3.6.2 5.5.14 Bases average air temperature required to be bases Control Program venfied in 4.6.15.2.

bo The "lA" designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.

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Farley Nuclear Plant ITS Conversion 4

Summary of CTS Requirements Removed From the TS

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and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section 3.6 1-LA 3/4.6.1,6 LCO, Applicabihty, Actions, and Containment 5.5.6 Pre-stressed surveillance requirements.

Tendon Concrete Surveillance Containment Program Tendon Surveillance Program 3.6 3-LA 3/4.6.1.7.b LCO provision regarding the 8 LCO 3.6.3 5.5.14 Bases inch mini-purge supply and exhaust isolation bases Control Program valves.

3.6 9 LA 3/4.6.1.7

  • footnote to LCO which describes LCO 3.6.3 5.5.14 Bases the applicability of the LCO to the 48 inch bases Control Program purge and exhaust valves and purge and exhaust leakage.

3.6 10-LA 3/4.6.1.7 Action "c" and associated TRM 10CFR50.59 surveillance (4.6.1.7.3.b) for containment purge supply or exhaust leakage in excess of G

0.05 la for each valve.

36 15-LA 4.6.1.7.4 Requirements for replacing resilient TRM 10CFR50.59 seals in containment purge and exhaust valves and requirement to compare current leakage with previous leakage to detect excess valve degradation.

3.6 2-LA 3/4.6.2.1 Operability description in the LCO LCO 3.6.6 5.5.14 Bases statement, bases Control Program 3.6 5 LA 4.6.2.1.b Surveillance details regarding the SR 3.6.6.4 5.5.14 Bases method of testing and required discharge bases Control Program pressure.

36 8-LA 4 6 2.1.c and d Surveillance details regarding LCO 3.6.6 SR 5.5.14 Bases the specific actuation signal and specific bases Control Program method for venfying each containment spray nozzle is unobstructed.

3.6 2-LA 3/4.6.2.3 LCO statement describing the LCO 3.6.6 5.5.14 Bases number of fans in each group bases Control Program OU

  • The "lX designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed A6-12

Farley Nuclear Plant ITS Conversion A

Summary of CTS Requirements Removed From the TS Q

and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

36 6-LA 4.6.2.3.a. and b Surveillance details regarding LCO 3.6.6 SR 5.5.14 Bases where each fan group is started and the bases Control Program specific automatic actuation signal.

3.6 1-LA 3/4.6.3 List of containment isolation valves in TRM 10CFR50.59 Table 3.6 1.

3.6 11 LA 4.6.3.1 Post maintenance testing requirements TRM 10CFR50.59 for containment isolation valves.

36 13 LA 4.6 3.2.a and b Surveillance details regarding SR 3 6.3.6 5.5.14 Baues the specific actuation signal tested bases Control Program 3.6 19-LA Table 3.6-1 " footnote regarding SR 3.6.3.2 5.5.14 Bases containment isolation valves which may be bases Control Program open with the power removed for overpressure protection requirements.

3.6 4 LA 4.6.4.2.b.1 Channel calibration requirement TRM 10CFR50.59 Q

for the hydrogen recombiners.

36 5 LA 4.6.4.2.a and 4.6.4.2.b 2 and 3 Surveillance LCO 3.6.7 SR 5.5.14 Bases details desenbmg specific requirements for bases Control Program hydrogen recombiner testing.

3.6 4-LA 4.6.4.3.a.1 Surveillance details regarding SR 3.6.9.1 5.5.14 Bases where the hydrogen dilution system is started.

bases Control Program 3.6 5-LA 4.6.4.4.a - Surveillance details regarding SR 3.6.8.1 5.5.14 Bases where the systens is started (control room).

bases Control Program 3.7 PLANT SYSTEMS 3,7 9 LA Table 3.7-3 Main Steam Safety Valve orifice LCO 3.7.1 5.5.14 Bases size.

bases Control Program 3.7 10-LA Table 3.7-3

3.7 2 LA 3/4.7.1.2 LCO information describing the LCO 3.7.5 5.5.14 Bases AFW system operabihty requirements, bases Control Pryram 1

' lhe "lX designalmn indicates that gun of u TS n remmed and the "R" designatmn irdicates an entire TS u muoved.

A6-13 i

1

8 Farley Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3,7 9 LA 4.7.1.2.2.a.3 Surveillance specific valve SR 3.7.5.1 5.5.14 Bases position guidance.

bases Control Program 3.7 14-LA 4.7.1.2.2.b, c.1, c.2 AFW valves and pumps LCO 3.7.5 SR 5.5.14 Bases specific auto start signals.

bases Control Program

.i.7 15-LA 4.7.1.2.2.c Requirement that the 18 month LCO 3.7.5 SR 5.5.14 Bases surveillance be performed "during shutdown" bases Control Program 37 17-LA 4.7.12.2.c 3 Specific turbine-driven AFW SR 3.7.5.5 5.5.14 Bases pump steam admission valve ID numbers.

bases Control Program 3.7 l-R 3/4.7.2 Steam Ger.erator TRM 10CFR50.59 Pressure / Temperature Limitation 3.7 6-LA 4.7.3.b Surveillance requirement to be SR 3.7.7.2 5.5.14 Bases perfonned during shutdown and specific bases Control Program automatic valve actuation signal.

3.7 2-LA 3/4.7.4 LCO description of operable SW LCO 3.7.8 5.5.14 Bases loop.

bases Control Program 3.7 6-LA 4.7.4.b Surveillance requirement to be SR 3.7.8.2 5.5.14 Bases performed during shutdown'and specific bases Control Program automatic valve actuation signal.

3.7 12-LA 4.7.4.c FNP specific surveillance to verify SR 3.7.8.4 5.5.14 Bases SW buried piping integrity. Descriptive term bases Control Program

" leak tight" 3.7 3 LA 4.7.6.2.2-4 Ultimate Heat Sink spillway TRM 10CFR50.59 channel and ground water seepage maintenance requirements.

3.7 4-LA 4.7.7.1.a - Surveillance description of SR 3.7.10.1 5.5.14 Bases CREFS flow path.

bases Control Program 3.7 8-LA 4.7.7.1.b, c, d.1, e, f Surveillances and Ventilation 5.5.11 Ventilation associated footnotes for the CREFS system.

Filter Test Filter Test Program Program and SR 3.7.10.2 The "lA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.

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Farley Nuclear Plant ITS Conversion

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Summary of CTS Requirements Removed From the TS Q

and Placed in, or Currently Located in, Other Documents ITS DOC 4 Description of CTS Requirement Decument Control Section a

3.7 10-LA 4.7.7.1.d.2 Surveillance description of SR 3.7.10.3 5.5.14 Bases specific CREFS actuation signal.

bases Control Program 3.7 4-LA 4.7.8.a - Surveillance details regarding where SR 3.7.12.2 5.5.14 Bases the PRF system is started and the required bases Control Program flow path.

3.7 5-LA 4.7.8.b, c, d.1, d.3, e, f Surveillances and Ventilation 5.5.11 Ventilation associated

  • footnotes for the PRF system.

Filter Test Filter Test Program Program and SR 3.7.12.3 3.7 7 LA 4.7.8.d.2 Surveillance details regarding the SR 3.7.12.4 5.5.14 Bases specific PRF actuation signal bases Control Program 3.7 3 LA 3/4.9.13 LCO statement describing the LCO 3.7.12 5.5.14 Bases operability requirements for the PRF when in bases Control Program the fuel handling accident mode of operation.

Oh 3.7 1-R 3/4.7.9 Snubbers TRM 10CFR50.59 3.7 l-R 3/4.7.10 Scaled Source Contamination TRM 10CFR50.59 3.7 l-R 3/4.7.13 (Unit 2) Area Temperature TRM 10CFR50.59 Monitoring 3.8 ELECTRICAL POWER SYSTEMS 3.8 2-LA 3/4.8.1.1 LCO description of DG set.

LCO 3.8.1 5.5.14 Bases bases Control Program 38 16-LA 4.8. l.12.a - Accelerated testing surveillance Replaced by 10CFR50.65 requirements for the DGs contained in Table Maintenance 4.8-1 (deleted).

Rule compliance 38 20-LA 4.8.1.1.2.a.4 Surveillance details regarding SR 3.8.1.2 and 5.5.14 Bases DG synchronous speed (RPMs) and output SR 3.8.1.6 Control Program breaker closing permissive (57 Ih).

bases 3.8 23-LA 4.8.1.1.2.a.6 Surveillance details regarding LCO 3.8.1 5.5.14 Bases the required alignment of a DG to the bases Control Program 7

i associated emergency bus.

  • 'Ihe "t.A" designation indicates that part of'a TS is removed and the "R" designation indicates an entire TS is removed.

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Farley Nuclear Plant ITS Conversion

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Summary of CTS Requirements Removed From the TS

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and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3.8 25-LA 4.8.1.1.2.c.) Surveillance requirement to TRM 10CFR50.59 inspect and maintain DG in accordance wn.

procedur;s prepared in conjunction with manufacturers' recommendation.

3.8 32-LA > 4.8.1.1.2.c.5 Surveillance details regarding SR 3.8.1.12 5.5.14 Bases the required steady state voltage and bases Control Program frequency.

3.8 36-LA 4.8.l.l.2 c.6 Surveillance verifications that LCO 3.8.1 5.5.14 Bases auto-connected for.ds do not exceed DG bases Control Program ratings.

3.8 39-LA 4.8.1.1.2.c.10 Surveillance verification that TRM 10CFR50.59 DG lockout features prevent DG stan when rcquired.

38 44-LA 4.8.1.1.2.c 11 Surveillance details regarding SR 3.8.1.8 5.5.14 Bases specific KW rating of single largest load.

bases Control Program u) 38 41-LA 4.8.1.1.2.d Surveillance details regarding SR 3.8.1.19 5.5.14 Bases required performance after any modifications bases Control Program which could afTect the DG interdependence.

3.8 43-LA 4.8.1.1.2.e Surveillance details regarding SR 3.8.1.18 5.5.14 Bases verification of DG breaker and ESF breaker bases Control Program positions and fuse status and " footnote allowance for this test to be performed on either unit for shared DGs.

3.8 3-LA 3/4.8.1.2 Specific DG ID numbers in the LCO 3.8.2 5.5.14 Bases LCO requirement for one operable DG.

bases Control Program 3.8 3-LA 3/4.8.2.1 Specific information regarding how LCO 3.8.7 5.5.14 Bases inverters are connected.

bases Control Program 3.8 4-LA 3/4.8.2.1 LCO requirement for H and J FSAR SB0 10CFR50.59 and 4160kV buses.

discussion (J 5.5.14 Bases bus) and LCO Control Program 3.8.1/2 bases (H bus) yy k)

  • The "LA" designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-16 i

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Farley Nuclear Plant ITS Conversion p

Summary of CTS Requirements Removed From the TS

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and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3.8 5-LA 3/4.8.2.1 LCO list of required AC buses.

LCO 3.8.9 5.5.14 Bases bases Control Program 3.8 2-LA 3/4.8.3.2 Specific LCO and Action LCO 3.8.4 5.5.14 Bases requirements regarding the battery ID and bases Control Program supporting chargers.

3.8 3-LA 3/4.8.3.2 Specific DC busses listed in tiu LCO 3.8.9 5.5.14 Bases LCO.

bases Control Program 3.8 5-LA 3/4.8.3.2 LCO and Action description of an LCO 3.8.9 5.5.14 Bases operable bus (energized).

bases Control Program 3.8 7-LA 4.8.2.3.2.b.2 Surveillance description of SR 3.8.4.2 5.5.14 Bases

" excessive" visible corrosion.

bases Control Program 3.8 9-LA 4.8.2.3.2.b.3 Surveillance specifics of exact SR 3.8.6.3 5.5.14 Bases number of battery cells checked (10),

bases Control Program 3.8 17-LA 4.8.2.3.2.e Surveillance description of SR 3.8.4.8 5.5.14 Bases battery degradation.

bases Control Program 3.8 22-LA Table 4.8-2 Note (a) specific electrolyte LCO 3.8.6 5.5.14 Bases temperature used for correcting specific bases Control Program gravity.

)

38 2-LA 3/4.8.2.5 LCO description of the specific LCO 3.8.4 5.5.14 Bases CTS battery banks and the required chargers bases Control Program for each battery.

3.8 3-LA 3/4.8.2.5 LCO description of specific 125V LCO 3.8.9 5.5.14 Bases DC busses.

bases Control Program 3.8 8-LA 4.8.2.5.2.b.2 Surveillance description of SR 3.8.4.2 5.5.14 Bases

" excessive" visible corrosion.

bases Control Program 3.8 10-LA 4.8.2.5.2.b.3 Surveillance specifics of exact SR 3.8.6.3 5.5.14 Bases number of battery cells checked (10).

bases Control Program 3.8 17-LA 4.8.2.5.2.e Surveillance description of SR 3.8.4.8 5.5.14 Bases battery degradation, bases Control Program O

V

  • The "!A" designation mdicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-17

Faricy Nuclear Plant ITS Conversion Summary of CTS Requirements Removed From the TS

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and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

3.8 lR 3/4.8.3.1 Containment Penetration Conductor TRM 10CFR50.59 Overcurrent Protective Devices (Unit 2).

3.8 l-R 3/4.8.3.2 Motor Operated Valves Thermal TRM 10CFR50.59 Overload Protection Devices (Unit 2).

3.9 REFUELING OPERATIONS 3.9 2-LA 3/4.9.1 LCO and surveillance descriptive LCO 3.9.1 5.5.14 Bases information regarding the portions of the RCS bases Control Program and refueling canal affected.

34 5 LA 3/4 9 I The boron concentration required by COLR 5.6.5 COLR this LCO will be contained in the Core Operating Limits Report (COLR) 3.9 8 LA 3/4.9.1 Actions specifying the makeup flow LCO 3.9.1 5.5.14 Bases rate and boron concentration are replaced bases Control Program with more general STS bases guidance.

3.9 2-LA 3/4.9.2 LCO description of flux monitor LCO 3.9.1 5.5.14 Bases display visual operability.

bases Control Program 3.9 lR 3/4.9.3 Decay Time TRM 10CFR50.59 3.9 l-R 3/4.9.5 Communications TRM 10CFR50.59 3.9 l-R 3/4.9.6 Manipulator Crane TRM 10CFR50.59 3.9 l-R 3/4.9.7.1 Crane Travel - Spent Fuel Storage TRM 10CFR50.59 Pool Building Bridge Crane 39 l-R

~3/4.9 7.2 Spent Fuel Cask Crane TRM 10CFR50.59 3.9 5 LA 3/4.9.8.1 Action "b" explanation of the LCO 3.9.4 5.5.14 Bases reason for the I hour out of 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> exception bases Control Program to the requirement to have RHR in operation.

3.9 4-LA 3/4.9.8.2 Action "a" provision to perform the LCO 3.9.5 5.5.14 Bases Action "as soon as possible"is effectively Actions bases Control Program replaced with the STS bases description of this Action.

  • 1he "!X designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed A6-18

Farley Nuclear Pimt ITS Conversion Summary of CTS Requirements Removed From the TS O

and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document -

Control Section 39 6 LA 4.9.9 Description of specific actuating SR 3.9.3.2 5.5.14 Bases signals.

bases Control Program 3.9 l-R 3/4.9.12 Storage Pool Ventilation (Fuel TRM 10CFR50.59 Storage)

CTS 3/4.10 TEST EXCEPTIONS AND 3/4.11 RADIOACTIVE EFFLUENTS 3.10 1-R 3/4.10.5 Position Indication System -

TRM 10CFR50.59 Shutdown 3.11 1-LA 3/4.11.1.4 Liquid Holdup Tanks Explosive Gas 5.5.12 Explosive and Storage Gas and Storage Tank Tank Radioactivity Radioactivity Monitoring Monitoring Program and Program and TRM 10CFR 50.59

3. I I l-LA 3/4.11.2.5 Waste Gas Monitoring Explosive Gas 5.5.12 Explosive and Storage Gas and Storage Tank Tank Radioactivity Radioactivity

)

Monitoring Monitoring Program and Program and TRM 10CFR 50.59 3 II l-LA 3/411.2.6 Gas Storage Tanks Explosive Gas 5.5.12 Explosive and Storage Gas and Storage Tank Tank Radioactivity Radioactivity Monitoring Monitoring Program and Program and TRM 10CFR 50.59 I

  • The "lA" designation indicates that pan of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-19

Farley Nuclear Plant ITS Conversion c

Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

4.0 DESIGN FEATURES 4.0 1-LA Exclusion Area, Figure 5.1-1, Low FSAR 2.1 10CFR50.59 Population Zone, Figure 5. l-2. Site Boundary for Gaseous Efiluents, Figure 5.1-3, and the Site Boundary For Liquid Effluents Figure 5 l-4 4.0 2-LA 5.2 Containment - design information.

FSAR 3.8 and 10CFR50.59 Table 6.2-1 4.0 3-LA 5.4 RCS - design information.

FSAR 5.0, 10CFR50.59 Table 5.1-1, and 5.2 4.0 4 LA 5.5 Meteorological Tower Location, Figure FSAR 2.3.3, 10CFR50.59 5.5-1 Figures 2.3-27 and 2.4-1 4.0 11-LA 5.7 Component Cyclic or Transient Limit, New FSAR FNP ITS 5.5.5, Table 5.7-1. New Table required to identify Table 5.2-2a Component and the TS limits.

Cyclic or Transient Limit Program, and 10CFR50.59 5.0 ADMINISTRATIVE CONTROLS 50 5-LA 6.2.2.a References to shift crew composition 10CFR 50.54 10CFR 50.54 (k) shown in Table 6.2-1 replaced with specifics (k)(1) and (m)

(1) and (m) not addressed in 10CFR 50.54 (k)(1) and (m).

5.0 9-LA 6.2.2.d Requirement for an SRO to supervise 10 CFR 10 CFR 50.54(m) all Core Alterations.

50.54(m) (2)

(2) (iv).

(iv) 5.0 11-LA 6.2.2.g Requirement that shift supervisors 10 CFR 50.54 10 CFR 50.54 (k) hold a senior reactor operator license and that (k)(1) and (m)

(1) and (m)and reactor operators hold a reactor operator and section 13 10CFR 50.59 license.

of the FSAR

  • lhe "lX designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-20

Farley Nuclear Plant ITS Conversion j

I Summary of CTS Requirements Removed From the TS and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

5.0 13 LA Table 6.2-1 Minimum Shifl Crew 10 CFR 50.54 10 CFR 50.54 (k)

Composition.

(k)(1) and (m)

(1) and (m) 5.0 15-LA 6.2.3 Safety Audit and Engineering Review Quality 10 CFR 50.54(a)

Group (SAERG).

Assurance Progmm 5.0 16-LA 6.4 Training (entire section).

FSAR Chapter 10CFR50.59 13.2 Training Program 50 17-LA 6.5 Review and Audit (entire section).

Quality 10 CFR 50.54(a)

Assurance Program 5.0 18-LA 6.6 Reportable Event Action (entire section).

10 CFR 50.72 10 CFR 50.72 and 10 CFR and 10 CFR 50.73 50.73 50 19-LA 6.7 Safety Limit Violation (entire section).

10CFR 50.36, 10CFR 50.36, 10CFR 50.72, 10CFR 50.72, and 10CFR and 10CFR 50.73 50.73 5.0 20-LA 6.8.1 Requirements for written procedures for Regulatory Regulatory Guide the following: 6.8.1.b, refueling operations, Guide 1.33,10 1.33,10 CFR 6.8. l.c, surveillance and test activities of CFR 50.54(p),

50.54(p),10 CFR safety related equipment,6.8.1.d Security 10 CFR 50.54(q) and 10 Plan implementation, and 6.8. I.e Emergency 50.54(q) and CFR 50 Appendix Plan implementation.

10 CFR 50 E

Appendix E 50 22-LA 6.8.1 g Requirement for written procedures FSAR 10CFR50.59 for the process control program.

10CFR Part 20, 61, and 71 5.0 25-LA 6.8.1.j(i) Procedures be established.

FSAR section 10CFR50.59 and implemented and maintained for the station 8.3.1.1.7.3 10 CFR 50.65 blackout Alternate AC (AAC) Source and Reliability Program to derme the testing, Maintenance maintenance, and parts procurement Rule (10 CFR requirements necessary to maintam the AAC 50.65)

]

[._s as a Class IE component.

  • The "lX designation indicates that part of a TS is removed and the "R" designation indicates an entire TS is removed.

A6-21

)

Farley Nu: lear Plant ITS Conversion Summary of CTS Requirements Removed From the TS Q

and Placed in, or Currently Located in, Other Documents ITS DOC #

Description of CTS Requirement Document Control Section a

5.0 27-LA 6.8.2 Requirements for the procedure and Quality 10CFR 50.54(a) policy review process, including changes Assurance made to the procedures and policies.

Program 5.0 29-LA 6.8.3.b in-Plant Radiation Monitonng FSAR 10CFR50.59 Program 5.0 34-LA 6.8.3.f Radiological Environmental ODCM

10CFR50, Monitoring Program Appendix 1, 10CFR50.34a and 10CFR50.36.a 5.0 22 LA 6.8.3.g Solid Radioactive Wastes Control FSAR 10CFR Part 20, Program, Process Control Program (PCP).

61, and 71 and 10CFR50.59 50 68-LA 610 Record Retention (entire section)

Quality 10CFR 50.54(a) p Assurance Program 5.0 69-LA 6.11 Radiation Protection Program to 10 CFR 10 CFR

{

maintain procedures in accordance with 20.1101(b) 20.1101(b) and j

10CFR20.

and 10 CFR 10 CFR 20.I101(c) 20.I101(c) 5.0 71-LA

'" footnote to CTS 6.12 specifying radiation 10 CFR 10 CFR 20.1602 measurement procedure.

20.1602 5.0 73-LA 6.13 Process Control Program (PCP)

FSAR 10CFR50.59 and 10 CFR Part 20, 61, and 71 AV

  • The "lA" designatwn tndientes that pun of a TS is removed and the "R" designation indicates an entire TS is removed A6-22

I JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 IMPROVED TECHNICAL SPECIFICATION (TS) CONVERSION CHAPTER 1.0 - USE AND APPLICATION CONTENTS O

ENCLOSURE 1 MARKUP OF CURRENT FARLEY TS e

ENCLOSURE 2 DISCUSSION OF CHANGES TO CURRENT FARLEY e

TS ENCLOSURE 3 SIGNIFICANT HAZARDS EVALUATIONS FOR e

CHANGES TO THE CURRENT FARLEY TS j

ENCLOSURE 4 MARKUP OF NUREG-1431, Rev.1 - LCOs j

ENCLOSURE 5 JUSTIFICATIONS FOR DIFFERENCES FROM e

NUREG-1431, Rev.1

.__

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