Text

Supplement to License Amendment Request (TSCR-183): Application to Revise Technical Specifications for the Permanently Defueled Condition
	ML19261A141
Person / Time
Site:	Duane Arnold
Issue date:	09/12/2019
From:	Dean Curtland; NextEra Energy Duane Arnold
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-2019-157, NG-19-0102
	Download: ML19261A141 (480)
	v • d • e

{{#Wiki_filter:September 12, 2019 NG-19-0102 L-2019-157 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555 Duane Arnold Energy Center Docket No. 50-331 Renewed Facility Operating License No. DPR-49 Supplement to License Amendment Request (TSCR-183): Application to Revise Technical Specifications for the Permanently Defueled Condition By letter dated June 20, 2019 (ML19176A356), NextEra Energy Duane Arnold, LLC (NEDA) submitted a request for an amendment to the Operating License (OL) and Technical Specifications (TS) for the Duane Arnold Energy Center (DAEC). The submittal requested revisions to the OL and TS consistent with the permanent cessation of reactor operation and permanent defueling of the reactor. Following the submittal, NEDA performed an analysis of a fuel handling accident (FHA) in the spent fuel pool. This analysis determined that, following a decay period of 19 days, Control Building emergency ventilation is not required to maintain FHA dose consequences for control room occupants below the acceptance criteria of 10 CFR 50.67(b)(2)(iii). Consequently, NEDA hereby requests additional changes to the DAEC TS to reflect the revised FHA analysis. Specifically, those Technical Specifications associated with Control Building emergency ventilation are proposed for deletion by this supplemental submittal. The revisions to the DAEC technical specifications are proposed in accordance with 10 CFR 50.51 (b) and 10 CFR 50.36(c)(6). The Enclosure to this letter provides NEDA's evaluation of the proposed change, as supplemented. Attachment 1 to the enclosure provides markups of the TS showing the proposed changes, as supplemented, and Attachment 2 provides the clean TS pages containing the proposed TS changes, as supplemented. The changes, as supplemented, to the TS Bases are provided for information in Attachment 3 and will be incorporated in accordance with the TS Bases Control Program upon implementation of the approved amendment. These Attachments supersede, in their entirety, the Attachments contained in the June 20, 2019 submittal. NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324

Document Control Desk NG-19-0102 Page 2 of 2 NEDA requests approval of the proposed license amendment by October 1, 2020. NEDA requests that the approved amendment, as supplemented, become effective not less than 19 days after plant shutdown and following docketing of the certifications required by 10 CFR 50.82(a)(1 )(i) and (ii).

In accordance with 10 CFR 50.91, a copy of this application with enclosures is being provided to the designated State of Iowa official.

As discussed in the Enclosure, the proposed change, as supplemented, does not involve a significant hazards consideration pursuant to 10 CFR 50.92, and there are no significant environmental impacts associated with the change, as supplemented. The DAEC Onsite Review Group has reviewed the proposed license amendment. The NRG is currently reviewing a supporting licensing action to change the organizational staffing and training requirements contained in DAEC TS Section 1.1, "Definitions" and Section 5.0, "Administration" that was submitted for approval by letter dated April 19, 2019 (ML19109A031 ). This letter contains no new or revised regulatory commitments. If you have any questions or require additional information, please contact Michael

Davis, Licensing Manager, at 319-851-7032. I declare under penalty of pe~ury that the foregoing is true and correct. Executed on September~. 2019 Dean Curtland Site Director NextEra Energy Duane Arnold, LLC Enclosure cc: Regional Administrator, USNRC, Region Ill, Project Manager, USNRC, Duane Arnold Energy Center Resident Inspector, USNRC, Duane Arnold Energy Center A. Leek (State of Iowa)

Enclosure NEXTERA ENERGY DUANE ARNOLD, LLC DUANE ARNOLD ENERGY CENTER NG-19-0102 SUPPLEMENT TO LICENSE AMENDMENT REQUEST (TSCR-183) DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGES Page 1 of 32

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 2 of 32 NEXTERA ENERGY DUANE ARNOLD, LLC DUANE ARNOLD ENERGY CENTER Supplement to License Amendment Request (TSCR-183): Application to Revise Technical Specifications for the Permanently Defueled Condition EVALUATION OF PROPOSED CHANGE 1.0 Summary Description 2.0 Detailed Description 3.0 Technical Evaluation 4.0 Regulatory Evaluation 4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 No Significant Hazards Consideration 4.4 Conclusions 5.0 Environmental Considerations 6.0 References - Proposed Technical Specrfication Changes (Mark-Up) - Revised Technical Specmcation Pages (Clean, with Proposed Changes) - Proposed Technical Specification Bases Changes (Mark-Up)

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 3 of 32 1.0

SUMMARY

DESCRIPTION By letter dated June 20, 2019 (Reference 1), NextEra Energy Duane Arnold, LLC (NEDA) submitted a request for an amendment to the Operating License (OL) and Technical Specifications (TS) for the Duane Arnold Energy Center (DAEC). The submittal requested revisions to the OL and TS consistent with the permanent cessation of reactor operation and permanent defueling of the reactor. The revised TS will be identified as the DAEC Post Defueled Technical Specifications (POTS). Currently, UFSAR Chapter 15.2 describes the FHA as occurring when a fuel bundle and the refueling mast detach from the refueling bridge and drop onto the reactor vessel core. After the certifications of permanent cessation of power operation and of permanent removal of fuel from the DAEC reactor vessel are docketed, in accordance with 10 CFR 50.82(a)(1)(i) and (ii) respectively, and pursuant to 10 CFR 50.82(a)(2), the 10 *CFR 50 license will no longer authorize reactor operation or emplacement or retention of fuel in the reactor vessel. Consequently, a fuel handing accident at DAEC will be limited to a fuel handling accident within the Spent Fuel Pool (SPF). Following the June 20, 2019 submrttal, NEDA performed an analysis of a fuel handling accident (FHA) in the spent fuel pool. This analysis determined that, following a decay period of 19 days, Control Building emergency ventilation is not required to maintain FHA dose consequences for control room occupants below the acceptance criteria of 10 CFR 50.67(b)(2)(iii). Consequently, NEDA hereby requests supplemental changes to the DAEC TS to reflect the revised FHA analysis. Specifically, those Technical Specifications associated with Control Building emergency ventilation are proposed for deletion by this supplemental submittal. The proposed supplemental changes to the DAEC TS are in accordance with 10 CFR 50.36(c)(1) through (c)(5). The proposed supplemental changes also include administrative changes to content format and revised page numbering. The TS Table of Contents will be revised accordingly. The current DAEC TS contain limiting conditions for operation (LCOs) that provide for appropriate functional capability of equipment required for safe operation of the facility, including safe storage and management of irradiated fuel. Since the safety function related to safe storage and management of irradiated fuel at an operating plant is similar to the corresponding function at a permanently defueled facility, the existing TS related to the SFP provide an appropriate level of control. LCOs and associated surveillance requirements (SRs) that are not required to mitigate the consequences of the Fuel Handling Accident in the SFP are being proposed for deletion. In the development of the proposed POTS changes, NEDA reviewed POTS requirements from other plants that have permanently shut down, as listed in Section 4.2, Precedent.

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 4 of 32 In accordance with the revised FHA analysis, the proposed changes, as supplemented, would become effective no less than 19 days after plant shutdown and following docketing of the certifications required by 10 CFR 50.82(a)(1 )(i) and (ii). Related Licensing Actions By letter dated April 19, 2019 (Reference 2), NEDA submitted a License Amendment Request (LAR) proposing changes to the organization, staffing and training requirements contained in TS Section 1.1, "Definitions" and Section 5.0, "Administration" that complements and supports this request. 2.0 DETAILED DESCRIPTION The proposed supplemental change is requested as a result of NEDA's formally-stated intention to permanently cease power operation at DAEC in the fourth quarter of 2020, to transfer all fuel in the reactor to the Spent Fuel Pool (SFP) soon thereafter, and is in accordance with the revised FHA analysis. The proposed amendment, as supplemented, revises the DAEC TS for a permanently defueled and shutdown condition where the only credible Design Basis Accident (OBA) is an FHA in the SFP. To support the proposed changes, NEDA has reevaluated the consequences of an FHA in the SFP of the permanently shut down and defueled DAEC. The revised FHA analysis provides the framework and basis for the proposed supplemental changes. Design Basis Accident Analyses Applicable to Proposed Change As discussed in the June 20, 2019 submittal, with the termination of reactor operations at DAEC and the permanent removal of fuel from the reactor as certified in accordance with 10 CFR 50.82(a)(1)(i) and (ii), and pursuant to 10 CFR 50.82(a)(2), the majority of the OBA scenarios postulated in the UFSAR will no longer be possible. During decommissioning, the irradiated fuel will be stored in the Spent Fuel Pool (SFP) or the Independent Spent Fuel Storage Installation (ISFSI) until it is shipped offsite in accordance with the schedule to be provided in the Post Shutdown Decommissioning Activities Report (PSDAR) and the Spent Fuel Management Plan. With the reactor

permanently shut down and defueled, the only remaining credible OBA is the FHA occurring in the SFP.

Fuel Handling Accident Analysis for the Permanently Shut Down and Defueled Condition

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 5 of 32 Summary On April 16, 2001, the NRG issued License Amendment 237 to the OL and TS of DAEC. The amendment implemented an alternative source term (AST) per 10 CFR 50.67 to perform the radiological consequence analysis of the design-basis FHA to support changes to the TS (Reference 3). The analysis of the FHA that supported these changes assumed the FHA occurred over the reactor core 60 hours after reactor shutdown from full power and assumed Control Building emergency ventilation functions to mitigate dose consequences to control room occupants. The analysis did not credit secondary containment, secondary containment isolation or filtration by the Standby Gas Treatment (SBGT) System. With respect to dose consequences for control room occupants, the acceptance criteria for an FHA, as found in 10 CFR 50.67(b)(2)(iii) is: Adequate radiation protection is provided to permit access to and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 0. 05 Sv (5 rem) total effective done equivalent (TEDE) for the duration of the accident. After the reactor has been completely defueled following permanent shut down, an FHA over the reactor core is no longer a credible accident and an FHA over the SFP becomes the bounding accident. NEDA has performed a revised analysis for an FHA in the SFP. This analysis did not credit secondary containment, secondary containment isolation or filtration by the SBGT System. This analysis determined that, following a 19-day decay period, Control Building emergency ventilation (CBEV) is not required to maintain dose consequences for control room occupants within the criteria of 10 CFR 50.67(b)(2)(iii). Consequently, TS LCOs and SRs associated with CBEV and support equipment are proposed for deletion. Methods and Assumptions Consistent with the DAEC UFSAR Chapter 15.2, the revised FHA analysis uses the Alternate Source Term (AST) Methodology from Regulatory Guide 1.183.

3.0 TECHNICAL EVALUATION

The following tables identify each section that is proposed to be changed by this supplement, the proposed changes and the basis for each change. TS sections proposed for revision in the June 20, 2019 submittal that are unchanged by this supplement, are indicated as such in bold text. Proposed additions are shown using red underline and deletions are shown using red strikethrough.

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 6 of 32 provides the marked-up version of the DAEC TS. This marked-up version supersedes, in its entirety, Attachment 1 of the June 20, 2019 submittal. The following administrative changes are not shown in the marked-up TS and TS Bases pages because they do not affect the technical content of the TS:

Reformatting (margins, font, tables, line spacing, etc.) content to create a continuous electronic file;
Renumbering of pages, where appropriate, to condense and reduce the number of pages; and _
Revisions to the TS Table of Contents. provides the re-typed affected POTS pages, these pages supersede those provided in Attachment 2 of the June 20, 2019 submittal.

The markups of the TS Bases, provided in Attachment 3, are provided for information only. Markups of TS Bases sections that are deleted in their entirety are not included in . Similarly, Attachment 3 supersedes, in its entirety, Attachment 3 of the June 20, 2019 submittal.

Duane Arnold Energy Center Docket No. 50-331

License Amendment Request Enclosure to NG-19-0102 Page 7 of 32 TECHNICAL SPECIFICATIONS TS SECTION 1.1, DEFINITIONS TS 1.1, "Definitions," provides defined terms that are applicable throughout the TS and TS Bases. In addition to the defi.ned terms deleted in the June 20, 2019 sLJbmittal, a number of additional Definitions are proposed. to be deleted because they*have no relevance to and no longer apply to the POTS.

CHANNEL CALIBRATION This definition is not proposed for inclusion in the POTS because the term is not used in any POTS specification . . CHANNEL CHECK This definition is not proposed for inclusion in the POTS because the term is not used in any POTS specification. CHANNEL CHECK FUNCTIONAL TEST This definition is not proposed for inclusion in the POTS because the term is not used in any POTS specification. DOSE EQUIVALENT 1-131 Thjs definition is not proposed for inclusion in the POTS because the term is not used in any POTS specification. LOGIC SYSTEM FUNCTIONAL TEST This definition is not proposed for inclusion in the POTS because the term

                        "                            is not used in any POTS specification.

OPERABLE - OPERABILITY This definition is not proposed for inclusion in the POTS because the term is.not used in any POTS specification. TS Section 1.2 LOGICAL CONNECTORS TS 1.2 explains the meaning of logical connectors, including several illustrative examples. Current Proposed 1.2 Logical Connectors 1.2 Deleted Logioal Connectors Basis After the certifications required by 10 CFR 50.82(a)(1) are docketed for DAEC, the 10 CFR Part 50 license will no longer authorize operation of the reactor or placement or retention of fuel in the reactor vessel p1,1rsuant to 10 CFR 50.82(a)(2). DAEC Will have spent fuel in the SFP and, after a 19-day decay period, the only required LCO will be 3.7.8, Spent Fuel Pool Level Indication. This LCO has a single Condition prompting a single Action and does not use logical connectors, which obviates the need for the explanatory text and examples in Section 1.2.

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 8 of 32 TS Section 1.3 COMPLETION TIMES TS 1.3 establishes the Completion Time convention and provides guidance for its use, including several illustrative examples. The changes presented below supersede those proposed in the June 20, 2019 submittal. Current Proposed BACKGROUND BACKGROUND Limiting Conditions for Operation Limiting Conditions for Operation (LCOs) specrfy minimum requirements (LCOs) specify minimum requirements for ensuring safe operation of the unit. for safely maintaining ensuring safe The ACTIONS associated with an LCO operation of the ooit facility. The state Conditions that typically describe ACTIONS associated with an LCO the ways in which the requirements of state Conditions that typically describe the LCO can fail to be met. Specified the .ways in which th~ -requirements of with each stated Condition are the LCO can fail to be met. Specified - Required Action(s) and Completion with each stated Condition are Time(s). Required Action(s) and Completion Time(s). DESCRIPTION DESCRIPTION The Completion Time is the amount of The Completion Time is the amount of time allowed for completing a Required time allowed for completing a Required Action .. It is referenced to the time of Action. It is referenced .to the time of discovery of a situation (e.g., discovery of a situation (e.g., inoperable equipment or variable not inoperable equipment or variable not within limits) that requires entering an within limits) that requires entering an ACTIONS Condition unless otherwise ACTIONS Condition unless otherwise specified, providing the unit is in.a specified, providing the URit facility is in MODE or specified condition stated in a MODE or specified condition stated the Applicability of the _LCO. Required in the Applicability of t~e LCO. Actions must be completed prior to the Required Actions must be completed expiration of the specified prior to the expiration of the specified Completion Time. An ACTIONS _Completion Time. An ACTIONS Condition remains in effect and the Condition remains *in effect and the Required Actions apply until the Required Actions apply until the Condition no longer exists or the unit is Condition no longer exists or the tffiit not within the LCO Applicability. facility is not within the LCO Applicability. Remaining DESCRIPTION text and

Examples 1.3-1 through 1.3-7 are proposed for deletion.

Duane Arnold Energy Center D.ocket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 9 of 32 Basis After the certifications required by 10 CFR 50.82(a)(1) are docketed for DAEC, the 10 CFR Part 50 license will no longer authorize op_eration of the reactor or placement or retention of fuel in the reactor vessel pursuant to 10 CFR 50.82(a)(2). DAEC will have spent fuel in the SFP and, following a 19-day decay period, the only required LCO will be 3.7.8, Spent Fuel Pool Level Indication. This LCO has a REQUIRED ACTION to suspend fuel movement in the secondary containment with a COMPLETION TIME of Immediately, which obviates the need for much of the explanatory text and examples in Section 1.3. TS Section 1.4 Frequency TS Section 1.4 defines the proper use and application of Frequency requirements, including several illustrative examples. The changes presented below supersede those proposed in the June 20, 2019 submittal. Current Proposed DESCRIPTION DESCRIPTION Each Surveillance Requirement (SR) has Each Surveillance Requirement (SR) has a specified Frequency in which the a specified Frequency in which the Surveillance must be met. in order to meet Surveillance must be met in order to meet the associated LCO ..An unqerstanding of the associated LCO. An understanding of the correct application of the specified th_e correct application of the specified Frequency is ne~ssary for compliance Frequency is necessary for compliance with the SR. - with the SR. The "specified Frequency is referred to +l=le "speeifies i;:FeEJ1:1eReif is FefeFFes ta tt,roughout this section and each of the tAFel:l§Ae1:1t tt=iis sestieA aRe east=i ef tt=ie Specifications of Section 3.0, Surveillance SpeeifieatieRs ef SestieR* 3.Q, S1:1FVeillaRS8 Requirement (SR) Applicability. The Re~1:1ireme1:1t (SR~ i~plisaeility. The ."specified Frequency" consists of the "specified Frequency consists of the requirements of the Frequency column of requirements of the Frequency column 9f. each SR, as well as certain Notes in the each SR, as well as certain Notes in the Surveillance column that modify Surveillance column that modify performance requirements.-. performance requirements. Sometimes special *Situations dictate Semetimes s~esial sit1:1atieRs eistate when the requirements of a Surveillance ,_.AleR the F8EJl:liFemeRts ef a S1:1FVeillaRse are to be met. They are "otherwise aFe ta ea met, +t=iey aFe "ett=ieFwise stat~d" conditions allowed by SR 3.0.1 . states" S9ReitieRS allewee ey SR J.Q.~. They may be stated as clarifying Notes in +t=iey may ee states as slaFifyiR~ Netes iR the Surveillance, as part of the tt=ie S1:1P1eillam,e, as part ef the . _ Surveillance, or both. S1:1F¥eillaRS8, SF eetA.

Dua*ne Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 10 of 32 Situations where a Surveillance c6uld be Situations where a SuP1eillance could be

required (i.e., its Frequency could expire), required (i.e., its Frequency co_uld expire),

but where it is not possible or not desired but where it is not possible or not desired that it be performed until sometime after that it be perfom,ed until sometime after the associated LCO is within its the associated LCO is 'lli=thin its Applicability, represent potential SR 3.0.4 Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is (i.e., the SuP1eillance or the Frequency) is stated such that it is only "required" when stated such that it is.only "required" when it can be and should be performed. With it can be and should be-performed. '.'Vith an SR satisfied, SR 3.0.4* imposes no an SR satisfied, ;SR 3.0.4 imposes no

restriction. restriction. -

The use of "met" or "performed" in these The use of "met" or "performed" in these instances conveys specific meanings. A instances conveys specific meanings. A Surveillance *is "met" only when the Surveillance is "met" only when the acceptance criteria are satisfied. Known acceptance criteria are satisfied. Known failure of the requirements of a failure of the requirements of a Surveillance, even without a Surveillance Surveillance, even without a Surveillance specifically being "performed," constitutes specifically being "performed," constitutes a Surveillance not "met." "Perfo,rmance" a Surveillance not "met." "Performance" refers only to the requirement to refers only to the requirement to specifically determine the ability to meet specifically determine the ability to meet the acceptance criteria. Some the acceptance criteria,. Somo Surveillances contain notes that modify SuPleillances *contain notes that modify the Frequency of performance or the the Frequenc,y of performance or the conditions during which the acceptance conditions during \*.:hich the acceptance criteria must be satisfied. For these - criteria must be satisfied. For-these Surveillances, the MODE-entry SuP1eillances, the MODE entry restrictions of SR 3.0.4 may not apply. restrictions of SR3.0.4 may not apply. Such a Surveillance is _not required-to be_ Such a SuP1oillanco is not required to be performed prior to entering a MODE or performed prior to entering a MODE or other specified condition in the other specified condition in the Applicability of the associated LCO if any Applicability of the associated LCO if any of the following three conditions are of the follo'Ning three conditions are satisfied: satisfied: *

a. The Surveillance is not required to be a. The SuP1oillance is not required to be met in the MODE or other specified - met in the MODE or other specified condition to be entered; or condition to be entered; or

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 11 of 32

b. The Surveillance is required to be met b. The Surveillanoe is required to be met in the MODE or other specrfied in tho MODE or other spooifiod condition to be entered, but has been oondition to be entered, but has been perfonned within the specified performed within tho spooi:fiod Frequency (i.e., it is current) and is Frequenoy (i.e., it is ourront) and is known not to be failed; or known not to be failed; or

c. The Surveillance is required to be met, o. The Surveillanoe is required to be met, but not performed, in the MODE or but not performed, in the MODE or other specified condition to be entered, other speoified oondition to be and is known not to be failed. entered, and is known not to be failed.

Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 Examples 1.4 3, 1.4 4, 1.4 5, and 1.4 6 discusses these special situations. disousses those speoial situations. EXAMPLES EXAMPLES The following examples illustrate the The following examples illustrate§ the vario1:1s ways tnat Frequencies are manner in which various ways that specified. In these examples, the Frequencies are specmed. In these Applicability of the LCO (LCO not shown) examples, the ,t\pplioability of the LCO is MODES 1, 2, and 3. (LCO not shmvn)-is MODES 1, 2, and 3. EXAMPLE 1.4-1 EXAMPLE 1'.4-1 SUR\IELl.ANCE REQUIREMENTS_ SURVElll.ANCE SURVEll.lANCE Example 1.4-1 contains the type of SR Example 1.4-1 contains the type of SR most often encountered in the Technical most often encountered in the Technical Specifications (TS). The Frequency Specifications (TS). The Frequency ,specifies an interval (12 hours) during specifies an interval (12 hours) during which the associated Surveillance must which the associated Surveillance must be performed at least one time. be perfonned at least *one time. Perfonnance of the Surveillance initiates Performance of the Surveillance initiates the subsequent interval. Although the the subsequent interval. Although the Frequency is stated-as-12 hours, an- Frequency is stated as 12 hours, an extension of the time interval to 1 .25 extension of the time interval to 1.25 times the interval specified in the _ times the interval specified in the *

Frequency is allowed by SR 3.0.2 for Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement operational flexibility. The measurement

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 12 of 32 of this interval continues at all times, even of this interval continues at all times, even when the SR-is not required to be met per when the-SR is not required to be met per SR 3.0.1 (such as when the equipmenf is SR 3.0.1 (sueh as when the equipment is inoperable, a variable is outside specified inoperable, a variable is outside specified limits, or the unit is outside the limits, or the -HM facility is outside the Applicability of the LCO). If the interval Applicability of the LCO). If the interval specified hy SR 3.0.2 is exceeded while specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified the ooit facility is in a MODE or other condition in the Applicabilrty of the LCO,

specified condition in the Applicability of and the performance of the Surveillance - the LCO, and the performance of the is not otherwise modified (refer to Surveillance is not otherwise modified Examples 1.4-3 and 1.4-4), then SR 3.0.3 (refer to Examples -1 .4_ 3 and 1.4 4), then becomes applicable. SR 3.0.3 becomes applicable.

'If the interval as specified by SR 3.0.2 is If theJnteP.(al as spasmed sy SR 3.Q.2 is exceeded while the unit is not in a MODE e~rneeded 11mile the unit is not,in a MOD~ or other specified condition in the OF other spesified GOAdition IA the .- Applicability of the LCO for which Applieasility of ~e bGO for i.~.ihieh * . performance of the SR is required, then performanoo of the SR is required, then SR 3.0.4 becomes applicable. The SR 3.Q.4 seeomes applieasle. +he Surveillance must be performed within the SuFVeillanee must' se performed >.,1,1ithin the*- Frequency requirements ofSR 3.0.2, as. i;'.requeney requirements--of SR 3.Q.2, as modified by SR 3.0.3, prior to entry into modified sy SR 3.Q.3, prior to anti='/ into the MODE or other specified condition or the MODE or-other speeified-eondition OF the LCO is considered not met (in the bGO is oonsidered not met (in accordance with SR 3.0.1) and LCO 3.0.4 aeeoi=aanee v"1ith SR *a:Q.1) and bGO 3.Q.4 becomes applicable. seoomes applieasle. EXAMPLE 1.4-2 EXAMPLE 1.4-2 is proposed for deletion EXAMPLE 1.4-3 EXAMPLE 1.4-3 is proposed for deletion EXAMPLE 1.4-4 EXAMPLE 1.4-4 is proposed for deletion

EXAMPLE 1.4-5 EXAMPLE 1.4-5 is proposed for deletion EXAMPLE 1.4-6 EXAMPLE 1. .4-6 is proposed for deletion Basis After the certifications required by 10 CFR 50.82(a)(1) are docketed for DAEC, the 10 CFR Part 50 license will no longer authorize operation of the reactor or placement or retention of fuel in the reactor vessel pursuant to 1O_ CFR 50.82(a)(2).* DAEC will have spent fuel in the SFP and, following a 19:.day decay period, the only required LCO will be 3.7.8, Spent Fuel Pool L~vel Indication. This LCO has an SR to check SFP level on a Frequency in accordance with the Surveillance Frequency Control Program (SFCP).

This straight forward Frequency obviates the need for much of the explanatory text and examples in Section 1.4.

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 13 of 32 TS Section 2.0 SAFETY LIMITS (Sls) Changes proposed in the June 20, 2019 submittal are unchanged by this supplement TS 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY TS 3.0, "Limiting Condition for Operation (LCO) Applicability," establishes the general requirements applicable to all 'Specifications and applies at all times, unless otherwise stated. After the certifications required by 10 CFR 50.82(a)(1) are docketed for DAEC, the 10 CFR Part 50 license will no longer authorize operation of the reactor or placement or retention of fuel in the reactor vessel pursuant to 10 CFR 50.82(a)(2}. DAEC will have spent fuel in the SFP and, following a 19-day decay period, the only required LCO will be 3.7.8, Spent Fuel Pool Level Indication. Consequently, some LCOs are no longer applicable and some must be revised to reflect the permanently defueled condition. Changes proposed to LCO 3.0.1 in the June 20, 2019 submittal are unchanged by this supplement Current TS LCO 3.0.2 Proposed TS LCO 3.0.2 (These chan~es supersede those made in the June 20, 019 submittal.) U8on discovery of a failure to meet an U~on discovery of a failure to meet an L - 0, the Required Actions of the L 0, the Required Actions of the associated Conditions shall be met, except associated Conditions shall be met, e~rnept as provided in LCO 3.0.5 and LCO 3.0.6. . as provided in LCO 3.0.5 and LCO 3.0.6. If the LCO is met or is no longer applicable If tl=le LCO is met eF is ne len9eF applisaele prior to expiration of the specified ~FieF te e*13iratien ef tl=le s13es1fied Completion Time(s), completion of the Gem~letien +ime(s), oom13letien ef tl=le Required Action(s) is not required, unless

Requir:ad Astien(s) is net FequiFed, unless otherwise stated.
etl=leiwise stated.

Basis Deletion of LCO 3.0.5 was proposed in Jhe June 20, 2019 submittal. Deleti_on of LCO 3.0.6 is discussed later. The second paragraph of LCO 3.0.2 allows flexibility in Completion Time(s) of Required Action(s). It is not anticipated that this_flexibility will be needed once the DAEC is permanently shut down and defueled and these TS changes become effective. LCO 3.0._3 proposed for deletion in the June 20, 2019 submittal, this is unchanged by this supplement

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 14 of 32 Current TS LCO 3.0.4 Proposed TS LCO 3.0.4 - Deleted. (These changes supersede those made in When an LCO is not met, entry into a the June 20, 2019 submittal.) MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or

c. When an allowance is stated in the individua*1 value, parameter, or other Specification.

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. Basis This LCO allows flexibility in changes in MODES or other specified conditions when an LCO is not met. It is not anticipated that this flexibility will be needed once the DAEC is permanently shut down and defueled and these TS chanQes become effective. LCO 3.0.5 was proposed for deletion in the June 20, 2019 submittal, this is unchanged by this supplement

Duane Arnold Energy Center Docket No. 50-331 -License Amendment Request Enclosure to NG-19-0102 Page 15 of 32 Current TS LCO 3.0.6 Proposed TS LCO 3.0.6 - Deleted. When a supported system LCO is not met solely due to a support-system LCO _not being met, the Conditions and Required Actions associated with this supported system are n.ot required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specmcation 5.5.11, "Safety Function

.Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

a When support system's Required Action directs a supported system to be declared - inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall. be entered in accordance with LCO 3.0.2. Basis This LCO establishes an exception to LCO 3.0.2 for support systems that have an LCO specmed in the TS. It is not anticipated that this exception will be needed once the DAEC is permanently shut down and defueled and this TS becomes effective. LCO 3.0.7 was proposed for deletion in the June 20, 2019 submittal, this is unchanged by this supplement. LCO 3.0.8 was proposed for deletion in the June 20, 2019 submittal, this is unchanged by this supplement.

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 16 of 32

Current TS LCO 3.0.9 Proposed TS LCO 3.0.9 - Deleted. -

When one or more required barriers are (These changes supersede those made in unable to perform their related support the June 20, 2019 submittal.) - Junction(s), any supported system LCO(s) are not required to be declared not met solely for this reason for up to 30 days provided that at least one train or subsystem of the supported system is OPERABLE and supported by barriers capable of providing their related support function(s), and risk is assessed and managed. This specmcation may be concurrently applied to more than one train or subsystem of a multiple train or subsystem supported system provided at least one train or subsystem of the supported_ system is OPERABLE and the barriers supporting each of these trains or subsystems provide their related support function(s),for different categories of inrtiating events. For the purposes of this specification, the High Pressure Coolant Injection system, the Reactor Core Isolation Cooling system, and ttie Automatic Depressurization System are considered independent _,subsystems of a single system. If the required OPERABLE train or -subsystem becomes inoperable while this specmcation is in use, it must be restored to OPERABLE status within 24 hours or the provisions of this specmcation cannot be applied to the trains or subsystems supported by the barriers that cannot perform their related support function(s). At the end of the specified period, the required barriers n:,ust be able to perform their related support function(s) or the supported system LCO (s) shall be declared not met.

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 17 of 32 Basis LCO 3.0.9 establishes condrtion_s under which systems described in the TS are considered to remain .OPERABLE when required barriers are not capable of providing their related support function(s). After the *certifications required by 10 CFR 50.82(a)(1) are docketed for DAEC, the 10 CFRPart 50 license will no longer authorize operation of the reactor or placement or retention of fuel in the reactor vessel pursuant to 10 CFR 50.82(a)(2). DAEC will have spent fuel in the SFP and, no less than 19 days after shutdown, the only required LCO will be 3}.8, Spent Fuel Pool Level Indication. There are no required barriers for this remaining TS.

Changes to SR 3.0.1 proposed in the June 20, 2019 submittal are not impacted by this supplement Current TS SR 3.0.2 proposed TS SR 3.0.2 The specified Frequency for each SR is The specified Frequency for each SR is met rf the Surveillance is performed within met if the Surveillance is performed within 1.25 times the interval specified in the 1.25 times the interval specified in the .

Frequency, as measured from the Frequency, as measured from the previous performance or as measured previous performance or as measured from the time a specified condition of the from the time a specified condrtion of the Frequency is met. Frequency is met. For Frequencies specmed as "once," the For Frequencies specified as "once," the above interval extension does not apply. above interval extension does not apply. If a Completion Time requires periodic If a Completion Time requires periodic performance on a "once per ... " basis, the performance on a "once per ... " basis, above Freque_ncy extension applies to the above Frequency extension applies to each performance after the initial each performance after the initial performance. performance. Exceptions to this Specification ~re stated 8cceptions to this Sp_~cification are stated in the individual Specifications. in tho indi\*idual Specifications. Basis SR 3.0.2 permits a 25% extension of the interval specified in the Frequency of TS Surveillances. This extension facilitates* Surveillance scheduling and considers conditions that may not be suitable for conducting the Surveillance. Discussion of specific Completion Times preformed* on a "once per. .. " basis and exceptions to this Specification are deleted. After the certifications required by 10 CFR 50.82(a)(1) are docketed for DAEC, the 10 CFR Part 50 license will no longer authorize operation of the reactor or placement or retention of fuel in the reactor vessel pursuant to 10 CFR 50.82(a)(2). DAEC will have spent fuel in the SFP and, followinQ a 19-day decay

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 18 of 32 period, the only required LCO will be 3.7.8, Spent Fuel Pool Level Indication. The deleted scenario and exception will not be needed once the DAEC is permanently shut down and defueled and this TS becomes effective. SR 3.0.3 is not impacted by either the June_20, 2019 submittal or this .supplement. Current TS SR 3.0.4 Proposed TS SR *3.0.4

                                                 . (These change_s supercede thc:>se made in the June 20, 2019 submittal.)

Entry into a MODE or other specified Entry into a MODE or other speeified condition in the Applicability of an LCO condition in the Applicability of an LCO.

shall only be made when the LCO's shall only be made when the LCO's Surveillances have been met within their Surveillances have been met within their specified Frequency, exc~pt as provided specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due by SR 3.0.3. \OJReA aA bGO is Rot FAet el:!e to Surveillances not having been met, to Sl:!rveillaAses f=!Ot haviA§ eeeA FAet,

_entry into a MODE or other specified eAtry iAto a MODE or otl=ier s13esifiee condition in the Applicability shall only be GOREiitioA iA the Ap13lisaeility shall ORiy 88 made. in accordance with LCO 3.0.4. FAaee iA aooomaAse 'Nith bGO a.0.4. - _This provision shall not prevent entry into This provision shall not prevent entry into MODES or other specified conditions in_ MODES or other spedfied conditions in the Applicability that are requi.red to the Applicability that are required to comply with ACTIONS or that are part of a comply with ACTIONS or that are 13art of a shutdown of the unit. shl:!teo11m of tRe l:!Ait. Basis This SR is revised to remove references to MODES and plant shutdown, neither of which apply to the DI\EC in the permanently defueled condition. Additionally, reference to LCO 3.0.4 is removed, deletion of LCO 3.0.4 is discussed earlier. Changes to TS Sections 3.1 through 3.3.6.3, proposed in the June 20, 2019 submittal, are unchanged by this *Supplement TS Section 3.3 page 1 markup is revised to reflect the deletion of 3.3. 7 .1 and 3.3.8.1. Current Progosed *- TS 3.3.7.1 - Standby Filter Unit (SFU) TS 3.3.7.1 - Standby Filter Unit (SFU) Instrumentation Instrumentation to be deleted. Basis The SFU System is designed to provide a radiologically controlled environment to ensure the habitability of the control room for the safety of control room operators under

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 19 of 32 all plant conditions including design basis accidents. TS 3.3.7.1, "Standby Filter Unit (SFU) Instrumentation," ensures automatic action to pressurize the control building envelope to minimize the consequences of radioactive material in the control building envelope. After the reactor has been completely defueled following permanent shut down, an FHA over the _reactor core is no longer a credible accident. An FHA in the spent fuel pool is the bounding accident. NEDA has performed a revised analysis for an FHA in the SFP. This FHA analysis determined that, following a 19-day decay period, Control Building Emergency Ventilation (CBEV) is not required to maintain dose consequences for control room occupants within the criteria of 10 CFR 50.67(b)(2)(iii). Consequently, JS

LCOs and SRs associated with CBEV and support equipment, specifically, SFU Instrumentation, are proposed for deletion.

With the TS section above deleted, the corresponding TS* Bases will also be deleted. Since it is deleted in its entirety, TS Bases section 3.3.7.1 i_s not included in Attachment 3. Current Proposed TS 3.3.8.1 - Loss of Power (LOP) TS 3.3.8.1 - Loss of Power (LOP) Instrumentation lnstrum*entation to be deleted. Basis TS 3.3.8:1, "Loss of Power (LOP) Instrumentation," monitors the 4.16 KV emergency bus voltages and the Startup and Standby Transformer secondary winding voltages. This *monitoring ensures that if insufficient power is available, the buses are disconnected from the offsite power sources and connected to the onsite Diesel Generator (DG) power sources. - - After the reactor has been completely defueled following permanent shut down, an FHA over the *reactor core is no longer a credible accident. An FHA in the spent fuel pool is the bounding accident. NEDA has performed a revised analysis for an FHA in the SFP. This FHA analysis determined that, following a 19-day decay period, Control Building Emergency Ventilation (CBEV) is not required to maintain dose consequences for control room occupants within the criteria of 10 CFR 50.67(b)(2)(iii). Consequently, TS LCOs and SRs associat~d with CBEV and support equipment, specifically, LOP Instrumentation, are proposed for deletion. Wrth the TS section above deleted, the corresponding TS Bases will also be deleted. Since it is deleted in its entirety, TS Bases section 3.3.8.1 is not included in Attachment 3.

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 20 of 32 Changes to 3.4, 3.5, and 3.6, proposed in the June 20, 2019 submittal, are unchanged by this supplement TS SECTION 3.7 PLANT SYSTEMS Changes to 3.7.1 through 3.7.3 and 3.7.6 through 3.7.9, proposed in the June 20, 2019 submittal, are unchanged by this supplement Current Proposed (These changes supersede those made in the June 20, 2019 submittal.) TS 3.7.4 - Standby Filter Unit (SFU) TS 3.7.4 - Deleted System TS 3.7.5 - Control Building Chiller (CBC) TS 3.7.5 - Deleted System Basis TS 3.7, "Plant Systems," contains LCOs that provide for appropriate control of process variables, de$ign features, or operating restrictions needed for- appropriate functional capabilrty of equipment required for safe operation of the facility. TS 3.7.4, "Standby Filter Unit (SFU) System," is applicable in MODES 1, 2, and 3, during movement of irradiated fuel assemblies in the secondary containment, and during CORE ALTERATIONS. The SFU System provides a protected e*nvironment from which occupants can control the unit following an _uncontrolled release of radioactivrty, hazardous chemicals or smoke. Specifically, the SFU System provides emergency treatment of outside supply air and a Control Building Envelope (CBE) boundary that limits the inleakage of unfiltered air .. TS 3.7.5, "Control Building Chiller (CBC) System," is applicable in MODES 1, 2, and 3, during "!lovement of irradiated fuel assemblies in the secondary containment, and during CORE ALTERATIONS. The CBC System provides temperature control for the control building HVAC system under both normal and accident conditions. After the reactor has been completely defueled following permanent shut down, an FHA over the reactor core is no longer a credible accident. An FHA in the spent fuel pool is the bounding accident. NEDA has performed a revised analysis for an FHA in the SFP. This FHA analysis determined that, following a 19-day decay period, Control Building Emergency Ventilation (CBEV) is not required to maintain dose .c~:msequences for control room occupants within the criteria of 10 CFR 50.67(b)(2)(iii). Consequently, TS LCOs and SRs associated with CBEV and support equipment, specifically SFU and CBC Systems, are proposed for deletion.

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 21 of 32 With the TS sections above deleted, the corresponding TS Bases will*also be deleted. Since they are deleted in their entirety, TS Bases sections 3.7.4 and 3.7.5 are not included in Attachment 3. TS SECTION 3.8 ELECTRICAL POWER SYSTEMS TS 3.8.1, 3.8.4 and 3.8.7 were proposed for deletion in *the June 20, 2019 submittal. This i*s unchanged by this supplement, however, they have been marked up to reflect deletion of Section 3.8. Current Proposed (These changes supersede those made in the June 20, 2019 submittal.) TS 3.8.2 -AC Sources - Shutdown TS 3.8.2 - Deleted TS 3.8.3 --Diesel Fuel Oil, Lube Oil, and TS 3.8.3 - Deleted Starting Air TS 3.85- DC Sources - Shutdown TS 3.8.5 - Deleted TS 3.8.6 - Battery Cell Parameters TS 3.8.6 - Deleted TS 3.8.8 - Distribution Systems - TS 3.8.8 - Deleted Shutdown Basis TS 3.8, "Electrical Power Systems," contains LCOs that provide for appropriate functional capability of plant electrical equipment required for safe operation of the 'facility. The TS are proposed for deletion. TS 3.8.2, "AC Sources - Shutdown," is applicable in MODES 4 and 5, and during .movement of irradiated fuel assemblies in the secondary containment The AC Electrical Power System ensures an ava\lable source of power to the Engineered Safety Feature (ESF) Systems via essential buses 1A3 and 1A4. TS 3.8.3, "Diesel Fuel Oil, .Lube Oil,*and Starting Air," is applicable when the associated diesel generator is required to be operable. These systems ensure proper operation of the EDGs by maintaining the quality of the fuel and lube .oils and adequate starting air capacity. TS 3.8.5, "DC Sources - Shutdown," is applicable in MODES 4 and 5 and during movement of irradiated fuel assemblies in the secondary containment. The DC Electrical Power System provides the AC Emergency Power System with control power. It also provides both motive and control power to selected safety related equipment. TS 3.8.6, "Battery Cell Parameters," is applicable when associated DC electrical power subsystems are required to be OPERABLE. The.battery cell parameter requirements ensure availability of the required DC power to maintain the facility in a safe condition

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 22 of 32' after a postulated FHA TS 3.8.8, "Distribution Systems - Shutdown," is applicable in MODES 4 and 5, and during movement of irradiated fuel assemblies in the secondary containment. The AC and DC Electrical Power Distribution Systems are designed to provide sufficient capacity, capability, redundancy, and reliability to ensure the availability of necessary power to ESF Systems so that the fuel, Reactor Coolant System, and containment design limits are not exceeded The above TS are related to assuring the appropriate functional capability of plant equipment, and control of process variables, design features, or operating restrictions required for safe operation of the facility only when the reactor is in MODES 1 through

3. After the reactor has been completely defueled following permanent shut down, an FHA over the reactor core is no longer a credible accident. An FHA in the spent fuel pool is the bounding accident. NEDA has performed a revised analysis for an FHA in the SFP. The analysis found dose consequences to be within the criteria of 10 CFR 50.67(b)(2). This FHA analysis did not credit Control Building Emergency Ventilation (CBEV) to maintain dose consequences for control room occupants within the criteria of 10 CFR 50.67(b)(2)(iii). Consequently, TS LCOs and SRs associated with CBEV and support equipment are proposed for deletion.

With the TS sections above deleted, the corresponding TS Bases will also be deleted. Since they are deleted in their entirety, TS Bases sections 3.8.2, 3.8.3, 3.8.5, 3.8.6 and 3.8.8 are not included in Attachment 3. Changes proposed to 3.9, 3.10 and 4.0 in the June 20, 2019 submittal, are unchanged by this supplement

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 23 of 32 TS Section 5.5 Programs and Manuals This section provides a description and requirements regarding programs and manuals that are to be established, implemented, and maintained. TS 5.5 will remain applicable once the reactor is permanently shut down and defueled. As such, it is proposed to be retained and revised to reflect the permanently defueled condition as described below. The deletions proposed below are in addition to the deletions proposed in the June 20, 2019 submittal. Current TS Basis for Chanqe TS 5.5.7 Ventilation Filter Testing TS 5.5.7 will be deleted. Program (VFTP) This program was established to implement required testing of Engineered Safety Feature (ESF) filter ventilation systems. Those ESF systems included the SBC3TSystem and the SFU System. Once the DAEC is permanently shut down and defueled, and 19 days of decay have elapsed, these systems are no longer required to mitigate the consequences of an FHA. The TS associated with the SBGT System and the SFU System, therefore, have been deleted. This obviates the need for a filter testing program for these systems. TS 5.5.9 Diesel Fuel Oil Testing TS 5.5.8 will be deleted. Program This program ensures acceptability of both new fuel oil and stored fuel oil. Once the DAEC is permanently shut down and defueled, and 19 days of decay have elapsed, the SBDGs are no longer required to mitigate the consequences of an FHA. The TS associated with the SBDGs and SBDG fuel, therefore, have been deleted. This obviates the need for a fuel oil testing program. TS 5.5.11 Safety Function TS 5.5.11 will be deleted. Determination Program (SFDP) This program ensures that any loss of safety function is detected and appropriate actions are taken. Once the DAEC is permanently shut down

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 24 of 32 and defueled, and 19 days of decay have elapsed, the only required TS LCO will be TS 3.7.8, "Spent Fuel Pool Level Indication." TS 3.7.8 is not included in the SFDP and all TS included in the SFDP are proposed for deletion after the DAEC is permanently shut down, defueled and 19 days of decay have elapsed. Therefore, this program is no longer necessary at DAEC. TS 5.5.13 Control Building Envelope TS 5.5.13 will be deleted. Habitability Program The Control Building Envelope (CBE) Hapitability Program ensures that the CBE habitability is maintained. Once the DAEC is permanently shut down and defueled, and 19 days of decay have elapsed, the CBE is no longer required to mitigate the consequences of an FHA. The TS associated with maintaining the CBE have been deleted. This obviates the need for a program to ensure CBE habitability is maintained. Changes proposed to 5.6 in the June 20, 2019 submittal, are unchanged by this supplement

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria The proposed changes, as supplemented, have been evaluated to determine whether applicable regulations and requirements continue to be met. NextEra Energy Duane Arnold, LLC (NEDA) has determined that the proposed changes, as supplemented, do not require any exemptions or relief from regulatory requirements. 4.1.1 , 10 CFR 50.82, Termination of License The portions of 10 CFR 50.82 providing the basis for this license amendment request (LAR) are: (a) For power reactor licensees-

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 25 of 32 (1) (i) When a licensee has detemiined to permanently cease operations the licensee shall, within 30 days, submit a written certification to the NRG, consistent with the requirements of

                          § 50.4(b)(8);                                                 .

(ii) Once fuel has been permanently removed from the reactor vessel, the licensee shall submit a written certification to the NRG that meets the requirements of§ 50.4(b)(9) and;_ (2) Upon docketing of the certifications for permanent cessation of operations and permanent removal of fuel from the reactor vessel, or when a final legally effective order to permanently cease operations has come into effect, the 10 CFR part 50 license no longer authorizes operation of the reactor or emplacement or retention of fuel into the reactor vessel. By letter dated January 18, 2019 (Accession No. ML19023A196), NEDA provided formal notification to the U.S. Nuclear Regulatory Commission (NRG) pursuant to 10 CFR 50.82(a)(1)(i) and 1_0 CFR 50 .4(o)(8) of the intention to permanently. cease power operations at the* DAEC in.the fourth quarter of 2020. After the certifications of permanent cessation of power operation and of permanent removal of fuel from the DAEC reactor vessel are docketed, in.accordance with 10 CFR 50.82(a)(1)(i) and (ii) respectively, and pursuant to 10 CFR 50.82(a)(2), the 10 CFR 50 license will no longer authorize reactor operation or emplacement or retention of fuel in the reactor vessel. As a result, DAEC will be authorized only to possess special nuclear m*aterial. 4.1.2 10 CFR 50.36 Technical Specifications In 10 CFR 50.36, the Commission esta~lished its regulatory* requirements related to the content of the TS. 10 CFR 50.36(c)(6) Decommissioning states:

                - This paragraph applies only to nuclear power reactor facilities that have submitted the certifications requi.red by § 50.82(a)(1) and to non-power reactor facilities which are not authorized to operate.

Technical specifications involving safety limits, limiting safety system settings, and limiting control system settings; limiting CO!"!ditions for operation; surveillance requirements; design features; and

administrative controls will be developed on a case-by-case basis.

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 26 of 32 After the certifications of permanent cessation of power operation and of permanent removal of fuel from the DAEC reactor vessel are docketed, in accordance with 10 CFR 50.82(a)(1 )(i) and (ii) respectively, and pursuant to 10 CFR 50.82(a)(2), the 10 CFR 50 license will no longer authorize reactor operation or emplacement or retention of fuel in the reactor vessel. As a result, DAEC will be authorized only to possess special nuclear material. After the* reactor. has been completely defueled following permanent shut down, an FHA over the reactor core is no longer a credible accident and an FHA over the SFP becomes the bounding accident. NEDA has performed a revised analysis for an FHA in the SFP. This analysis determined that, following a decay period of 19 days, Control Building emergency ventilation is not required to maintain FHA dose consequences for control room occupants below the acceptance criteria-of 10 CFR 50.67(b)(2)(iii). -Consequently, TS LCOs and SRs associated with CBEV and support equipment are proposed for deletion. This proposed amendment, as supplemented, modifies the remaining TS to correspond to the permanently shut down condition. 4.1.3 10 CFR 50.51, Continuation of License 10 CFR 50.51 (b) states: Each license for a facility that has permanently ceased operations, continues in effect beyond the expiration date to authorize ownership and possession of the production or utilization faciltty,* untiL the Commission notifies the licensee in writing that the license is terminated. During such period of continued effectiveness the licensee shall: - (1)'Take actions necessary to decommission and decontaminate the facility and continue to maintain the facility, including, where applicable, the storage, control and maintenance of the spent fuel, in a safe condition, and (2) Conduct activities in accordance with all other restrictions applicable to the facility in accordance with the NRC regulations and the provisions of the specific 10 CFR part 50 license for the facility. *

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 27 of 32 4.1.4 10 CFR 50.46, Acceptance Criteria for Emergency Core Coolfng Systems for Ught-Water Nuclear Reactors

                      - 10 CFR 50.46(a)(1)(i) states "This section does not apply to a nuclear power reactor facility for which the certifications required under §50.82(a)(1) have been submitted."

4.1.5 10 CFR.50.62, Requirements for Reduction of Risk from Anticipated Transients without Scram (ATWS) Events for Light-Water-Cooled Nuclear Power Plants 10 CFR 50.62(a) states "The requirements of this section apply to all commercial lightwater- cooled nuclear power plants, oth_er than nuclear power reactor facilities for which the certifications required und.er §50.82(a)(1) have been submitted." 4.2 Precedent The proposed changes, as supplemented, are largely consistent with the Post Defueled Technical* Specifications currently in effect for the permanently shut down and defueled Vermont Yankee Nuclear Power Station (ML15117A551 ), Crystal River Nuclear Plant, Unit 3 -(Accession No. ML152248286), San Onofre Nuclear Generating Station, Units 2 and 3 (ML15139A390), Kewaunee Power Stations (ML14237A045), and Fort Calhoun Station Unit 1 (ML 1801 OA087). 4.3*

No Significant Hazards Consideration NextEra Energy Duane Arnold, LLC (NEDA), pursuant to 50.90, requests an amendment to the Duane Arnold Energy Genter (DAEC) Technical Specrfications (TS). The proposed changes, as supplemented, will revise or

            *delete TS consistent with the permanent cessation of reactor operation, permanent defueling of the reacto_r, and consistent with the revised analysis for a FHA in the SFP. The TS requirements being changed would be applicable once it has been certified that all fuel has been permanently removed from the DAEC reactor in accordanqe with 10 CFR 50.82(a)(1 )(ii)

and a period of no less than 19 days has transpired since shutdown.

Once the final certification is submitted documenting the permanent

          , cessation of operations and permanent fuel removal, the 10 CFR 50 license
           . for DAEC no longer will authorize operation of the reactor or placement of fuel in the reactor vessel, in accordance with 10 CFR 50.82(a)(2).

Duane Arnold Energy Center Docket N9. 50-331 License Amendment Request . Enclosure to NG-19-0102 Page 28 of 32 NEDA has evaluated whether a significant hazards consideration is-involved with the proposed amendment(s) by focusfng on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed changes, as supplemented, would not take effect until DAEC has certified t6 the NRC that it has permanently ceased operation, - entered a permanently defueled condition, and a period of 19 days has transpired since shutdown. Because the 10 CFR Part 50 license for DAEC will no longer authorize operation of the reactor, or emplacement or retention of fuel into the reactor vessel with the certifications required by 10 CFR Part 50.82(a)(1) submitted, as specified in 10 CFR Part 50.82(a)(2), the occurrence of postulated accidents associated with

reactor operation is no longer credible. DAEC's accident analyses are contained in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR). In a. permanently defueled condition, the only credible UFSAR described accident that remains is the Fuel Handling Accident (FHA).

Other Chapter 15 accidents will no longer be applicable to a permanently defueled reactor. The UFSAR-described FHA analyses for DAEC shows that, provided the SFP water level requirement of TS LCO 3. 7 .8 is met, the dose consequences are .acceptable without relying on secondary containment or the Standby Gas Treatment System. Once the DAE_C has permanently shut down and defueled, the only credible FHA is a fuel drop in the SFP. NEDA performed an analysis of the SFP FHA. This analysis determined that, following a decay period of 19 days, Control Building emergency ventilation is not required to maintain FHA dose consequences for control room occupants below the acceptance criteria of 10 CFR 50.67(b )(2)(iii). Consequently, the TS requirements for the systems supporting the Control Building _emergency ventilation are proposed for deletion.

The probability of occurrence of previously evaluated- accidents is not increased, since safe storage and handling of fuel will be the only operations performed, and therefore, bounded by the existing analyses.

Additionally, the occurrence of postulated accidents associated with reactor operation will no longer be credible in the permanently defueled

Duane Arnold Energy Center Docket No. 50-331

License Amendment Request Enclosure to NG-19-0102 Page 29 of 32 condition. This significantly reduces the scope of applicable accidents.

The deletion of TS definitions and rules of usage and application requirements that will not be applicable in a defueled condition has no impact on facility SSCs or the methods of operation of such SSCs. The deletion of design features and safety limits not applicable to the. permanently shut down and defueled DAEC has no* impact on the remaining applicable OBA. The removal of LCOs or SRs that are related only to the operation of the nuclear* reactor or only to the prevention, diagnosis, or mitigation of reactor-related transients or accidents do not affect the applicable DBAs previously evaluated since these DBAs are no longer applicable in the permanently defueled condition. Therefore, the proposed change, as supplemented, does not involve a significant increase in the probability or consequences of an accident previously evaluated. *

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?*

Response: No The proposed changes, as supplemented, to delete or modify certain DAEC TS, and current licensing bases (CLB) have no impact on facility SSCs *affecting the safe storage of spent irradiated fuel, or on the methods of operation of such SSCs, or on the handlhg and storage of the spent irradiated fuel itself. The removal of TS that are related only to the operation of the nuclear reactor, or only to the prevention, diagnosis, or

mitigation of reactor related transients or accidents, cannot result in different or more adverse failure modes or accidents than previously evaluated because the reactor will be permanently shut down and:

defueled. The proposed modification or deletion of requirements of the DAEC TS, and CLB do not affect systems credited in the accident analysis for the

remaining credible OBA at DAEC. The proposed TS will continue to require proper control and monitoring of safety significant parameters and activities. The TS regarding SFP water level is retained to preserve the current requirements for safe storage of irradiated fuel. The proposed amendment, as supplemented, does not result in any new mechanisms that could initiate damage to the remaining relevant safety barriers for _

defueled plants (fuel cladding, spent fuel racks, SFP integrity, and S~P

Duane Arnold Energy Center Docket No. 50-331

License Amendment Request Enclosure to NG-19-0102 Page 30 of 32 water level). Since extended operation in a defueled condition and safe fuel handling will be the only operation allowed, and therefore bounded by

_.the existing analyses, such a condition does not create the possibility of a new or different kind of accident. Therefore, the proposed change, as supplemented, does not create the possibility of a new or different kind of accident f~om any previously

evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No The proposed changes, as supplemented, are to delete or modify certain TS and CLB once the DAEC facility has been permanently shut down and defueled and a period of no less than 19-days has transpired since shutdown. As specified in 10 CFR 50.82(a)(2), the 10 CFR 50 license for DAEC will no longer authorize operation of the reactor or emplacement or retention of fuel into the reactor vessel following submittal of the certifications required by 10 *cFR 50.82(a)(1). As a result, the occurrence of certain design ~asis* postulated accidents. are no longer considered credible when the reactor is permanently defueled. The only remaining credible UFSAR described accident is a FHA. Further, an FHA in the reactor core is no longer credible. An 'FHA in the SFP is the* only remaining credible accident. NEDA has performed a revised analysis for an FHA in the SFP. This analysis determined that, following a decay

period of 19 days, Cor:itrol Building emergency ventilation is not required to maintain FHA dose consequences for control room occupants below the acceptance criteria of 10 CFR 50.67(b)(2)(iii): Consequently, TS LCOs and SRs associated with CBEV and support equipment are proposed for deletion. The proposed changes, as supplemented, do not adversely affect the !nputs or assumptions of the revised FHA analysis.

The proposed changes, as supplemented, are limrted to those portions of the TS, and CLB that ar:e not related to the safe storage of irradiated fuel. The requirements proposed to be revised or deleted from the TS, and CLB are not credited in the existing accident analysis for the remaining postulated accident (i.e., FHA in the SFP); and, as such, do not contribute to the margin of safety associated with the accident analysis. Certain postulated DBAs involving the reactor are no longer possible because the

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 31 of 32 reactor will be permanently shut down and defueled and DAEC will no longer be authorized to operate the reactor.

Therefore, the proposed changes, as supplemented, have no impact to the margin of safety. -

Based on the above, NEDA concludes that the proposed change, as supplemented, presents no significant hazards consideration under the standards set forth _in 10 CFR 50.92, and, accordingly, a finding of "no significant hazards consideration" is justified. 4.4 Conclusions Based on the considerations* discussed above, (1) there is reasonable assurance that the health and safety of the public ~ill not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security_ or to the heaith and safety of the public.

5.0 ENVIRONMENTAL CONSIDERATION

S NEDA has evaluated the proposed amendment, as supplemented, for environmental considerations. The review has determined that t.he proposed amendment, as supplemented, would change a requirement with respect to installation or use of a facility component located within th_e restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment, as supplemented, does not involve (i) a

_significant hazards consideration, (ii) a significant ch~nge in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individuai or cumulative occupational radiation exposure.

Accordingly, the proposed amendment, as supplemented, meets the eligibility criterion for categorical exclusion set for in 10 CFR 51.22(c)(9). In addition, the proposed changes, as supplemented, involve changes to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the proposed amendment, as supplemented, meets)he eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). - Therefore, pursuant to 10 CFR 51.22(b ), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendm,ant, as supplemented. '

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request Enclosure to NG-19-0102 Page 32 of 32

6.0 REFERENCES

6.1 Letter from Dean Curtland, NextEra Energy Duane Arnold, LLC to U.S. Nuclear Regulatory Commission - "License Amendment Request (TSCR-183): Application to Revise Operating License and Technical Specifications for Permanently Defueled Condition," dated June 20, 2019, (ML19176A356). 6.2 Letter from Dean Curtland, NextEra Energy Duane Arnold, LLC to U.S. Nuclear Regulatory Commission - "License Amendment Request (TSCR-181): Application to Align Technical Specification Staffing and Administrative Requirements for Pennanently Defueled Condition," dated April 19, 2019, (ML19109A031). 6.3 Letter from D. Hood (U.S. Nuclear Regulatory Commission) to G. Van Middlesworth - "Jssuance of Amendment Regarding Secondary Containment Operability During Movement of Irradiated Fuel and Core Alterations," dated April 16, 2001, (ML011070147). LIST OF ATTACHMENTS - Proposed Technical Specification Changes (Mark-Up)* - Revised Technical Specification Pages (Clean, with Proposed Changes) - Proposed Technical Specification Bases Changes (Mark-Up)

Duane Arnold Energy Center Docket No. 50-331 License Amendment Request NG-19-0102 Enclosure, Attachment 1 Page 1 of 361 ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)

NEXTERA ENERGY DUANE ARNOLD, LLC CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE. DOCKET 50-331 DUANE ARNOLD ENERGY CENTER RENEWED FACILITY OPeR,'\Tl~JG LICENSE Renewed License No. DPR-49

1. The Nuclear Regulatory Commission (the Commission) having found that _.

A. The application for license filed by FPL Energy Duane Arnold, LLC, Central Iowa Power Cooperative and Com Belt Power Cooperative (the licensees) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), - Deleted and the Commission's rules and regulations set forth in 10 CFR ChaJ:E)r I and all required notifications to other agencies or bodies have been duly 1T1ade;

               .eeff!pletee iA eoAfoFl'Rity \\.#A G0AstA:Jeti0A P0FFF1it Ne. DPPR 7Q; tRe ap,-satioA, as 8fflOA808; tl:le pF0!1RSiOAS 0f.tl::i0 /\et; 8A8 ti:10 Fl:1106 aAe Fegulati0R8 ef tho GeFRFRieeioA; C. The facility will eperate

ormi with the application, as amended; the provisions of the Act; and the rules and regulations of the o be maintained D. There is reasonable assurance: (i) that the activities authorized by this rene~ed eperatiAg license can be conducted without endangering the health and safety of the public; and (ii) that su*ch actMties will be conducted in compliance with the rules and regulations of the Commission; E. NextEra Energy Duane Arnold, LLC is technically qualified and NextEra Energy Duane Arnold, LLC, Central Iowa Power Cooperative and Com Belt Power Cooperative .are financially qualified to engage in the activities authorized by this renewed eperat:iRg license -I in accordance with the rules and regulations of the Commission; F. The licensees have satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G. The issuance of this renewed eperatiRg license will not be inimical to the common - I defense and Sec\Jrity or to the health and safety of the public; H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of renewed Facility OporatiRg License No. DPR-49 is in accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirements of said Appendix D have been satisfied;

         .On April 16, 2009, the name "FPL Energy Duane Arnold, LLC" was changed to "NextEra Energy Duane Arnold, LLC.D
                                                      !Amendment                 .I       Renewed LlGSnse No. DPR-49
                                                                                                         ;:I!-

I'Deleted I. Tho rosoipt, possession, and use of sourso, by predust and sposial nuslear material as authoriicod by this renmvod operating lisonso will bo in assordanoo with tho Commission's regulations in 1O Cr"R Part d0 and 70, inoluding 1O CPR aootion ao.aa, 70.24 and 70.31. ,...p_e_nn-an_e_n_tl_y_d_e_fu_e_l_ed--,

2. Renewed Facility Oporating License No. DPR-49 is hereby issued to NextEra Energy Duane Arnold, LLC, Central Iowa Power Cooperative (CIPCO) and Com Belt Power Cooperative (Com Belt) to read as follows:

A This renewed oporatin§ license applies to the Duane Arnold Energy Center, a oiling water reactor and associated equipment (the facility), owned by NextEra Energy Duane Arnold, LLC, Central Iowa Power Cooperative and Com Belt Power Cooperative and operated by NextEra Energy Duane Arnold, LLC. The facility is located on NextEra Energy Duane Arnold, LLC's, Central Iowa Power Cooperative's and Com Belt Power Cooperative's site near Palo in Linn County, Iowa. This site consists of approximately 500 acres adjacent to the Cedar River and is described in the "Final Safety Analysis Report as supplemented and amended (Amendments 1 through 14) and the Environmental Report as supplemented and amended (Supplements 1 through 5). B Subject to the conditions and requirements incorporated herein, the Commission hereby licenses: as required for nuclear fuel storage (1) NextEra Energy D ne Arnold, LLC, pursuant to Section104b of the Act and 10 CFR Part 50, "Licensin of Production and Utilization Facilities," to possess,*-U:Se-and ~ oporato the facil" , and CIPCO and Corn Belt to possess the facility at the designated location in Linn County, Iowa, in accordance with the procedures and limitations set forth in this license; that was used (2) NextEra Energy Duane Arnold, LLC, pursuant to the Act and CFR Part 70, to rosoi\10, possess and use at any time special nuclear materia as reactor fuel, in accordance with the limitations for storage and amounts required for roaotor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended as of June 1992 and as supplemented by letters dated March 26, 1993, and November 17, 2000. or (3) NextEra Energy Duane Arnold, LLC, pursuant to the Act and 1O FR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct source and spooial nuoloar material as sealed neutron souroos for reaotor startup, ealed sources for roaotor mstrumontation and radiation monitoring equipment calibration, aR<e-a,s fission dotootors in amounts ao required; (4) NextEra Energy Duane Arnold, LLC, pursuant to the Act and 1O CF and 70, to receive, possess and use in amounts as required any b~ roduct, source or special nuclear material without restriction to chemical or physi I form, for sample analysis or instrument calibration or associated radioactive app atus components; ....-----. rithat were (5) NextEra Energy Duane Arnold, LLC, pursuant to the Act and CFR Parts 30 a~-l~ 70, to possess, but not to separate, such byproduct and sp 1al nuclear materials as I may bo produced by the operation of the facility. and to possess any byproduct, source and special nuclear material as sealed neutron sources previously used for reactor enewed License No. DPR-49 startup or reactor instrumentation; and fission detectors;

                                                                                  !Am_e_nd_m_e_n_t
                                                                                  ......              _     ___,~

C. This renewed opm:atin§ license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I; Part 20, Section 30.34 of Part 30, Section 40.41 of.Part 40, Sections 50'.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Mmernurn Po1Ner Level ~....D_e_le_t_e_d_ _ _ ___,

                                                                                                           .I
                 ~Jo~ra ~l.lOFQY Duane_ Amela, LLG is authorizes to operate tho Duane A'=nols Energy Cantor at stoasy state reaotor oore power lo*;ols not in oMooss of 1Q12 rnogawatts (thomiaQ.

(2) Technical Specifications Pennanently Defueled The Technical Specifications contained in Appendix A, as r *sed through / Amendment No. ~ . are hereby incorporated in the licens NextEra Energy Duane 11 Arnold, LLC- sh operate the facility in accordance with the echnical Specifications. maintain ' . Lioonso DPR _4Q, those SRs are not requires to bo porforrnos _until their neMt sshosulos porforrnanoo,*whioh is Eluo at tho one of tho first survoillanoo intoJVal that bog ins on tho Elate tho SuJVoillanso 'Nae last porforrnos prior to irnplernontation of Arnonsrnont ~Jo. 24~.

              * (b) Deletes.

(3) Fire Protection Program NextEra Energy Duane Arnold, LLC shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated August 5, 2011 (and supplements dated October 14, 2011, April 23, 2012, May 23, 2012, July 9, 2012, October 15, 2012, January 11, 2013, February 12, 201°3, March 6, 2013, May 1, 2013, May 29, 2013, two supplements dated July 2, 2013, and supplements dated August 5, 2013 and August 28, 2013) and as approved in the

              . safety evaluation report dated September 10, 2013. Except where NRC approval for changes or deviations is required by 10 CFR 50.48( c), and provided no other regulation, 'technical specification, .license condition or requirement would require prior. NRC approval, the licensee may make changes to the fire protectiof) program without prior approval of the Commission if those changes-satisfy the provisions set forth in 10 CFR 50.48(a) and 10 *CFR 50.48( c), the change does not require a change to a technical specification or a license condition, and the criteria listed below
             . are satisfied.

Renewed License No. DPR-49

                                                                                         *Amendment~.      f

Fire Alarm and Detection Systems (Section 3.8);
Automatic and Manual Water-Based Fire Suppression Systems (Section 3.9);
Gaseous Fire Suppression Systems (Section 3.10); and,
Passive Fire Protection Features (Section 3.11).

This License Condition does not apply to any demonstration of equivalency under Section 1.7 of NFPA 805.

2. Fire Protection Program Changes that Have No More than Minimal Risk Impact Prior NRC review ahd approval are not required for changes to the licensee's fire protection program that have been demonstrated to have no more than a minimal risk impact. The licensee may use its screening process as approved in the NRC safety evaluation report dated September 10, 2013 to determine that certain fire protection program changes meet the minimal criterion. The licensee shall ensure that fire protection defens_e-in-depth and safety margins are maintained when changes are made to the fire protection program.

Transition License Conditions (1) Before achieving full compliance with 10 CFR 50.48(c), as specified by (2) and (3) below, risk-informed changes to the licensee's fire protection program may not be made without prior NRC review and approval unless the change has been demonstrated to have no more than a minimal risk impact, as described in (2) above. * * (2) The licensee shall implement the modifications to its facility, as described in Enclosure 2, Attachment S, Table S-1, "Plant modifications Committed," of DAEC letter NG-13-0287, dated July 2, 2013, to complete the transition to full compliance with 10 CFR 50.48(c) by December 31, 2014. The licensee shall maintain appropriate compensatory measures in place until completion of these modifications. (3) The licensee shall implement the items listed in Enclosure 2, Attachment S, Table S-2, "Implementation Items," of DAEC letter NG-13-0287, dated July 2, 2013, by March 9, 2014. * (4) ~~::::a. o~ora\J lo l~a DwaRa Amal8 ieReF§y Geater fallawiR§ iRsHlllatioR of moelifioel safe ORels OR tho eight primar,, rooiro1:1latioR system iRlot liRoe 1.'lhioh are elosoriboel iR tho liooRsoo lotter elatoel d1:1ly 31, 1978, aRel e1:1pplom0Rteel by lotter elatoel DosoFRbor 8, 4Q.78.. * (5) Physical Protection NextEra Energy Duane Arnold, LLC shall fu.i'ly implement and maintain in effect all provisions of the Commission-approved physical security, training and qualificatio11, Renewed License 'No. DPR-49 Amendment~ +

                          !Deleted

2e,

                                                          ! _                      7_

(11) la tao YF~R '"pelemea\ a, ,.,;,,a, ""'" "80 ou,.uaal le 10 ci;:R !i4,21 (a), shall eo 1RooFJ30FOtoa 1Rto tho UP:a/\R Ro later thOA tho Ro~ sohoal:lloa l:lJ*lato roeiwroa ey 1 Q CP:R eQ 71 (o) followmg tho 1ssl:l0Roo of t/:tls roRowoa oporalmg h00Rso. URtll this l:lpaato 1s 90FRploto, tho hGGnsoo FRB'f Rot FRako shangos to tho mforrnatlon 1n tho s1:1pplornont i;:ollowing 1nsoFJ30FOtlon mto t/:to UFal'.R, tho Roos for prior CoFRFRiss10R approval of aRy ohaRgeo YAII eo govornoa ey 1Q CP:R !iQ.!iQ. (12) ~:=::e1~:R;:,F?=,==::;t~:1!~:~~*G!~~=~::=r===8 Amela eROFflY Co Ator," sates Movomeor 2Q1 Q, as s1:1pplom0Rtoa ey lotter from tho h00Rsoo to tho MRC ey sates ~JOYOFRBOF 23, 2Q1 Q, 88S6f1BOS GGrtalR progFOFRS to BO IFRplOFRORtOS ORS astlVff!OS to BO D==e=le=t=e=d=====} =I oomplotoa eoforo tho porioa of ol4'3Raoa ope ratio A a,. Mo~eFO eROFflY Q1:1aRO Amela, LLC shall 1FRplomoRt t/:toso ROW prograFRs BAS ORhaAGOFROAts to O'K1Stlng progrOFAs RO later thaR POBFUary 21, 2Q14. e- Mo)<<f;ra eAOFflY Q1:1ano Amela, LLC shall soFRploto tl=toso astl\titlos no later thaR Foeruary 21,

Tho hoonsoo shall notify tho NRG IA writing within 3Q says after ha\tlng aoooFRphshoa item (a) aeovo ORS 1Rol1:180 tho stab:ls of those astJ\tltlOS that haYO B88A OF romam to BO OOFRplotoa in F1:0FR (b) 090¥0 (J13)Tho hooRsoo shall 1FRploFR0Rt tho FR est resent staff approYOa YOFSIOR of tho Boiling Water Roaotor

                          ~teasels ans Internals Projost (191/\/WAP) Integrates S1:1F¥oillanoo Program (ISP) as t/:to mothoa to aoFRonstFOto oeFRplianso wfth tho roei1:11roFRonta of 1Q CP:R Part §Q, Apponai'K 1-1 Any ohangos to tho
  ~ID-e-le_t_e_d__         BV1J.R\llP ISP saps1:1lo wltharawal ashoa1:1lo FR1:1st eo a1:1eFR1ttoa for staff review ans appro¥OI Afly
  ....- - - - - - ' . ohangos to tho QV\/RVIP ISP 0afJS1:1lo witharawal sshoa1:1lo whioh affosts tho tiFRo ofwitharawal of any a1:1P.101llanso eai:is1:1los rn1:1at l:lo 1nsari:ioFOtoa into tho hoonsmg l:lasls, If any a1:1rve1llanG0 oai:ia1:1los are roFRovoa wlthol:lt tho 1Rtont to test thoFR, those oai:is1:1los FRl:lat eo stores 1n a FRannor wtiish FRaintains them In a eona1tion wh1oh 'NOl:lla al:lpport re insertion Into tho roaster pross1:1ro vessel if nosossary D. This license 1s effective as of the date of Issuance and shall 0*131ro at FR1an1ght P:oeFUary 21,
                      ~~                is effective until. the Commission notifies the licensee in writing that the license is terminated.

FOR THE NUCLEAR REGULATORY COMMISSION Original signed by Enc J. Leeds Enc J Leeds, Director Office of Nuclear Reactor Regulation Enclosures*

1. AppendlX A Technical Speaftcabons

2. AppendlX B Additional Condibons Date of Issuance* Deceml::ier 16, 2010 Renewed License No. DPR-49 J...-

Amendment~ 'I

APPENDIX B ADDITIONAL CONDITIONS OP~RATl~JG LICENSE NO. DPR-49 I NextEra Energy Duane Arnold, LLC (the term licensee In Appendix B refers to NextEra Energy Duane Arnold, LLC or prior license holders) shall comply with the following conditions on the schedule noted below: t Amendment Number Additional Conditions Implementation Date 223

NextEra Energy Duane Arnold, LLC is authorized to relocate certain requirements included in Appendix A to licens~ntrolled documents. This amendment is effective immediately and shall be implemented within 180 days of the date r Implementation of this amendment of this amendment. shall include the relocation of these requirements to the appropriate documents, as described in the licensee's application dated October 30, 1996, as supplemented and consolidated in its March 31, 1998, submittal. These relocations were evaluated in the NRC staffs Safety Evaluation enclosed with this amendment. 260 (1) At tho time of tho olosing of tho tFansfor This amendment is of the lioenso from Interstate Power and effective immediately 121; Light Company (IPL) to FPLE Duane Arnold*, IPL shall transfer.to FPL~ Duane and shall be implemented within 30 days of the date Arnold* IPL's dosommissioning funds assumulatod as of suoh time, with a aggregate minimuFR value of at least $18e of this amendment. t million, and FPLe Duane.Arnold* shall deposit euoh funds in*an external dosommissioning trust fund ostal31ishod. 13yFPLEDuaneArnold* for D/\~G. NextEra

established at the

                   !the . n                    e Arnold shall take all necess     time *of the closing steps to ensure          tRis external trust fund s

-!D_e_ce_m_b_e_r_2_3_,_2_0_0_5_L.me.iritained in accordance with*the requirements of the transfer of the 1 of~ order approving the license_ transfer,

license from NRC regulations, and consistent with the Interstate Power safety evaluation supporting the order. The and Light Company trust agreement shall be in a form acceptable (IPL) to FPL_E to tho NRC. Duane Arnold A On April 1e, 2009, tho name "FPL ~no'1')y Duane /\mold, LLG" was ohangod to "~Joxt~ra Eno'1')y Duane Arnold, LLG." . f.

Amendment No. 270

Amendment Number Additional Conditions Implementation Da~e 260 ~) DELETE6

260 (3) Nm<tEra ERorgy Dueno Arnold shall take RO aof:ioR to oauso f;PL Group Capital, OF its BUOOOSSOFS BRd aseigRs, to void, oaROOI, OF FRodify its $60 FRilliOR ,.;..D_E_L_ET_E__,_D_ _ _- ooRtiRgoRsy GOFRFRitFRoRt to ~Joxt~ra ~Rorgy ,___ _ _ _ _ ____, DuaRO Arnold, BG ropFOGORtod iR tho liboRse traRsfor applioatioR, OF OBUGO it to fail OF porforFR OF iFRpair its perfoffi!BROO URdOF tho OOFRFRitFRE>Rt, OF FOFROVO OF iRtorforo with ~JOxtEra EROFQY DuaRo Arnold's ability to draw upoR tho GOFRFRitrRoRt, v~hout tho prior wril;t(;IR OORGORt froFR the ~JRG. AR oxosuted oopy of tl:le Support AgrooFRORt shall be GUbFRittod to tho ~JRG RO later thaR :;m days after ooFRploiioR of tho liooRso traRsfor.. Aleo, ~Joxtera ~Rorgy DuaRo Arnold shall iRfoffil tho ~m.c iR WllBRg aRy tiFRO

                          ,that it drm\16 upoR tho $60 FRillioR ooFRFRitrRoRt.

Amendment }fo. 279

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions NOTE----- - - - - - - - - - - - - - - - - - - The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

                               -De fin itio n ACTIONS                        ACTIONS.shall be that part of a Specification that prescribes Required Actions to be taken under *

designated Conditions within specified Completion Times.

AVeR/\Ge PLA~J/\R Tho APLl-:IGR shall BO a1=1plioaBlo to a sposifis planar LINEAR PIEAT , height anel is eeiual to tho surn ~f #lo heat gonl?ration Ge~JeR/\TION ~'\TE rafo per unit length of fuel reel for all tho fuel reels in (APLl-=IGR) tho sposifioel Bunello at tho sposifioel height elfvieloel BY

                               -tho nurnBor of ftlol reels in tho fuol-Bunelle at tho height.

A Gl-=IA~J~Jel CALIBRATION shall BO tho aeljustrnont, as nooossary, of tho ohannol output sush that it rosponels *.vithin tho nosossary range anel asourasy to known values of tho pararnoter that tt:io channel rnonitors. Tho GPIA~JNeL GALIBR/\TIO~J shall enoornpass-all elovioos-in tho ohannol roeiuiroel for shannol OPeR/\BILITY anel the Gl-1/\~JNEL rUNGTIONAL TEST. GaliBration of instrilrn6nt ohannols- ..vith Rosistanso Tornporature Doteotor t (RTD) or thorrnooouple sensors rnay sonsist of an

                               -inplaso eiualitativo assossrnent of sensor Bohmfior anel
                               -normal oaliBration of tho rornaining aeljustaBlo elovioos in tho ohannel. The Gl-1/\~J~JEL G/\LIBR/\TION rnay BO porforrnoel BY rnoans of any series of soeiuontial, overlapping, or total ehannel stops.-              -

(continued) DAEC 1.1-1 Amendment ~Jo. 234

Definitions 1.1

1.1
Definitions (continued)

Gl-l/\~JNEL CHECK A GI-IA~JNEL CHECK shall BO tho qualitati¥o assossfflent, BY obsor.iation, ot' ohannol Behavior eturing Of3eration. This etoterrnination shall inolueto, 1.vhero J30ssible, 00ff1J3arisen of tAo .ehannel inetioation anet status to other inetioations or status etorivoet froffl i.R00f30R00Rt instruffleRt ohannols ffleasuring tho Baffle J3araffletor. CHANNEL FUNGTION/\L A GHA~J~JEL rU~JGTIONAL TeST shall be the

 +eST                             injeotion of a sifflulatoet or aotual signal into tho

ohannol as slose to the sensor as J3raotioaBlo to *1erify OPER/\BILITY of all etovioos in the ohannol requiroet 1-for shannel OPERABILITY. Tho GHA~JNEL 1 FUNGTIO~J/\L TEST fflay BO J3orforrnoet by ffleans of any so.Fies of sequential, ovorlaJ3J3in*g, OF total shannol -{"

StOJ3S. GORE ALTERATION GORE ALTERATION shall BC the fflO'JCfflCRt of any fuel; souroos, or roasti\*iey oontrel OOfflJ30Ronts, *

                                  *A,tithiR tt:ic*
                                              . reactor ,,accol with tAo ,,ooool head romo'lOd

anet fuel in tho 11ossel. Tho follov,ing exoeJ3tions are not sonsietoroet t.o be GORE ALT~RATIO~JS:

                                  &.-     Mo\'emont of souroo range fflonitors, local J3ower range monitors, interrnoetiato range fflORitore, traversing ins*oro f3FOBos, OF Bf3eoial ff10 11able etotestors (inolueting uneter.iossol FOJ3laooffleRt);

aff4

                                 -1:r. Control reef fflOVOfflORt, J3revietoet there are no fuel assofflblios in tho assooiateet*oore sell.

SusJ3onsion* of GORE ALTERATIO~JS shall not

                                  ~ro*slueto oomJ3lotion of fflovofflont of a somJ3onont to a
                              . safe f30~ition.
                                                                                   . I (continued)

DAEC 1.1-2 Amendment No. 234

Definitions 1.1 1.1 Definitions (continued) GORe OPeR/>.TING LIMITS The GOU~ is tho 1:1nit spasms dos1:1ment that provides REPORT (GOU~) syole speoifis parameter limits for the s1:1rront reload oyolo. These syslo spooifis limits shall be determined for eash reload oyolo in aooordanoo with Spooif:ioation 6.e.6. Plant operation within those limits is addressed in indwid1:1al Spooif:ioations. _ - DOSE EQUI\LALeNT I 131 shall be that oonoontration of DOSE EQUIVl\LE~Jrl 1-31 I 131 (misros1:1Fios/ml), that alone wo1:1ld prod1:1so tho same dose as tho q1:1antity and isotopis mi*1:1:1ro of I 131, I 132, I 133, I 134, -and I 136 aot1:1ally present. Tho dose oonversion fastors 1:1sod for this oalo1:1lation shall be those listed in Federal G1:1idanoo Report (FGR) 11, "Limiting \lal1:1os of Radion1:1slido Intake and Air Gonsontration and Dose Conversion Fastors for Inhalation, S1:1bmorsion, and Ingestion," 1Q8Q and i;GR 12, "~omal expos1:1ro to Radion1:1slidos in Air, \'\later, and Soil," 1QQ3. DR/\l~J TIMe Tho DRl\l~J TIME is tho time it wo1:1ld take for tho water invontol)' in and above tho Roaster Pross1:1ro Vassal (RPV) to drain to the Roaster Vessel \1\/ater Laval Safety Limit of T.S. 2.1.1.3 ass1:1ming: a) Tho *1,,1ator invontol)' above tho T.S. 2.1.1.~ Safety Limit is divided by the limiting drain rate; (sont'd)_ (continued) DAEC 1.1-3 Amendment~

Definitions 1.1 1.1 Definitions (continued) DR/\IN TIM~ (eent'd) 13) Tho lin,iting dr=ain mte is the larger of tho -dr=ain rate thro1:1gh a single penotmtion flov.* path 1.vith the highest flow mte, or tho s1:1n, of tho drain rates thro1:1gh n11:1ltiple penotr=ation flmv paths s1:1sseptielo to _a GOR1n1on n,ode fail1:1Fo (e.g., soisn,is 0 1,ont, loss of norn,al *power, single h1:1n,a_n error), for all penetration flow paths eolow tho T.S. 2.1.1.a Safety Lin,it mmopt:

1. Penetration flow paths sonnostod to an intaot olosod syston,, or isolated ey n,an1:1al or a1:1ton1atis *,al-vos tl:iat are loskod, sealed, or othmwiso so*o1:1rod in tho olosod position, elank fiaRgos, or other do,,iaec that pro\*ont Jlo'.\' of roaster soolant tl:iro1:1gh tho penetration flow

paths;

2. Ponotr=ation flow paths oapaelo of eeing isolated ey val-ves that will oloso a1:1ton1atisally witho1:1t offsito power prior to the RPV water level eoing

OEfl:lal to tho T.S. 2.1.1.a aafety Lin,it when ast1:1atod ey RPV water level isolation instF1:1n1ontation; or

a. Ponotr=ation flow paths with isolation dovioos that oan eo olosod prior to tho RPV water level eeing oei1:1al to thQ T.e. 2.1.1.a Safety Lin,it ey a dodieatod operator tr=ainod in *the task, who is in GOntin1:101:1e oon,n,1:1nioation 1Nith tho oo-ntrol roan,, is stationed at tho oontrols, and is sapaelo of elosing tho penetration flow path isolation do,,iao i.*1itho1:1t offsito pov,er. -

o) Ttfo ponotr=ation flow paths reei1:1ired to eo oval1:1atod par par=agraph 13) are ass1:1n1od to open instantaneo1:1sly and are _not s1:1el§jeEf1:1ently isolated, and no water is ass1:1n1od to ee s1:1esoei1:1ontly added to tho RP\t \\*ator in\1ontol)*; - d) ~Jo additional dr=aining events 0001:JF; and - - o) Roalistio sross sostional :areas and dr=ain r=atos are

                                -HSe4, A eo1:1nding DRAIN TIME. n,ay ea 1:1sed in lio1:1 of a oalo1:1latod val1:10.

(continued) DAEC 1.1-4 Amendment~

Definitions 1.1 1.1 Definitions (continued) E~JD 01= CYCLE The eOG RPT SYSTeM ReSPO~JSe TIMe shall be that ReGIRGUU\TION PUMP time intoP1al from initial signal generation by the TRIP (EOG RPT) SYSTEM assosiated rurbine sto13 valYo limit switsh or from when ReSPO~JSE TIME the turbine sontrol val 110 hydraulis oil oontrol oil 13ressure dro13s below tho 13rossuro switoh sot13oint to aotuation of tho breaker sooondary (auxiliary) oontaot. The res13onso time may be measured by means of any series of sequential, ovorla1313ing, or total sto13s so that tho entire ros13onso time is measured. _ INSeRVIGe TeSTING Tho l~JSeRVIGE TESTING PROGR/\M is the lioonsoo 13rogram Umt fulfills tho requirements of 10 G~R 60.56a(f). (continued) DAEC 1.1-5 Amendment W§

Definitions 1.1 1.1 Definitions (continued) Le/\KAGE st:iall be: a-: Identified L~KAGE

1. L~KAGE into tile drywall, eust:i as that from pump seals or valve pasking, that is sapturod and oondustod to a sump or sollosting tank; or

2. LE-AKAGE into tho dF)0.voll aBT1ospl=ioFo from

souroos tt:iat are bott:i speeifioaUy looated and kno 1Nn not to interfere witt:i the operation of leakage dotostion systems;

                              &:    Unidontif:iod LE,A,KAGE All LE-/\K/\GEinto tho dF)!\'.'OII that is not idqntifiod lE,A,KAGE;.                          *
                              &:    Total LEAKAGE Sum oft.ho idonti:fiod and 1:1nido1;1tifiod Le/\KAGE LOGIC SYSTEM*               A LOGIC SYSTEM i;'.UNCTIO~J/\L TEST shall be a test FUNCTIONAL TEST             of all logia so*mpononts roeiuirod for OPER/\BIUTY of a logis sirouit, from _as oloso to tho son'sor as praotioablo up to, but not inoluding, tho aotuatod dovioo, fo verify OPERABILITY. Tho .LOGIC SYSTEM i;u~JCTIO~JAL TEST may be performed by moans of any series of soeiuontial, 0 11orlapping, or total system steps so that t.he o*ntiro logia system is tested.

MINIMUM CRITICAL Tt:io MCPR shall be tho smallest oritioal power .. PO\OJ~R-RATIO (MCPR) ratio (CPR) that o>Eists in tho ooro for oaoh olass of fuel. Tho CPR is that power in tho assembly that is oaloulatod by applisation of tile appropriate oorrolation(s) to oause soma point in tt-lo assembly to e>Eperienoo transition boiling, di11idod by tho aotual assembly operating power. Transition boiling moans tho boiling .regime

between nuoleate and t:ilm boiling. Transition boiling is t.ho regime in whioh both nuoleate and (continued)

DAEC 1.1-6 Amendment~

Definitions 1.1 1.1 Definitions (continued) MINIMUM CRITICAL filRl boiling oss1:1r intoFRlittontly 1Nith neither typo being POWER RATIO (MCPR) 00R1plotoly stable. MODE A MODE shall oorrospond to any one insl1:1sP10 soR1bination of R1odo switsh p_osition, average roaotor ooolant toR1porat1:1ro, and roaotor vessel hoael slos1:1ro _ bolt ten~ioning spooifioel in Table 1.1 1 vfitl-1 ruol in tho roaster vessel. OPERABLE OPERABILITY A systoRl, s1:1bsystoA1, elPJision, soA1ponent, or elevioo

                              -shall be OPERABLE or have OPERABILITY when it is sapablo of performing its spooifioel safofy fl:Jnstion(s) anel v,hon all nosossary attenaant instruA1entation, oontrols, noFRlal or eA1ergonoy eleotrioal power, sealing anel seal 'Nater, l1:1brisation, anel other a1:1xiliary oq1:1ipA1ent tf:lat are roq1:1ireel for tho systoA1, S1:Jbsyst0A1, elPJiSion, OORlpOnont, OF elovioo to porfoFRl its spooifioel safofy fl:Jn9tion(s) are also sapablo of performing their rolatoel s1:1pport runotion(s).

PRESSURE A~JD Tho PTLR is tho 1:1nit sposifio elos1:1A1ont that provieles TEMPERATURE LIMITS tho Foaotor vessel pross1:1ro anel toA1porat1:1ro 1iA1its, REPORT (PT!,.R) inol1:1eling hoat1:1p anel ooolelown rates, for tho _s1:1rront roaster vessel fl1:1onso porioel. Those pross1:1ro anel _ toA1porat1:1ro 1iA1its shall be elotoFR1inoel for oaoh f11:1onso porioel in assordanoo with Sposifisation 6.e.7. RP.TED Tl=4ERMAL RTP shall BO a total roamer aero heat transfer rate to PO\"/ER (RTP) tho roaster soolant of 1Q12 MJ.'\<t. RE+\CTOR Tho RPS.RESPONSE TIME shall BO that tiA10 i1;1ten.<al PROTECTION SYSTEM froRl i..*,hon tt:io A1onito_roel paraA1otor oxsooels _its RPS (RPS) RESPO~JSE trip sotpoint at tho ohannol sensor 1:1ntil elo

+JMe                          onorg~ation of t~o soraA1* pilot valve solonoiels. Tho response tiA10 A1ay be A1oas1:1roel by A1oans of any series of seq1:1ential, overlapping, or total stops so that_

tho entire response tiA10 is A1oas1:1roel. (continued) DAEC 1.1-7 Amendm'ent -3Qe

Definitions 1.1 1.1 Definitions (continued) al-lUTOO'NN MARGI~~ SOM shall BO tho ammJRt of roaotivity BY *Nhioh tho (SOM) roaotor is suBsritisal or 1Nould Bo suBsritisal throughout tho oporatiRg oyolo assumiRg that:

                            &.-  The roaster is xoRoR free;
                            -Ir. The moderator temperature is~ e8°F (20°G),

oorrespoRdiRg to tho most roastivo state; aRd

                            &.   /\II soRtrol rods are fully iRsortod exoept for the siRglo soRtrol rod of highest roaotivity worth, whioh is assumed to Bo fulPf 1,.vithdra'lm*with tho oore iR its most reasbvo sb;ito duriRg tho oporatiRg syslo. 'Nith ooRtrol rods Rot oapaBle of BeiRg fully iRsortod, tho roaotivity \*torth of these ooRtrol rods must Bo aooouRted for iR tho dotermiRatioR of
                                 ~                                '

(continued) DAEC 1.1-8 Amendment~

Definitions 1.1 1.1 Definitions (continued) H=IER~.,'\L POVV-ER _ TI-IERMAL POVI/ER shall be tho total FOastor sore heat traRsfor i:ato to tho roaster soolaRt. TURBl~JE BYP/\SS SYSTEM The TURBl~JE BYPASS SYSTEM RESPO~H,E TIME RESPONSE TIME ooRsistc of two GOFRpORORts: a:- Tho tiFRe froFR iRitial FR0\1eFReRt of tho FRaiR turbiRO stop valve or ooRtrol valvo uRtil 80% of the turbiRo bypass sapasiey is established; aRd

                              ~     Tho tiFRO froFR iRitial FR0 1/0FRORt of tho FRaiR turbiRe stop \1alve or ooRtrol val¥e URtil iRitial FRoveFRoRt of tho turbiRo bypass valve.

Tho rospORSO tiFRO FRay be FROaSUFOd by FROaRS of aRy series of so~uoRtial, ovorlappiR§, or total stops so that tho ORtiFO rospORSO tiFRO is FROasurod. (ooRtiRued) DAEC 1.1-9 Amendment ,30,e

Definitions 1.1 Table 1.11 (J:lage 1 of 1)

                                           - MOD~S ReAbTQR MQDe                     /\-VERAGe SV>llTbl=-4                RE:l',bTQR MQDE              TITLe
                                                .POSITIO~J                   bQQL/\~JT TEMPe~.TblR~ (0 J;:)

4 Po1Ner QJ:}eration ~ -NA

    ~        StartuJ:l                       Rd1:m1<et or StartuJ3/l=-4ot        -NA Stanaby
    ~        -M&t 81'11:1tae't'*'flfet       SRuteown                            ~~

4 ~ 81'11:1taowfl(a, SRutdm\'n ~~ e Reft:lelifl~ee, 8Rut~o 1l1n or Refuel -NA W All reactor 11essel Road slosure bolts fuUy tensioned. tat Qne or more reaotor 11essel Read closure bolts less tRan fuUy tensioned. DAEC 1.1-10 Amendment~

Logioal GoRReotoFB

~.

1.d USE AND APPLICATION 1.2 Logioal Gonneotors ~DELETED PURPOSE Tho purpose of this ooetion is to e*J)lain tho moaning of logieal OORnootoFS. Logioal eoRnootoFS aFO 1:1se0 iR TeehRieal SpeeifiootioRs (TS) to 0isoFimiRate eetv.men, aR0 yet ooRReet, 0isorete Gon0itions, Roq1:1iF00 AetioRs, GomplotioR Timoe, SurvoillaRoos, an0 FFOq1:10Reioe . .The only logioal oonAeotors tt-iat appear in TS are 6M_Q aR0 QB... Tho physi_eal arraRgomoRt of those OORROOtors 00Rstit1:1tes logioal sonvontioRe with epooifio moaniRge. BACKGROUND Several levels of logia may eo 1:1000 to state RoquiFOd Aotions. These levels aFO iaentified ey the plaooment (or RestiRg) of tho logieal -OORROOtOFS ana BY tho Rl:lmBOF assignee to oaeh Roq1:1ired

                  ,i\stioR. Tho first level of logio is iaeRHfied ey the fiFBt aigit of tho a

R1:1meer' assigRed to Roq1;1iFOd AotioR ana tt-lo plaoomoRt of tt-lo logioal so ARoster iR tt-io first level of nostiRg (i.e., loft justified .....ith the R1:1meor of the Req1:1ired AetioR). The suooessive levels of logia ai=O idoRtifiod ey aaditioRal digits of tt:lo Required Aotion n1:1meer.a_Rd ey s1:1ooossive iRdORtiORS of the logieal OORROotOF8.

                  'A.LheR logisal soRRootors are 1:1sod to state a GoRaition, GompletioR Time, SuNeillaRoe, or FrequeRoy, only the first 101101 of logia is 1:1sed, aRd tho logioal ooRRootor is loft justified with tho statemeRt of tho GoRditioR, GompletioR Time, S1:1NeillaRoe, or rFOql:IORoy.                         . .

'EXAMPLES Tho followiRg eMamples ill1:1strate tho use of logioal eoRReotors. (OORt.iRU08) DAEC 1.2-1 Amendment~

I

 -*1 1

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times. PURPOSE The purpose of this section is fo establish the Completion Time

                          . convention and to provide guidance for its use.

safely maintaining facility

                                                                                  ---------r-------'

um

BACKGROUND Limiting Conditi s for Operation (LCOs) specify mi requirements fo eRe1:1riR§ safe 013er=atioR of the ,l:J,A,ff. he

                         , ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times(s).

DESCRIPTION The Completion Time is the amounf of time allowed for" completing a Required*Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not .--fa_c_il_i- - - - - - - . within limits that re u* e e terin an ACTIONS Condition unless '----'----------' otherwise specified, providing th

is in a MODE or specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until, the Condition no longer exists or

......_---'________.* th~t:fflit is not within the LCO Applicability. !!_acility r-" If sit1:1ati0Rs are. disoovorod tl=lat req1:1iro oRtl)' iRto FRore thaR ORO GoRditioR at a tiFRo withiR a s.iR§lo LGO (FR1:1ltiplo GoRditioRs), tl=lo Roq1:1ired ,i\otioRe for oaol=I GoRditioR FR1:1st be porfoFA1oe( 1.vitl=liR tl=lo assooiatod GoFRplotioR TiFRe. VV-tloR iR FR1:1ltiplo GoRditioRs, separate GOR'.IJ:llotioR TiFRes are traokod for oaol=I GoRditioR startiR§ froFR tl=le tiFRe of disoo1Jery of tl=lo sit1:1atioR tl=lat req1:1ired ORtl)' iRto tl=le GoRditioR. . . 0Roe a GoRditioR l=las booR eRtered, s1:1bsoq1:10!1t di1Jisi0Rs, s1:1bsystoFRG, OOFRJ:IORORtG, OF variables. e>EJ:IFOGGOd iR tl=lo GoRditioR, dieoo1,ored to be iRopor=ablo or Rot witl=liR liFRito, will flfil res1:1lt iR sopar=ato oRtl)' iRto tl=le GoRditioR 1:1Rloss speoifioally stated. Tl=lo Required ,i\otioRs ef tl=lo GoRditioR 00RtiR1:10 to a1313ly to oaol=I additioRal fai11:1re,.witl=I GoFR13lotioR TiFRos based OR iRitial ORtry iRto tl=le GoRditioR. (ooRtiRl:IOdj DAEC 1.3-1 Amendment~

Completion Times 1.3 1.3 Completion Times DESCRIPTION Hm.*1e'ler, when a subsequent di\*ision, subsystorn, oornponont, (oontinued) OF '1Briablo O*J)rossod in tho Condition io diSOO'IOFOd.to be inoperable or not within lirnits, tho Cornpletion Tirne(s) rnay be o>E-tended; To app~ this Cornpletion Tirne e>E-tension, P#O criteria rnust f.irst be rnet. The subsequent inoporability:

                  &.-     Muot exist sonourront with the R!fil inoperability; 6fte .
                  -Ir. Must rernain inoperable or not 1Nithin lirnits after Yle f.irst inoperability is resol 1ted.

Tho total Cornplotion Tirno allov.*od for oornploting a Required Aotion to address the subsequent ineperability shall be lirni:tod to tho rnore rostrioti¥o of either: *

                  &.-   * =R:te stated Cornplotion Tirno, as rnoasured frorn the ini:tial entry into thci Condi:tion, plus an addi:tional 24 hours; or
                  -Ir. The stated Cornpletion Tirno as rneasured frern disoovery of.

the subsequent inoporability.' ' ' Tho abo 110 Cornpletion _Tirne e>E-tensions do not apply to those Speoif.ioations that ha1,o exoeptions that allow oornpletely separate re entry into the Qondi:tion (for oaoh di'lioion, suboystorn, oornponont or variable expressed in the Condi:tion) and separate trasking of Cornplotion Tirnos based on this re entry. Those exceptions are stated in indi'lidual *spooif.ioations. Tho al;)o'lo Cornplotiofl Tirne e>E-tonsion does not aj3ply to a Cornplotion Tirno with a rnodifiod tirno :i!Oro." This rnodifiod tirno

i!ero" rnay be expressed as a repetitive tirno (i.e., "onoo par 8 hours," 1where the Cornplbtion Time is FOforenoed frorn a previous oornpletion of th(!! Required Aotion versus the tirne of Condition entry) or as a tirno rnodifiod*by tho phrase "frorn dissever:,* ... "

e>Earnple 1.a a illustrates one use of this typo of Cornplotion Tirno. The 10 day Cornplotion Tirno sposified for Condition A and B in Exarnple 1.a a rnay not ee e>E-tended. * (oontinued) DAEC . 1.3-2 Amendment~

Completion Times 1.3 1.3 Completion Times (continued) 8(/\MPLEe TRe follm.viAg mmmplos illustrate the use 9.f Gomplot-ioA Times with difforeAt types of GoAdit-ioAS OAd ORaAgiAg GoAdit-ioAS. EXt\MPLE 1.a 1

                ,t\GTIO~Je GONDITIO~J         REQUIRED AGTIO~J        GOMPLETIO~J TIME B. RoEJuirod            B.1* Be iA MODE a.       12 ROUFS AstiOA OAd assooiated GomplotioA Time Aotmot.       B.2 Be iA MODE 4.        ae ROUFS GoAditioA B Ras-two ReEJUiFed AotioAs. EaoR RoEJuirod AotioA Rae its owA soparatb GomplotioA Time. EaoR GomplotioA Time is roferoAood to tRo time tRat GoAditioA B is eAtered.

TRo RoEJuirod AstioAo of GoAditioA B are to be iA MODE a witRiA 12 Rours Afill iA MODE 4 witR.iA ae ROUFS. A total of 12 RO~FS is allo 1Ned for reaoRiAg MODE a aAd a total of as Rouro (Rot 48 ROUFS) is allowed for reasRiAg MODE 4 from tRo time tRat GoAdit-ioA 8 was eAtorod. If MODE a is roasRed witRiA S ROUFS, tho time allowed for roasRiAg MODE 4 is tRe Ae'K4 ao ROUFS beoauso tRe total time allowed for i=eaoRiAg MODE 4 io ae Rouro.

If GoAditioA 8 is oAtorod wRilo iA MODE a, tRo time allowed for roaoRiAg MODE 4 io tRo Ao'K4 as Rours. (ooAtiAUOd) DAEC 1.3-3 Amendment~

Completion Times 1.3 1.3 Completion Times EXAMPLES EX1\MPLE 1.a 2 (ooAtiAues)

                   /\CTIOf.>JS CONE;>ITION               REQldl~EQ ,A,CTIQ~J           CQMPLETIO~J TIM~

A: 0Ae J3Umf3 iO,.~ RostoFe 13um13 to 7 says iAOJ3eFaele. - - Anco/\DI C

                                                                         ~ ~- *-

B. ReeiuiFes 8.1 Be iA MQQE a. 12 ReUFS

                          ,'\stieA aAS assosiates            ANQ Com13letieA Time Aot met.         B.2 Be iA MOQe 4.                ae RouFS
                   \t\LtleA a 13um13 is seolaFOs iA0130FBelo, CoAsitioA A ie eAtOFes. If tRe 13um13 is Aot mstorns to OPERABLE status witRiA 7 says, CoAsitioA B is also eAteros aAs tRe Com13letioA Time olool<s feF Roeiuirns AotioAs B.1 aAs 8.2 start. If tRe iA013emele 13um13 is mstOFes to OPERABLE status aftOF CoAsitioA B is eAteFes, CoAsitioAs A aAs B am exited, aAd tRerofem, tRe Reeiuirnd AotiOAS of CoAditioA 8 may ee toFmiAated.

VVheA a seo0Ad _13um13 is seolarnd iA013eFaele 'NRile tRe fiFSt 13um13 is still iA013er=able, CoAditioA /\ is AOt FO eAtOFed feF tRe seoeAd 13um13. LCQ a.a.a is eAtmed, siAse tRe ACTIQNS do Aot inolude a Condition feF mom tRaA one ino13emble 13um13. TRe Com13letion Time slosk foF ConditioA A does not sto13 aftm LCQ a.a.a is entmec;i, but sontiAuos to be tFaoked fFom tRe time Condition /\ was initially entmed. VVRile iA LCQ a.a.a, if one of the ino13eFBble 13um13s is rnstoFed to OPERABLE status and tRe Com13letion Time foF Condition A Ras not ex13imd, LCQ a.a.a may ea exited and 013eFBtioA qontinued in aosor:danoo 1NitR CoAsition A (oontinues) DAEC 1.3-4 Amendment~

Completi9n Times

                                                                                            . 1.3 1 .3 Completion Times eX/\MPLES           EJ(/\MPLE 1.a 2 (ooRtiRl:JOB)

VVflile iR LGO a.a.a, i:f ORO of tJ:lo iRopomblo p1:1mps is FOStOFOB to OPER/\BLE staH:Js aRB the GomplotioR Time foF GoRBitioR A l:las o*J)iFoB, LGO a.a.a may be mc.iteB .aRB ope.FatioR 00RtiR1:1eB .iR aoooFEiaRoe witt-1 GoRBitioR 8. Tl:le GompletioR Time foF GoRBitioR 8 is tmokeB fFom tJ:lo time tl:lo GORBitioR /\. GomplotioR Time mcpirnB. OR rnstoFiRg ORO of tl:le p1:1mps to OPERABLE stat1:1s, tl:lo GORBitioR /\. GomplotioR Time is Rot FOSOt, b1:1t OORtiRl:JOS fFom tl:lo time tl:le fiFst p1:1mp 1Nas BoolaFOB iRopOFablo. Tl:lis GomplotioR Time may be exteRBeB if tl:le pw'°'p mstoFCB to OPER'\BLE stat1:1s 1Nas tl:lo fiFSt iRopemble p1:1mp. /\ 24 l:101:1F exteRsioR to tA.e stateB 7 Bays is allowoB, pmviBoB tl:lis Boos Rot Fos1:1lt iR tt-io soc;,oRB p1:1mp beiRg iRopomblo foF 7 7 Bays. (GORtiRl:JOB) .DAEC 1.3-5 Amendmen_t ~

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.d d (ooRtiRued) ACTIONS GO~H;}ITIQN REQbHReg /1,GTIQN GQMPLETION TIME A: GRe A.1 RestoFe FURffiiOR X 7 days FUROtiOR X suesystem to sueeystem QPERABLE etaa1s. ANQ iROpOF0Ble. 1Q days fFom disoo11ept of failuFe to moot U1e LGQ

                    ~    Qfle            8.1 RosteFO P:uRffiieR ¥ 72 hOUFS FuRotioR ¥            suesystem to suesystem             OPER/\BLE statu~. ANQ iRopCFaele.

1Q days fFem diseo11ept ef failuFO ta meet U1e LGQ C. ORO G.1 ResteFO 72 heuFS FURffiiOR X FURffiiOR X suesystem suesystem ta iROpCFaBle. OPERABLE status. ANQ* AA GRe G.2 RestOFo 72 heuFS FuRstioR ¥ FURffiiOR ¥ suesystem sues;istem to iRopoFBelo OPER,1\BU:

                                              *status.

(GORtiRued) DAEC 1.3-:-6 Amendment~

Completion Times 1.3 1.3 Completion Times EX.1\MPL~S EX.<\MPLE 1.a a (oontimJOs)

                   'Nhon one F1:1notion X s1:1bsysten=1 ans one *F1:1notion Y e1:1bsysten=1 aFO inopoFable, Consition /\ ans Consition B are oono1:1rrontly applioablo. The Con=ipletion Tin=ioo for Consieon /\ ans Consition 8 are traokes separately for oaoR- e1:1bsyston=1, starting fron=i tRe tin=io oaoR s1:1bsyston=i 1Nae soolares inepeFable ans tRe Condition was entoros. /\ sepaFate Con=iplotion Tin=io is ostablisRos for Consition C ans traokos fren=i tRe tin=ie tAe seoond s1:1bsysten=1 was doslaros inoperable (i.e., tRo tin=io tRe sit1:1ation describes in Condition C was* sisoovered).

If Roql:liros /\otion C.2 is oon=iplot9s witRin tRe speoifiod Con=ipletioA Tin=ie, Consitions B end C are e>Eited. If U,o Con=ipletion* Tin=io for Req1:1iros /\otion/\1 Ras not e>Epired, operation n=iay oontin1:1e in aooordanoo witR Condition /\. TRe ron=iaining Con=ipletion Tin=io in Condition /\ is n=ioas1:1red fron=i tRo tin=ie tAe affootos sl:lbsysten=i 1Nas doolaros inoperable (i.e., initial onw; into Consition /\). TRo Con=ipletion Tin=io*e of Cor:tditions A BAS 8 afe n=iQdified by a logioal sonnostor, witR a separate 10 day Con=iplotion Time , n=ioas1:1rod fron=i. tt-ie tin=ie it ,..,as sieoo'leres tRe LCO was Rot n=iot. In tRis o>Ean=iple, 1NitR01:1t tRo eoJ:>arato Coi=nJ:)leeon Tin=ie, it wo1:1ls be J:>Ossible* to alternate between Conditions/\, 8, and C in s1:10R a n=iannor tRat OJ:>eration oo.1:1ls sontin1:1e insefinitely witR01:1t ever restoring eysten=is to n=ioot tAe LCO. TRe seJ3arato Con=1J3letion Tin=io n=iosified= by tRe J:)Rraso "fron=i discovery of fail1:1ro to n=ioot tRo t.CO" is sosigned to _J:)FC'lent_ indefinite oontin1:1ed OJ:>eft)tion \'tRilo not n=ieeting tRo LCO. TRis* Con=1J3letion Tin=io allows for an O>EOOJ:)BOn to tAe normal "tin=io 2ero" for beginning tRO Con=1J3lotion Tin=io "olook". In tRis instanso; tRe Con=1J3letion Tin=ie "tin=io zero" is SJ:)ooifios as oon=in=ienoing at tRe tin=ie tRe LCO was initially not

n=iet, ir,stoas of at tRo tin=ie tRe as-sosiatos Consition* was ente'rod.

(oontin1:1es) PAEC 1.3-7 Amendment~

Completion Times 1.3 1.3 Completion Times EX/\MPLES EXAMPLE 1.g 4 (OOAtiAl:led)

                    /\GTIO~Jg GQNglTIGN                  ~EQbll~eg iArGTIQ~j             GOMPLETIO~J TIME A:     0Ae or ffloro          A ,4 n-
                                                                         . - ,-, . _ AL..-,_

va!Yes GPER/\BLE. iAoporaelo. stat1:1s. B. Roet1:1irod B.1 Be iA MQgE d. 12 ROl:JFS

                           /\otioA aAel assooiatoel             ANQ GofflplotioA Tiffie Rot fflet.       B.2 Bo iA MQgE 4.                 d8 ROl:JFS A siAgle Gofflplotion Time is 1:1soel for a Ry Al:lff1Ber of valves iAoperaelo at tf:lo same t:ime. Tf:le Gom~letioA Time assooiateel witf:1 GoAelitioA /\ is eases OR the iAitial OAtry iAto GoAelitiOA A BAel .

is Rot traok.eel OR a per valve easie. goolariAg s1:1eseet1:1eAt val¥oe iAoporaelo, wf:lilo GoAelitioA A is still iA offoot, aooe Rot trigger tf:lo traok.iAg of separate GomplotioA Tifflos. GAoe oAe of tf:lo 1, 1alvos f:lae eeeA restoreel to OPERABLE otat1:1s, tf:lo CoRaitioA /\ GofflplotioA Time is Rot reset, 01:1t 00AtiA1:1oe froffl tf:le time tf:lo first 1, 1alve 111as eloolaroel iAoperaele,. Tf:lo GofflplotioA , Time may so e*1eAeleel if tf:lo .\1alvo rostoreel to GPER/\BLE stat1:1s

                   *.vas tf:lo first iAoperaele valve. Tf:le GoAaitioA /\ GompletioA Tiffie fflay BO o*1om:loa for l:lp to 4 ROl:JFS provieleel tf:lis eloos Rot ros1:1lt iA a Ry s1:1es0Ef 1:10At val¥o eeiAg iAoperaele for~ 4 ho1:1rs..

If tf:lo GomplotioA Time of 4 f:101:1rs (pl1:1e tf:lo o*1oAsioA) o><piros nf:lilo oAo or fflore valves are stifl iAoporaelo, GoAelitioA B is 1

eAtered. (ooAtiAl:JOd) DAEC 1.3-8 Amendment~

Completion Times 1.3 1.3 Completion Times eX1>...11APLES @</\MPLE 1.a § (eo_AtiAued) ACTIONS Separate CoAditioA OAR)' is allowed for eaoR iAoperaele valve. CONDITION

                        -A-:   0AO OF fflOFO vel1,os iAop9raele.

B. Reetuired B.1 B'o iA MOD~ a. 12 ROUF8

                             /\otioA aAd QE)OOGiatod          A~JD CoFApletioA TiFAe Aot fflet. B.2 Bo iA MOOE 4.       ae ROUFS TRo Noto aeovo tRe /\CTIO~JS Teele is a FAotRod of FAodifyiAg Row tRe CoFAplotioA TiFAo is tracked. If tRis FF10Ulod of FAodifyiAg Row tRe CoFApletioA TiFAo is traekod was applioaele oAly to a opooifio CoAditioR, tRe Note 1Nould appear in t:Aat Condition ratRor tRaR at tRo top of tRe /\CTIO~JS Teele.

TRe ~Joto allows CoRdition A to ee entered se~aratety for eaoR inoperable val'lo, and CoFAplotion Tiff!os _tn;lokod on a por.val'lo basis. VVReR a 11al11e is declared iRoporablo, CoRditioA A is eRtered aRd its CoFAplotion TiFAo starts. If subsoetuont val¥os are doolarod iRoporable, CoRditioR A is eAtered for eaot:l val*ve aAd oeparafo CoFAplotioR TiFAos start aRd are traoked for eaoR valve.

(oontinuod) DAEC 1.3-9 Amendment -2,2.3

Completion Times 1.3 1.3 Completion Times EX,'\MPLES eXAMPLE 1.a e (eontinued) If tRe Cofflpletion Tiffie associated witR a ,_.al*,10 in Condition A o><pires, Condition B is entered for tllat 1&'al*&'e.

If tRe Cor:Rplet-ion Tifflos aosooiatod witR *subsequent valves in Condition A e>Epiro, Condition B is entered separately for oasR valve and separate Cofflpletion Tiffles start and are traoked for eaoR val*t'o. If a val 1t'o tRat sausod ontiy into Condition B is rostered to OPER/\BLE status, Condition B is o><ited for tRat valve.
Sinoe tRo Noto in tRis oxafflplo allows fflultiple Condition ontiy and traoking of separate Cefflplotion Tiffles, Cofflpletion Tiffie extensions do not app~.

EXAMPLE 1.3 e ACTIO~JS CON91TION REQldlRe9 ,ti,CTION COMPLETIO~J TIME A: One 0Ran1;1el A.1 Porfofffl Oneo per 8 inoperable. SR a.><xx. flet:tfS GR.

                                           ,At.2 Reduse                  8 ROUFS
                                                 +~ERMAL PQl.OJER to ~ eG%

R+P-:- 8-: Required B.1 Be in M09E a. 12 ROUFS

                         ,o,otion and assesiatod Coffl.plotion
                         +iffle not fftet:-

(sontinuod) DAEC 1.3-10 Amendment~

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.a e (oontinued) Entry into Condition A offers a ot=ioioo botv.mon Roeiuired Aotion

                 /\.1 orA.2. Reei~ired Aotion /\.1 t=ias a "onoo per Completion Time, whish eiualmos for tt=ie 26% mrtenoion, per SR a.0.2, to oaoh performanoo a:f:l:or the initial performanso. Tho initial 8 hour interval of Required Aotion A.1 begins when Condition A is entered and tt=io initial porformanse of Required /\stion A.1 must

be oomplete within tt=ie first 8 hour interval. If Required /\stion A.1 is follov1od and tt=ie Required Aotion is not met within the Completion. Time (plus tAe e*1:enoion allowed ey SR a.0.2),

Condition B is entered. If Required Aotion /\.2 is followed and tt=io Completion Time of 8 hours is not met, Condition Bis entered. If a:f:l:or entry into Condition B, Required Aotion A.1 or /\.2 is mot, Condition B is o>Eitod and operation may tt=ion oontinuo in Condition A. (oontinued) DAEC 1.3-11 Amendment~

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.a 7 (oontinl:lea) AGTIO~JS GQNglTIO~J R[i;Qt!IR~g AGTIO~J GOMPLeTIO~J TIME A: Gfle A.1 VeFify affeffiea 1 ROl:IF Sl:lesysteFfl Bl:lesysteFfl inoporaele. isolatoa. ANQ Onoo per 8 f:lol:lrs tf:lereaftor ANQ

                                                     ",., n
                                                                  .L---
                                                                        - .L-  *- --- "7"> .__    -

to OPERABLE statl:ls.

8. ReEtl:lirea 8.1 Be in MQgE a. 12 ROl:IFS Affiion ana assooiatoa AN,Q Completion Tiffie not Fflot. 8.2 Be in MQgE 4. as f:lol:lre RoE11:1irea AotioA A.1 f:las t\vo GoFflplotion TiFfles. Tf:lo 1 f:101:1r GoFflpletion Tirno eegins at tf:le tiFflp ~f:lo Gonaition is ontoroa ana eaof:1 "Onoe per *8 t:lo1:1FS tf:loroafter interval eegins 1:1poR pertoFF1:Janoe of RoE11:1irea Aotion A.1 .

If after Gonaition A is enteroa, RoE11:1irea Astion-A.1 is not Fflot-

                   '.vitt:lin eitf:ler tt=io initial 1 f:101:1r or any s1:1esoql:lont 8 f:lol:lr interval froFfl tt:le previol:ls perforrnanoe (pll:ls tho o>ftonsion allowoa ey SR a.0.2), Gonaition B is enterea. Tf:lo Gornpletion Tirnq ol~ok for Gonaition A aoes not stop after Gonaition 8 is ontoroa, el:lt oontin1:1es frorn tf:le tirno Gonaition A was initially e*ntoroa. If .

_ReE11:1irod Affiion A.1 (continued) DAEC 1.3-12 Amendment~

Completion Times 1.3 1 .3 Completion Times EX,<\MPLES EXAMPbE 1.a 7 (ooiltiRl:led) is ffiet after GoRd.itioR 8 is eRtored, GoRditioR B is exited aRd oporatioR !flay 00RtiR1:1e iR aooordanoe witA GoRdition A, provided tAo Go1T1plesoR Tiffie for Reei1:1ired AotioR A.2 Aas not expired. IMMEDIATE When "Immediately" is used as a Completion Time, the Required COMPLETION Action should be pursued without delay and in a controlled TIME manner. DAEC 1.3-13 Amendment~

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements. DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR. Tl:io "spooif:iod i;F9ef1::10Rey" ie rnforrod tQ fr-lF01::1gl:i_o1::1t tl:iie eostioR

               - aRd eaol:i of tl:ie SpeoifioatioRs of SootioR a.a, SwvoillaRoo Req1::1iFOA1eRt (SR) /\pplioaBility. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modi_fy performance requirements.

S0A1etiA1es speoial sit1::1ati0Rs diotato wl:ioR tho mq1::1iFoA10Rts of a el::lF\'OillaROO aFO to BO AlOt. Tl:ioy BFO "otl:iePA'ise stated" ooRditioRs allowed BY SR a.0.1. Tl:ioy RlBY Be stated as olarifying v

                 ~Jatos iR tl:ie S1::1NeillaRoe, as part of tl:io SmveillaRoo, OF Botl:i.                  1 Sit1::1atiORS 1NAOFO B el::lFVOillBROO SOl::lld BO FOQl::liFOd (i.e., its i;rnq1::10Roy 901::1ld O*J)iFO),.Bl::lt WAOFO it is Rot poSGiBle nF Rot deeiFed tl:iafit Be perfufff!od l::IRHI BOAlOtiAlO aftoF tl:io assooiatod LGO is witl:iiR its_ Applieaeility, FepFeseRt potential SR a.0.4 oonfliots. To avoid ttiose ooRfliots., tl:io SR (i.e., fr-lo S1::1Noillanoo OF tl:io i;Foq1::1onoy) ie stated s1::1ol:i tl:iat it is ORiy "FOq1::1irnd" wl:ieR it oaR Be aRd sl:io1::1ld Bo poFfoFfflod. 'Nifr-1 an SRsatiefied, SR a.0.4 *
              - iAlposes RO FestFiotioR.

The use of "mer or "performed" in these instances conveys specific meanings. A Surveillance is "met' only when the acceptance criteria are satisfied. Known failure of the req~irements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance

{continued) DAEC -1.4-1 Amendment ,2,e8

Frequency 1.4, 1.4 Frequency DESCRIPTION criteria. Some Surveillanses sontain notes tl=iat mod~* (continued) the Frequonoy of 13orfom=ianoo *or tho oonditions during '.Vhioh the aooe13tanoe criteria must be satisfied. For these Surveillan<;>es, the MODE entry restriotions of SR a.0.4 may not

a1313ly. Suoh a SuFYeillaneo is not required to be 13orforFAed 13rior to entering a MOD~ or other s13eoified oondition in the A1313lioability of tho aeeosiatod LGO if any of tho-following throe oonditions are satisfied:

Tho _8urveillanoe is not required to be met in the MODE or other 013eoified oondition to be entered; or Tho SuFYeillanoe is required- to be met in the MODE or other 013ooified oondition to be entered, but has been 13erformed within tho s13osifiod F"requonsy (i.e., it is ourront) and is known not to be failed; or The SuFYoillanoo is required tQ be mot, but not 13orfom:1od, in the ~ODE or other e13ooifidd oondition to be entered, and is known not to be failed. E:><am131es 1.4 a, 1.4 ~. 1.4 e, and 1.4 ij disouseoe those s13eeial situations. (continued) DAEC 1.4-2 Amendment~

Frequency 1.4 1.4 Frequency (continued) manner In which illustrates EXAMPLE.S* The following examples illustr9te e various 1nays that Frequencies are specified. IA those mmFRplos, tl=1e Applioability of tho LGO (LGO Rot showR) is MODES 1, 2, aRd a. EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours - Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours) during which the associated Surveillance must be *performed at least one time. Performance of the Surveillance - initiates the subsequent interval. Although the F"requency is stated as 12 hours, an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this .interval continues at all times, even when the SR is not required to be met per SR

         .--fa-c-il-ity------,   3.0.1       such as when the e ui ment is inoperable, a variable is outside specified limits, or t i:ffiff is outside the Applicability of the
                               - LCO). If the interval specified qy SR 3.0.2 is exceed.ed while the ity___________, ~ ~ 1 - J ; *_ is in a MODE or otl=l~r specified condition in the Applicability of

.....fa_c_il__ the LCO, and the performance of the Surveillance is not otherwise a modified (refer to E>EaFRploe 1.4 aRd 1.4 4), then SR 3.0.3 becomes applicable. If fr.lo iRteF\1al as spooified by SR a.0.2 is oxaoodod wl=!ilc tl=!o uRit is Rot iR a MODE or other spooifioel eeRditioA iR tho 1~13lioaeilify of tl=!e LGO for v.ihioh 13erfommRs0 of fr.lo SR is required, tRoR SR a.0.4 boooFRes ai:iplioablo. Tho SurvoillaRoe FRuet be performed witl=liR tl=!o P:roqucRoy roquiroFR.oRts of SH a.0.2, as FRodifiod by SR a.a.a, prior to oRtF)' iRto tl=!e MODE or otl=!or epooified ooRditioR or

                              - tho LGO is ooRsidorod Rot FRot (iR aooordaRoo with SR a.0.1) aRd LGO a.0.4 boooFRes applioablo.                     *-            -

(ooRtiRUOd) DAEC 1.4-3 Amendment No. 2Qa

Frequency 1.4 1.4 Frequency B<AMPLES EXl\MPLE 1.4 2 (oontinuod) SURVEILU\~JGE REQUIREME~HS SURVEILU\~JGE FREQUENCY Verify f:low is within limits. Onso within 12 ROUFS eftef~~ H+P, 24 houFS tt:loFCafter E>Eamplo 1.4 2 t:ias t\vo FFCquenoies. Tt:le first is a one time porformanoe Frequenoy, and the sesond is of tt:ie type shown in

              &ample 1.4 1. Tt:io logioal oonneotor "8!'.ill" indioates that bott:i Frequensy requirements must be met. Eaoh time reaotor power is inoreased from a power level-<: 26% RTP to~ 26% RTP, tt:io 8uF\1oillanoo must be porfom::ied witt:lin 12 t:iours.

The use of "onso" indisatos a single porformanoo will satisfy tho speoified Frequonoy (assuming no ott:ior Froquonoies are sonnostod by "8NQ"). Tt:lis type of Frequenoy does not qualify for tt:io o>ftonsion allowed by SR d.0.2.

              Thereafter" indieatos future perforrnanoes must be establist:led per SR e.0.2, but only after a sposifiod sondition is first mot (i.e.,

tt:io "onoe" perfom::ianoo in tt:lis o>Eamplo). If reaotor power dooroasos to~ 20% RTP, tt:ie measurement of both intervals stops. ~Je*,N intervals start upon roaster power roast:iing 26%

(sontinuod) . DAEC 1.4-4 Amendment ~Jo. 268

Frequency 1.4 1.4 Frequency EXAMPLES EX/\MPLE 1A a (oontin1:1ed) SURV~ILLANGE REQUIREMENTS SURVEILLANCE l=REQUENCY

                                         ~JOTE Not r=eei1:1ired to be 13orfoFA1ed 1:1ntil 12 AOl:JFS after~ 26% RTP.

PorfoFFR oAannel aelj1:1stmont. 7 days* TAo inforval oontin1:1es wAotAor or not tho 1:1nit 013eration ie

              -<: 26%    RTP between 13erfoFA1anooe.

As tAo Note n=ioelifioe tAe roei1:1ired aerfoFA1enoo of tAo Sl:irveillenoo; it ie oonstrued to be 13art of tAo "s13eoified Freei1:1onoy." SA01:1ld the 7 day interval be e>toeedoel WAile 013eretioR is~ 26% RTP, tAis ~fote allows 12 AOl:JFG after 1301.Ner reaoAes ~ 2eq4, RTP to 13erfoFA1 tAo S1:1FVoillanoo. TAo S1:1rveilleRoo is still oonsieloroel to be 1NitAin tAe "s13ooifioel Froei1:1enoy." TAet=eforo, if tAe S1:1rveillef1oe wore n_ot 13erfoFA1oel witAin tt:io 7 elay interval (13l1:1s tAo o>ttonsion allov.mel ey SR a.0.2), b1:1t 013eretion 1Nee ~ 2eq4, RTP, it wo1:1lel not oonstit1:1te a fai11:1ro of tAe SR or fei11:JFe.to n=ieettAe LGO. Also, no violation of SR a.0.4 0001:1re wt:ien oAenging MODES, even* 1NitA tAe 7 elay Freei1:1onoy not n=iot, 13rovidoel 013oretion does*not o>tooed 12 AOl:JFS (13l1:1s tAO e>ttension allm.voel by SR a.0.2) witA.J30W0F ~ 26% RTP. .. t Onoe tAO 1:1nit FeBOAes 26% RTP, 1i AOl:JFS ..... 01:Jlel be allo 1Neel for oon=113leting tAo S1:1rvoillenoe. If tho S1:1FVoillan.oe *.,..ere not 13erfoFFRoel witAin tAis 12 AOl:JF intoFVal (13l1:1s tAe e>ttonsion _ J..,. allowoel by SR a.0.2) tAer=e wo1:1ld tAon be a fail1:1re to 13orfoFA1 a *1 S1:1FVeillanoe witAin tt:io s13eoifieel FfCei1:1enoy, and tAe 13rovisions of SR a.a.a WOl:Jlel a1313~. (oontin1:1eel) DAEC 1.4-5 Amendment~

Frequency 1.4 1.4 Frequency

~X/\MPLE8          EXAMPLE 1.4 4

. (oontin1:1eel) SURVEIL6'\NGE REQUIREMENTS SURVEIL6'\NG~ i;REQUENGY NOTE Only Feet~iFOel to be mot in MODE 1. Verify leakage Fates are t.YithiR limits. 24 AOl:IFS Eifam13lo 1.4 4 e13ooifieo tAat tAe Foei1:1iFOments of tAis S1:1FVeillanoe .elo not Aa 1,o to be mot 1:1ntil tAO 1:1nit io in MODE 1. TAo intoFVal moao1:1Fement foF tAe FFOet!-Jenoy of tAis S1:1FVeillanoe oontin1:1os at all times, as elesoFiboel in E.>Eam13lo 1.4 1. l-loweveF, tAe ~fote oonst-ia:itoo an "otAOFwioo etatoel" 0Moo13tion to tAo

                  /\1313lioability of tt:iis 81:JF\'eillanoe. TAeFef<>Fe, if tAe S1:1FVeillanoe woFb not 130Ffom:ieel witAin tAe 24 AOl:IF int0Pt1al (13l1:1s tfl_o oMtension alloweel by SR 2.0.2), b1:1t tflo 1:1nit was not in MODE 1, tAeFO wo1:1lel be no fail1:1Fo of tflo SR noF fail1:1FO to meet the LGO.

TAeFoforn, no violation of SR 2.0.4 0001:1FS wAen oAanging MODES, 0 1,on witA tho 24 AOl:IF F'FOei1:1onsy oMsooeloel, 13Fovieloel tAe MODE OAango was not maelo into MODE 1. PFioF to entering MODE 1 (ass1:1ming again tAat tAo 24 AOl:IF rFOei1:1onoy 1ileFO not mot), SR 2.0.4 wo1:1lel FOE11:JiFO satisfying tAe SR

                                                                                     . (oontin1:1oel)

DAEC 1.4-6 Amendmenr~

Frequency 1.4 1.4 Frequency EXAMPLES _eXAMPLE 1.4 6 (oontimied) SURVEILU\NGE REQUIREME~HS SURVEILU\~JGE l=REQUE~JGY NOTE Only i=eq1:1ired to be 13erfom=ted in MODE 1. t= Tho interval oontin1:1os, whether or not tfle 1:1nit 013eration is in MODE 1, 2 or d (tho ass1:1n:1ed /\1313lioabilit:y of tho assooiatod LGQ) between 13orforn:ianooe. As tho _Noto n:iodifios tho roq1:1irod porfom=tanoe of tho S1:1rveillanoe, the ~Joto is sonstr1:1od to be 13art of tl:ie "s13eeified Fi=etj1:1onsy." Sho1:1ld the 7 day' interval be o>Eooodod 'NRilo 013oratien is net in MODE 1, tflis ~Joto allows entry into and 013eratien in MO_DES 2 and d to 13orfom=t the S1:1rveillanee. Tl:io S1:1rveillanee is still oensidorod to be 13orfeFFAod \.Vitl:iin tl:io ,

              ~s13eeified l=i=eq1:1enoy" if oon:113leted 13rier to entering MODE 1.

Tl:iorofero, if tl:io S1:1rvoillaneo 'Nore not 13erfem=ted witl:iin tl:ie 7 day (13l1:1s the o>Etonsien allev.md by SR d.0.2)-intorval, b1:1t 013oratien 1Nas not in MODE* 1, it we1:1ld net eenstit1:1te a fail1:1re of tl:ie SR or fail1:1re to rneot tl:io LGO. /\Isa, no 11iolation of SR d.0.4 0001:1rs wt:ion ol:ia~ging _MODES, oven witl:i tl:io 7 day l=req1:1onoy not n:iot, 13rovided 013eratiori does not res1:1lt in entry into MODE 1. Onee the 1:1nit reaol:ies MODE 1, tl:io roq1:1iron:1ont fer tl:io S1:1rvoillanee to be 13ertorn:ied within its s13osifiod l=i=eq1:1enoy a1313lioe and wo1:1ld roq1:1iro tl:iat tl:io S1:1rvqillanoe l:iad been 13erforn:ied. If the S1:1rveillanee wei=e not 13er:fom=tod 13rior fo entering MODE 1, tl:iero wo1:1ld ti:io-n be a fail1:1ro to 13erforn:i a S1:1rvoillanoo within the-s13eoified l=req1:1enoy, and tho 13ro1Jisions of SR d.0.d wo1:1ld a1313ly. (oontin1:1ed) DAEC 1.4-7 Amendment No. 293

Frequency 1.4 1.4 Frequency EXAMPLES. EXAMPLE 1.4 8 ' (ooRtiRl:IOd) SURVEILLJ\NGE REQUIREMEt>JTS SURVBLLJ\NGE FREQUENCY

                                             ~JOTE
                   ~Jot FO*q1:1iFod to Be FRet iR MODE     a.

Vofi:fy 13mamotOF is v.:ithiR limits. 24 hOl:IFS E>Eam13le 1 .4 e s13ooifios that tho Foq1:1immeRts of this S1:1rvoillaRoe do Rot ha\'o to BO mot while the l:IRit ie iR MODE d (the ass1:1mod Ap13lioaeility of tl=lo assooiatod LGO is MODES 1, 2, aRd a). Tho iRtOFVBI FReBSl:IFemeRt foF_ tho rFOql:IOROY of this S1:1rveillaROO 00RtiR1:1cs at all times, as dosoFieod iR .E>Eam13le .1.4 1. l-lo\vo110F, the Note 00Rstit1:1tos BR "otfloFwise stated" cxoo13tioR to tho A1313lioability of tJ:iis S1:1rvoillaRGO. ThoFOfoFO, if the Sl:IFVCillaROO WOFO Rot 130FfoFFRed withfR the 24 .ho1:1F iRtorval (13l1:1s tflo oxteRsioR allmvod BY SR a.0.2), aRd the 1:1Rit was iR MODE a, thoFO wo1:1ld ec Ro faih:JFo of the SR ROF fai11:1FO to moot tho LGO. ThCFefoFe, RO 11iolatioR of SR a.0.4 0001:1FS \'.'heR ohaRgiRg MODf::S to oRtOF MODE d, C\'CR with the 24 ho1:1F. Fr=eq1:10Roy oxooodod, 13mvided the MODE ohaRgo docs Rot Fos1:1lt iR oRtr,r iRto MODE 2. PFioF to cRtoFiRg MODE 2

               ' (ao01:1miRg agaiR tflat the 24 hOl:IF rFOql:IOROY WOFO Rot FRet), SR d.0.4 'i.vo1:1ld FOq1:1iFo satisfyiRg tho SR DAEC                                      1.4-8                             Amendment ~Jo. 20a

!DELETED I 2.~Si\FleTY LIMITS (Sbs) 2.1.1 Roaster Coro SLs 2.1.1.1 ruol CladdiRg IRtogrity \A/ith tho reactor stoaFR driFRo

                                'pressure~ 686 psig or sore ~ow~ 1oq<, *rated sore ~O'N:

H=IERM,'\L PO'NER shall be~ 21.7% RTP. 2.t1 .2 MCPR V\J.ith tho roaster sto.aFR doFRo pressure~ 686 psig andxGOFO fie,;/~ 10% Fated GOFO flov,*: MCPR shall be~ 1.08 for two_ .resirsulatioR loop operatic~ or

                                ~  1.11 for siRgle reoirsulatioR loop oporatioR.                .

t 2.1.1.d Reactor \/ossel \C\<ator Lo\'ol Reactor \*ossol i.vator 10,,101 shall be greater thaR 16 iRshos abo\'o ~o top of aoti¥o irradiated fuel. 2.1.2 Roaster CoolaRt SvstoFR Pressure SL Roaster stoaFR doFRe pressure shall be~ 1336 psig. 2.2 SL 'AolatioRs

           \O/ith aRy SL \'iolatioR, th~ followiRg aotioRs shall be soFRplotod wi~iR 2 hours:
           ~         Restore ooFRpliaRse wi~ all SLs; aRd
           ~         ruUy iRaort all iRsortablo rods.

DAEC 2.0-1 Amendment No. 297

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY. LCO 3.0.1 LCOs shall be met during the MODeg or otl=lor specified conditions in the Applicability, .except as provided in LCO 3.0.2,-bbG 3.0.7, LGO 3._0.8, aAd LGO 3.0.Q. LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met; eMeopt as previded iA

                            . LGO 3.0.e aAd LGO 3.0.e.                          *                    .*

If tl:io LGO is rnot or is Ae.leAgor applioablo prier ta eMpiratioA of tl=lo spooifiod GornpletioA +irne(s), sornpletioR of tl=lo ReE1l!liroei

                              /\otioR(s) is *Rot FOE1l!lired, 1::1Rlose otl=lorwiso stated.

LCO 3.0.3 VVheR *aR LGO is Rot rnot aREi tho assooiatoei ACTIONS are Rot ._!D_e_l~_te_d_._ _ ______._ et, aR assooiated AGTIO~J is Rot providea, or if Eiireotea by tl=lo r - - - - - - - - . ass.oo!ated AGJIO~JS, tt:ie 1::1*Rit st:iall be plaeod iR a MODE OF other speoifiod ooRditioR iR wt:iiot:i tho LGO is Rot applioablo. AstioR sl=lall be iRitiated withiR 1 t:10_1::1r to plaeo tt-io 1:1Rit, as applisablo, iR: a:- MODe 2 v.Att:liR Q t:lol!lrs;

                              &.-       MODe 3 1.'Jitt:liR 13 ho1:1rs; a Rei
                             &:-        MODe 4 withiR 37 t:101:1rs.

fqEooptioRs to tt:iis SpooifioatioR are stated iR tho iRdivid1:1al SpooifioatioRs. *

V\ll=loro OOFFOOti-\'O rnoas1:1res are o6rnplotod tt:iat porFRit oporatioR.

iR aooordaRso witl=I_ tl=lo LGO_ or AGTIO~JS, oornplotioR of tho aotioRs FOE11:1irod by LGO 3.0.3 is Rot FOE11:1iro0. LGO 3.0.3 is ORiy applioablo iR MODES 1, 2, aRa 3. Leo 3.0.4 ~~~:t~~-0 is A9t mJ, eAIF)' iR!e a MODE er et~er s~00ilie8 e0A8ili0A iR tl=lo /\pplioabilit:y sl=lall OR~ be rnado*:

                            &:-*

V\Q:ioR tho assooiatod AGTIO~JS to be oRtorod poFFRit 00RiiR1:1od operatioR iR tho MODe or other spooifiod soRditioR iR the Applioability for aR 1:1Rlirnited porioei of tirne; (continued)

DAEC 3.0-1 Amendment~

LCO Applicability 3.0 3.0 LCO APPLICABILITY . LGO d.0.4' Mer *perfeRTianse of a risk asoooomont addressing (sontinued) inoperable systems and. sompononts, sonsidoration of the results, detoRTiination of tt:10. asseptability of entering the MODE or other sposifiod eondition in tho Applisability, and o_stablishmont of risk management aotions, if appropriate; exeoptions to this Sposifisation are stated in tho individual Spoeifieations,. or *

                                      '.'\/-hon an allowanso is stated in tho.indwidual value, parameter, or other *epoeifioation.

This epeeifieation shall not prei.*ont shanges in MODE8. or. other spooifiod eonditions in tho /\pplisabiliey that aF(;l required to eomply 1Nith AGTIONg or that are part of a shutdo 1Nn of tho unit. , r.

      . LCO 3.0.5 Deleted.

LCO 3.0.6 J \/\/hen .~.supported ~ystom LGO is no~ !11ot solely due _to a su~port system*LCO not being mot, tho Cond1t,ions ~nd Required Aet1ons D_e_le_te_d_._ _ ____, assoeiatod with this supported system are not required to be entered. Only the support system LCO AGTION8 are required to be entered. This is an oxeoption to LCO a.0.2 for the supported

system. ~n this avant, an ei.*aluation shall .be porfeRTiod in aeeordanse with gposifisation 6.6.11, "Safety runotion DotoRTiination Program (8rDP)." If a loss of safety funstion is dotoRTiined to. exist by .this program, tho appropriate Conditions and Required /\stions of tho LCO in whioh *the loss of safety fuRetion exists are required to be entered. *

                              'JV.hon a support system's Required /\etion diroets a supported system to be deolared inoperable or dirests entrJ into Conditions and Required /\stions for a supported system, tho applisablo Conditions and Required /\etions shali' be entered in assordanso 1.vith LCO d.0.2.                     .

(continued) DAEC 3.0-2 Amendment ee f

LCO Applicability

                                                                                                       - 3.0 3.0   LCO APPLICABILITY (continued)
 .---Ioele-~::-.3.o_.7- ~ a ! T § } ? . A ~ ~ ~ § ~ i o a l Gom13liaRso 1Nitf:I S13ooial 013or=ati0Rs LGOs is 013ti0Ral. 'Nl:ioR a Sposial 013omti0Rs LGO is dosiFod to be me.t but is Rot mot, tile ACTIONS of tt:io S13eoial 013emti0Rs LGO st:iall be met. ',O.QioR a S13eoial 013or=ati0Rs LGO is Rot desired to bo met, eRtF)' iRto a MODE OF otl:ioF s130oifiod soRditioR iR th-e A1313lioability st:iall ORiy be made iR assoFdaRso witR tt:io otl:ioF a1313lisablo S13osifisati0Rs. .

LCO 3.0.8 WRoR ORO OF morn rnquirnd SRUbboFS aFO URablo to !30FKlFR1 thoiF ,...!D_e_le_t_e_d_---- ..__ _ _ _ ___. J assosiatod su1313ort fuRstioR(s), aRy affostod su1313ortod LGO(s) am Rot rnquimd to be deolarnd Rof met sole~' foF tt:i_is FeasoR if Fisk is assessed aRd maRagod, aRd:

a. tt:io sRubboFS Rot able to 130Ffom, tt:ioiF assosiatod su1313ort fuRstioR(s) aFo assosiatod witR oRJy ORO tFaiR OF subsystem of multi13lo tr=aiR OF subsystem su1313ortod system OF arn ..

assooiatod 11.iitt:i a s_iRglo tmiR OF subsystem su1313ortod system aRd aFo i;iblo to 130FfoFR1 tt:ioiF assosiatod su1313ort fuRstioR

                                  ,,vitRiR 72 Ro1:1FS; or

b. tt:ie sRubbeFS Rot able to _130FfoFm theiF assooiatod su1313ort

                                  ~mstioR (s) arn assooiatod witt:i morn tl:iaR ORO tr=aiR OF subsystem of a multi13lo tFafR OF subsystem su1313ortod syst_om aRd aFo able to 130FfoFR1 thoiF assooiatod su1313ort fuRotioR witRiR 12 ROUFS.                 -
                             -At tt:io oRd of tt:io s13osifiod 130Fiod tt:io Foquirnd sRubboFS must be
    !D_e_le-te_d
    .....      ___[__=-:J

_ __, able to 130FfoFm tt:ioiF assosiatod su1313ort fuRstioR(s), OF tt:io _ ~ alfeolo8 swppoFlee sysleFR LCO(s) s~all ~e eeolaree aot FRol. LCO 3.0.9 - W~ea oae or"'""' re~wire8 ~errio,s are waa~lo le poFfe"" t~eir Folatod su1313ort fuRstioR(s), aRy su1313ortod system LGO(s) aFO Rot mquirod to be doslaFOd Rot met solely foF tt:iis masoR foF u13 to ~O days 13rovidod tt:iat afloast ORO tr=aiR OF sl:Jbsystom of tt:io su1313ortod system is* OP~RAQL~ aRd su1313ortod by baFFioFS oa13ablo of 13rovidiRg tt:ieiF rnlatod (OORtiriuod) OAEC 3.0-3 Amendment~

LCO Applicability 3.0 3.0 LCO APPLICABILITY (continued). LCO d.0.Q support funstion(s), and risk i~ assessed and managed. This (oontim1od) sposif.ioation may ea sonsurrontly applied* to more than one train or suesystom of a multiple train or suesystom supported system provided at least one train or suesystem of tho s1;1pportod system is OP~RABL~ and the harriers supporting oaoh of those trains. or suesys_toms provide their related support. funstion(s) for diffeFQnt oatogorios of initiatin_g events. For tho ~urposos of this sp*osifisation, tho ~igh Pressure Coo1a*nt lnjostfon system, tho ~easter Coro Isolation Cooling system, and tho Automatis Doprossuri:zation Systom**aro sonsidorod independent suesystoms of a single system. If tho roeiuirod OPER/\BLE B=ain or suesystom eosomos inoporaelo 1Nhilo this spooif.ioation is in.use, it niust ea restored to OPERABLE status within 24 hours or tho provisions of this spooifioation oannot eo applied .to tho trains or suesystems supported ey the harriers that oannot perform their related support funceon(s).

At the end of the specif.ied period, the reeiuired earners must ea aele to p'3rfoFR1 their related support funotion(s) or the s~pportod system LCO (s)*shall ea doolarod not mot.

DAEC .3.0-3a

Amendment~

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or oU:ior specified conditions in the Applicability for individual LCOs, unless othetwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the *perfonnance of the Surveillance or between perfonnances of the Surveillance, shall be failure to meet the LCO. Failure to perfonn* a Surveillance within the specified Frequency shall be failure to meet the LCO mmopt'as prov-idod in SR ~.O.~. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is perfonned within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a spec;:ified condition of the Frequency is met. For Frequencies specified* as "once," the above interval extension does not apply. . If a GomJ:)letion Time roei1:1iros poriodie J:)Ooormanoo on a "onso

per ... " sasis, t-1:lo aso,,o Froei1:1ensy e><<ension applies to oasl=I pooormanGO after tt:io- initial pooormanso.

              ~GOJ:)tions to tl=lis Spooifioation are stated in tl=lo individbml SJ:)oomoations.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its t

specified Frequency, then compl_iance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified Freque.ncy, whichever is greater. This delay period is pennitted to allow performance of the Surveill~nce. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed.

If the Surveillance is not performed within the delay. period, the LCO must_immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be

declared not met, and the applicable Condition(s) must be entered.

(continued) DAEC 3.0-4 Amendment~

SR Applicability 3.0 3.0 SR APPLICABILITY (continued) - SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. 'Nhon an LGO is not FRot d1:10 to Smvoillanses not having boon FRot, entry into a MODE or other spooifiod sondition in tho /\pplisability shall only be FRade in assordanso with* LGO a.0.4.

This provision shall not prevent entry into MODES.or other specified conditions in the Applicability that are required to
comply with ACTIONS or that are part of a sh1:1tdown of tho 1:1nit.

DAEC 3.0-5 Amendment~

3.1.1 SHUTDOVV~J MARGIN (SDM) LGO 3.1.1 SDM shall 130: a.,. z: 0.38% Aki'k, 1.vith tt-io highest v.*orth oontrol rod analy:tioally dotom,ined; or

                      ~    z: o.2sq~ Ak.lk, \Vith the highest i.r.'orth oontrol rod dotom,inod 13y
                           -test-:

APPLICABILITY: MODeS 1, 2, 3, 4, and 5. ACTIONS CONDITIO~J ~eQUl~eD ACTION COMPLeTIO~J TIM~ A-: SDM net within liFRits in A-:4 Restore SDM to 11.*ithin e he1::1rs MODe 1 er 2. ffffiff&.,

RoE11::1irod ,O,stien and ,B4 Be in MODe d. 12 he1::1rs asseeiatod CeFR13letien TiFRo of Condition A net fR&t:.

~    SDM net within liFRits in        ~         Initiate astien to f1::1lly  IFRFRodiately MOD~~-                                     insert all insertal31o oentrol reds.
~*   SDM not within liFRits in        .Q.:4     Initiate astien to f1::1lly  IFRFROdiatoly MODe 4.                                   insert all insortal31e oentrel reds.

ANG

                                                                                           \     llo,I ---,

DAEC 3.1-1 Amendment~

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 ~oe ll:lol:l:l131:1owv                                                                                          33VO
                    ~ 30.eVII 1:1! 91:lO!l~:1080 B1:1!:IAl3 :10:ijeo:101:n 110/v'<VII 000 ~

Otfv' ll:IOl:l:JOBe1elo:1 130:1 18:lll:189

18 10990ill O:IR998:18

10iseo:1 0~n l:J!llt!'" ll:JOWO,*,ow IORj :IOijB elRl:lels B1:1!i't'l8118J:

91:18!l!l31:189 l:l:JR!:lq!l!RB8 e1:1,40e0:1 PB . ")b')IV % ~* T tft4ltM mije 9:IROl:l_ ~z 9! )f 0:189 j30l8!j38:18 01:jl j31:10 PB)! 0:189 j30:18l1.1:10.l:l:l U!lltlh', OSUQ 04l l:IOPf*'loq 901:10:1otJ113 . .

                                                                   . - ~,\ll0*e0:1  0:189 ~uo.
                                                                                           )  . {  '      ~-z* ~- MS A3t{3A03M::I                                             3 3 t~\Fl=i 131'tt! AS I       I S+/-N3~3MIA03
~

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ContFOI Roel SsFaFl1 Assun,ulators 34:,e J\f"'Tlf"\I"~ /-- ,:_ --n

  -   -   *- \--   , ..... ---,

cori.JDITIOri.J REQUIRED ACTION COMPLETION TIME

.8-:    Two or n,ore sontrol reel .Q.4     RestoFO oharging water         1 hour fron, ssran, assun,ulators               heaeler pressure to            diGCO\'OPf Of inoperable with roaster           ~ Q40 psig.                     sondition* B stean, elen,e pressure                                            eonourrent v:ith
        ~*goo psig.                                                       oharging water heael~r pressure
                                                                          ~ Q40 psig B.2.1              NOTE Only applioablo if tho assosiatod *sontrol reel saran, tin,e was within tho lin,its of Table 3.1.4 1 eluring tho last soFaFl1 tin,e Surveillanoo.

Doslare the assosiated 1 hour oontrol reel saran, tin,e "elev,*." B.2.2 Deslaro the assooiatoel 1 hour sontrol .roel inoperable. (oontinueel) DAEG 3.1 10 An,oneln,ent 223

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osuernoAJAS 01:n 4:J::!11, *po~oo1quA 9! UO!l9A9 8U:IA8 pu~ ~U~l oeuep:toeee u1 oee:fOlS U00i'"l0Q BU!8!8 p098:fl tee4 IIB vtj:!=18H ~rt*~- ~g U:10:1eo:1i:1 1e:1tuo3

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esuep:tosse u1 Ll:IO:fJ. Ll:IOlS~sqAs 3=tS oue 4BAB:f4l i'IIOIJ. vtj:!=10n t"t"~*E t'IS tN\11:::le>O~c e>t~l+/-S3+/- 33IA~3SNI ~ t 04l 4:J::!M . - o:1Ass0:1a oe:te4ss,p lB Ll:lae z*~z ~ o

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APLHGR

                                                                                        ~
             ~DELETED 3.2 PQlNER DISTRIBUTIO~J LIMITS
~.2.1 ,WERAGE PU\N/\R LINE,1\R H~/\T GENER/\TION ~/\TE (APLHGR)

LCO a.2.1 /\11 /\PLI-IGRs sRall be less tRan or oei~al to tRo limits spoomod in tRe COLR.

/\PPLICABILITY:     THERMAL PQlNER ~ 21.7% RTP.
/\CTIO~JS CONDITION                    REQUIRED .'\CTIO~J              COMPLETIO~J
                                                                               +JMe A:  /\ny APLI-IGR not vtitRin     A:4      Restore /\PLl-=IGR(s) to  2 ROUFS fffflff&:-                            1#itRin limits.
 ,B,. Roeiuirod Astion and*         ",84    Reduoo TI-IERMAL           4 ROUFS assosiatod Completion                 POVVER to~ 21.7%

Time Rot met. -R+P-: SURVEILLP.NCE REQUIREMENTS SURVEILU\NCE r:REQUE~JCY SR d.2.1.1 Verify all APLI-IGRs are less tRan or oeiual to Once i.*,itAiFl tRo limits spasmed. in tRe COLR. 12 ROUFS after

                                                                       ~21.7% RTP In aooordanoo witR tho Sur,1oillanoo Froeiuonsy Control Program              t DAEC                                      3.2-1                             Amendm_ent -28Q

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  !DELETED                ]                                                        d.d.1.1 3.3 l~M~~ff/\TIG~J a.3.1.1 Roaotor Protestion System (RPS) Instrumentation LCQ a.a.1.1            TRe RPS instrumentation for oaoR l=unstion in Taele a.a.1.*1 1 sRall eo OPER/\BLE

/\PPLIC/\BILITY: /\ooordiAJ to :J:aele d.d.1.1_ 1. ACTIONS Separate Conelition entry is allowed for oasR eRannel. CONglTIO~J R~Ql:JIReg ACTION COMPL~TIO~J TIMe A: One or.more _FOE1Uiroel M Plaee oRannol in 12 ROUFS eRannols inoporaelo. ~ QR A-!J: Piasa asseeiated trip 12 ROUFS syste~ 'in .trip.

&     Ono or more                 ,8.:4    Plaeo sRannol in one trip e Rour=s l=unotions witR one or               system in trip.

more reE1uiroel GRannols inoperaelo QR in eotR trip*systems.

                                  ~        Plaee one trip system in  e Roura
                                          ~

(eontinueel) DAEC 3.3-1 Amendment~

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-~ LLS IAstn1R1eAtatioA a.a.a.a CONDITION REQUIRED ACTION COMPLETION TIME

~     Roq1:1iFOd AetioA aAd               .Q4     Deolaro the              IR1R1odiato~y assooiated CoR1J3lotioA                     assooiated LLS TiR10 of CoAditioA A, B,                    ,,alvo(s) iAOJ:>oraelo.

or C Aot R1ot. Both LLS 1,ahi<es iAOJ:)eraele d1:1e to iAOJ:)OFaBIO ohaAAOIS. SURVEILU\NCE REQUIREMENTS +. Refer to Teele a.a.a.a 1 to doto.FRliAe whioh 8Rs BJ:>J:>IY for oaoh F1:1AetioA. ~ \OJheA 8 shaAAel is J3leood iA BA inoJ3ereelo stat1:1s solely for J3erfoFR1BAOO of roq1:1irod S1:1rvoillaAooa, oAtry iAto assooi_atod CoAditioAs aAd Roq1:1irod AstioAs R1ay ea delayed for l:lJ:l to a ho1:1rs J:lFOVided the assooiated F1:1AetioA RlaiAtaiAs LLS iAitietioA OOJ:)BBility. SURVEILU\NCE FREQUENCY sR a.a.s.a.1 PerfoFRl QI-IA~J~JEL FU~JGTIONAL TEST for IA aooordaAso J:>OrtioA_ of tho ohaAAol 01:1tsido J3riR1ary with tho OOAtaiARlOAt. Sl:lF\'OillaAOO FFOql:leAoy CoAtrol Pro~raRl SR a.a.a.a.2 PoFfoFRl GI-IAN~JEL i;u~JGTIONAL TEST. IA asoordaAoe v,ith the el:JF\10illBAOO Froq1:10Aoy CoAtrol Program (ooAtiAl:lOd) DAEG d.d 71 ARlOAdRlOAt am;

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                                                                                                       ~
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3.4 R~GTOR COOLANT SYSTEM (RCS) 3.4.1 Rooir01:.1lation Loo13s 013orating LGO 3.4.1 Two resirs1:1lation loops witl:i R1atsl:iod p1:1R1p speeds sl:iall so in 013eration ._,,itt:i ooro flow as a ~notion of Tl-leRMAL POVVER 01:1teide

                    - tile EMel~sien Region s13osified in tl:ie GOLR Ono roeir01:1lation 10013 Rlay so in operation witl:i aero flow as a fHnstion of TI-IERMAL PO\OJER 01:1tsido tl:ie §Eel1:1sion Region speeified in* tl:ie GOU~ and 1.vitl:i tl:io following liRlits ap13liod \'.:Ren tl:io assoe~ated LGO is a13plioaelo:
                      &:     LGO 3.2.1, "AVERAGE PLA~JAR LINE/\R 1-1*E/\T GE~JER/\TION RATE (/'.PU-4GR)," single loop 013eration liRlits spooifiod in tl:ie GOLR;                                   *
                      &:-    LGO -~-2.2, "Ml~JIMUM CRITICAL POl/i/eR RATIO (MGPR),"

single loop opeFatien liRlits spooifiod in tl:io GOLR; and

                      &.-   LGO 3.d.1.1, "Roaoter Proteotion- SystoRl (RPS)

_lnstFl:lFAontation," F1:1nstion 2.e 0'worago Power Range Monitors i;:1ow Biase~ l-ligl:i SsraR1), Allowaelo Val1:10 of Tasia d.d.f1 1 is reset for single 10013 013eration. APPLICABILITY: MODES 1 and 2. ACTIONS GO~JDITIO~J REQUIRED ACTION GOMPLETIO~J TIME No rooiro1:1lation leaps A:4 Plaeo tl:ie roaotor IR1R1ediate~ in operation. meeio c*Ni:tch iR tho Sl:i1:1tdown position-. (oont-in1:1od) DAEC 3.4-1 Amendment~

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        ~DELETED                                                                            ~

3.5 ~M~RGENGY GORE GOOLlt>JG SYST~MS (~GGS), RPV \AJ/\TeR INV~t>JTORY l,. GOt>ffROL, At>JD R~GTOR GOR~ ISOL.ATIOt>J COOLING (RGIG) SYST~M 1 3.5.1 EGGS OpOFating LGO d.e.1 Eaoh EGGS injootiontspray s1:1bsystom anel the /\1:1tomatio Depress1:1rization System (ADS) R:Jnstion of fo1:1r safety/relief valves shall be OPERABLE. /\PPLIG/\BILITY: MOD~ 1, MODES 2 anel d, oxsopt High Pross1:1re Coolant lnjostion (HPGI) is not roei1:1ireel to be OP~R/\BLE *.vith roaotor steam elome pressme ~ 160 psig anel ADS valves are not reei1:1iroel to be OPERABL~ *Nith roaster steam elome pross1:1ro ~ 100 psig. AGTIOt>JS LGO 3.0.4 .b is not applisablo to I-IPGI. GOt>JDITION ReQYIR~D /\GTIOt>J GOMPL~TIOt>J TIME ~ Ono Resiel1:1al Heat M Restore RHR p1:1mp to 30 Days Removal (RHR) p1:1mp OPeR/\BL~ stat1:1s. inoperable. -B-: Ono low pross1:1re ~GGS S:4 Restore low pFOSSl:IFO 7 elays s1:1bsystom inoperable fer EGGS s1:1bsystom to reasons other than ' OP~RABLe stat1:1s. Gonelition ,Ar.. G:- One Coro Spray G:-4 Restore Gor-e Spray 72 ho1:1rs s1:1bsystom inoperable. s1:1bsystom to OPERABLE stat1:1s. ANQ One or two RI-IR ~ p1::1mp(s) inoperable. 72 ho1:1rs G:-2 Restore RI-I~ p1:1mp(s) to OP~~.BL~ stat1:1s. ~ Both Gore Spray .Q-4 Restore one Coro 72 ho1:1rs s1:1bsystoms inoperable. Spray s1:1b.systom_ to OPEAABLE stat1:1s. (sontin1:1oel) DAEC 3.5-1 Amendment~

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                                                                                         ~
                                        --Initiate aotion to restore DR/\l~J Tl~

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DRAIN TIME < 1 Aour. aURVEILLP.NCE

        -      RE QUIREMENTg aURVelLU\~JCe                                      rREQUe~JCY
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Primary Containment d.e.1.1

      ~DELETED 3.6 CONTAl~JME~JT SYSTEMS 3.e.1.1 Primary Containment LCO 3.e.1.1           Primary sontainmont sl=lall be OPERABLE.

APPLICABILITY: MODES 1, 2, ans d. ACTIONS CQ~H;)ITION ~eQbll~eD ACTIO~J COMPLeTION TIME 4- Primary oontainmont A:4 ~estore 13rimar;1 1 ROl:lr ino13orable. sontainff!ent to OPeAABLe stat1:1s. ~ ~eEf1:1ires Astion ans S4 Be in MODe d. 12 ROl:IFS assosiates Com13letion Time not met. ANG

                                   ~     Bo in MQDE 4.        3e 1=101:1rs DAEC                                   3.6-1                       Amendment~*

Primary GoRtaiR*moRt

                                                                                          *a.s.1.1

'SURVEILLANCE REQUIREME~ns SURVEILU\NGE FREQUE~JGY SR a.6.1.1.1 POFk3Fffl roei1:1iro0 *1is1:1al eMamiRatloRS BAG IA aoeoreaR00 leakage rate tost,iRg OM0013t for 13rimary * \1,*ith tho Primary

               *'ooRtaiRmeRt air losk tOSHRQ, iR assoreaROO               G0Rta1Rmorit
                *nith the Primary GoRtaiRmoRt Leakage Rate                Leakage Rate Program.                                                *Program.

t SR a.6.1.1.2* Verify s1:11313rossi0R' ehameer 13ress1:1re eees IA aoooreaRoo with Rot iRsreaso at a rate :!!>' O.OOQ 13si 13qr miR1:1t0 . tho 81:1rvoillaRso

               *testoe 01Jer a 1O miR1:1t0 130rio0 at a                   l=FOE!l:JORGY GoRtrol eif:feroRtial 13ross1:1r0 of:!!>' 1.0 13si0.              Program D/\EG                                                                    /\.moRemoRt 280

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1oije site~

cB LI!lfl!N. 09LIQ flMit We:100::ld 10::llLI03 i\9LIOABO:l:I osLiell!Oi'tlAS 04i *s1eos lLIO!l!SO::I lff!i'l'I oi1,1e1*1 e6::1nd lLIOi:l:ILI!eiLioe 1:ff!1'0'1 osLiep::1osse LIi 1~ew,::1d 4seo ::IOj DLI!isoi eie:i e6e~ee1 W:IO:j:IOr::I v*f* nrf MS

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9::IA999::ld DLI!l::18LI! ep 'DLI!:J:IOLI! ::IOj Liede e::1e se11,1ei1t e6::1nd lLIOWLI!eiLioe klew!:lel lfSLI! 8 ~ 9ljl LIOlji\11iew OE! ei p9::1!ABO:I lOM

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        *3ff3At5~~:I                                                  33M'V'99131\~AS e*nre 9td3d

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Suppression Pool h10Fago TempeFatum d.e.2.1 d.e CONTAl~JME~H SYSTEMS d.e.2.1 Suppmssion Pool A11orago TompoFature LCO d.e.2.1 . Supprossion_ pool a1,10Fago tompOFatuFo sRall be: a:- ~ Q0°i; wRon any OPERABLE inteR11ediate range monitoF (IRM) is~ 25/40 divisions of full soale on Range 7 and no testing tRat adds Roat to tRo suppFossion pool is being poFfoR11od;

                     &.-   ~  1Oe°F WROn any OPERABLE IRM ORannol is~ ,2,e,149 di-visions of full ssale on Range 7 and tasting tRat adds Roat to tRo suppFOssion pool is being peFformed; and .

G:- ~ 110°F wRon all OPERABLE IRM oRann_ols a m ~ ~ divisions of full ssalo on Range 7: APPLICABILITY: MODES 1, 2, an*d d. ACTIONS CONDITIO~J ReQUIRED ACTIO~J. COMPLETIO~J TIME A. Suppressio.n pool A:4 'JoFify suppFossion Onse par Rour average tomporatum pool average

     => 95oi; but~ 110°i;.                     temperature
                                                ~ 11 goi;_

Any OPERABLE IRM GRannOl7~ A./J: Restore suppression 24 Rours divisions of full soalo on ~eel average Range 7. temperature to

                                               ~~
     ~Jot poFforming testing tRat adds Roat to tRo suppmssion pool.

(sontinuod) DAEC d.0 24 Amendment 22d

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RI-IRaVV System

LCO 3.7.1 T'NO Rl=IRSVV subsystems shall be OP~RABLE. APPLICABILITY: MODES 1, 2, and 3. ACTIO~JS-CQNDITIQ~J REQbllRED ,O,CTION COMPLETIO~J TIMe A: Ono Rl=IRS\"! pump inepoFablo. A:4 RostoFe RI-IRS~!\! p_ump to QP.ERABLE status. d0 days 1

,S:, Ono RlqRS>,f!J pump in      -84    RostOFO eno Rl=IRS),a_(  7 days oaeh subsystem                     p1:1mp to OPER/\BLE inepoFablo.                        staais.

G:- Ono Rl=IRSVV G-4 ~JOTE subsystem inopoFablo EntoF applisablo fflF FOasens ethoF than Conditions a_nd Condition A. Ro~uiFod Aetiens of LCQ 3.4.7, "Residual

                                        ~eat Remei.ial (R~R)

Shutdown Coolin§ System ~et Shutdown," fflF R~R shutde\11n 080liR§ maae inoperable by Rl=IRS>N System. RestoFe R~RSVV 7 days subsystem to QPERiAcBLE statl:fs. (eentinued) DAEC 3.7-1 Amendment~ ,r

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R\I\IS System and UHS Deleted ~ 3.7.2 River V'Jator S1:1pply (RVVS) System and Ultimate Ff oat Sink (UHS) LCO ~.7.2 Two R'A'S s1:1bsystoms and UHS shall be OPeR/>.BLE. -APPLICABILITY: MODeS 1, 2, and 3. ACTIO~JS CO~JDITIO~ ReQl:IIReD 11\CTIO~J COMPLeTIO~J TIMe

~     Ono R\OJS s1:1bsystem         A:4       Restore tho RVVS              7 days inoperable.                             s1:1bsystom to OPe~.BLe statl:ls.
.g,. RoE11:1irod ,l\stion and                     ~JOT~

assesiatod Completion enter applisablo Conditions Time of Condition A not and RoE11:1ired Astions of LCO

      -met,.                        3.4 .7, "Rosid1:1al 1-leat Romoi.ial (RHR) *sh1:1tdown Coolin§-
      ~                             System I-lot Sh1:1tdo1,¥n,° for RPIR sh1:1tdo111n eoolin§ made Both RVVS s1:1bsystoms        inoperable by R'JIJS System.

inoperable.

      ~                             ~        Bo in MODe 3.                  12 ho1:1rs UHS inoperable.               AN,g
                                    ~        Bo in MO De 4.                 3e ho1:1rs DAEC                                     3.7-3                             Amendment~

ES'A' System

LCO 3.7.3 Two ES'.'\' sYbsystoms shall be,OPeRABLE. /\PPLIC/\BILITY: MODES 1, 2, aRs 3. /\CTIO~JS

"      CONDITION                        ~EQ6ll~ED ACTIQ~J             COMPLeTION TIMe A:        ORO ES'.'\'                               NQTE8 sYbsystom            4-:     ERtoF a1313lisable CoRsiUoRs iROJ30Fable.                 aRS Re~YiFOS /\etioRS of LCO ~.8.1, ",A,C SOYF606 Q130FatiR~," feF siesol
                                      ~OROFatoF ~aso iROJ30Fablo by E8\fl/ ~ystom.
                              ~       ERtOF a1313lieablo CoRsitiORS
                                    . aRS ~O~YiFOS ,A,stiORS of LCQ ~.4 .7,"'~osisYal l=loat Remo¥al ~Rl=IR) Sl=IYtsowR CooliRf:J System Plot.

81=1YtS0\1~R," feF ~l=H~: sl=IYtso\\lR sooliRf:I maso iR0130Fable by ES'.'\' System. A:4 ~ostoFO tl=lo E8\C!J 7 says sYbsystom to OPERABLE statYs.

  -S:- . ~O~YiFOS /\stiOR     -8:-4    Be iR MODE      a.            12 ROYFS aRs /\ssosiatos Com13lotioR Time     AWQ of CoRsitiOR /\

Rot mot. ~ Bo iR MODE 4. ~e ROYFS QR Both E8\C!J sYbsystoms iROJ30Fablo. DAEC 3:7-5 Amendment~*

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8rU System

3.7 p ~ D e l e t e d 3,-7.4 ~ F U ) System LCO d.7.4 Tv.10 8FU subsystems sl=iall be OPERABLE Tl=io oontrol building en 11elope (CSE) boundary may be opened intom,ittently under administratii,e oontrol. /\PPLIC/\BILITY: MODE8 1, 2, and*d, During movement of irraeliateel fuel assemblies in tl=io seoondary oontainment,

                       . During CORe ALTERATION£.

ACTIONS CO~JDITION ~EQUl~ED ACTIO~J COMPLETIO~J TIM~ A: .one 8P:bl subsystem A:4 Restore 8P:U subsystem 7 days inoperable for reasons to OPER/\BLE status. otl=ier tl=ian Conelition B. & Ono or more 8FU ~ Initiate aetions to Immediately subsystems implement mitigating inoperable elue to astions. ino13orablo CSE ANQ bounelary in MODE8 1, 2, anel d. ~ ~lerify mitigating aetions 24 ROUFS ensure CBE oooupant e*J3osures to raeliologieal Rai!!arels will not OMSOOel limits anel 11erifiJ by administrati110 means tl=iat CBE oooupants are protooteel from smoke anel ot=iomioal Rai!!arels. ANQ

                                       ~      Restore Cl3E bounelapt       . QO elays to OPERi~BLe status.

(oo ntin uoel) DAEC 3.7-7 Amendment No. d06

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. . . I . CBC System

                                                                                      ~-
         =::Deleted*

. 3.7 PLANT SY S 3.7.5 ~ : ( G B G ) S y s t e " ' LGO a.7.e Two CBC euesystoms sRall ee OPeRABLE. APPLICABILITY: MODES 1, 2, aRd d, . . DuriR~ movomoRt of iFFadiatod fuel assemelies iR tf:le soooRdaF)' OORtaiRmORt,

                      *DuriR~-GORe ALTeRATIO~JS.

ACTIONS CONDITION REQIJIRED AGTIO~J GOMPLeTIO~J TIMe A: 0Ro CBC eueeystom M Restore CBC ao d_ays I iRoporaele. suesystom to OPeRABLe status.

.Q..;. Two C BG suesystoms             M      Verify soRtrol euildiR~ 0ROO per 4 ROUFS iRoporaelo.                            aroa tomporaturos
                                              < QQor".

ANQ

                                       ~      Restore ORO CBC         72  ROUFS suesystom to OPeRABLe status.
~      Roetuirod /\stioR aRd          G:-4    Bo iR MODe d.           12 ROUFS assoeiatod GompletioR Time of GoRditioR .,t:,, or B   /\Nb Rot met iR MODE_ 1, 2, ef-6-:-                         ~      Bo iR MODe 4.           de RouFS (eoRtiRued)

DAEC 3.7-11 Amendment~

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~ --\- \\ Main Condenser O#§as

                                                                                        &-7-:e

-3.7 PLANT SY~~D_el_et_e_d_ _ __ 3.7.6~gas LCO d.7.e Tho gross gamma activity rate of tho noble gases rnoas1:1red at tho Stearn Jot Air Ejootor-(SJAE) offgas 13rotroatmont monitor shall be ~ 4:-Q Citsooond after dosay of ~O rnin1:1tos. APPLICABILITY: MODe 1,

                       , MODES 2 and ~ with any main steam lino not isolated and SJAE in 013oration.

ACTIONS CO~JDITION _ ~EQbll~ED ,A,CTION COMPLeTION TIMe

 ~    Gross gamma a1;1ti¥iP,<<          A4       ~oetoro gross gamma        72 ho1:1rs rate of the nobl_o gases                 _aotw~<< rate of tho noble not 1,t.iithin limit.                     gas~s to within limit.
 &    ~0~1:1irod ,A,stioR and.         :4     . Isolate all rnairi

12 ho1:1rs assosiatod Corn13lotion steam lines.

Time not mot.

                                       ~
                                       ~           Isolate SJAE            12 ho1:1rs AA
                                       -B-:&-4     Bo in MODE~-            12 ho1:1rs ANQ
                                       ~           Bo in MODE 4.           ~e ho1:1rs DAEC                                         3.7-14                         Amendment~

Main T1:1rbino Bypass System

3.7 PLANT SYSTEMS The Main T1:1rbine Bypass System The Main T1:1rbine Bypass System shall be OPERABLE Deleted LCO d.2.2, "Ml~HMUM CRITIC/>.L POVVER RATIO (MCPR)," limits for an inoperable Main T1:1rbine Bypass System, as speoiffod in the COLR, are made applisable. APPLICABILITY: T~ERMAL POVV~R ~ 21.7% RTP. ACTIONS CO~H;>ITIO~J ~~QUIReQ ACTION COMPL~TIO~J TIM~ A: Req1:1irements of the A:4 Satis~ the 2 ho1:1rs LCO not met. req1:1irements of the

                                                   ~
       ~     Req1:1ired Astion and        :4    Red1:1se T~~RM16,L         4 ho1:1rs assooiated Completion Time not met.

PO\O/~R to~ 21.n~

                                                   -RTP-:
                                                                                                 -r DAEC                                     3.7-16                           Amendment~

Spen_t Fuel Storage Pool Water Level 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Spent Fuel Storage Pool Water Level LCO 3.7.8 The spent fuel storage pool water level shall be~ 36 ft. -APPLICABILITY: During. movement of irradiated fueLassemblies in the spent fuel storage pool. ACTIONS CONDITION 'REQUIRED ACTION COMPLETION TIME A. Spent fuel storage A.1 ~ldT~ pool water level not LGO 3.0.~ is not within limit. applioaelo. Suspend movement of Immediately irradiated fuel assemblies in the spent fuel storage pool. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 t Verify the spent fuel storage pool water In accordance with level is ~ 36 ft. the Surveillance Frequency Control Program DAEC 3.7-18 Amendment~ -

CB/SBGT Instrument Air System

                                                                                    &.-7-:9 LCO 3.7.Q            Two CB/SBGT lnst11.1ment Air subsystems shall be OPeRABLE.

APPLICABILITY: MODES 1, 2, and a. , ACTIO~Ja CO~JDITIG~J ~eQl:ll~eD ,A,CTIO~J COMPLeTION TIMe 4- Ono CB/SBGT A:4 Deslaro required 4 hours from lnst11.1ment Air foature(s), su1313orted dissovery of subsystem by the ino13erable Condition A ino13erable. CB/SBGT lnst11.1ment Air eonour,=ent with subsystem, ino13erable ino13erabiliPl of 11,1hen the redundant redundant required required foature(s) fearure(s) are ino13erable. AN.Q

                             ~       ~estore the CB/SBGT        +eays lnst11.1ment Air subsystem to OPeRABL~

status. : Required Astion and :4 Be in MODe d. 12 hours

     ,Acssooiated Com13letion Time of     AN.Q Condition A not ma-                     ~       Be in MODe 4.               de hours
     ~

Both CBtSBGT lnst11.1ment Air subsystems ino13erable. DAEC 3.7-19 Amendment~

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 . .                       . : All '
        . I !.

AG Souroos OporatiAg

    /DELETED                                                                               &-&4-_,

3.8 ELECTRICAL PO'A'ER SYSTEMS d.8_.1 AG Souroos _OperatiAg LGO d.8.1 .Tho follo'NiAg AG elootrioal power sourses shall be OP_ERAB~E T\vo qualified oirsuits botwooR tho offsito traAsmissioA Aotwork aAd tho oAsite Glass 1 E AG Eleetrieal Power DistributioA System; aAd Two diesel geAorators (DGs). APPLICABILITY: MODES 1, 2; aAd 3. _Lc_o_3_.o_._:_~_.b_i_sA_ot_a...:.p..:..p_lio_a_b_1e_t_o_D_G_s_._-,------------------t GO~JDITIO~J REQUIRED ACTION GOMPLETIO~J TIME 0Ae offsite oirouit A4 PeRerm SR d.8.1.1 for 1 hour iAoperable. OPERABLE offsite oirouit.. ANQ* QAoe per 24 ff9HfS thereafter

Restore offsite oirouit Prior to eAteriAg to OPERABLE status. MODE 2 irom MODE 3-ef.4 (ooAtiAUOd)

                                                                   !Amendment          I
                                                                       .      ~

DAEC 3.8-1 . * . AMD 266 t-

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F 1:1nplann.o OF ci. a 0 a,,an t ~ tl=tat sa _ 1, this SR. . - - a loss of offsito ',OFifl*1 on an aot~ al.i1:1notion OF sim1:1latov1itl=t an aot1:1al OF ' '

I in sonJ
1*

powoF s1gna iniaaaon s1gna . sim1:1latoa EC~S . f ossonaal e1:1sos; ~abon o . . Qe 0A0f!l- *atial 8YS0S,

a. bea8 She88iag*treFA esse .

a, aR<ia1:1to start .fFom staa8By sea<liliea gG "' ""'* OROFgi2:0S. pOFITI as' aaeal~* e0aa0610<l +. loaas *IA 410 - SOGOR ' B eneFgi:z:os a1:1 t o as oonnooto~ in tl=to prnpoF1m t' oa ;i, eFAef!leAey lea . Se "l:IOROO, . O q ,,06 stea ay s-a--' t to "oltag ~. i..* aONIO, ~74 4\/ ana ~ 4576V, ~ l=tioves stoaa) Statey ana V ; W0Ejl:J0R6Y ,4.; ae 8 .a 1,g e~*. . ~ 09.51=12: an - : ' ootea ana

tly GORR

&:- 61:lpp I'IC 6nnostoa-OITIOFQORGy pOFITIBROR ' _loaas K>F . a1:1to oo ~ e min1:1tos. AITIORBITIORt 280 ) t

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_- 1 - . . - . cJi . qi ,.jj . ii cJj . . . i \. \ I .< 1*. - Refueling ~eiuipment lntorlosks !DELETED I &94 3.9 ~E:Ll~JG OPER/\TIO~JS 3.Q.1 Refueling E:eiuipment lnterlooks LCO 3.Q.1 Tt:ie refueling eeiuipment interlosks assooiated witt:i tt:ie Refuel position st:iall be OPERABLE. /\PPLIC/\BILITY: During in 11essol fuel movement witt:i eeiuipmont assooiatod witt:i tt:ie interlosks 1Nl:ion tt:io roaster mode switst:i is in tt:ie Rof1:10I position. ACTIO~Ja CO~JDITION REQUIRED ACTIO~J COMPLETION TIME: One or more roei1:1irod A4 S1:1spend in vessel Immediately rof:uoling oei1:1ipmont f1:10I RlO\IORlORt WitR intorlooks inoperable. oei1:1ipmont assosiatod 'Nitt:i tt:io inoperable intorlook(s). DAEC 3.9-1 Amendment~ .1:1Aew 'is1e4 pei l!E:1e1:1ew W:l IBAJ .pepee1 BffEjd j8FijBtl !84 PBJl:JABW OWEJ p1:1e 'popeo110Aj 'JS j W:IOJ:tEjd jOAjO~ .:..o. '1:1 -.:7 };IIA:1- o1dde:ie 1a omsed poioeJ10J 'P

AJ "'II 8 '

epeo110AJ ' 0 1 d d e 1 IBAJOM !.A ' E:IB jOAj W:l TT;rt:t:t:H:O~flt8Btt:ll I"' dl-+j~ QACl.l j"'O 'ti .:.S 1:10!.):!SOd W:IOJ:tBjd IOfliOM ~ 'l:l! _spoJ IIV .:.e 01:1 :~Ad1:1~1~~~e~o~~~~~- se +/-;3 110 ~;>< P8J!RB8J *6:1/81"' jS8lti8!RB8

,----+/--lv_N-0-=1+/-=3~t~:A,:.::l l. nOIIOJ mn JO 4000

+ ~tN--~=* *,t . :INNltt-1:') 1tH8JJ8d 3 3 tf\791137\~ AS \ - ' I -. . ~ - \ ' \ J \ \ I . . .* .* . . I :. . . 1 ill ill ~I . : I . .* . .: . .:I . I * { I I { I . . j 1 . .: I I ~ I *- . I .*_ . i \ \ } .. + i1 l!I

I I I

. 1' i <t ofi I I I ~ \I . .. i - <J; . . i I .-.-. _ i ~ . --+- .: I . \ . \ System Leakage anEI FlyElrostatis Testing Operation a.10.1 3.10 £::bE:::RATION~ a.10.1 System Leakage anEI l-lyElrostatio Testing Oporatio.n LGO a.10.1 The a1, 1erago roaotor ooolant ten,perat1:1ro sposi:f:ioEI in Teele 1.1 1 for MOD~ 4 may be ohangeEI fo "~U\," anEI operation sonsiEloreEI not to ea in MODE a; anEI the req1:1iron,on,ts of LCO a.4 .8, "RosiEl1:1al Float Removar(RI-IR) Sh1:1tElown Cooling System ColEI Sh1:1tElown," may ea s1:1sponEleEI, to allow reastor oo-olant ton,porai1:1ro > 212°i;:

l=or perforn,anso of a system leakage or hyElrostatio test,
As a sonseq1:1enoe of maintaining aEleq1:1ate pross1:1re for a system leakage or hyElrostatio test, -or
As a sonseq1:1enoe of maintain'ing aEleq1:1ate press1:1re for sontrol roEI saran, time testing initiates in sonj1:1nstion with a syston, loak~ge or hygrostatio test, proviEleEI. tho following MOD~ a LCOs are mot:

a:- LCO a.3.e.2, "SeoonElary Containment Isolation lnstR:Jmontation," l=Ynotions 1, 3, anEI 4 of Tasia a.a.e.2 1; a-:- LCO a.e.4.1, "SosonElary Containment'; &.- LCO a.e.4 .2, "SooonElary Containn,ont isolation ValvestDan,pors (SCIWDs)"; anEI 4 LCO a.e.4.a, "StanEley Gas Treatment (SBGT) System." APPLICABILITY: MODE 4 _'Nith average roaster ooolant tomporat1:1re ~ 212°1=. DAEC 3.10-1 Amendment -2e4 I ~~

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. . <t: . \ \ - ,11 - i ...* i Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The plant site, Which consists of approximately 500 acres, is adjacent to the Cedar River approximately 2.5 miles northeast of the Village of Palo, Iowa. Distanee freR1 the reaoter oenterline to the neare!,t site bmrnaary is appre>EiR1at0~ 2000 ff. The bounda_ry of the exclusion area defined in 10 CFR. 100 is delineated by the property lines. The distance to the outer boundary o.f the low population zone is 6 miles. The plan of the site is shown on* UFSAR Figures 1.2-1 and_ 1.2-2. * ~._D_e_le_ted _ _ _ __. 4.2 ~ G e r e 4.2.1 i;uel Ass0R1blies. The roaster shall oensist of net R1ere than ~e8 fuel ass0R1blies. Eaoh asseR1bly shall eonsist of a R1atruc of Ziroalley er ZIRLO fuel reas 'Nith an initial oeR1pesitien ef natural er sli§htly enriohea uraniuR1 aie>Eiao (U0 2 ) as fuel R1aterial, ana water reas. Lir;nitea substitution of zirooniuR1 alloy or stainless steel filler reas for f1::Jel roes, in aoooraanee 1nith approvea applioations_ of fuel roa oonfi§1::Jratiens, r:nay be 1::Jsea. r1::JOI ass0R1blies shall be 1iR1itea to these f1::Jel aesi§ns that have been ana~;z:ea with NRG staff appro11ea ooaes ana R10tJ:ieas ana have been *shoWfl by tests or analyses to 00R1ply with all *safe1:y aesi§n bases. A 1iR1itea nu_R1ber of leaa test asse.Rlblies tJ:iat have not eoR1pletea representatwe testin§ R1ay be plaooa in nenliR1itin§ aero re§ions. ~ Control Roa Ass0R1blies The (easter sere shall oentain SQ GR:Joi:foFFR shaJ3ea oontrol rea . ass0R1blies. The oontrol R1aterials shall be boron ~rbiao ana hafni1::JR1 R10tal, as aJ3J3revea by tho NRG. (continued) DAEC . 4.0-1 Amendment~- Design Features I 4.0 . 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
a. Fuel assemblies having the following limits for maximum k-infinity in the normal reactor core configuration at cold conditions and maximum lattice-average U-235 enrichment weight percent:
k-o'.) wt% , i) 7x7 and 8x8 pin arrays ~ 1.29 ~ 4.6 (Legacy Fuel Assemblies only; Holtec and PaR racks) ii) 1Ox10 pin arrays ~ 1.29 ~ 4.95 (Holtec and PaR racks)
b. ketr ~ 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in 9.1 of the UFSAR; and C. A nominal 6.060 inches for HOLTEC designed and 6.625 inches for PaR designed center to center distance between fuel assemblies placed in the storage d.
racks. The Boral neutron absorber shall have a 8 areal 10 density greater than or equal to 0.0162 grams 10 B/cm2 with an uncertainty of 0.0012 grams 10 B/cm 2 . t 4.3.1.2 Tho now fl:Jol stoFago Faoks are designed and shall be r:naiRkliRod v,1ith: . a:- !=1:101 assemblies havihg a maxim1:1m k infinity Of 1.31 in tho normal roaotor ooro oonfig1:1Fation at sold oonditions; ~ *err*~ O.Qe j:f 'R:tlly flooded with 1:1nb0Fatod water, whioh inol1:1des an allowanoe for 1:1noertaintios =as desoribed in Seotion Q.1 Of tho Ul=SAR; e,. *err~ O.QO j:f dry, whioh inol1:1dos an allowanoe for 1:1noertainties as desoribed in Sootion Q.1 oHhe UFSAR; aflG ' Ek A nominal 6.620 insh oentor to oenter distanoe betv.men fl:JOI assemblies 13laoed in storage raoks. (continued) DAEC 4.0-2 Amendment No. -2QQ. Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3.2 Drainage The spent fu*e1 storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 831 ft. - 2 3/4 in. 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2563 fuel assemblies in a vertical orientation, including no more than 152 fuel t assemblies stored in the cask pit in accordance with UFSAR Section 9.1. Tho ne'N fblel storage vabllt is eqblipped with rasks fur storage of blp to 110 fblel assernblios in a vortisal orientation. DAEC 4.0-3 Amendment~ Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The- plant m-anager sh-~11 be responsible for overall unit operation arid shall delegate in writing_the succession 'to this responsibility during his absence. The- plant manager or his designee shall approve, prior to implementation, each prop*osed test, experiment or modification to systems or equipment that affects nuclear safety. 5.1.2 The Operations Shift Manager shall be responsible for the control room command function. During any abseQce of the Operations Shift Manager from the control room while the unit is in MODE 1, 2, or 3, an . individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control *room command function. During any absence of the Operations Shift Manager from the control mom while the µnit is in MODE 4 or 5, an individual with an active SRO license or
Reactor Operator license shall be designed to assume the control room command function. -
DAEC 5.0-1 Amendment~ Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 .Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.
a. Lines of authority, responsibility, and communication shall be defined and e_stablished throughout highest management levels, intermediate levels, and all operating organization positions.
These relationships shall be documented and updated, as appropriate, in.organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions,for key personnel positions, or in equivalent forms of documentation. These requirements includin'g the plant specific titles. of those personnel fu,lfilling the responsibilities of the positions delineated in the Technical Specifications shall be documented in the UFSAR or QA Program Description; , b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant;
c. The corporate officer with direct responsibility for the plant shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures_.
(continued) DAEC 5.0-2 Amendment~ Organization 5.2 5.2 Organization (continued) 5.2.2 Unit Staff The unit staff organ.ization shall also include the following:
a. A non-licensed operator shall be assigned to the reactor when containing fuel and an additional non-licensed operator shall be assigned to the reactor when operating in MODES 1, 2, or 3.

b. Shift crew composition shall meet the requirements stipulated herein and in 10 CFR 50.54(m).

c. Shift crew composition may be, less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and .5.2.2.g for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.*

d. A person qualified to implement radiation protection procedures shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
e; Not used.
f. The Operations Manag.er or Operations Supervisors shall hold an

SRO license.
(continued) DAEC 5.0-3 Amendment~ Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
g. An individual shall provide advisory technical support to the unit operations shift crew in the areas of them1al hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. This function is not required in MODES 4 and 5.
DAEC 5.0-4 Amendment~ Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions in ANSI/ANS 3.1-1978. The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. 5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m). DAEC 5.0-5 Amendment~ Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures - 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:
a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and to NUREG-0737, Supplement 1, as stated in Generic Letter 82-33;

c. Quality assurance for effluent and environmental monitoring;

d. [Deleted]; and t

e. All programs specified in Specifications 5.5.
DAEC 5.0-6 Amendment~ Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS
5.5 Programs and Manuals
'The following programs shall be established, implemEinted and maintained. 5.5.1
Offsite Dose Assessment Manual (ODAM)

a. The ODAM shall contain the methodology and parameters used in the ca.lculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and
. liqu.id effluent monitoring alarm and trip setpoints, and in the conduct. of the radiological environmental monitoring program; and *
b. . The ODAM shall also contain the radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and Radioactive Material Release Report required by Specification 5.6.2 and Specification 5.6.3. *

c. Licensee initiated changes to the ODAM:

1. Shall be documented and records of reviews performed shall be. retained. This documentation shall . contain:

a. Sufficient information to support the change(s) t9gether with the appropriate analyses or evaluations justrfying the change(s), and

b. A determinatiop that the change(s) maintain the lev~ls of radioactive effluent control required by 10 GFR 20.1302, 40 CFR 1:90, 10 CFR 50.3oa, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations;

2. Sh~II become effective after the approval of the plant ~
manager; and .... I
3. Shall be submitted to the.NRG in the form of a complete, legible copy of the entire ODAM as a part of or.
concurrent with the Radioactive Material Release Report for the period of the report in which any change in the ODAM was made. Each change shall be identified by (continued) DAEC 5.0-7 .
Amendment No. 2~4
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1. Offsite Dose Assessment Manual (ODAM) (continued) markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and ye~r) the change was implemented. 5.5.2 Primary GoolaRt Soursos Outsise GoRtaiRmeRt *. ,-ID_e_le_t_ed _____ J TA is pro9ram 13rovisos GORtrols to miRimi:ce leaka90 from tA060 13ortiORS of systems outsise ooRtaiRmeRt tl:iat souls ooRtaiR Ai§Aly rasioaoUve fluiss suri119 a serious traRsioRt or aooiseRt to levels as l9w as 13raotioael0. TAe systems iRoluso Coro S13ray, l=li§A Pressure GoolaRt IRjeotioR, Resisual l=leat Removal, Reaotor Gore lsolatioR GooliR§, Reaotor 'Nater GloaRu13 (oRly to seooRs isolatioR .valve). - Post AooisoRt Sam13liR§ (uRtil susA time as a mosifioatioR elimiRates PASS as a 13oteRtial leaka9e 13atA), GoRtaiRmeRt Atmos13Aerio MoRitoriR§, GoRtrol Rod Drwe (soram sis0Aar9e volume *oRly) aRs Liquis Rasv,aste (oR~)' Roaster BuilsiR§ i;:1oor aRs Equi13m0Rt DraiR sum13 13um13s, 13i13iR§, aRd taRks u13 to aRs iRslusiR§ sollestor taRks). TAe 13re9ram sAall iRoluse tho followiR§: a-:- Pro*10Rfr:0 maiRteRaRoo aRs 13eriosio visual iRs130otioR requiromeRts; aM -Ir. System leak test requiromeRts for eaoA system at least oRoe 5.5.3 13er 24 moRtAs. TAo 13rovisi0Rs of SR ~.0.2 a.re a1313lioaelo. fDeletecij t (continued) DAEC 5.0-8 Amendment No. 258 Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.4 Radioactive Effluent Controls Program This program, conforming to 10 CFR 50.36a, provides for the control *of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as .low as reasonably achievable. The program shall be contained in the ODAM, .shall be implemented by procedures, and shall include remedial actions to be taken wheneve'r the program limits are exceeded. The program shall include the
following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODAM;

b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to unrestricted areas, con~orming to ten times (1 Ox) the concentrations listed in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 -20.2402;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and para.meters in the ODAM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODAM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatm_ent *systems to ensure that the appropriate portions of these systems which were used to establish compliance with the design objectives in 10 CFR 50, Appendix I, Section 11 be used when specified to provide reasonable

assurance that releases of radioactive material in liquid and

gaseous effluents be kept as low as reasonably achievable_;
(continued) DAEC 5.0-9 Amendment~ Programs and Manuals -5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
g. Limitations on the dose rate resulting from radioactive material
-released in gaseous effluents from the site to areas at or beyond l-the site boundary shall be limited to the following: 1
1. For noble gases: less than or equal to a dose rate of 500 mrem/yr to the whole body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and
+-
2. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half lives> 8 days: less than or equal to a dose rate of 1500 mrem/yr to any organ;

h. Limitations on th~ annual and quarterly air doses resulting from nobl~ gases released in gaseous effluents to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarte.rly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released*to areas beyond the site boundary, conforming to 10 J....
CFR 50, Appendix I; and . ~I
j. Limitations on the annual dose or dose commitment to any member* of the public, beyond the site boundary, due to releases --f of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the J> Radioactive Effluent Controls Program surveillance frequency. - I 6 . ~ 6 . 6 Gomsonont Gyolio or Transient Limit _ This program provides Qontrols tQ traok tho UFa/\R gootion 6.3.3, oyolio and transient oomuronoos to ons1:1ro that oompononts are maintained within - !Deleted _ tho design limits. - * (continued) DAEC 5.0-10 Gorrootod ey ~JRG Lotter dated Ootoeor 28, 2002 Amendment fl.kr. ,248, Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.6 DELETED (continued) DAEC 5.0-11 Amendment No. 300 Programs and Manuals Q.5 5.5 Programs and Manuals (continued) 5.5.7 Ventilation Filter Testing Prograrn (VFTP) * . IDeleted / A -~,egFam *Rall ~e esta~lisRe<i le im~lemeRI !Re fellewiRg re~"ireos in S13esifispJions p.6._7.a ans 5.5.7.13 sRall l:>o 13orfoFR1os onoo 13or 12 rnonths for stansl:>y sorviso, after 720 ROUFS of systorn 013oration, follmving signi:f:isant 13ainting, fire or GRornisal release . in any 1;ontilation :eono sornrnunisating witR tRe systorn, after any struotural rnaintonanoo on tho systorn Rousing, ans after oasR 13artial or oom13leto ro13laoernont of tRo I-IEP/\ filter train or GRarsoal assorbor, Fospocti¥oly. TRo test sosoril:>os in S1300ifisation 6.6.7.s sRall l:>o 13orfoFR1os onoe 13er 12 montR.s for stansl:>y servioe, after 720 Rours of systorn 013oration ans following signif:isant 13ainting, firo or oRornioal release in any ventilation
eono sornrnunisating wittl tho systorn.
TRe test sossril:><;>s in S13ooifioation 5*.6.7.s sRall l:>o 13orfoFR1os annuall-y. i;:or tRo SBGT Systorn only, tRo test sossril:>os in S~osifisation 6.6.7.o sRall { ea 13orfoFR1os after oaeR sorn13loto or 13artial ro13laoorno_nt of tRo ~ePA filter sank ans after any strustural rnaintonanoo on tRo systorn Rousin_g. For tRo SBGT Systorn only, tRe test sesoril:>es in S13ooifioation 6.5.7.f .+--' sRall l:>o 13orforrnos in oonjunstion v1itR tRo tests sossril:>es in S13esifisation 6.5.7.G. a... Dernonstrate for eaeR of tRe ESF systerns tRat an in13laoo tes_t of tRe f:clePA filters sRows a 13enetration ans systern l:>y13ass at tRe value s13esifies ans at-tRe systorn flowrate s13eeifies l:>elmu: eSi;: Ventilation Systqrn Penetration Flowrate (sm,) ans Systern By13a!,s (%) . . SBGT Systern ~ Q.;.1. 3600 4400 si;:u Systern ~+.Q QOO 1100 (continued) DAEC 5.0-12 Amendment.~Jo. 286 Programs and Manuals 5.5 5.5 Programs and Manuals ~ Ventilation F'ilter Testing Program NF'TP) (sontinuod) &. Demonstrate for oaoh of tho ESF' systems that an in13laoo test of tho oharooal adsorbor shows a 13onotration and system 13y13ass at tho lfaluo s13osified and at the system flowrato s13ooifiod 13olmn: ESF Ventilation- System Penetration r"lowrato (sfm) and System By13ass (%) SBGT System ~Q..,4 ~eOO 4400 SFU gystom ~ 4..,.Q QOO 1100 &:- Demonstrate for_ oaoh of tho ESF systems that a lal3oratory test of a sam13le of the oharooal adsorbor, v,hon ol3tainod as dosoril3od in Ro§ulatory Guido 1.62 Rolfision 2, shows tho methyl iodide 13onetration less than tho. 11aluo s13ooifiod 13olow when tested in assordanso with AgTM 03803 1Q8Q at a tom13oraturo of 30°G and tho rolatilfo humidity s13osified 13olow: ESF' Ventilation System Penetration RolatFVe Flumidity ~s-EIB..... Gt-tT-,S~~ff,<Srt1tO,ttm------<-t,0,.,;.6cf,"~ffi1e SF'U System < 6.0~1e ~ ' + 4:- Demonstrate for oash of tho Esi; systems that the 13rossuro dro13 aoross tho ooml3inod l=-IEPA filters, tho 13rofiltors (SBGT System only), and tho sharsoal aelsorbors is less than the 1/aluo s13osifiod 13elow and at tho system flowrato s13osifioel as follows: (continued) DAEC 5.0-13 Amendment No. 286 Programs and Manuals 5.5 5.5 Programs and Manuals * ~ Ventilation l=ilter Testing-Program NFTP) (sontinuod) ESI= Ventilation System Delta P (inotms wg) rlowrato (Offfl) SBGT System. 3600 4400 Sl=U System 900 1100 e-:- Demonstrate tAat air distrieution is uniform 'Nithin 20% of - averaged flow- per unit ao*ross eBGT System HEP/\ filters. t Visually inspost tile SBGT System oAarooal adsoreor to ensure no { .flow eloskago Aas ossurrod. TAO provisions of SR d.0.2 and SR d.0.a are_ applioaelo to tAo VFTP test froetuonoios. 5.5.8 E*Plosivo Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially o*plosila'e gas mi*1uros sontainod in tAo Offgas System downstream of tAe reoomeiners and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. The liquid radwaste quantities shall be detem,ined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures". The program shall include.;. TAo limits for sonoontrations of Aydrogen in tAe Offgas System downstream of tAo rooomeinors and a survoillanQO program to_ ensure tAo limits *are maintained. SuoA limits sAall so appropriate to tAo system's design sriteria (i.e., wAetAer or not tAo system is designed to witAstand a Aydrogen e*plosi9n); (continued) DAEC 5.0-14 Amendment No. 285 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8. ~plosi¥o Gas aRd Storage Tank Radioactivity Monitoring Program (continued) e,. A urveillance program to ens*ure that the quantity of radioactivity contained in all outdoQr liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holdi_ng the tanks' contents an_d that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System
is ~ 50 curies, excluding tritium and dissolved or entrained noble gases. The liquid radwaste storage tanks in the Low-Level Radwaste Processing and Storage Facility are considered unprotected outdoor tanks.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the ~xplosi\'o Gas aRd Storage Tank Radioactivity Monitoring Program surveillance freque~Deleted - . _ I 5.5.9 ~ I TostiRg Progi=am A diesel fuel oil tostiRg program to implomoRt roquiFod tostiRg of both RO'N fuel oil aRd storod fuel oil shall be established. Tho pFogi=am shall iRoludo s_ampliRg aRd tostiRg FequiFomeRts, aRd aoooptaRoe oriteFia, all iR aoooFdaRoe with applioable /\aTM StaRdaFds. Tho puFpose of the pmgi=am is to establish tho follov.iiRg: a:- Aooeptability of Row fuel oil for use pFioF to add.itioR to stoFage -
taRks by detoFR1iRiRg that tho fuel oil has:
4-: AR API gi=a\'ity i.vithiR limits, ~ A \'isoosity withiR limits foF ASTM 2 D fuel oil, aRd ~ 'NateF aRd sedimimt within limits; - a-:- . Visoosity, watoF. aRd sodimoRt foF stornd ASTM 2 D fuel oil am \ \1RRiR limits O\'OI)' 31 days; aRd e,. Total partioulato ooRooRtFatioR of tho stomd fl:lol oil is ~-10 mg.£1 whoR tested e11ory 92 days. Tho provisioRs of SR a.0.2 crnd SR a.a.a aFO applioablo to tho Diesel i;uol I__.... Oil TostiRg Progi=am TostiRg i;roeiuoRoios. 1-* (ooRtiRUOd) DAEC 5.0-15 Amendment -Ne-: -2d4 . Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.1.0 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.
a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
-t-
1. A change in the TS incorporated in the license; or

2. . A change to the UFSAR or Bases that requires NRC v approval pursuant to 10 CFR 50.59. '1

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d. Proposed changes that meet the criteria of Specification 5.5.10b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e) ..
.5.5~11. s.af.ow F~mstion Determination Proaram (Sr"DP) _* _ _ ___,____ . ~ Tl=tis pro9R3m ensures loss of saf.oty funotion is detested and appropriate !Deleted
aotions taken. Upon entry into LGO d.0.6, an evaluation sl=tall be made to determine if loss of safoiy funstion e>Eists. /\ddit.ionally, otl=ter .
appropriate limitat.ions and remedial or oompensatory aotions may be identified to be taken as a result of tl=te support system inop.eR3bility and oorrespondina e>Esopt.ion to entorina supported system Condition and . Required Astions. Tl=tis pro9R3m implements tl=te requirements of LGO ~ a:- Tl=te SFDP sl=tall oentain tl=te followina: ' . 4-:- P_ro 11isions for oross. di11ision sl=tosks fo ensure a loss of tl=te oapability to perform tl=te safety,funstion assumed in tl=te aosidont analysis does not 90 undoteotod; (continued) DAEC s.o.:.1s Amendment No. 241 . Programs and Manuals 5.5 5.5 Programs.and Manuals 0.0.11 Safety i;unotion Determination PFogFam (SFDP) (continued) Prnvisions feF ensuFing t~Q 1:>lant is maintained_ in a safe eondition if a loss of funotion oondition exists; . Prnvisions to ensuF.0 that an inoJ:>erable SUJ:>J:>Orted system's ComJ:)letio*n Time is not inaJ:>J:)Fo13Fiately extended as a rnsult of multi1:>le SUJ:>J:>Ort system inoJ:)embilities; and OtheF aJ:)J:>FOJ:>Fiate limitations and rnmedial OF oomJ:>ensatol)' aotions. 5~5e;: loss of safety funetion may exist 1Nhen a SUJ:>J:>Ort system is inoJ:)erable, and: /\ FequiF0d system r:edundant to system(s) SUJ:>J:)Ortod by tho inoJ:)erablo SUJ:)J:)Ort systeFR is also inOJ:)OFablo; OF /\ rnquiFod system Fodundant to SUJ:>J:>Ort systom(s) feF tho SUJ:>J:)Orted systems (1) and (2) above is also inoJ:)erable. The si;op identifies 1.vhorn a loss of safety funotion exists. If a loss
~:=~~==::i=~::i~~~!!::r:~Tabt>whioh Deleted the loss of safety funotion exists arn FOquiFed to be ontOFod. \!\'hen a loss of safety funstion_ is oausod by the moJ:>eFabilify of a single .
!:;=i~$!t:::To6~=~:= 1:ri::~=~=~ions 5.5.12 PFimapt Containment Leakage Rate Testing PFogram a-,. A J:>FOgFam shall be established to imJ:)lomont tho leakage Fate testing oHho J:>FiFRal)' sontainmont as mquiFOd by 10 CFR e0.e4 (o) and 10 ci;R eO, AJ:>J:>OndFM J, 01:>tion B, as modified by aJ:)J:>F0'1od oxomJ:)tions .. This J:)FOgram shall be in aooOFdanoe w-ith tho guidelines sontainod in ~lfil Q4 01', Revision 3 /\, "lndustl)' Guideline feF lmJ:)lomonting - PoFformanoo Based 01:>tion of 10. ci;R eO, ApJ:>ond0< J," and sonditions and limitations s,aeoified in Nfil Q4 01, Revision 2 A, as modified by tho fellmNing exGeJ:)tlons: DfilfiT~D (continued) DAEC 5.0-17 Amendment No. 2Q6 Programs and Manuals 5.5 5.5 Programs and Manuals 6.6.12 Primary Containment Leakage Rate Testing* Program (sontinued) * ~ exemption fFom Seotion Ill.A of 1O CrR Part 60, Append~ cl, Option B, to allow the oontribution H=Om Main Stean:i pathway leakage to be exoluded from tho OVOFall integi=atod leakage rate fFom Ty.po A tests. ~ Exemption fFOm Sostion 11.B of 10 Cr"R Part 60, Appendix cl, Option B, to allo1N the eontribution fFOm Main StFOam pathway leakage to be oxo!uded fFOm tho sum of tho leakage rates fFOm Typo B and Typo C ,test&: The peak oaloulated sontainmont internal pFossuFO foF tf:lo ~osign basis loss of o_oolant aooidont, Pa, is 46.7 psig. t Tho mtHEimum allm.\'ablo primary oontainmont leakage Fate, La, at Pa, shall be 2.0~~ of primary containment aiF*woight poF day. + Leakage Rato *asseptanoe oritoria aFO: +-* 4,. PFimary Containment leakage Fate aooeptanso sritorion is~ 1.0 La. During tho fiFSt startup fellowing testing in assoFdanoo ¥Jith this t pFo~ram, tf:lo leakage rate asseptanoo oritoria are: ~ O.eO La foF tl:\o Typo B and Typo* C tests; and, ~ Q.7e La foF tho Typ_e A *test~; and ~* Tho aiF losk testing aosoptanoo oFiterion is ovoi=all aiF losk leakage -Fate~ 0.05 La 1Nhen tested at~~ Tho provisions of SR a.a.a arn applioablo to tho PFimary* Containment Leakage Rate Testing PFOgFriFR. *
5.5.13 Deleted * . I safely undOF noFmal sondit.i_ons and maintain it in* a safe sondition following a_
Fadiologisal event, h~ar=dous shon:iioal Feloaso, OF a smoke GRallonge. Tho progmm. shall onsuFO that adoEtuato mdiation pFOtostion is pFO'lided to porrnit aooess and oosupansy of tho CBe under design basis assidont (DBA) oonditions e without personnel rnooiving mdiation oxposuFos in oxooss of rem total offosUvo dose OEtUivalont (Te De) ~r tho duration of tho aooidont. The progFam shall inoludo tho following, elements: a-: Tho definition of tho CBe and the CBE boundary. RoEtUiFOments feF maintaining the CBe boundal)' io its design _sondition insluding sonfiguration oontFol and pFevonti¥e maintonanoe. * (oontinuod) DAEC 5.0-18' Amendment No. 270 Programs and Manuals 5.5 5.5 Programs and Manuals e,i'.1 d Control Building En 1.ioloao l-labitability Program (sontinued) * &. Roeiui.FO_ments for (i) d.otormining tho unfiltered air inleakago past tho CBE boundary into tho CBE in aooordanoo 1Nith tho tasting methods an~ at tho r;roeiuonsios spesifiod in Sootions C.1 and C.2 of Regulatory Guido 1.tQ7, "Demonstrating Control Room envelope Integrity at Nuoloar Po*Nor Reaotors," Revision 0, May 200a, and (ii) assessing CB~ habitability at tho t=reeiuonoios spooifiod in Sostions C.1 and C.2 of Regulatory Guido 1.197,* Revision 0.
Measurement, at designated losations, of tho CBe pressure relative to all oxfomal aFOas adjaoont to tho GBe boundary during tho prossuri2:ation mode of operation by one subsystem of tho FU a System, operating at the flow rate roeiuiFOd by tho VFTP, at a FFOeiuonsy of 24 months on a StaggoFOd Test Basis . ThE? results shall be *trended and used as part of tho 24 month assessment of tho GBe boundary.
Tho eiuantitativo limits on unfiltered air inloakago into tho GBE Those limits shall be stated in a manner to allm,.. diFOst somparison to tho unfiltered air inloakago measured ~Y tho testing dossribod. in paragraph o. The unfiltered air inloakago limit for radiologisal ohallongos is tho inloakage flmv rate assumed in tho lioonsing basis analyses of OBA oonsoeiuonoos. Unfiltered air leakage limits for ha2:ardous ohomioals must ensure that tho O*JJOSUFO *of CBe osoupants to those h~rds will be within the assumption_s in tho lioonsing basis. Tho pre1.'isions of SR d.0.2 aFO applioablo to tho i;'roeiuenoies for assessing CBE habitabilii)*, determining GBE unfiltoFOd inloakago, and measuring CBe pressure and assessing tho CBE boundary as
roeiuiFOd by paragraphs o and d, rospooti 1.ioly. *
(continued) ... A St8!iJf:1eF0El Test Basis shall sonsist of ttrn testinf:1 ef one ef tho systoR'ls, subsystoR'ls, ehannols, or other ElosifjnatoEl eom13ononts Elurinf:1 tho interval s13oeifi0El by tho SuF¥01llaneo Froeiuoney, so that all systems, subsystems, shannols, or other ElosifjnatoEl s0Fl'l13ononts aF0 tostoEl Elurinf:1 n auNoillaneo FF0eiuonsy intoNals, wi=10F0 R is.tho total nuR'lber of systoR'ls, subsystoR'ls, ehannols, or othor-~osifjnatoEl s0Fl'l13ononts In tho asso01ateEl funstion. t DAEC 5.0-1 Ba Amendment~ Programs and Manuals 5.5 5.5 Programs. and Manuals 5.5.14 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performec::I at intervals sufficient to assure the associated Limiting .Conditions for Operation are met.
a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency* is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the. Frequencies established in the Surveillance Frequency Control Program.
5.5.15 Spent Fuel Pool Neutron Absorber Monitoring Program This program provides routine monitoring and actions to ensure that the
condition of Boral in the spent fuel pool racks is appropriately monitored to ensure that the Boral neutron attenuation capability described in the criticality safety analysis of UFSAR Section 9.1 is maintained. The program shall include the following: .

a. Neutron attenuation in situ testing for the PaR racks shall be performed at a frequency of not more than 10 years, or more frequently based on observed trends or calculated projections of Boral degradation. The acceptance criterion for minimum Boral areal density will be that value assumed in the criticality safety analysis. _

b. Neutron attenuation testing.of a representative Boral coupon for the Holtec racks shall be performed at a frequency of not more than 6 years, or more frequently based on observed trends or calculated projections of Boral degradation. The acceptance criterion for minimum Boral density will be that value assumed in the criticality safety analysis.

c. Description of appropriate corrective actions for discovery on nonconforming Bora!. _
DAEC 5.0-18b Amendment -2QQ Reporting Requirements 5.6 .5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be s*ubmitted.in accordance with 10 CFR 50.4. 5.6.1 DELETED t 5.6.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include . summaries, interpretations,* and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Assessment Manual (ODAM), and in 10 CFR 50, Appendix I,* Sections*IV.B.2, IV.B.3, and IV.C.
The Annual Radiological Environmental Operating Report shall include the results of analys~s of all radiological environmental samples* and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODAM, as well as.summarized and.tabulated results of these analyses and measurements in the format of the table in Regulatory Guide 4.8.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons .for the missing results. The missing data shall be submitted in a supplementary report as soon as,poss.ible. J (continued) DAEC 5.0-19 Amendment No. 2ae Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.3 Radioactive Material Release Report The Radioactive Material Release Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODAM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1. 5.6.4 DELETED 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. The Average Planar Linear Heat Generation Rate (APLHGR) for Specification 3.2.1;

2. The Minimum Critical Power Ratio (MCPR) for Specification I_,,,
3.2.2; 1
3. Exclusion Region in the Power/Flow Map for Specification t
3.4.1; and
4. The Minimum Critical Power Ratios (MCPR) in Table 3.3.2.1-1 for Specification 3.3.2.1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A, (GESTAR II). The revision number is the one approved at the time the reload fuel analyses are performed.
(continued) DAEC 5.0-20 Amendment No. d0d Reporting Requirements 5.6 _5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
~ !DELETED t- d. The C(?LR, including any midcycle revisions or supple-ments, shall be provided upon issuance for each reload cycle to the NRC. 5.6.6 - PAM Report VVhoR a report is roquiroEI 13y CoRElitioR B or. i;: of LCO 3.3.3.1,. "Post AooiEloR_t MoRitoriRg (PAM) IRstrulfloRtatioR," a roport st:iall 130 sul31flittoet i.Nitl:iiR tt:io follo'lliRg 14 Elays. Tt:io report st:iall outline tho proplaRRoEI altolflato lflothoEl(s) of lflOriitoriRg, ElespriQo tho Elogroo tQ 'IIRioR tt:io altomato lflott:ioEl(s) are oquivaloRt to tt:io iRstalloEI PAM sl:iaRRels, justify tt:ie areas iR wt:iiot:i tt:ioy aro Rot oqui¥aloRt, tt:i-e eause of tt:io iRoporal3ility, aREI tJ:lo plaRs aREI sot:ieElulo for rostoriRg tt:io
iRst11:JlflORtatioR sl:iaRRols of tho FURstioR to OPERABLE status.
-5.6.7 Reactor Coolant Syste-m (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
a. RCS pressure and temperature limits for heat up, cooJdown, low temperature operation*, criticality, and hydrostatic testing as well as heatup*and cooldown rates shall be established and documented in the PTLR for the following:
i) Limiting Conditions for Operation Section 3.4.9, "RCS Pressure and Temperature (Pff) Limits" ii) Surveillan_ce Requirements Section 3.4.9, "RCS Pressure and Temperature *(Pff) Limits" -
b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:
DAEC 5.0-21 Amendment~ R~porting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued) i) SIR-05-044-A, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," Revision 1, dated June 2013.
c. The PTLR shall be proviqed to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.
DAEC 5.0-21a Amendment~ High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area-As provided in paragraph 20.1601(c) of 10 CFR P-art 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20: - 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation a.. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that inclµdes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requi~ement for'an RWP or equivalent while performing their assigned duties-provided that they are otheiwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously displays radiation dose rates in the area; or

2. A radiation monitoring device that continuously transmits dose rates in the area and alarms when the device's dpse alarm setpoint is-.reached, with an appropriate alarm _
setpoint, or
3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information- to a remote receiver monitored by radiation protection personnel re*sponsible for controlling personnel radiation exposure within the area, or

4. A self-reading dosimeter (e.g., 'pocket ionization chamber or electronic dosimeter) and, (continued)
DAEC 5.0-22 Amendment No. 248 High Radiation Area 5.7 5.7 High Radiation Area (continued) (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area,* of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have' been detem1ined and entry personnel are knowledgeable of them. These
. continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate detem1ination, knowledge, and pre-job briefing does not require documentation prior to initial entry. 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation
a. Each entryway to such an area*shall be conspicuously posted as a high radiation area and shall be provided ,with a locked or continuously guarded door or gate that prevents unauthorized entry, and, h addition:

1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee.

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.
(continued) DAEC 5.0-23 Amendment No. 248 High Radiation Area 5.7 5.7 High Radiation Area (continued)
b. Access to, and ac;;tivities in, each area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures. , * *

c. Individuals qualified in radiation *protection procedures may be exempted from the requirement for an RWP .or equivalent while performing radiation surveys in such areas provided that they are otheiwise following plant radiation protection procedures for entry to, exit-from, and work in such areas.

d. Each individua_l or group entering such an area shall possess: ,

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached with an appropriate alarm setpoint, or

2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection. p*ersonnel responsible for controlling personnel radiation exposu_re within the area with the means to communicate with and control every individual in the area, or
,3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as speGified in .the RWP or equivalent, while in the area, -by means of closed circuit television, or personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure.in the area, and with the means to communicate with and control every individual in the area. (continued) ' \ DAEC 5.0-24 Amendment No. 248 CorF0otea by ~JRC Lotter aatoa Ootober 28, 2002 High Radiation Area 5.7 5.7 High Radiation Area (continued)
4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area. -

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to

entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably_be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible light shall be activated at the area as a warning device.
DAEC 5.0-25 Amendment No. 248 Duane Arnold Energy Center Docket No. 50-331 License Amendment Request NG-19-0102 Enclosure, Attachment 1 Page 1 of 55 ATIACHMENT2 REVISED TECHNICAL SPECIFICATION PAGES (CLEAN, WITH PROPOSED CHANGES) NEXTERA ENERGY DUANE ARNOLD, LLC CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET 50-331 DUANE ARNOLD ENERGY CENTER RENEWED FACILITY LICENSE Renewed License No. DPR-49
1. The Nuclear Regulatory Commission (the Commission) having found that:
A. The application for license filed by FPL Energy Duane Arnold, LLC,
Central Iowa Power Cooperative and Com Belt Power Cooperative (the licensees) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made; B Deleted; C. The facility will be maintained in conformity with the application, as amended; the provisions of the Act; and the rules and regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this renewed license can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; E. NextEra Energy Duane Arnold, LLC is technically qualified and NextEra Energy Duane Arnold, LLC, Central Iowa Power Cooperative and Com Belt Power Cooperative are financially qualified to engage in the activities authorized by this renewed license in accordance with the rules and regulations of the Commission; F. The licensees have satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G. The issuance of this renewed license will not be inimical to the common defense and security or to the health and safety of the public; H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of renewed Facility License No. DPR-49 is in accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirements of said Appendix D have been satisfied;
on April 16, 2009, the name "FPL Energy Duane Arnold, LLC" was changed to "NextEra Energy Duane Arnold, LLC."
Renewed License No. DPR-49 Amendment I. Deleted.
2. Renewed Facility License No. DPR-49 is hereby issued to NextEra Energy Duane Arnold, LLC, Central Iowa Power Cooperative (CIPCO) and Com Belt Power Cooperative (Com Belt) to read as follows:
A. This renewed license applies to the Duane Arnold Energy Center, a permanently defueled boiling water reactor and associated equipment (the facility), owned by NextEra Energy Duane Arnold, LLC, Central Iowa Power Cooperative and Com Belt Power Cooperative and operated by NextEra Energy Duane Arnold, LLC. The facility is located on NextEra Energy Duane Arnold, LLC's, Central Iowa Power Cooperative's and Com Belt Power Cooperative's site near Palo in Linn County, Iowa. This site consists of approximately 500 acres adjacent to the Cedar River and is described in the "Final Safety Analysis Report" as supplemented and amended (Amendments 1 through 14) and the Environmental Report as supplemented and amended (Supplements 1 through 5). B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses: (1) NextEra Energy Duane Arnold, LLC, pursuant to Section104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities/ to possess and use the facility as required for nuclear fuel storage; and CIPCO and Com Belt to possess the facility at the designated location in Linn County, Iowa, in accordance with the procedures and limitations set forth in this license; (2) NextEra Energy Duane Arnold, LLC, pursuant to the Act and 10 CFR Part 70, to possess at any time special nuclear material that was used as reactor fuel, in accordance with the limitations for storage, as described in the Updated Final Safety Analysis Report, as supplemented and amended as of June 1992 and as supplemented by letters dated March 26, 1993, and November 17, 2000. (3) NextEra Energy Duane Arnold, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source or sealed sources for radiation monitoring equipment calibration, and to possess any byproduct, source and special nuclear material as sealed neutron sources previously used for reactor startup or reactor instrumentation; and fission detectors; (4) NextEra Energy Duane Arnold, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated radioactive apparatus components; (5) NextEra Energy Duane Arnold, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear materials that were produced by the operation of the facility. Renewed License No. DPR-49 Amendment C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I; Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Deleted (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. , are hereby incorporated in the license. NextEra Energy Duane Arnold, LLC shall maintain the facility in accordance with the Permanently Defueled Technical Specifications. (3) Fire Protection Program NextEra Energy Duane Arnold, LLC shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated August 5, 2011 (and supplements dated October 14, 2011, April 23, 2012, May 23, 2012, July 9, 2012, October 15, 2012, January 11, 2013, February 12, 2013, March 6, 2013, May 1, 2013, May 29, 2013, two supplements dated July 2, 2013, and supplements dated August 5, 2013 and August 28, 2013) and as approved in the safety evaluation report dated September 10, 2013. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied. Renewed License No. DPR-49 Amendment
Fire Alarm and Detection Systems (Section 3.8);

Automatic and Manual Water-Based Fire Suppression Systems (Section 3.9);

Gaseous Fire Suppression Systems (Section 3.10); and,

Passive Fire Protection Features (Section 3.11 ).
This License Condition does not apply to any demonstration of equivalency under Section 1. 7 of NFPA 805.
2. Fire Protection Program Changes that Have No More than Minimal Risk Impact Prior NRG review and approval are not required for changes to the licensee's fire protection program that have been demonstrated to have no more than a minimal risk impact. The licensee may use its screening process as approved in the NRG safety evaluation report dated September 10, 2013 to determine that certain fire protection program changes meet the minimal criterion. The licensee shall ensure that fire protection defense-in-depth and safety margins are maintained when changes are made to the fire protection program.
Transition License Conditions J (1) Before achieving full compliance with 10 CFR 50.48(c), as specified by (2) and (3) below, risk-informed changes to the licensee's fire protection program may not be made without prior NRG review and approval unless the change has been demonstrated to have no more than a minimal risk impact, as described in (2) above. (2) The licensee shall implement the modifications to its facility, as described in Enclosure 2, Attachment S, Table S-1, "Plant modifications Committed," of DAEC letter NG-13-0287, dated July 2, 2013, to complete the transition to full compliance with 10 CFR 50.48(c) by December 31, 2014. The licensee shall maintain appropriate compensatory measures in place until completion of these modifications. (3) The licensee shall implement the items listed in Enclosure 2, Attachment S, Table S-2, "Implementation Items," of DAEC letter NG-13-0287, dated July 2, 2013, by March 9, 2014. (4) Deleted. (5) Physical Protection NextEra Energy Duane Arnold, LLC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, Renewed License No. DPR-49 Amendment (11) Deleted. (12) Deleted. (13) Deleted. D. This license is effective as of the date of Issuance and is effective untll the Commission notifies the licensee in writing that the license Is terminated. FOR THE NUCLEAR REGULATORY COMMISSION Original signed by Eric J. Leeds Eric J. Leeds, Director Office of Nuclear Reactor Regulation
Enclosures:

1 Appendix A Technical Speclftcat1ons 2 Appendix B Additional Conditions Date of Issuance: December 16, 2010 Renewed License No. DPR-49 Amendment
APPENDIX B ADDITIONAL CONDITIONS LICENSE NO. DPR-49 NextEra Energy Duane Arnold, LLC (the term licensee in Appendix B refers to NextEra Energy Duane Arnold, LLC or prior license holders) shall comply with the following conditions on the schedule noted below: Amendment Number Additional Conditions Implementation Date 223 NextEra Energy Duane Arnold, LLC is This amendment is 275 authorized to relocate certain effective immediately requirements included in Appendix and shall be implemented A to licensee-controlled documents. within 180 days of the date Implementation of this amendment of this amendment. shall include the relocation of these requirements to the appropriate documents, as described in the licensee's application dated October 30, 1996, as supplemented and consolidated in its March 31, 1998, submittal. These relocations were evaluated in the NRC staffs Safety Evaluation enclosed with this amendment. 260 (1) NextEra Energy Duane Arnold shall take all This amendment is 275 necessary steps to ensure that the external trust effective immediately fund is established at the time of the closing of and shall be implemented the transfer of the license from Interstate Power within 30 days of the date (IPL) to FPLE Duane Arnold is maintained in of this amendment. accordance with the requirements of the December 23, 2005 order approving the license transfer, NRC regulations, and consistent with the safety evaluation supporting the order. The trust agreement shall be in a form acceptable to the NRC. 260 (2) DELETED 279 260 (3) DELETED Amendment
Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

-----NOTE The defined tenns of this section appear in capitalized type and are applicable throughout these Technical Specmcations and Bases.

Definition ACTIONS ACTIONS shall be that part of a Specrfication that prescribes Required Actions to be taken under designated Conditions within specrfied Completion Times. DAEC 1.1-1 Amendment
1.0 USE AND APPLICATION 1.2 DELETED DAEC 1.2-1 Amendment
Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use. BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for safely maintaining the facility. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times(s). DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the facility is in a specrfied condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the ~acility is not within the LCO Applicability. IMMEDIATE When "Immediately is used as a Completion Time, the Required COMPLETION Action should be pursued without delay and in a controlled TIME manner. DAEC 1.3-1 Amendment
Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements. DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR. The "specified Frequency" consists of the requirements of the Frequency column_ of each SR, as well as certain Notes in the Surveillance column that modrfy performance requirements. The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria. (continued) DAEC 1.4-1 Amendment
Frequency 1.4 1.4 Frequency (continued) EXAMPLE The following example illustrates the manner in which Frequencies are specified. EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perfonn CHANNEL CHECK. 12 hours Example 1.4-1 contains the type of SR most often encountered in the Technical Specrfications (TS). The Frequency specifies an interval (12 hours) during which the associated Surveillance must be perfonned at least one time. Perfonnance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours, an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the facility is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the facility is in a specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified, then SR 3.0.3 becomes applicable. ) DAEC 1.4-2 Amendment
2.0 DELETED DAEC 2.0-1 Amendment
LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the specified conditions in the Applicability, except as provided in LCO 3.0.2. LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met. LCO 3.0.3 Deleted. LCO 3.0.4 Deleted. LCO 3.0.5 Deleted. LCO 3.0.6 Deleted. LCO 3.0.7 Deleted. LCO 3.0.8 Deleted. LCO 3.0.9 Deleted. DAEC 3.0-1 Amendment
SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. For Frequencies specified as "once," the above interval extension does not apply. SR 3.0.3 If rt is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified Frequency, whichever is greater. This delay period is permrtted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed. If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered. When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered. (continued) DAEC 3.0-2 Amendment
SR Applicability 3.0 3.0 SR APPLICABILITY (continued) SR 3.0.4 Entry into a spectfied condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with ACTIONS. DAEC 3.0-3 Amendment
3.1 DELETED DAEC 3.1-1 Amendment
3.2 DELETED DAEC 3.2-1 Amendment
3.3 DELETED DAEC 3.3-1 Amendment
3.4 DELETED DAEC 3.4-1 Amendment
3.5 DELETED DAEC 3.5-1 Amendment
3.6 DELETED DAEC 3.6-1 Amendment

3. 7 PLANT SYSTEMS 3.7.1 Deleted DAEC 3.7-1 Amendment

3.7 PLANT SYSTEMS 3.7.2 Deleted DAEC 3.7-2 Amendment

3. 7 PLANT SYSTEMS 3.7.3 Deleted DAEC 3.7-3 Amendment

3. 7 PLANT SYSTEMS 3.7.4 Deleted DAEC 3.7-4 Amendment

3. 7 PLANT SYSTEMS 3.7.5 Deleted DAEC 3.7-5 Amendment

3.7 PLANT SYSTEMS 3.7.6 Deleted DAEC 3.7-6 Amendment
3.7 PLANT SYSTEMS 3.7.7 Deleted DAEC 3.7-7 Amendment
Spent Fuel Storage Pool Water Level 3.7.8

3. 7 PLANT SYSTEMS 3.7.8 Spent Fuel Storage Pool Water Level LCO 3.7.8 The spent fuel storage pool water level shall be 2:: 36 ft.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel storage pool. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage A.1 Suspend movement of Immediately pool water level not irradiated fuel within limrt. assemblies in the spent fuel storage pool. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify the spent fuel storage pool water In accordance with level is ~ 36 ft. the Surveillance Frequency Control Program DAEC 3.7-8 Amendment

3. 7 PLANT SYSTEMS 3.7.9 Deleted DAEC 3.7-9 Amendment

3.8 DELETED DAEC 3.8-1 Amendment
3.9 DELETED DAEC 3.9-1 Amendment
3.10 DELETED DAEC 3.10-1 Amendment
Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The plant site, which consists of approximately 500 acres, is adjacent to the Cedar River approximately 2.5 miles northeast of the Village of Palo, Iowa. The boundary of the exclusion area defined in 10 CFR 100 is delineated by the property lines. The distance to the outer boundary of the low population zone is 6 miles. The plan of the site is shown on UFSAR Figures 1.2-1 and 1.2-2. 4.2 Deleted 4.3 Fuel Storage 4.3.1 Criticality The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having the following limits for maximum k-infinity in the nom,al reactor core configuration at cold conditions and maximum lattice-average U-235 enrichment weight percent:

k-oo wt% i) 7x7 and 8x8 pin arrays ~ 1.29 ~ 4.6 (Legacy Fuel Assemblies only; Holtec and PaR racks) ii) 1Ox10 pin arrays ::; 1.29 ::; 4.95 (Holtec and PaR racks)

b. keff ~ 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in 9.1 of the UFSAR; and

c. A nominal 6.060 inches for HOLTEC designed and 6.625 inches for PaR designed center to center distance between fuel assemblies placed in the storage racks.

d. The Bora I neutron absorber shall have a 10 B areal density greater than or equal to 0.0162 grams 10 B/cm 2 with an uncertainty of 0.0012 grams 10 B/cm 2 .

(continued) DAEC* 4.0-1 Amendment
Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 831 ft. - 2 3/4 in. 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2563 fuel assemblies in a vertical orientation, including no more than 152 fuel assemblies stored in the cask pit in accordance with UFSAR Section 9.1. DAEC 4.0-2 Amendment
Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence. The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affects nuclear safety. 5.1.2 The Operations Shift Manager shall be responsible for the control room command function. During any absence of the Operations Shift Manager from the control room while the unit is in MODE 1, 2, or 3, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the Operations Shift Manager from the control room while the unit is in MODE 4 or 5, an individual with an active SRO license or Reactor Operator license shall be designed to assume the control room command function. DAEC 5.0-1 Amendment
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions.

These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements including the plant specific titles of those personnel fulfilling the responsibilities of the positions delineated in the Technical Specifications shall be documented in the UFSAR or QA Program Description;

b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant;

c. The corporate officer with direct responsibility for the plant shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager, however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

(continued) DAEC 5.0-2 Amendment
Organization 5.2 5.2 Organization (continued) 5.2.2 Unit Staff The unit staff organization shall also include the following:

a. A non-licensed operator shall be assigned to the reactor when containing. fuel and an additional non-licensed operator shall be assigned to the reactor when operating in MODES 1, 2, or 3.

b. Shift crew composition shall meet the requirements stipulated herein and in 10 CFR 50.54(m).

c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.g for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

d. A person qualified to implement radiation protection procedures shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

e. Not used.

f. The Operations Manager or Operations Supervisors shall hold an SRO license.

g. An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. This function is not required in MODES 4 and 5.

DAEC 5.0-3 Amendment
Unit Staff Qualmcations 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications referenced for comparable positions in ANSI/ANS 3.1-1978. The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. 5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m). DAEC 5.0-4 Amendment
Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and to NUREG-0737, Supplement 1, as stated in Generic Letter 82-33;

c. Qualrty assurance for effluent and environmental monitoring;

d. [Deleted]; and

e. All programs specified in Specifications 5.5.

DAEC 5.0-5 Amendment
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be e~tablished, implemented and maintained. 5:5.1 Offsite Dose Assessment Manual (ODAM)

a. The ODAM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and

b. The ODAM shall also contain the radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included. in the Annual Radiological Environmental Operating Report and Radioactive Material Release Report required by Specification 5.6.2 and Specification 5.6.3.

c. Licensee initiated changes to the ODAM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

a. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and

b. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations;

2. Shall become effective after the approval of the plant manager; and

3. Shall be submitted to the NRC in the form of a complete, legible copy .of the entire ODAM as a part of or concurrent with the Radioactive Material Release Report for the period of the report in which any change in the ODAM was made. Each change shall be identified by markings in the margins of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e.,

month and year) the change was implemented. (continued) J DAEC 5.0-6 Amendment
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.2 Deleted 5.5.3 Deleted 5.5.4 Radioactive Effluent Controls Program This program, conforming to 10 CFR 50.36a, provides for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODAM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODAM;

b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to unrestricted areas, conforming to ten times (1 Ox) the concentrations listed in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 - 20.2402;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the ODAM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODAM at least every 31 days; (continued)

DAEC 5.0-7 Amendment
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems which were used to establish compliance wrth the design objectives in 10 CFR 50, Appendix I, Section II be used when specified to provide reasonable assurance that releases of radioactive material in liquid and gaseous effluents be kept as low as reasonably achievable;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the srte to areas at or beyond the srte boundary shall be limrted to the following:

1. For noble gases: less than or equal to a dose rate of 500 mrem/yr to the whole body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and

2. For iodine-131, iodine-133, trrtium, and for all radionuclides in particulate form with half lives > 8 days: less than or equal to a dose rate of 1500 mrem/yr to any organ;

h. Limrtations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the srte boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, trrtium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limrtations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency. (continued) DAEC 5.0-8 Amendment
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.5 Deleted 5.5.6 Deleted 5.5.7 Deleted 5.5.8 Storage Tank Radioactivity Monitoring Program This program provides controls for the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. The liquid radwaste quantities shall be determined in accordance with Standard Review Plan, Section 15.7.3, "Postulated Radioactive Release due to Tank Failures". The program shall include a surveillance program to ensure that the quantrty of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System is ~ 50 curies, excluding tritium and dissolved or entrained noble gases. The liquid radwaste storage tanks in the Low-Level Radwaste Processing and Storage Facility are considered unprotected outdoor tanks. The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Storage Tank Radioactivrty Monitoring Program surveillance frequencies. 5.5.9 Deleted 5.5.10 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. . Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or (continued)

DAEC 5.0-9 Amendment
Programs and Manuals 5.5

\__

5.5 Programs and Manuals 5.5.10 Technical Specifications (TS) Bases Control Program (continued)

2. A change to the UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d. Proposed changes that meet the criteria of Specification 5.5.1 Ob above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.11 Deleted 5.5.12 Deleted 5.5.13 Deleted 5.5.14 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

(continued) DAEC 5.0-10 Amendment
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.15 Spent Fuel Pool Neutron Absorber Monitoring Program This program provides routine monitoring and actions to ensure that the condition of Boral in the spent fuel pool racks is appropriately monitored to ensure that the Boral neutron attenuation capability described in the criticality safety analysis of UFSAR Section 9.1 is maintained. The program shall include the following:

a. Neutron attenuation in situ testing for the PaR racks shall be performed at a frequency of not more than 10 years, or more frequently based on observed trends or calculated projections of Boral degradation. The acceptance criterion for minimum Boral areal density will be that value assumed in the criticality safety analysis.

b. Neutron attenuation testing of a representative Boral coupon for the Holtec racks shall be performed at a frequency of not more than 6 years, or more frequently based on observed trends or calculated projections of Boral degradation. The acceptance criterion for minimum Boral density will be that value assumed in the criticality safety analysis.

c. Description of appropriate corrective actions for discovery on nonconforming Boral.

DAEC 5.0-11 Amendment
Reporting RequirJments 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4. 5.6.1 DELETED 5.6.2 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the rxevious calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period._ The material provided shall be consistent with the objectives outlined in the Offsite Dose Assessment Manual (ODAM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken dwring the period RUrsuant to the locations specified in the table and figures in the ODAM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in Regulatory Guide 4.8. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submrfled in a supplementary report as soon as possible. (continued) DAEC 5.0-12 Amendment
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.3 Radioactive Material Release Report The Radioactive Material Release Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODAM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.8.1. 5.6.4 DELETED 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. The Average Planar Linear Heat Generation Rate (APLHGR) for Specification 3.2.1;

2. The Minimum Critical Power Ratio (MCPR) for Specification 3.2.2;

3. Exclusion Region in the Power/Flow Map for Specification 3.4.1; and

4. The Minimum Critical Power Ratios (MCPR) in Table 3.3.2.1-1 for Specification 3.3.2.1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A, (GESTAR II). The revision number is the one approved at the time the reload fuel analyses are performed.

(continued) DAEC 5.0-13 Amendment
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT {COLR) (continued)

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 DELETED 5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits'for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

i) Limiting Conditions for Operation Section 3.4.9, "RCS Pressure and Temperature (PIT) Limits" ii) Surveillance Requirements Section 3.4.9, "RCS Pressure and Temperature (PfT) Limits"

b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

DAEC 5.0-14 Amendment
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued) i) SIR-05-044-A, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," Revision 1, dated June 2013.

c. The PTLR shall be provided to the NRG upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

DAEC 5.0-15 Amendment
High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS

5. 7 High Radiation Area As provided in paragraph 20.1601 (c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permrt entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously displays radiation dose rates in the area; or

2. A radiation monrtoring device that continuously transmrts dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monrtored by radiation protection personnel responsible for controlling personnel radiation exposure wrthin the area, or

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (continued)

DAEC 5.0-16 Amendment
High Radiation Area 5.7 5.7 High Radiation Area (continued) (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1. All such door and gate keys shall be maintained under the administrative control of the shrft supervisor, radiation protection manager, or his or her designee.

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

(continued) DAEC Amendment
High Radiation Area 5.7 5.7 High Radiation Area (continued)

b. Access to, and activities in, each area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while perfonning radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exrt from, and work in such areas.

d. Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alanns when the device's dose alann setpoint is reached with an appropriate alann setpoint, or

2. A radiation monitoring device that continuously transmits dose rate and cumulative dose infonnation to a remote receiver monrtored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for '

controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, or personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area. (continued) DAEC 5.0-18 Amendment
High Radiation Area 5.7 5.7 High Radiation Area (continued)

4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible light shall be activated at the area as a warning device.

DAEC 5.0-19 Amendment
Duane Arnold Energy Center Docket No. 50-331 License Amendment Request NG-19-0102 Enclosure, Attachment 3 Page 1 of 28 ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATION BASES CHANGES (MARK-UP)
LCO Applicability B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY_ BASES LCos* LCO 3.0.1 through LCO 3.0.9 establish the general requirements

applicable to all Specifications in Sections 3.1 through 3.10 and

+

apply at all times, unless otherwise stated. *

facility LCO 3.0.1 LCO 3.0.1- establishes the Appli bility statement within each individual Specification as the re irement for when the LCO is required to be met (i.e., when the

is in the MOD~S or otJ:ter specified conditions of the Applicability statement of each Specification).

LCO 3.0.2

LCO 3.Q.2 establishes that upon discovery of a failure to meet an LCO, the associated ACTIONS shall be met.' The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements-of an LCO are not met. TAis SJ:)ooifioatioA oetaBlioAoo tAat:

Completion of the Required Actions within the specified Completion Times con_stitutes compliance with a Specifica'tio n-;--aRe GoFAJ:lloeoA of tAo Roeiuirod AotioAs* ie Aot rcieiuirod 1t'JA0A BA LGO is FAot witAiA tAo SJ:looifiod GoFAJ:llotioA TiFAe, uAlese otAerwise BJ:looifiod. -

TAero are two Basie fyJ:Jes of Reeiuired AotioAs. TAO firet t)'J:lo of Roeiuirod AotioA_BJ:losifioe a tiFRe limit iA WAiOA if:te LGO FAust BO

*FAet. TA is tiFAe liFAit is tAe GoFAJ:)lotieA Time te *restore ari iAOJ:lOFaBIO system OF. OOmJ:l*OAOAt fo OP-ERP.BL~ status 'or to restore variaBIE;lB to witAiA BJ:losified limits. If tt::iis fyf)e of Reeiuired AotioA is Aot OOFAJ:lleted witAiA tAo SJ:looifiod GoFAJ:llotioA TiFAo, a sAutdowA FABY Be roeiuired to J:)laoe tAe uAit iA a MOD~ or ooAditioA iA wAioA tAe SJ:)ooifioatioA is Aot aJ:)J:)lioaBlo. (WAotAor-etatod as a Reeiuirod AotioA or Aot, oorrootioA of tAo oAtorod GoAditioR is SA aotioA tAat FABY always BO OOASidered UJ:)OA eAtoriRg ACTIONS.) TAe BQOOAd typo of Reeiuired AotioA DAEC B 3.0-1 TSCR~

LCO Applicability

.B 3.0 BASES LCO a.0.2 s13eofl:ies the reffiodial ffioasu*res tt::iat 130FFR1t oontiRuod oporatioR (GORtiRued) of tt::ie UR it that is Rot f1:1rtt::ior roetriotod by tt::io Com13lotioR Tiffie. IA tl=lis ease, oom13liaRoe witt::i tl=le R0Et1:1irod AotioRs 13rovidoe aR aooo13taelo level of safety for 00RtiR1:1ed 013eratioR.

Go1T113l,otiR~ tho R0Et1:1irpd AotioRe je r=iot reEtuired wl=leR aR LCO ie met OF is RO IORQOF 0l3l3lioaelo, l:IRless E>tRCFWise St(:!ted iR tRO iRdivid1:1al $13eoifioati0Rs. Tt=ie Aat1:1re of SOffiO ROEtl:lirod AotiORS of some CoRditiORS Roooeeitatoe tt::iat, oRoo tl=lo GoRditioR is eRterod, the ReEtuirod AotioRs 1T11:1st be som13leted e11eA thougt::i tt=io assooiatod. CoRditioR* RQ loRger m<ists. Tl=lo iRdividual LCO's /\CTIO~JS s13oqify M=!o R0Et1:1irod AstioRs wt::ioro tt::iis ie tt::io ease. (\R exam13lo of tt::iis is iR LCO a.4.Q, "RCS Pross1:1re aRd Tom13ora_turo (P,q). Limits." Tt::ie Co1T113letioR Times of tl=lo ReEtuired AotioRs are also a1313l~oeble 'NROR a system OF oom130ReAt is romo*,od from SOPlioo iAtOAtioAaUy. Tt::io F08SOA8 for iAteAtioAally relyiAg OA tt::io - ACTIO~JS iRol1:1do, but are Aot liffiitod to, 13orformaAoo of Surveilla'Aoes, J:IF0'/0Atf\'O maiAtORQROO, oorrootivo maiRtOR0R60, or iRvostigatioR of 013orati0Ral 13robleffis. eRtoriRg ACTIO~JS for tROSO FOBSORS ffil:1St be dORO iR a ffi8RROF tt::lat does ROt

+

001T113ro1T1iso safety. IRtoRtioRal oAtl)' iRto /\CTIO~JS st::ioi:ild Rofeo made for 013orati0Ral OOR'/ORiORGO. AdditioRally, if iRtORtioRal - - oRtry iRto ACTIO~JS wo1:1ld roe1:1lt iR rod1:1RelaRt OEtl::ii13moRt b'oiRg iR013oraelo, altoFRativos st::iould so 1:1sed iRstead. DoiRg so liffiits tRO tiffiO bott, 61:lBSystOffiSJdwisiOAB ofa safot)* fUROtiOR *are

iR013era01e*aRd liffiits tt::ie_ tiffie OOFlditioRe exist 1Nl=list::i may result iR LCO a.a.a BOiRg ORtoroa. IREiiviaual S13eoifioatiORS may s13eoify a j.-

timo*liffiit for 13orfoFFRiRg*aR SR '#ROA oqui13m0Rt is removed from *1 seP:ioe 0(0Y13assed for testiRg. IR tt::iis ease, tl=lo Com13lotioR : Times of tt::io R0Et1:1irod /\stioRs are a1313lioable wl=leR tl=lis-timo limit . ex13iros, if tho OE11:Ji13meRt remaiRS removed from SOPliGO OF by13aeeoa. * - **

'AlReR a ol=laRge iR MODE or ott::ior s1300ifioa ooRditioR is roEtuirea to 0om13~ witl=I RoEtuiroa AstioRs, tt::ie l:IAit FABY eRter a MODE or ott::icir s1300ifiod eoRditioR iR wt::iiot::i aRott::ior S13ooifioatioR beooff!ee a1313lioaele. IR tt::iis ease, tt::ie Com13letioR Times of tt::io assoeiatea RoEtuiroa /\sti_oRs woula a1313ly from tt::io 13oiRt iR time tt::11;1t tho Row S13e'oifiootioR besomos a1313lisaele aREi tt::io ACTIONS GoRditioR(s) are oRtoroa.

183 DAEC B 3.0-2
LCO Applicability

- B 3.0 -r-4Deleted.

BASES (continued) / LCO 3.0.3 'tea a.a.a esta~lishes the a~tioAs t~at must Bo implomoAtod nhoA aA LGO is Rot mef aAd: 1 a:- A-A assosiated Reeiuired AotioA aAd GomplotioA Time is Rot

.mot a Ad Ao- othor.CoAditioA* applies; or &:- Tho ooAditiOfl of the uAit is Rot sposifisally addressed BY the assooiated AGTIO~JS. This moaAs that AO oomBiAatioA of GoAditions stated iA the ACTIONS oaA Bo made that oxasUy eorrespoAds to the aotual ooAditioA of the UR it.

Sometimes, poesiBlo somBiAatioAs of GoAditioAs era suoh that eAtoriAg LGO a.a.a is \'.'arraAtod; iA suoh oases, tho ACTIONS spooiffoally state a GoAditioA oorrospoAdiAg to

- suoh somBiAatioAs aAd also that LGO d.a.d BO eAterod immediately.

This SposifisatioA deliAeates ihe time limits for plasiAg tho unit iA a safe MOD.E or other speoified ooAditioA whoA oporatioA oaAAot Be maiAtaiAod withiA tho limits for safe operatioA as dofiAed BY tho LGO aAd its ACTIONS. It is Rot iAtehded to BO used as BA operatioAal OOAIJOAiOAGO that permits routiAO IJOIUAtary rem-oval of roduAdaAt systems or oompoAoAte from soP1ioo iA lieu of other altematives that would Rot result iA reduAdaAt systems or oompoAoAts BOiAg iAoporaBlo. UpoA OAtORAQ LGO a.a.a, 1 liour is allowed to prepare for aA orderly shutdowfl Before iAitiatiAg a ohaAgo iA uAit O.PeratioA. This iAoludes time to pom:1it tho operator to ooordiAato tho reduot-ioA iA elostrioal geAeratioA 't'IHR tho load dispatshor to oAsure tAo

staBility aAd availaBility of the eleotrioal grid. +ho time l_fmits sposifiod*to reaoh lower MODES of oporatioA permit tho shutdowA to prooood iA a ooAtrolled aAd orderly maAAOF that is well withiA tho spooified ma>fimum oooldowA rate aAd v,ithiA tho oapaBilities of the uAit, assumiAg tAat ORiy tho miR_imum reeiuirod oeiuipmoAt is OPERABLE. This reduees therrnal stresses OR oompoAeAts of the Reaotor GoolaAt System aAd the poteAtial for-a plaAt upset th*at ooul.d ohalloAgo* safety systems *uRdor ooAeitioAs to whioh this SposifioatioA applies. Tho use aAd iAlerpretatioA of spooified times to oompleto the aetioAs of LGO a.a.a are ooAsisteAt with tho disoussioA bf S0stior1 1~d., GompletioA Times.

!TSCR-183 DAEC B 3.0-3 AffioAdmeAt 22d

LCO Applicability B 3.d BASES LGO 'J.0.3 A 1:1nit sh1:1tdown FOEfl:liFod in aoooFdanse witt:1 LGO 3.0.d FABY be (oontin1:1od) toFFRin_ated and LGO_ d.0._3 oMitod if any of tho follo 1.ving 0001:1~:

&.- Tho LCO is no1N FRot.

e... .A Condition m<ists foF 1NhisJ:i tho Roet1:1imd /\otions ha'le

now boon 130FfoFFRod.

&. ACTIONS OMist that do not ha,*e OMf9iFOd GoFR13lotion TiFROS. Tt:1eso GoFR13lotion TiFROS aFO a1313lisable fFOFR tho 13oint in tiFRo U:lat the Condition is initially enteFea and net froFR tho tiFRe LC0*3.0.3 is eMitod.

The tiFRo liFRits of S13eoifioation :ro.3 allow 37 ho1:1FS foF the 1:1nit to be in MODE 4 1Nt:lon a sf:11:1tdmun is FOEf l:liFOd d1:1ring MODE 1 0190FBtion. If tf:le 1:1nit is in*a loweF MODE of 0190FBtien Y.if:lon a st:i1:1tdown is FOEfl:liFod, tt:ie tiFRO liFRit foF FOast:iing tt:i.o ROM! loWOF MODE a1313lios, If a lowOF MODE is FOaof:lod in loss tiFRo than allowoet, Ro*,,c-vor, tRo tOtal allowable time to FOa.cR MOD~ 4, or oit:IOF a1319lieablo MODE, is f!Ot Fed1:100d. P:oF e~aFR13lo, it'MOD.E.2 is FOaohod in 2 ho1:1FS, then tt:io tiFRo allov.*ed foF FOashing MODE d is tt:io no'Kt 11 ho1:1FS, boea1:1so .tho total tiFRo foF Foaet:iing MODE a is not Fod1:1ood fFoFR tho allowaelo liFRit of 13 t:io1:1FS. Th_eFofoFO, if

. FOFRedial FROaSl:IFOS aFe OOFRJ3lotod that '1.".'01:lld 13eFFRit a FOtl:IFR to MODE 1, a 19onalty is not ins1:1FFOd ey ha'ling to Foaof:l a lowOF MODE of 013eFBtion in loss tf:lan tho total tiFRo allo 1Ned. -In MODES 1, 2, and 3, .LCO 3:0.3 f9FO'lidos aetions foF Conditions not OO\IOFod in ott:loF S13oeifisations. Tt:io FOEfl:liFeFRonts of LGO a.0.3 do*not a13l=>~Y in MODES 4 .and e eosa1:1se tt:io 1:1nit is already in the FRost FOstrieti,,'e Condition Feet1:1irod ey LCO 3.0.3.

Tho Feet1:1iFeFRonte of LGO 3.0.3 do not a1313ly in ott:leF sposified oonditions of tho Ap13lioaeility (1:11:1loss in MODE 1, 2, OF 3) eooa1:1s0 the AGTIO~JS of indi-vid1:1al Sposifioations s1:1ffisiontly define the FOFRedial R')eBSl:IFes to BO takpn. E:Moo19tions to LCO 3.0.3 aFo pro 1a<idod in instanoos wheFO FOEfl:liring a 1:1nit sh1:1tdm'.'n, in aooor:danoo 1Nith LGO 3.0.3, wo1:1ld

net provide ap13Fo13Fiat0 FOFRodial FRoas1:1Fos foF tho assooiatod condition of the 1:1nit.

An oMaFRplo of this is in LCO 3.7.8, "S13ont 1=1:101 StOFago Pool Vi/atOF Level." LGO 3.7.8 ha~ an A13f9lioaemty of "D1:1Fing FR0 1a'OFRORt of irradiated f1:1ol assoFRblios in tho SJ)ORt f1:1e~ .

TSCR-183. DAEC B 3.0-4
LCO Applicability B 3.0 BASES Leo* a.a.a storage pool." Therefore, this LGO oan be applioablo in any or all (oontin uodr. MODES. If tho LGO and tho Required Astions of LGO a.7.8 are

not mot 1.vhile in MODE 1, 2, or.a, there is no safety bonofH to be gained by !;)lasing the unit in a shutdown oondition. Tho Required Aotion of L.GO 3.7.~ of "Suspend mo1, 1omont of irradiated fuel .

assemblies in tl:io spent fuel storage pool" is tho appropriate

Required AoUon to eoFRploto in lieu of the aotions of LGO a.a.a.

Those oxooptions are addressed 'in tho individual Spooifioations .. LCO 3.0.4

LGO a.0.4 establishes limitations on shangos in MODES or other

~poo'1fmd oonditions in tho Applioability when anJGO is not met.*

~ID-e-le-t-ed-.----µ ~ allows plaoin'g tho unit in a MODE or other spoomed oondition --- - - - - - - stated in that Applioobility (e.g., tho Applioability desired to be entered) when unit oonditions are suoh that tho requirements of tho LGO would not be FRO( in assordanso with LGO 3.0.4 .a, LGO a.0.4 .b, or LGO 3.0.4 .s.. LGO 3.0.4 .a allmus entrJ into a MODE or other sposifiod sondition in the Applioability with the LGO not met v,hoR tho assoeiatod ACTIONS to be entered permit sontinuod operation in the MODE or other spoemod condition in tho Applisability for an unlimited period of tiFRo. Gomplianse with Required /\otions that permit continued operation of tho unit for an unlimited period of time in a MODE or other sposifiod sondition provides an asoeptablo level of safety for oontinuod operation. This is without regard to the status of the unifbok>re or.after the MODE ohango. Therefore, in sush oases, entry into a MOOE or other specified condition in tho Ap1=1lioability .may bp made in aooordanoo with the provisions of the Required'Aotions. LGO a.0.4 .b allows entry into a MODE or other specified oondition in the A1=1pliocibility with. the Leo* not mot after 1=1erformanoe of a risk assessment addressing ino1=1erable systems and oom1=1ononts, sonsidoration of the. results, determination of.the aooeptability of entering the MODE or other spetiified oondition in_ the Ap1=11ioability, and establishment of risk m~nagoment'astions, if a1:1pro1=1riate. The ri_sk assossmeRt may use quahtitatr,e, qualitative, o~ blended a1=1proashes, and tho risk assessment will be oonduoted using tho planf program, 1=1rooodures, and oriteria in 1=1laoo to iFFlplomont DAEC B 3.0-5 TSCR-004
LCO Applicability B 3.0 BASES LGO d.0.4 10 ci;R §0.e6(a)(4), whioh Fequiros that FiSI( impaots of (ooRtiRUOd) maiRtORBR60 aoti 11itios BO assessed aRd maRagod. Tho Fisk assossmoRt, foF the pui=poses of LGO d.0.4 .B, musttake iRto aooouRt all iRopCFaBle TeohRioal SpooifiootioR oquipmoRt mgaFdloss of whothOF tho equipmeRt is iRoluded iR the RoFmal 10 f GFR 60.e6(a)(4) Fisk assossRJoRt. soopo ... The Fisk assessmoRts will BC OORduotod usiRg tho prnoodUFOB BRd guidaRoe ORdOFBOd BY Regulatory Guido 1.1 eO, "MoRitoFiRg the Effeoti>teRess o.f MaiRtoRaR6o at NuoloaF Po1NeF Pia Ats." Regulatory Guide 1.1 eO oRdoFSos Re>tisioR 4A of NUMARG Qa 01 dated April 2011, "IRdustr::,1 GuidoliRe for MoRitoFiRg the Effeoti¥eRoss of MaiRteRaRoe at Nuolear Power PlaRts." Those dooumoRts address geReml guidaR60 for ooRduot of tho Fisk assossmoRt, quaRtitati¥e aRd qualitati>to guidoliRos for ostaBliehiRg Fisk maRagomoRt aotioRs, aRd mmmple risk maRagemeRt aotioRs. Those iRolude aotioRs to plaR aRd ooRduot other aoti 11ities iR a maRRer that 60Rtrnls ol/orall Fisk, iR6roasod risk awaroRo_ss BY shift BRd maRagomoRt pOFSORRel, aotiORS to FOduoo tho duratioR of the oeRditioR, aotioRs to miRim~e the magRit=ude of Fisk iRoroasos (estaBlishmeRt of Baokup su66oso paths o.r 6ompoRsatory measures), aRd deteFAliRatioR that the prnposed MODE ohaRgo is aooeptaBle. GoRsidemtioR should also Be gwoR to the proBaBility of oomplotiRg FOetoratieR su6h that tho roquiremeRts of the LGO 1..'leuld BO met prior to tho oMpiratioR of ACTIONS GompletioR Times that would require eMitiRg tho ApplioaBility. LGO a.0.4.B may BO used with siRgle, or multiple systems aRd oompoRoRts una'lailaBle. ~JUMARG Qa 01 provides guidaRoe mlatwe to ooRsidoratioR of simultaRoous uRa*,ailaBility of mi;..ltiplo systems aRd oompoRoRte. Tho results of tho Fisk aoaossmoRt shall BO oeRsidorod iR dotom,iRiRg the aooeptaBility of oRtoriRg tho MODE or other epooified ooRditioR iR tho /\t3plieaBility, aRd BAY oorrospoRdiRg risk maRagemoRt aotioRo. Tho LGO a.0.4 .B risk assossmoRts do Rot hal/e to Bo dooumeRted. The ToohRioal SpooifioatioRe allov, ooRtiRuod operatioR with equipmeRt uRa1,ailaBlo iR MODE *1 for tho duFatioR of tho ComplotioR Time. SiRoo this is allowaBlo, am;i siRoo iR goReFal the Fisk impaot iR that partioular MODE BOURds tho Fisk of traRsitioRiRg into tho through tho applioaBlo MODES or..other spooifiod oeRditioRs iR tho ApplioaBility of tho LGO, tho use of tho LGO a.0.4.B allowaAoo should Bo goRorally aoooptaBlo, as loRg as tho 11s3 I (contint DAEC B 3.0-6 TSC
LCO Applicability B 3.0 BASES LCO a.0.4 risk is assesses aRa FRaRagoa as states above: l-lowovor, tt:iore is (OORtiRUO~) a SFRall Sl:lbsot of systOFRS aRa GOFRpOReRtB that have beeR aotoFFRiR08 to be FROFO iFRpOrtaRt to risk ana l:160 of tho LCQ d.0.4 .b allo\1.'aRoo is proAibitoa. The LCOs go 11omiRg those syetoFRs aRa ooFRpoRoRts ooRtaiR ~Iotas prohibitiRg tho use of LCO a.0.4 .b by statiRg that_ LC9 a.o. 4.b is riot applioeiblo., LCO a.0.4_.o allows pRtry iRto a MODE or otAer speoifiea ooRaitioR iR tAo Applisabiliey witA tAo LCO Rot FRot basea_oR a Note iR tho SpooifioatioR whioh states LCO a.0.4 .s is applisablo. TAoso epooifis allm'laRsoe pq~it oRtry iRto MODES or otAor spooifiea ooRaitioRs iR the Applioability whoR tAo aeeooiatoa ACTIO~JS to be eRterea ao Rot proviso for ooRtiRl:loa oporatioR for aR l:IRliFRitoa peri9a of tiFRe aRa a risk assessmeRt has Rot booR porfoFFRoa. TAis allowaReo FABY op-ply to all tAo ACTIONS or to a speoifio Reql:liroa AotioR of a SpooifioatioR. 'Tho risk 0S80SSFRORtS perfoFFRe8 to justify tAe use of LCO a.0.4.e l:ISl:IBI~ ORiy ooRsiaor systoFRs ai=ta GOFRpORORts. -!=or tAiB F00SOR, LCO a.0.4.o is ptpioally applies to SposifisatioRe whioh aosoribo vall:los aRa paraFRoters (e.g., Roaster CoolaRt SystoFR Spooifio Aotivity), aRa FRay be applies to other SpooifioatioRs bases o_R ~JRC plaRt spooifio approval.

TAo provisioRs of tAis SpeoifioatioR shoula Rot be iRtorprotoa as

,eRaorsiRg-tAe faill:lre to mmroiso tAo goos pf0otioo of rostoriRg systOFRS OF-OOFRpORORts to OPER,'\BLE statl:IS before ORtoriRg ctR assooiatoa MODE o.r otAor speoifiea ooRaitioR iR the Applioabilify.

The pro 11isi0Rs of LCO a.0.4 sAall Rot preveRt oAaRges iR MODES OF other spooi:tioa OORBitiORS iR tho Applioabilipt that are FOql:liroa to OOFRp~_with ACTIONS: IA aaaitiOR, tho pro 1liSiOR6 of LCO a:o.4 sAall Rot provoRt oAaRgos iR MODES or otAer speoifiea ooRaitioRs iR tAe Applioabiliey tAat resl:llt froFR aRy uRit. SAl:ltaowR'. IA this OORtex=t, a l:IRit 6AUt80WR is aofiRea 06 a ohaRge iR MODE OF other spooifioa ooRaitioR iR tho Applioabiliey aseooiatoa witA traRsitioRiRg froFR MOD~ 1 to MODE 2 OF MODE .a, MODE 2 to MODE a, BAS MODE a to MODE 4. U~oR oRtry iRto a MODE or otAor speoifioa ooRaitioR iR the Applioabilit)1 witA tho LCO Rot FROt, LCO a.o*.1 BAS LCO a.0.2 roql:liro eRtry iRto tho applioaele CoRaitioRs aRa Requires AotioRe uRtil tAo CoRaitioR is resolves, l:lritil the LCO is FF1et, or uRtil tho l:IRit , is Rot withiR tho Applioaeility of tho ToohRioal SpooifioatioR. 11s3 - I (continue~) kt DAEC B 3.0-7 TSCR-004
LCO Applicability B 3.0 BASES t LGO -3.0.4 S1:1rvoillansos elo not tmvo to be performoel on tho assosiatoel (oontinuoel) inoperable oq1:1iprnont (or on 1,ariablos 01:1tsielo the spooiffoel lirnits), as pon:nittoel by SR d.0.1. Therofere, 1:1tilizing LGO 3.0.4 iE! not a violation of SR 3.0.1 or SR d.0.4 for any S1:1rvoillanoos tt=lat have

.not been perforrnoel* on iRoporable equiprnonl *1-1owover, SRs rn1:1stbo rnot to ons1:1ro OPERL\BILITY prior to eloolaring tho

assooiatoel oq1:1iprnont OPERABLE (or va.riable within lirnits)' anel restoring oornplianoo 1Nith the affeoteel LGO.

,............,.Lc_o_3.o_.s__, -!D_e_le_t_ed_._ _ _ _ µ

~;~:;:t:::=;::v:11::::.!:::S:: ::~O:,~ ;;rn sorvioo or eloolareel inoperable to oornply with ACTIONS. Tho sole purpose of this Spoomoation is to provielo an o>E.ooption to LGO d.0.2 (e.g., to not oornply with tho applioablo Roq1:1iroel Aotion(e)) to allow tAe performanoo of roquireel testing to _

elornonstrato:

&.- The OPERABILITY of tho equiprnent being rotuFReel to sorvioo; or * &: Tho OPERABILITY of other eq1:1iprnent.

The aelrninistrativo oont~ols ensure tho tirno tho equiprnont is retuFRoel to sorvioo in ocinfliot with tho roquirernents *of tho AGTIO~JS is lirnitoel to the tirne absoh:1tely noOQssary to *perform tho roquii=eel testing to elornonstrato OPER/1,BILITY. This Spooifioation eloes not provielo tirno to perform any other preventive.or oorrootivo rnaintenanoe. An o>Earnplo of elornonstrating tho OPER/1,BILITY of the oquiprnent being roturnqel.to servioo is reopening a oontainniont isolation val 11e that has been*olosoel to oor~ply with Roquiroel Aot.ions anel *

rnust be roopeneel to perform tho roquireel testing.

An* e>iarnplo* ofelornonstrating the OPER/1,BILITY of other - e*quiprnent is takiR§ an ino13erable ohannol or'trip systern out of tho tri1;1poel oonelition to prevent the trip funotion frorn ooouning eluring tho porforrnanoo of roquiroel testing on another ehannel in tho othor'trip systern. A sirnilar o>Earn13le of elornonstrating tho OPERABILITY of oJhor equiprnont is taking an inoperaele ohannel or tri13 .systern 01:1t of tho tri13poel oonelition to 13errnit tho logia to funotion anel inelioato the appropriate response eluring the . 13eirformanso of requiroel testing on Qnother ohannol in tho sarne

!Fi~ sysleR'I. ! . 183 I (eon.inl.tl) .

DAEC B 3.0-8 TSCR-Qe4
LCO Applicability B 3.0 BASES LCO 3.0.6 ~LCO d.0.6 establishes an o*eo13tion to LCO d.0.2 for s1:11313ort .---------,. -ystems that have an LCO s13esified in tho Toshnioal ID_e_le_t_e_d_. .... ---~ Spoeifioations (Te). This oMeoption is ~rovidod boea1:1se

LCO ~.0.2 would req1:1ire that tho Conditions and Required Aotione of tho assooiatod inopor:ablo supported system LCO be entered solely .due to tho inopor:ability _of the support sys.torn. This __ _

eMooption is justified boeause the aotions ~at are required to ensure the pla~t is maintained in a safe oondition are speoifiod in the su13port system LCO's Required Aotions. Those Required Astions may insl1:1de entering tho supported system's Conditions and Required Actions or may epoeif)1 o~er Required Aetions.

'."then a sup130rt system is inoperable and there is an LCO speoified for it in tho Te, the supported systern(s) are Fequirod to be doolared inoperable if determined to be inoperable as a result of tho support system inoperability.

l-lo1N0v0r, it is not neoossal)' to enter into tho supported systems' Conditions and Requirod Aetion*s unless dirostod to do so by tho

~upport sy1;1torn'q Required A_otions. Tho potontial oonf~eion and_

inoonsistonsy of requirements related to tho entry into multiple sup13ort and supported systems' LCOs' Conditions and Required Aotions are eliminated by pro*,iding all tho aotiens that.are neoessary to ensure tho plant is maintained in a safe oondition in tho support system's Required Aotions.

l-lewovor, there are instansos whore a support system's Required Astion may either direst a supported system to be deolared .

inoperable or direst entry into Conditions and Required Astions for the s1:1pported system. This may ooour immediately or after some spooifiod*dolay to perfuFFR some other Required Aotion. Regarelless of whether it is immediate OF after some delay, when 'a support system's Required /\stioo direots a supported system to be doolared inoperable or diroots entry into Conditions_ and

Required /\otions for a supported system, ~a applioable Conditions and Required /\otions shall be entered in aooordanoe with. LCO ~.0.2.

Spooifioation e.e.11, "Safety runotion DotoFFRination Program (Si;DP)," ensures loss of safety funotion is detested and appr613riate aotions are taken. Upon entry into LCO ~ ..0.6, an evaluation shall be made to determine if loss of safety fl:Jnotion e*Mists. Additionally,* ott:1er limitations, remedial aotions, or (eontinuod) DAEC B 3.0-9 .
LCO Applicability B 3.0 BASES LGO a.0.6 sorn13onsatol)' aotions may be identified as a result of tho su1313ort (oontinuod) system ino13orability and sorros13onding oxoo13tion to entering su1313ortod sysfom Conditions aAd Required Aotions. Tho St=DP in:i13lomonts tho requirements of LGO a:o.8. Gross division shooks to identify a loss of safety .funotion for those eu1313ort sys~ems that su1313ort safety systems are required. Tho oress eiivision shosk 11orifioe that tho su1313ortod systems of tho roduneiant OPeRABLe su1313ort system are OPERABLE, thereby ensuring safety ft:Jnotion is retained. *

A loss of safety funotion may exist 1..'lhen a su1313ort system is ino13orablo, and: * -

~ A required system roduneiant to systom(s) su1313ortoei by tho ino13orablo su1313ort system is also ino13erable; or (eXAMPLe Ba.0.6 1) . * & A required system i=odundant to systom(s) in "turn su1313ortod by tho ino13erable su1313orted system is also ino13orablo; or (gJ\MPLE Ba.0.6 2) ~ A required system redundant to su1313ort systom(s) for tho su1313orteei systems (a) anei (b) above is alee ino13orablo.

(8(/\MPL~ B3.0.6 3) eXAMPLe Ba.0.6 1 e If System 2 ~f Train A is ino13orable, and System of Trai.n Bis 013orablo, a los*s of safety funotion exists in. su1313ortpd System 0 .

.gJ\MPLe B3.0.8'2 If System 2 of Train /\. is ino13orabJo, anei System 11 of Train B is ino13orablo, a loss of safety funotion exists in System 11 v.ihioh is in tum su1313ortod by System 0. ~MPLe B3.0.6 a If System 2 of Train A.is ino13erable, and System 1 of Train B is ino13orablo, a loss of safety funotion exists in Systems 2, 4, 0, 8, Q, 10, anei 11.

If this 0~1aluation determines that a loss of safety funstion exists, the a1313re13riato Gon-ditions anei Required Aotions of tho LGO in Whish tho loss of safoPj funofion exists.are FO~Uiroei ta be ontoreei*. (oontinuod)

!183 OAEC B 3.0-10

LCO Applicability B 3.0 BASES LCO 3.0.6 (continued) r------, System 8

~------< System 11 ~-----< System 11 System 1 System 3 ,------, System 14

1!183 h DAEC B 3.0-11 TSCR~
LCO Applicability B 3.0 BASES Leo* a.o.e This loss of safety fuRetioR does Rot FoquiFo the assuR:iptioR of (ooRtiRued) additioRal siRglo*failuFQs OF loss of offsito pm*.10F. SiRse operotioR is beiRg rnstrioted iR aeeoFdaRoo \Vith tho /\GTIO~JS of tho support systoR:i, aRy rnsultiRg toR:ipOl'.3F)' loss of mduRdaRoy OF siRglo-failuFO prntootioR is takoR iRto asoouRt. SiR:iilaFly, tho AGTIO~JS. fOF iRopomblo offsito siFGuit(s) aRd iRopeFablo diesel goRomtoF(s) prnvido tho ResessaF)' FOstriotioR foF ornss tmin iRopeFabilitios. This O*Jllioit oFoss fraiR vorifisatioR foF iRopeFablo /\G o'lostrioal pm.*JoF sou Foos also ael<Rowledges that supported systeR:i(s) aFo Rot (!eelaFed iRopoFablo solely a~ a rnsult of iRopeFability of a ROFFRal OF eR:iOFQOROY olootrisar PO'l.'OF SOU FOO (FOfOF to tho dofiRitioR of OPl!:AABILITY).

\OJheR a loss of safety f1:1RotioF1 is dotoFFRiRod to eMist, aRd tho SFDP mquiFOs oRtF)' iRto tho apprnpriate GoRditioRs aRd Requimd AotioRs of tho LGO iR 11.1hioh tho loss of safety fi:IRotioR mcists, eoRsi~eFBaeR: R:iust be givoR to the speoifio typo of fuRstioR affootod. 'NheFe a loss ef fuRstion is solely duo to a siRglo ToohRioal SposifisatioR support systoR:i (o.g.;_loss of autoR:iatio*

start duo to iRopoFablo iRstFUR:iORtatioR*, OF loss of puR:ip suetioR sou Foe due to Im*, taRk level) tho apprnpFiato LGO is tho _LGO foF tho support systoR:i. The AGTIO~JS fQF a s~pport systeR:i LGO adequately addFOSSeS f:he iRopombilitios of that systeR:i 'Nithout FeliaRoe OR oRtOFiRg its supported systeR:i LGO. 'NhoR tho loss of fuREffioR is tho FOsult of R:iultiplo support systeR:is, tho appFOpriato LGO is tho LGO foF the supported systoR:i. LCO 3.0.7 ThoFO aFe oortaiR sposial tests aRd opeFBtiORS FOqUiFOd to be porfqFFRod at various tiR:ios ovo.F tho life of tho uRit. Those spoeial tests aRd opoFatioRs am ReoessaF)' to deR:ions:e=ate soleot unit Deleted.* pOFfoFR:iaROO ohamoteristios, to pQFfOFFR spooial R:iaintenaROO - aoti*,ities, aRd to peFfoFFR. spooial 0'1oluti0Rs. Speoial OpoFations LGOs in SeotioR a.1 O allow spooifiod TS mquiFeR:ieRts to be ohaRgod to poFFRit_ peFfoffilanoes of those spooial tests aRd opOFatioRs, whish othoP.viso oould not be peFfoFFRod if Foquirnd to ooR:iply with tho FOquiFoR:ioRts of these TS. URlest;; othorwiQo speoified, all tho ethoF TS FOquiFOR:iORts FOR:iaiR UROhaRgod. This will OR!,UFO all ap13rnpriate mquiFOR:iORts of tho MODI!: OF othOF - sposifiod soRditioR Rot dirnotly assooiated with OF FequiFOd to 13.oFfo*FFR tho spooial test OF opoFBHOR 'Nill roR:iai~ iR offoot. (ooRtiRued)

~.

DAEC B 3.0-:-12 ~ TS~-.Q+Q
LCO Applicability

- B 3.0 BASES LCO 3.0.7 Tt:io A1313lioability of a S13ooial 013orations LGO ro13resonts a (oontinl!.loe) soneition not nooossarily in oon,131_ianoo with tho normal Foql!.liren,onts of tho TS. Con,13lianoo with S13ooial 0130Fations LC Os is 013tional. A *s13eoial 013eFation _n,ay be 13eFformee eithoF l!.lneoF t~o 13Fovisions of tho a13J3Fo13riato S13ooial 0130Fations LCO OF l!.lneoF tho othoF-a1313lisablo TS Foql!.liFoF11onts. If it is eosiree to 13eFform the s13ooial 0130Faijon l!.lneoF tho 13Fo11isions of tho S13ooial 013emtions LCO, tho FOql!.liFORlOnte of tho S13ooial 0130FOtione LGO shall be followed. \f\lhon a S13ooial 013omtions LCO F,Oql!.liros anothoF LCO to be n,ot, only tho FOql!.liFoF11onts of tho LGO

etaton,ont aFO FOql!.liroe to be n,ot rogaFelose of that LC O's . -

A1313lioability (i.e., shol!.lle the FCql!.liFCF11ents of Y=lis otheF LCO not be n,et, tho ACTIONS of tho S13osial 013omtions LCO a1313ly, not tho ACTIONS of tt10 othoF LCO). ~owe1,,'0F, thot=e are instanoes whoFo tho S13osial 0130Fatione-LCO'e AGTIO~JS-n,ay direst tho othoF LCO's ACTIONS be n,et. Tho Sl!.IFVoillanoos of tho othoF LCO are -not reql!.liFod to be n,ot, l!.lnlost;; s13osifio~ in tho S13ooial 013omtions LCO. If ooneiijons exist sl!.loh that tho A1313lioability of any othoF LCO is n,ot, all tho othoF LCO's -Foql!.liFOFRonts - - (ACTIO~JS and SRs) aFC Feql!.liFOe to be n,e_t oonol!.lrrent 1Nith tho Foql!.liFoF11onts of tho S13ooial 013emtions LCO. LCO 3.0.8 LCO a.0.8 establishes sonditions l!.lneoF whish syston,s are ....--------, JI sonsidoFoe to Fon,ain sa13ablo of 130FfoFF11ing thoiF intoneoe safety -1D_e_le_te_d_._ _ ___..~ ~motion when assooiatoe snl!.lbboFS aFo not oa13ablo of 13r'oviding - thoiF assooiatoe Sl!.IJ:IJ:IOrt fl!.lnstion(e). Thie LCO states that tho e1:11313ortoe syston, 'is not oonsideFee to be ino13emble sole~ el!.le to one OF n,ore E!_nl!.lbboFS not 0013ablo of 130Fforming theiF asso_oiatoe Sl!.IJ:IJ:IOrt f1:1notion(s). This is a1313Fo13riate bosa1:1se a lin,itod length of tin,o is allowoe foF n,aintenanoo, tasting, OF Fe13aiF of one OF _ n,ore sn1:1bbeFS flOt 0013able of 13erforming theiF assooiated s1:113130(1 fl:lnotion(s) ans a1313Fo13riato eon,13onsatoF)' n,oasl!.IFOS ar=e s13ooified in tho sn1:1bbeF.Feq1:1irnments, whioh aFe loootod 01:1tsieo of the Toehnioal S13ooifiootione (TS) 1:1neoF lioonsee oontrnl. Tho sn1:1bbCF FO_ql!.liFeF11ents ea not n,eet the oritmia in 10 GFR eO.ae(o)(2)(ii), and, as si;ioh, aFO a1313Fo13Fiate foF oontFol by tho lioenseo. If the allowee tin,e ex13iFes and ~he snl!.lbbCF(s) aFO l!.lnable to 130Fform thoiF assooiatee s1:11313ort f1:1notio11(~). the affeoted Sl!.IJ:IJ:IOrtod syston,'s LCO(s) n,1:1st be doolciFoe ~et n,ot ans tho Coneitions ans Roql!.liFOe Aotions on~eFoe in aooOFdanoo 1Nith .LCO

~

DAEC B 3.0 T TSCR-Q79
LCO Applicability B 3.0 BASES LCO 3.0.8 LGO a.0.8.a applies when one or more snubbors are not oapable of providing their assooiated support funotion(s) to a single train or subsystem of a multiple train or subsystem supported system or to a single train or subsystem supported system. LGO 3.0.Ra allows 72 hours to restore tho snubbor(s) 'before deolaring the supported system inoperable. Tho 72 hour Completion Timo_is reasonable based on tho low probability of a seismio o*,ent oonourrent wfth an event that 1Nould require operation of tho supported system ooourring *.vhilo tho snubbor(s) are not sapablo of performing their assooiatod support funotion and due to tho availability of the redundant train of tho supported system LGO 3.0.8.b applies \¥hon one or more snubbors are not oapablo of providing their assooiated support funotion(s) to more than one train or subsystem of a multiple train or subsystem supported system. LGO a.0.8.b allows 12 hours to restore the snubber(s) before doolaring tho supported system inoperable. Tho 12 hour Completion Time is reasonable based on tho lo*N probability of a soismis event oonourrent

*with an event that 't'rould require operation of tho supported system osourring while the snubbor(s) are not oapablo of performing their assooiatod support funotion.

LCO 3.0.8 requires that risk be assessed and managed. Industry and ~H~C guidanoo on tho implementation of 10 CFR 60.66(a)(4) (tho Maintonanoo Rulo) does not address soismis risk. However, use of LCO 3.0.8 should be sonsidorod with rospeot to other plant maintenanee aetivises, and integrated into tho oMisting Maintenanoe Rule prooess to the mctont possible so that maintenanoe o:n any unaffested train or subsystem is properly oontrolled, and emergent issues are properly addressed. Tho risk assessment need not be quantified, but may be a qualitative awareness of ijio vulnerability of systems and oompononts v,hon one or more snubbors are not able to perform their assooiatod support funotion. LCO 3.0.9 (sontinuod) LCO 3.0.Q ostabJishos oonditions under whish systems desoribei;i in the Teshnioal Speoifisations are sonsidered to remain OPER/\BLE: when required barriers are not oapablo of pro 11iding t their related support funstion(s). Deleted. (oontinuod) 1183~ DAEC B 3.0-13A TSCR
LCO Applicability B 3.0 BASES LGO ~.O.Q BaFFiOFS aFO elOOFS, walls, flooq:>IU§S, SUFBS, hatshos, installoel stA:lotUFOS _(continued) ,OF sompononte, OF othoF elo'Fi806, not o>Eplisitly elosoFisoel in Toohnioal Speoifioations, that support tho porfeFFRanoe' of tho safof;y funotion of systems eloseFisoel in tho Toehnieal Spoeifiootions. This LGO states that

.tho supporfoet system is net eonsieloFoel to so inopornslo solely etuc:i to rneiuirnel sciFFioFs net oopaslo of poFfoFFRin1;1 thoiF FOlatoel support funetion(s) uneloF tho eloseFisoel eonelitiens. LGO a.O.Q allews :30 elays sofoFo eloolaFin1;1 tho suppertoel systom(s) inoporaslo anel tho .LCO(s) assoeiatoel w-ith tho suppertod systom(s) not FF1ot. /\ milMimum tin:io is plaooel on oaeh uso of this allewanso to onsurn that ae rneiuirnel sarFioFS arn found or am ethorwie9 maelo un:availaslo, they are rnsterod.

l-lowo\10F, tho allo'Nasle eluFBtion may so less than the spoeifieel mraemum time eased on th.a risk assessment. If tho* allo1.\1oel time D*PiFos anel tho sarFieFS am unaslo to poFfoFFR their rnlated suppert funetion(s), the supported system's LGO(s) muot so doelarnd not mot and tho Gen.ditions anel Roeiuirnd /\etions enteFOd in aeeordanoo vfit/:1 LGO :3.0.2. Thie pF0'1ieion does net apply to saFFioFS *Nl=lieh support 1,o~tilation systems or to fire saFFioFS. Tho.Teohnieal Spoeifieations ,for 1,ontilation systems provielo spoeifie Gonelitions for ino*pernslo saFFiors. P:iro saFFioFS aFO addrnssod sy other ro1;1ulatory rneiuirnmonts and assoeiatod plant prngmms. Thie prn1Fieien elooe not apply to sarriora 1Nhieh am not roeiuirnel te support system OPERABILITY (see ~JRG Re1;1ulatoiy Issue Summary 2001 09, "Gon1:Fel of l-lezerel BerFiora," elated ApFil 2, 2001). Tho provisiene of LGO :3.0.Q arn justified sooaueo of tho law Fisk assoeiatoel with ~oeiuired saFFiom not soing eapaslo of porfeFFRing their misted euppert funetion. Thie prnvis,ion is scieoel on oonsielomtion of tho following initiating event 00to1;10Fioe:

* - Loss of ooolant aooidonte; ., l-ligt:1 energy lino breaks;*

l=oodv,tator liRo bi:oakc;

Internal flooding;

* ~ernal flooding; *

Turbine missile ejeotion; and

Tornado or t:ligt:1 wind.

(continued)

11a3 1 DAEC B 3:0-138 TSCR:i
LCO Applicability

*s 3.o BASES LGO d.0.Q The risk iFA13aet of the 13ar:ri0FS whieh oannet 130rf0rn:1 thei.r r0lat00 (soRtimJOd) su1313ort funotieil(s) FAUSt 80 000F0SS00 J3UFSUORt ta the 'risk a08088FAORt one FA*onotJoFAont 13revio1on of tho Mointonanoo Rulo, 1o GrR e0.6e (a)(4), one the oss0oiot00 iFA13l0FA0ntoti0n tJUieonoo, RetJulatory Guiao 1.160, "M0nit0rinJ the effeotiv0n00s of Maintonanoe at ~Juoloar Power, Plante*.~ Rog-ulatery G~ieo*1.16Q. 0*R~OF806 RQIJision'4A of ~iu'M/\RG Qd O'!. eotoe A13ril 2011, "lneustry Guie0lin0 for MenitorintJ the Effootivenoso f

of Maintonanoe at ~Juolear Power Plants." This tJUieanoo 13ro11ieoe for* the OORSieeratien of eynaFAiO J3lant OORfitJUFOti0R iSSU06, eFAeFtJORt . ooneitiens, one other as13eots 130rtin0nt ta 13lant 0130rati0n '.'.<<ith tho 13arri0FS unal31o to 13orfoFFR their relates 0u13130rt funotien(e). Those oensieoratione FABY result in riok FABROtJOFAont ane.ethor 00FA13onsat01)1 aotiens 13ointJ rofluiree eufintJ the 13orioe that 13arri0FS are unal31o to 13orf0rFA their rolatoe eu13130rt funotion(e). LGO a.O.Q FABY 130 a1313lioe to 0n0 or FA0re trains er sul3systeFAs of a eyetoFA* eu13130rtoe 13y baFFioFS that oannot 13revido their relates su1313ort funotien(e), 13re11ieee that Fisk ie aeeoeeoe_ane*manatJoe (inolueintJ oensieoration of tho offoots on LartJ0 Early Release ane froFA o*1ornal 011onts). If a13131iee oonourrently ta FA0*re than one train or sul3eyetom of a FAulti13lo train or sul3system su1313ort00 system, tho 13arriors su13130rtintJ oaoh of those trains or e~l3syetoFAe FAuet 13revieo their relatoe .su13130rt funotion(s) for eifferont oatotJories of ini:BatintJ events. Fer o~FA13lo, LGO ~.O.Q FABY 13e a1313liee for u13 to d0 eays fer mere than one train of a FAulti13lo train eu1313ortoe eyetoFA if tho affootoe sorrier for one train 13retoote BtJBinet internal flooeintJ one tho affootoe 13ar:rier for tho other train 13r0toote BtJOinet temaeo FAieeiloe. In this o><aFA13lo, tho affootoe

13arrier FAay 130 the saFAo 13hysioal sorrier 13ut serve eifferent 13roteotion funotiens for oaoh train.

Tho I-IPGI (l-litJh Pressure Coolant ln:iootien) one .RGIG (Roaster Gero Isolation GeolintJ) eyetoff!e are eint)lo train eyetoFAe for 1njootintJ FA*akou13

,..,9ter into the reaotor eurintJ an_aooieent er transient event. The RCIG systoFA is not a safofy systoFA, nor r9E1uiroe ta 013orato eurintJ a transient, therefore, it 0000 net have ta moot tho eintJlo failure oritorion. Tho. MPGI eyetoFA 13r01.iieos 13aoku13 i_n ease of. a RGIG systoFA failur9. ThQ /\OS (AutoFAatio Do13reeeuri:zation SystoFA) ane low 13reosure E:GGS eoolant*

in:iootion 13roviee the oere oeolintJ funotien in tho event of failure of tho I-IPGI eyeteFA eurintJ an aooieent. Thus, for the 13ur130sos of LGO d.0.Q, .

tho I-IP.GI system, tho RGIG systoFA, one the ADS are 00nsie0roe ineo130ne0nt eul3syetoFAe of a eintJl0 0yet0FA ane LGO d.0.Q oan 130 usee en those sintJle train systoFAs in a FAannor siFAilar ta FAulti13le train er eutieyeteFA eyeteFAs. * * (OORtin1:10d)

~

DAEC B 3.0-13C TSCR~
LCO Applicability B 3.0 BASES LGO ~.O.Q If duriAg tho time that LGO a.O'.Q is soing used, tho roeiuired OPE:RABLE: (ooAtiAued) *train or sussystom sosomos ino19oreslo, it must so restored to OPE:RABLE: status within 24 hours.' Otherwise, tho train(s) or sussystom(s) su1919orted sy sarriors that sonnet 19orform their related su1919ort funotion(s) rnust so doslered ino19ereslo and tho assooietod LGOs doolered not mot. Thie 24 hour 19oriod 19rovideo time to res19ond to om-orgont oonditfons t~af;.vould othor,*Aso -likely 1ea1f tci *entry iAtci Leo . a.a.a end .a re19id 19lant shutdown, wt\ish is not justified gwoA tho low 19resesility of en initietin§ 01,ont whish woulel reeiuire tho sarrior(o) not oe19eslo of 19erforn=ting their related ou1919ort funotion(s). During this 24 hour 19eriod, tho 19lant riok aeeosietod ...Ath the 0)0Sting soAditions is aeeoeood end managed in aooordanoo with 10 Gr"R 60.66(a)(4).

~

DAEC B 3.0-13D TSCRk
SR Applicability B 3.0 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES J SRs SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all Specifications in Sections 3.1 through 3.10 and apply at all times, u*nless otherwise stated. SR 3.0.1 - - SR 3.0.1 establishes the requirement that SRs must be met during the MODl!:S er etl'lor specified conditions in the Applicability for which the requirements of the LCO apply, -unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified lim~s. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO. Surveillance may be performed by means of any series of sequential, overlapping, or total steps provided the entire Surveillance is performed within the specified Frequency. Additionally, the definitions related to instrument testing (e.g., CHANNEL CALIBRATION) specify that these tests are performed by means of any series of sequential, overlapping, or total steps. Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in this Specification, however, is to be cx>nstrued as implying that systems or components are OPERABLE when:

a. . The systems or components are known to be inoperable, although still meeting the SRs; or

b. The requirements of the Surveillance(s) are known to be not met between required Surveillance performa ,..........___,

- facility Surveillances do not have to -be perfo*rmed when the 1s m a MODI!: er etl'ler specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified. Tl'le SRs asseeiated witl'I a Spooial Operatiens LGO are enPJ' appliooele 1.vl'len tl'lo Spoeial Oporatiens LGO is 1:1sed as an allewaele exoeptien te Rio req1:1iromonts ef a Spoeifieatien.

Surveillances, including Surveillances invoked by Required Actions, do not have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to OPERABLE status. * (continued) DAEC B 3.0-14 TSCR-4&7 _!183 ~-
SR Applicability B 3.0 BASES SR 3.0.1 Upon completion of maintenance, appropriate post maintenance (continued) testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 3.0.2. Post maintenance testing may not be possible in the current MODE or otf:lor specified conditions in the Applicability due to the necessary

~ parameters not having been ,established. In, these situations, , , the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to'a MODE or e#tet= specified condition where other necessary post maintenance tests ?an be cor:npleted.

SoR=ie eMaR:iples of tf:lis proooss are:

a:- GoRtrol Rod Dnve R=i'aiRtoRaRoo dur:iRg *ro~oliRg tf:lat requires ssraR=i testiRg at > 800 psi: l=lowever, if other approJ:)riate testiRg is sat-isfaotorily 80R=iJ:llated, tf:le oor=ttrol rod oaR 00 QORsidereQ OPE_RABLE. Tf:l_i.e alloi,ue startup to _proseed _to reaef:I. 800 psi to perform otf:lor Rososeary . testiRg.

-Ir. l-ligf:I pressure eeolaRt iRjeOtiOR (I-IPGI) R:iaiRteRaROO duriRg shutdowR tf:lat requires systoR=i fuRotioRal tests at a speoifiea pressure. Provided otf:ler appfopriate testiRg is satisfaetorily oeFRploted, startup oaR preoood with l=IPGI ooRsidered OPER1\BLE. Tf:lis allow!S operatioR to reaof:I tf:le speoifiod pressure to ooR=iploto tf:le Rooossary post R=iaiRtORBROe testiRg.

SR 3.0.2 SR a.0.2 ostablief:loe tf:lo roquiroR=ioRte for R=ioetiRg tf:le spooified FroqueRoy for SunmilleRoes aRd eRy Required AetioR witf:I a .- GoR=iplotioR Tiffie tl=lat requires tf:lo period is performaRoo of tf:lo . Required Aotio*R OR a "oRoo per: .. " iRtorval. SR 3.0.2 permits a 25% extension of the interval specified in the ~fa_c_i_lity~_ _ _ ___..---=_,,,uency. This extension facilitates* Surveillance scheduling and consi e plaRt oporatiRg conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities). *

!183 (contin2 DAEC B 3.0-15 TSC

SR Applicability B 3.0 BASES SR 3.0.2 The 25%: extension does not significantly degrade the reliability (continued) that results from performing the Surveillance at its specified Frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is. the verification of conformance with the SRs. Tho mmoptions to SR a.0.2 a~o U:ioso SJuveillanoo.s .for 1Nbish the 2eq~ o~ension of the inteF\1al epooif:iea in tho i;roei1:Jonoy aoee not apply. Thoeo mmoptions are statoa in the. inefrlia1:Jal Speoif:ioatione. The

roet1:Jirements of rog1:Jlatione take proooaonoe over tho TS.

Thoroforo, *when a test interval is speoifioa in the reg1:Jlations, the test interval eannet eo e>Etondea ey TS, ana the SR insl1:Jaos .a

~Joto in tho Froei1:Jenoy stating, "SR a.0.2 is not applioaele." /\s states in SR a.0.2, tf:lo 2eq~ o>Etonsion also aops* not apply to tho initial portion of a porioaio* Comp lotion Time. that FOE11:Jires porfom=ianoe on a onoo per... " easis. Tho 20% e>Etonsion ap~lies to eaoh porfo1TF1anoe after tho initial performanoo. The initial porformanoo of tho Roq1:Jirea .'\otion, 1Nhether it is a partio1:Jlar S1:Jrvoillanoe or some ott:ior remoaial aotion, is ooneiaoroa a single aotion with a sin_glp Complotipn Time. Ono reason for not allowing *tho 20% *e>Etension to this Completion Time is !Rat s1:Joh an astion l:JSl:Jalty verifies that no loss of f1:Jnotion has 0601:JFFOa ey shosking the stat1:Je of roa1:Jnaant or aivoreo oompononte or aooomplishoe tho f1:Jnstion of tl-le inoporaelo OE11:Jipment in an altemati\10 manner.

The provisions of SR 3.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals (otl=lor than those oonsietont i.*.'ith reft:Joling intervals) or periodic Completion Time intervals beyond those specified. SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours or up to the limit of the specified Frequency, whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was. not met. 11a3 I (continid) . DAEC . B 3.0-16 TSCR~
SR Applicability

**s 3.o BASES SR 3.0.3 This delay period provides adequate time to complete (continued) *surveillances that have been missed .. This*delay period permits the completion of a Surveillance before complying with Required Actions or other remedial me~sures that might preclude completioll of the S.urveillance. )taci:r )

The basis for this delay period includes consideration of i::fftff conditions, adequate planning, availability of personnel, the time required to perform. the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements. *

'NhoR a SurvoillaRGO witt-1 8 i;:FOE1UORO)' BBBOel ROt OR tiRle iRtOFvals, BUt upoR spooifiod URit OORelitiORS, opOFBHRQ situatiORS, OF FOE1UiFOR10RtB of mgulatiORS (e.g., pFioF to ORtOFiRg MOD~ ~

affoF oaoh fuol loaeliRg, OF iR assoFelaRoe \Vith 10 GFR eO, J\ppoRelix d, as* RlOelifioel BY appFOVOel OXORlpHORS, eta.) _is elisoovOFeel to Rot h;:avo BOOR pOFfoFR1oel whoR ~posifioel, SR a.o.;;J allows klF tho full elolay pOFioel of up to tho sposifioel FroE1UeRoy to poFfoFR1 tho SurvoillaRoo. l-lowovoF, siRso thoFO is not a tiR10 interval spooifieel, ij:Je FAisseel SurveillaRoe shoulel BO poFfoFR1oel. at the fiFSt FeasonaBle opportunil:y. SR a.a.a pFOVielos a tiRlO liRlit foF, anel allowanoos foF tho poFfoFR1anoo of, Survoillanses that BeooR1e applisaBlo as a soRseeiueRoe of MODE ohanges iFAposoel BY-RoE1uiFOel /\otiORS. . Failure to comply with specified Frequencies for SRs is expected to. be an infrequent occurrence. Use of the delay period e_stablished by SR 3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals. While up to 24 hours or the limit of the specified Frequency is provided to perform the missed Surveillance, it is

~xpected that the missed Surveillance will be performed at the first reasonable* opportunity. The determination of the first

reasonable opportunity should include consideration of the.impact IM1711Cl'TT1: risk (from delaying the Surveillance as well as any~

facility ** figuraton changes required OF shuttiRg the plant elown to assumptions, in addition tor perform the Surveillance) and impact on any analysis

~

conditions, planni,-n'g_,_a_v_a_ila--'------,

* ....a_c_il-"ity.___ _ ____.

l183

. (contin~d)

DAEC B 3.0-17 T,SCR~
SR Applicability

- B 3.0 BASES SR_3.0.3 personnel, and the time required to perform the Surveillance. This (continued) risk impact should be managed through the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC Regulatory Guide 1.16Q, "Monitoring the Effectiveness of - ~.

Maintenance at Nuclear Power Plants." This Regulatory Guide 1. addresses consideration_of temporary and aggregate risk i1J1pacts, determination of risk management action thresholds, and ris_k management action up to and including plant shutdown. The missed Surveillance should be treated as an emergent condition. as discussed in the Regulatory Guide. The risk evaluation may use quantitatjve, qualitative, or blended methods. The degree of depth and rigor of the evaluation should be commensurate with the importance of the component. Missed Surveillances for important components should be analyzed quantitatively. If the results of the risk evaluation determine the risk increase is significant, this evaluation should be used to determine the safest course of action. All missed Surveillances will be placed in the Corrective Action Program. If a Surveillance is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the delay period,_jhen the. equipment is inoperable, or the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon the failure of tbe Surveillance. Completion of the Surveillance within the delay period allowed by this Spedfication, or within the Completion Time of the ACTIONS, restores compliance with SR 3.~.1. SR *3.0.4 SR 3.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE OF otl:ioF specified condition in the Applicability.

This Specification ensures that system and component OPERABILITY requirements and variable limits are met before f

entry into MOD~S OF ot-1:ioF specified conditions in the Applicability for which_ these systems and components ~ns.ure safe 13eFatioR oft -Hffit. ._

, !maintenance I facility 11a3 I (contint DAEC B 3.0-18 TSC

SR Applicability B 3.0 BASES ., SR 3.0.4 The provisions of this Specification should not be interpreted as (continued) endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability. A 13_rovisioA_is iAoh,Jdod to allo1N oAtry iAto ,a MODE or other _ s13ooiJiod ooAditioA iA the A1313lio0Biliey \'11hoA aA LGO is Rot !Tiet due to SUF\10ill0A00 AOt BeiA!:) ITIOt iA 0000F80AOe 1Nith LGO 3.0.4. However, in certain circumstances, failing to meet an SR will 'not result in SR 3.0.4 restricting a MODE ohaA!:JO er ether specified condition change. When a system, subsystem,' division., component, device, or variable is inoperable or outside its specified limits, the as.sociated SR(s) are not required to be performed per SR 3.0.1, which states that Surveillances do not have to be performed on inoperable equipment. When equipment is inoperable, $R 3.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform .the Surveillance(s) within the specified Frequency does not result in an SR 3.0.4 restriction to changing MODES or et/:Jor specified conditions of the Applicability. l-10 1Ne*1or, siAse the LGO is Rot mot iA this iAstaAoo, LGO 3.0.4 v.*ill

!:JOVOFA BAY rostristioAs that ITIBY (or 1T1ay Rot) a1313ly to MODE or other s13eoiJiod soAditioA ohOA!:Jes. SR a.0.4 does Rot rostriot ohaA!:JiA!:J MODES or other s13ooif:iod soAditioAs of tho /\1313lioaBility

wheA a SurvoillaAso has Rot BOOR 130FfoF1T1od withiA U:ie s13osiJiod

~reeiuoAoy, 13rovidaa tflo roeiuiro1T1eAt *to doolaro tho LGO Rot 1T1ot has BOOR delayed iA aooordaAso 1Nith SR a.a.a The provisions of SR 3.0.4 shall notprevent changes in MODeS or other specified conditions in the Applicabilify that are required _

to comply with ACTIONS. IA-additioA, the 13ro\1isi0As of SR a.0.4 shall Rot 13ro*10At shaA!:Jes iA MODES or other s13osiJiea soAditioAs iA tho /\1313lioaBility that result fFOn:I aAy UAit shutdolNA. IA tflis _ O(;IAtO'Kt, a UAit shutdO'IIA is dofiAoel as B ohaA!:)0 iA MODE OF other s13eoifiod ooAelitioA iA tfle Ai:)13li00Biliey assooiatod with traAsiUoAiA!:J fFOITI MODE 1 to MODE 2 OF MODE d, MODE 2 to MODe a, aAel a MODE to MODE 4. . DAEC B 3.0-19 TSCR~
SR Applicability B 3.0 BASES SR 3.0.4 The precise requirements for performance of SRs are specified (continued) -such that exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) sp_ecified in a Surveillance_ procedure require entry into the MODe er eUmr specified condition-in the Applicability of the associated LCO prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after entering the LCO's Applicability would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Surveillance may be stated in the form of a Note, as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4, Frequency. - 11a3 I DAEC B 3.0-20 TSC~Q.!Q
Spent Fuel Storage Pool Water Level

. B 3.7.8 B 3. 7 PLANT SYSTEMS B 3. 7.8 Spent Fuel Storage Pool Water Level BASES BACKGROUND The minimum water level in the spent fuel storage pool meets the assumptions of iodine decontamination factors following a fuel handling accident.

A general description of the spe_nt fuel storage pool design is found in the UFSAR, Section 9.1,2 (Ref. 1). The assumptions of the fuel handling accident are found in the UFSAR, Section 15.2.5 L, (Ref. 2). 1 APPLICABLE The water level above the irradiated fuel assemblies is _an explicit SAFETY *assumption of the fuel handling accident. A fuel handling accident ANALYSES is evaluated to ensure that the radiological consequences (calculated whole body and thyroid doses at the exclusion area and low population .zone boundaries) are well .below the guideline limits of 10 CFR 50.67 (Ref. 3) and meet the exposure guidelines of Regulatory Guide 1.183 (Ref. 4). A fuel handling accident could release a fraction of the fission product inventory by breaching the fuel- rod cladding as discussed in UFSAR, Section J.., 15.2.5 (Ref. 2). - - . *1 The fuel handling accident is evaluated for the dropping of an irradiated fuel assembly onto the reactor core.' The consequences of a fµel handling accident over the spent fuel storage pool.are no more severe than those *of the fuel handling accident over the reactor core, as discussed in the UFSAR, Section 15.2.5 (Ref. 2). ,r The water level in the spent fuel storage pool provides for absorption of water soluble fission product gases and transport delays of soluble and insoluble gases that must pass through the water before being released to the secondary containment atmosphere .. This absorption and transport delay reduces the potential radioactivity of the release during a fuel handling accident. The spent fuel storage pool water level satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii). . An analysis of a fuel handling accident in the spent fuel s.torage pool has also been performed.

~-

DAEC B3.7-37. *TSCR-044A
Spent Fuel Storage Pool Water Level B 3.7.8 BASES (continued) LCO The specified water level preserves the assumptions of the fuel handling accident analysis (Ref. 2). As such, it is the minimum required for fuel_ movement within the spent fuel storage pool. APPLICABILITY This LCO applies during movement of irradiated fuel assemblies in the spent fuel storage pool since the potential for a release of . fission products exists. ACTIONS LGO a.a.a is not applioaelo in MODE 4 ore. 1-lowevor, sinoe irradiated ft:Jol assomely mo1.<ement oan 0001:1r in MOD~ 1, 2, or a, roq1:1ired /\otion /\.1 is modified ey a Note indioating that LGO a.a.a does not apply. If moving irradiated f1:1el assomelies while in MOD~ 1, 2, or a, tho f1:1ol movement is independent of roaotor operations. Therefore, inaeility to s1:1spond movement of irradiated ft:Jol assomelies is not a s1:1#ioiont reason to roq1:1iro a roaster sh1:1tdown. When the initial conditions for an accident cannot be met, action must be taken to preclude the accident from occurring. If the spent fuel storage pooi'level is less than required, the movement of irradiated fuel assemblies in the.spent fuel storage pool is suspended immediately. Suspension of this activity shall not preclude completion of movement of an irradiated fuel assembly to a safe position. This effectively precludes a spent fuel handling accident from occurring.

SURVEILLANCE SR 3.7.8.1 REQUIREMENTS t

This SR verifies that sufficient water is available in the event of a fuel handling accident. The water level in the spent fuel storage pool must be checked periodically. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. . The Frequency is acceptable, based on operating experience, considering that the water volume in the pool is normally stable, and all water level changes are controlle~-it'procedures.

- !facility _ ._!T_S_C_R-_1_83

___ r:\ (continued) DAEC B 3.7-38 - \J-TSG~ 120
Spent Fuel Storage Pool Water Level

- B 3.7.8 BASES (continued)

REFERENCES 1. UFSAR, Section 9.1.2.

2. UFSAR, Section 15.2.5.

3. -. 10 CFR-50.67.

4. Regulatory Guide 1.183.

!183 DAEC B 3.7-39}}

v t e Letter Sequence Supplement
EPID:L-2020-LLQ-0002, Certification of Permanent Cessation of Power Operations (Approved, Closed)
Initiation Request, Request, Request, Request Acceptance... Supplement Administration Questions 28 May 2020 Answers 26 June 2020 Results Approval Other: ML20225A000
MONTHYEAR2020-02-13 [Table View]

L-2019-157, Supplement to License Amendment Request (TSCR-183): Application to Revise Technical Specifications for the Permanently Defueled Condition

Text

SUMMARY

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

Enclosures:

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L-2019-157, Supplement to License Amendment Request (TSCR-183): Application to Revise Technical Specifications for the Permanently Defueled Condition

Text

SUMMARY

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

Enclosures:

Navigation menu

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