Text

Nuclear Management Company, LLC - License Amendment Regarding Adoption of Consolidated Line Item Improvement Process (CLIIP) Technical Specification Change
	ML033650404
Person / Time
Site:	Palisades, Point Beach, Prairie Island, Duane Arnold
Issue date:	12/23/2003
From:	Rogoff J; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML033650404 (239)
	v • d • e

Committed toiNudearEXce Nuclear Management Company, LLC December 23, 2003 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Duane Arnold Energy Center Point Beach Nuclear Plant Units I and 2 Docket 50-331 Dockets 50-266 and 50-301 License No. DPR-49 License Nos. DPR-24 And DPR-27 Palisades Nuclear Plant Prairie Island Nuclear Generating Plant Units I and 2 Docket 50-255 Dockets 50-282 and 50-306 License No. DPR-20 License Nos. DPR-42 and DPR-60 Adoption Of Consolidated Line Item Improvement Process (CLIIP) Technical Specification Change Regarding Technical Specification Task Force (TSTF) Generic Traveler - TSTF-359. Revision 9. "Increased Flexibility In Mode Restraints"

Reference:

Federal Register Notice (FRN), 68 FR 16579, Dated April 4, 2003.

Pursuant to 10 CFR 50.90, the Nuclear Management Company, LLC (NMC) is submitting a license amendment request to change Appendix A, Technical Specifications (TS), to the licenses listed above. The proposed amendment would modify the TS requirements for mode change limitations pursuant to the referenced CLIIP, as prescribed in Nuclear Energy Institute (NEI) Industry Implementation Guidance for adopting TSTF-359, Revision 9 (NEI 03-10).

Enclosure I provides a description of the proposed change (including tables of affected TS for each site with a brief descriptor of the change); the requested confirmation of applicability; and, plant-specific verifications. Enclosure II provides the existing TS pages marked up to show the proposed change for each unit. Enclosure III provides revised (typed) TS pages for each unit. Enclosure IV provides the existing TS Bases pages marked up to reflect the proposed changes for each unit.

ADD 700 First Street

Hudson, Wisconsin 54016 Telephone: 715.377.3300

December 23, 2003 Page 2 NMC is asking that the implementation of the revised TS be made within 120 days of NRC approval. The enclosed changes to the TS Bases will be implemented concurrently with the TS change in accordance with the TS Bases Control Program.

These proposed changes have been approved by the Plant Operations Review Committee at each site and reviewed by the Offsite Safety Review Committees in accordance with the requirements of each site's Quality Assurance Program.

In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated state officials.

This letter makes no new commitments or changes to any existing commitments.

Please contact Tony Browning at (319) 851-7750 if you have any questions regarding this application.

I declare under penalty of perjury that the foregoing is true and correct.

an M. Rogoff Vice President & Counsel Nuclear Management Company, LLC cc: Regional Administrator, USNRC Region III Project Managers, Office of Nuclear Reactor Regulation (Duane Arnold Energy Center, Palisades Nuclear Plant, Point Beach Nuclear Plant, Prairie Island Nuclear Generating Plant)

NRC Resident Inspectors (Duane Arnold Energy Center, Palisades Nuclear Plant, Point Beach Nuclear Plant, Prairie Island Nuclear Generating Plant)

State Officials (Iowa, Minnesota, Michigan, and Wisconsin)

Enclosures:

I) DESCRIPTION AND CONFIRMATION OF APPLICABILITY

11) PROPOSED TECHNICAL SPECIFICATION CHANGES (markups)

Ill) PROPOSED TECHNICAL SPECIFICATION CHANGES (typed)

IV) PROPOSED BASES CHANGES (markups) 700 First Street . Hudson, Wisconsin 54016 Telephone: 715.377.3300

NUCLEAR MANAGEMENT COMPANY (NMC)

ADOPTION OF CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (CLIIP)

TECHNICAL SPECIFICATION CHANGE TSTF-359, REVISION 9, INCREASED FLEXIBILITY IN MODE RESTRAINTS" ENCLOSURE I DESCRIPTION AND CONFIRMATION OF APPLICABILITY

Enclosure I Page 1 of 12

1.0 DESCRIPTION

The proposed amendment would modify Technical Specifications (TS) requirements for mode change limitations in Limiting Condition for Operation (LCO) 3.0.4 and Surveillance Requirement (SR) 3.0.4. The affected TS and a brief description of the proposed changes for each site are included in Tables 1 - 4 of this Enclosure.

The proposed changes are consistent with Nuclear Regulatory Commission (NRC) approved Technical Specification Task Force (TSTF) Standard TS (STS) change TSTF-359 Revision 8, as modified by the notice in the Federal Register published on April 4, 2003. That Federal Register Notice (FRN), 68 FR 16579, announced the availability of this TS improvement through the CLIIP. TSTF-359 Revision 8 was subsequently revised to incorporate the modifications discussed in that FRN and other minor changes, and was submitted to NRC on April 28, 2003, as TSTF-359 Revision 9.

2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation NMC has reviewed the safety evaluation included in FRN 68 FR 16579, as part of the CLIIP. This review included a review of the NRC Staffs evaluation, as well as the information provided to support TSTF-359 Revision 8, and included the updates made in TSTF-359, Revision 9. NMC has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC Staff are applicable to these NMC sites, and justify the incorporation of the changes into their respective TS.

2.2 Optional Changes and Variations NMC is not proposing any variations or deviations from the TS changes described in TSTF-359 Revision 9 and the NRC Staffs model safety evaluation contained in FRN 68 FR 16579, with the following exception.

For Prairie Island, Units 1 & 2, the following deviation is requested.

Description:

The Prairie Island TS Limiting Condition for Operation (LCO) 3.1.3, Isothermal Temperature Coefficient (ITC) differs significantly from the STS.

Currently Prairie Island TS include a Note in LCO 3.1.3 Condition C, which states that LCO 3.0.4 does not apply. With the revised LCO 3.0.4, NMC proposes to include a similar Note in LCO 3.1.3 Condition C, which states that LCO 3.0.4.c applies.

Justification: Prairie Island TS include SR 3.1.3.3, which requires verification that the ITC will be within limits at the core end of cycle (EOC). This SR must be performed prior to reaching 70% Rated Thermal Power (RTP) after each refueling outage. If the SR is performed and subsequently not met, then LCO 3.1.3, Condition C would be entered. Condition C allows operation to continue, but the Required Action requires the core design to be re-evaluated prior to

Enclosure I Page 2 of 12 reaching an all rods out boron concentration of 300 ppm. If, subsequent to the failure of SR 3.1.3.3, but prior to the completion of the re-evaluation, the plant has either not completed power ascension into the Mode of Applicability or has exited the Mode of Applicability for some other reason (e.g., shut down), LCO 3.0.4.a would not allow entry into the Mode of Applicability (i.e., Modes 1, 2 and 3), as the ACTIONS do not allow indefinite operation in this Condition. Thus, absent relief from LCO 3.0.4, subsequent plant restart and/or power ascension would not be allowed. Because this is a variable or parameter that does not lend itself readily to the use of the new LCO 3.0.4.b, NMC proposes to include a Note invoking LCO 3.0.4.c in Required Action C.1 of LCO 3.1.3 in the Prairie Island TS.

As discussed in the Bases to LCO 3.1.3, the ITC lower limit is only of concern at EOC. For this reason the Completion Time allows plant operation to continue until "reaching the equivalent of an equilibrium RTP all rods out boron concentration of 300 ppm." This Completion Time defines the core "end of cycle" at which the lower ITC limit is of concern. Prior to this point in the core operating cycle, the plant can operate safely without concern for the ITC lower limit.

The wording of Required Action C.1 and the associated Completion Time clearly intended to allow plant operation to continue. The current Note intended power ascension to be allowed if Condition C was entered prior to entering the Mode of Applicability. The plant can continue to operate safely until the limit in the Completion Time is reached. If the Required Action C.1 is not completed by this time, Condition D would be entered, and the Mode of Applicability would be exited. Re-entering the Mode of Applicability is not allowed (neither currently nor with the proposed new LCO 3.0.4.c allowance) without completing the re-evaluation, as the Completion Time for Condition C would have already expired.

Thus, the proposed LCO 3.0.4.c allowance will preclude an unintended hardship with the adoption of TSTF-359, is consistent with the current licensing basis, and will not allow any undue relaxation in current operation.

Due to differences between each site's TS and TS Bases and their corresponding model STS (see Table below) in several cases variances from the TSTF marked-up changes are made. These variances are discussed below for each site and do not affect the adoption or application of TSTF-359, Revision 9.

Site STS NUREG STS Title Duane Arnold 1433 Rev. 2 Standard Technical Specifications, General Electric Plants, BWR/4 Palisades 1432 Rev. 2 Standard Technical Specifications, Combustion Engineering Plants Point Beach 1431 Rev. 2 Standard Technical Specifications, Westinghouse Plants Prairie Island 1431 Rev. 2 Standard Technical Specifications, Westinghouse Plants

Enclosure I Page 3 of 12 Duane Arnold Energy Center (DAEC)

1. In the TSTF mark-ups, STS 3.4.6, RCS Leakage Detection Instrumentation, is modified by deleting the "LCO 3.0.4 is not applicable" Note to the ACTIONS.

The equivalent DAEC TS is LCO 3.4.5 (same title) and the equivalent Note, which is also being deleted, is located in Required Actions A and B.

2. In the TSTF mark-ups, STS 3.6.3.1, Primary Containment Hydrogen Recombiners, is modified by deleting the "LCO 3.0.4 is not applicable" Note to Required Action A. 1. DAEC TS do not have an equivalent LCO, so these changes are not needed in the DAEC TS to adopt the TSTF.

3. In the TSTF mark-ups, STS 3.6.3.2, Drywell Cooling System Fans, is modified by deleting the "LCO 3.0.4 is not applicable" Note to Required Action A.1. DAEC TS do not have an equivalent LCO, so these changes are not needed in the DAEC TS to adopt the TSTF.

4. In the TSTF mark-ups, STS 3.6.3.4, Containment Atmosphere Dilution (CAD)

System, is modified by deleting the "LCO 3.0.4 is not applicable" Note to Required Action A.1. The equivalent DAEC TS is LCO 3.6.3.1 (same title).

However, the DAEC TS does not have such a Note and thus, do not require this change.

5. In the TSTF mark-ups, STS 3.7.3, Diesel Generator (DG) [1 B] Standby Service Water System, is modified by deleting the "LCO 3.0.4 is not applicable" Note to the Required Actions for Condition A. DAEC TS do not have an equivalent LCO, so these changes are not needed in the DAEC TS to adopt the TSTF.

In addition, changes to the DAEC TS BASES are being made for consistency with the above TS changes, as allowed by the TS BASES Control Program of TS 5.5.10.

Palisades

1. Use of the term "unit" in applicable TSTF-359 LCO and Bases sections has been replaced with the word 'plant." Palisades TS currently uses the word "plant" instead of "unit" (example: LCO 3.0.3.) This change will maintain continuity with existing TS.

2. The STS uses the terminology "Reactor Coolant System (RCS)" in a number of LCOs, and corresponding Bases. Palisades uses the equivalent term "Primary Coolant System (PCS)" to describe the same system.

3. Palisades TS do not contain equivalent TS for the following TSTF-359 changes. Therefore, no changes are needed for any of the following:

Enclosure I Page 4 of 12 a) In NUREG-1 432, there are equivalent series of LCOs for plants with digital and analog control systems. Palisades has analog systems and thus, uses that series of LCOs in the STS.

b) LCO 3.3.1, RPS Instrumentation - Operating (Analog), deletion of the Note in Required Action E.1.

c) LCO 3.3.2, RPS Instrumentation - Shutdown (Analog), deletion of the Notes in Required Actions B.1 and D.1.

d) LCO 3.3.4, ESFAS Instrumentation (Analog), deletion of the Note in Required Action E.1.

e) LCO 3.3.6, DG - LOVS (Analog), deletion of the Note in Required Action B.2.1.

f) LCO 3.3.9, CVCS Isolation Signal (Analog), deletion of the Note in Required Action C.I.

g) LCO 3.5.3, ECCS - Shutdown, insertion of CEOG Insert 2.

h) LCO 3.6.9, HMS (Atmospheric and Dual), deletion of Note in Required Action A.1.

4. The following shows the minor variations from TSTF-359 changes due to Palisades-specific TS numbering:

a) In the TSTF mark-ups, STS 3.3.1 is modified by deleting the "LCO 3.0.4 is not applicable" Note in Required Action B.1. The equivalent change in the Palisades TS deletes the same Note in LCO 3.3.1 Required Action E.1 b) In the TSTF mark-ups, STS 3.3.4 is modified by deleting the "LCO 3.0.4 is not applicable" Note in Required Action C.1. The equivalent change in the Palisades TS deletes the same Note in LCO 3.3.3 Required Action B.1 c) In the TSTF mark-ups, STS 3.3.11 is modified by deleting the "LCO 3.0.4 is not applicable" Note to the ACTIONS. The equivalent change in the Palisades TS deletes the same Note to the LCO 3.3.7 ACTIONS.

d) In the TSTF mark-ups, STS 3.3.12 is modified by deleting the 'LCO 3.0.4 is not applicable" Note to the ACTIONS. The equivalent change in the Palisades TS deletes the same Note to the LCO 3.3.8 ACTIONS.

e) In the TSTF mark-ups, STS 3.4.12 adds Note 2 to the ACTIONS that LCO 3.0.4.b is not applicable to PORVs when entering MODE 4. The Palisades TS do not have the STS Note 1 to the ACTIONS. Thus, the equivalent change in the Palisades TS adds the same Note to the LCO 3.4.12 ACTIONS as Note 1.

Enclosure I Page 5 of 12 f) In the TSTF mark-ups, STS 3.6.8 is modified by deleting the "LCO 3.0.4 is not applicable" Note in Required Action A.1. The equivalent change in the Palisades TS deletes the same Note to LCO 3.6.7 Required Action A.1.

Point Beach Nuclear Plant (PBNP)

1. The changes to STS 3.3.4, Remote Shutdown System, are not being adopted. STS 3.3.4, Remote Shutdown System, was not adopted as part of PBNP's conversion to the Improved Technical Specifications (ITS). Therefore, this change is not applicable to PBNP.

2. The changes to STS 3.4.12, Low Temperature Overpressure Protection (LTOP) System, are being slightly modified to accommodate an existing Note.

PBNP TS 3.4.12, LTOP, contains an existing Note regarding Mode change restrictions that is not in the STS. The existing Note is consistent with the Note being added by TSTF-359. The variation being proposed consists of separately numbering the two Notes and modifying the TS Bases accordingly.

A statement in the Bases for the existing Note, which referred to TS language being deleted by TSTF-359, is also being deleted. Therefore, this change is consistent with the intent of TSTF-359.

3. The changes to PBNP TS 3.4.15, RCS Leakage Detection Instrumentation, differ slightly from TSTF-359 due to plant-specific differences between the PBNP TS and STS. The STS 3.4.15 Note specified for deletion in TSTF-359 is contained in two separate but identical Notes in PBNP TS 3.4.15.

Therefore, both the corresponding Notes are being proposed for deletion. The corresponding discussion in the TS Bases, associated with these two Notes, is also being deleted. Therefore, this change is consistent with the intent of TSTF-359.

4. The changes to STS 3.6.8, Hydrogen Recombiners, are not being adopted.

STS 3.6.8, Hydrogen Recombiners, was not adopted as part of PBNP's conversion to the ITS. Therefore, this change is not applicable to PBNP.

5. The changes to STS 3.6.9, Hydrogen Mixing System, are not being adopted.

STS 3.6.9, Hydrogen Mixing System, was not adopted as part of PBNP's conversion to the ITS. Therefore, this change is not applicable to PBNP.

6. PBNP relies on Auxiliary Feedwater (AFW) for startup. Therefore, the appropriate bracketed information in STS 3.7.5, Auxiliary Feedwater System, is being adopted in accordance with the Reviewers Note. The corresponding bracketed information is being adopted in the Bases for this TS.

7. The changes to the Bases for STS 3.7.5, Auxiliary Feedwater System, are being modified to substitute the term 'AFW pump system' for the term 'AFW train'. PBNP TS LCO 3.7.5, specifies Operability requirements for AFW 'pump

Enclosure I Page 6 of 12 systems' (vice the STS terminology of AFW 'trains'). This change is consistent with PBNP design and the PBNP TS and does not change the intent of TSTF-359.

8. The changes to STS 3.8.1, AC Sources - Operating, and its associated Bases, are being modified to substitute the term 'standby emergency power source' for the term 'DG'. PBNP TS LCO 3.8.1 specifies Operability requirements for 'standby emergency power sources' (vice the STS terminology of 'diesel generators [DGs]'). This change is consistent with PBNP design and the PBNP TS and does not change the intent of TSTF-359.

Prairie Island Nuclear Generating Plant (PINGP)

1. PINGP does not have STS LCO 3.3.4 for a Remote Shutdown System. The NUREG-1431 changes included in TSTF-359 for this LCO do not apply to PINGP TS and Bases and are not included.

2. Due to the cold overpressurization protection need to progressively isolate safety injection (SI) pumps as the RCS temperature is reduced in Mode 4, the STS LTOP requirements of LCO 3.4.12 are split into two specifications in PINGP TS, LCO 3.4.12 and 3.4.13. According to TSTF-359, Rev 9, Attachment 4, "Qualitative Risk Assessment Supporting Increased Flexibility in MODE Restraints," the controls on cold overpressurization are important in "the lower end of Mode 4." The intent of "lower end of Mode 4" was to apply to all temperatures included in the other Conditions of the Applicability of MODE 4 for the STS LTOP Specification. Therefore, the TSTF-359 Note prohibiting use of LCO 3.0.4.b to enter MODE 4 in STS LCO 3.4.12 is appropriately applied to both PINGP TS LCO 3.4.12 and 3.4.13.

3. In the TSTF mark-ups, STS 3.4.15, RCS Leakage Detection Instrumentation, is modified by deleting the "LCO 3.0.4 is not applicable" Note to the ACTIONS. The equivalent PINGP TS is LCO 3.4.16 (same title) and the equivalent Note is also being deleted.

4. In the TSTF mark-ups, STS 3.4.16, RCS Coolant Activity, is modified by deleting the "LCO 3.0.4 is not applicable" Note to Required Action A.1 and replacing it with a LCO 3.0.4.c is applicable Note. The equivalent PINGP TS is LCO 3.4.17 (same title) and the equivalent changes also being added.

5. In the TSTF mark-ups, STS 3.5.3, ECCS - Shutdown, is modified by adding a LCO 3.0.4.b is not applicable Note to the ACTIONS for the ECCS high head subsystem. The PINGP TS use the terminology "safety injection" or "SI" in an equivalent Note.

6. In the TSTF mark-ups, STS 3.6.8, Hydrogen Recombiner, is modified by deleting the "LCO 3.0.4 is not applicable" Note to Required Action A.1. The

Enclosure I Page 7 of 12 equivalent PINGP TS is LCO 3.6.7 (same title) and the equivalent Note is also being deleted.

7. PINGP does not have STS LCO 3.6.9 for a Hydrogen Mixing System. The NUREG-1431 changes included in TSTF-359 for this LCO do not apply to PINGP TS and Bases and are not included.

8. In the TSTF mark-ups, STS 3.7.4, Atmospheric Dump Valves (ADVs), is modified by deleting the "LCO 3.0.4 is not applicable" Note to Required Action A.1. PINGP does not have an LCO for its ADVs. The equivalent TSTF LCO and Bases changes have been made to PINGP LCO 3.7.4, "Steam Generator (SG) Power Operated Relief Valves (PORVs)." Therefore, this change is consistent with the intent of TSTF-359.

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination NMC has reviewed the proposed no significant hazards consideration determination published in FRN 68 FR 16579. NMC has concluded that the proposed no significant hazards consideration determination presented in the FRN is applicable to these sites and is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).

3.2 Verification and Commitments As discussed in the notice of availability for this CLIIP published in FRN 68 FR 16579, plant-specific verifications were performed as follows:

NMC has established TS Bases for LCO 3.0.4 and SR 3.0.4 at each site, which state that use of the TS mode change limitation flexibility established by LCO 3.0.4 and SR 3.0.4 is not to be interpreted as 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 TS Applicability.

This proposal also includes changes to the Bases for LCO 3.0.4 and SR 3.0.4 that provide details on how to implement the new requirements. The Bases changes provide guidance for changing Modes or other specified conditions in the Applicability when an LCO is not met. The Bases changes describe in detail how: LCO 3.0.4.a allows entry into a MODE or other specified condition in the Applicability with the LCO not met 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; LCO 3.0.4.b allows entry into a MODE or other specified condition in the Applicability with the LCO not met 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; and LCO 3.0.4.c allows entry into a MODE or other

Enclosure I Page 8 of 12 specified condition in the Applicability with the LCO not met based on a Note in the Specification, which is typically applied to Specifications which describe values and parameters (e.g., Reactor Coolant System Specific Activity), though it may be applied to other Specifications based on NRC plant-specific approval. The Bases also state that any 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 1.182, "Assessing and Managing Risks Before Maintenance Activities at Nuclear Power Plants," and that the results of the risk assessment shall be considered in determining the acceptability of entering the MODE or other specified condition in the Applicability, and any corresponding risk management actions. In addition, the bases state that upon entry into a MODE or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicable Conditions and Required Actions until the Condition is resolved, until the LCO is met, or until the unit is not within the Applicability of the Technical Specification. The Bases also state that SR 3.0.4 does not restrict changing MODES or other specified conditions of the Applicability when a Surveillance has not been performed within the specified Frequency, provided the requirement to declare the LCO not met has been delayed in accordance with SR 3.0.3.

Finally, each site's TS have a Bases Control Program consistent with Section 5.5 of their respective STS (identified in Section 2.2 above), and the equivalent of STS SR 3.0.1 and associated Bases.

4.0 ENVIRONMENTAL EVALUATION NMC has reviewed the environmental evaluation included in the Staffs model safety evaluation included in FRN 68 FR 16579 and concludes that the Staffs findings presented in that evaluation are applicable to these sites and the evaluation is hereby incorporated by reference into this application.

Enclosure I Page 9 of 12 Table 1 Proposed Changes to the Duane Arnold Energy Center TS Affected TS Description of Change LCO 3.0.4 Addition of risk-informed evaluation of Mode changes.

SR 3.0.4 Clarification of relationship to SR 3.0.3.

3.3.3.1 Post Accident Monitoring Deletion of the Note exempting the Instrumentation LCO ACTIONS from LCO 3.0.4 3.3.3.2 Remote Shutdown System Deletion of the Note exempting the LCO ACTIONS from LCO 3.0.4 3.3.6.3 Low-Low Set (LLS) Deletion of the Note exempting Instrumentation Required Action B.1 from LCO 3.0.4.

3.4.5 Reactor Coolant System (RCS) Deletion of the Note exempting Leakage Detection Required Actions A.1 and B.1 from Instrumentation LCO 3.0.4 3.4.6 RCS Specific Activity Deletion of the Note exempting Required Action A.1 from LCO 3.0.4.

Addition of Note stating applicability of LCO 3.0.4.c to Required Action A.1.

3.4.7 Residual Heat Removal Deletion of the Note exempting the Shutdown Cooling System - Hot LCO from LCO 3.0.4 Shutdown 3.5.1 Emergency Core Cooling Addition of Note stating that LCO Systems (ECCS) - Operating 3.0.4.b is not applicable to the High Pressure Coolant Injection System (HPCI) 3.5.3 Reactor Core Isolation Cooling Addition of Note stating that LCO (RCIC) System 3.0.4.b is not applicable to RCIC 3.7.1 Residual Heat Removal Service Deletion of the Note exempting Water System Required Action A. 1 from LCO 3.0.4.

3.7.5 Control Building Chiller (CBC) Deletion of the Note for the "one time System only" exemption from LCO 3.0.4 and companion footnote.

3.8.1 AC Sources - Operating Addition of Note stating that LCO 3.0.4.b is not applicable to diesel generators (DGs)

Enclosure I Page 10 of 12 Table 2 Proposed Changes to the Palisades TS Affected TS Description of Change LCO 3.0.4 Addition of risk-informed evaluation of Mode changes.

SR 3.0.4 Clarification of relationship to SR 3.0.3.

3.3.1 Reactor Protective System Deletion of the Note exempting Instrumentation Required Actions E.1 and E.2 from LCO 3.0.4 3.3.3 Engineered Safety Features Deletion of the Note exempting Instrumentation Required Actions B.1 and B.2 from LCO 3.0.4 3.3.7 Post Accident Monitoring Deletion of the Note exempting the Instrumentation LCO ACTIONS from LCO 3.0.4.

3.3.8 Alternate Shutdown System Deletion of the Note exempting the LCO ACTIONS from LCO 3.0.4 3.4.11 Pressurizer Power Operated Deletion of the Note exempting the Relief Valves (PORVs) LCO ACTIONS from LCO 3.0.4.

3.4.12 Low Temperature Overpressure Modification of the Note exempting the Protection System LCO ACTIONS from LCO 3.0.4. Note now states that LCO 3.0.4.b is not applicable to the PORVs when entering MODE 4.

3.4.15 Primary Coolant System (PCS) Deletion of the Note exempting the Leakage Detection LCO ACTIONS from LCO 3.0.4.

Instrumentation 3.4.16 PCS Specific Activity Modification of the Note exempting Required Actions A.1 and A.2 from LCO 3.0.4. Note now states that LCO 3.0.4.c is applicable.

3.6.7 Hydrogen Recombiners Deletion of the Note exempting Required Action A.1 from LCO 3.0.4.

3.7.4 Atmospheric Dump Valves Deletion of the Note exempting Required Action A.1 from LCO 3.0.4.

3.7.5 Auxiliary Feedwater System Addition of Note stating that LCO 3.0.4.b is not applicable.

3.8.1 AC Sources - Operating Addition of Note stating that LCO 3.0.4.b is not applicable to diesel generators (DGs)

Enclosure I Page 11 of 12 Table 3 Proposed Changes to the Point Beach TS Affected TS Description of Change LCO 3.0.4 Addition of risk-informed evaluation of Mode changes.

SR 3.0.4 Clarification of relationship to SR 3.0.3.

3.3.3 Post Accident Monitoring Deletion of Note 1 exempting the LCO Instrumentation ACTIONS from LCO 3.0.4.

3.4.11 Pressurizer Power Operated Deletion of Note 2 exempting the LCO Relief Valves (PORVs) ACTIONS from LCO 3.0.4.

3.4.12 Low Temperature Overpressure Addition of Note 2 stating that LCO Protection (LTOP) System 3.0.4.b is not applicable when entering MODE 4.

3.4.15 Reactor Coolant System (RCS) Deletion of the two Notes exempting Leakage Detection the Required Actions for Conditions A Instrumentation and B from LCO 3.0.4.

3.4.16 RCS Specific Activity Deletion of the Note exempting the Required Actions for Condition A from LCO 3.0.4. Addition of Note specifying applicability of LCO 3.0.4.c to the Required Actions for Condition A.

3.5.3 Emergency Core Cooling Addition of Note stating that LCO Systems (ECCS) - Shutdown 3.0.4.b is not applicable to ECCS high head subsystem.

3.7.4 Atmospheric Dump Valve (ADV) Deletion of the Note exempting Flowpaths Required Action A.1 from LCO 3.0.4.

3.7.5 Auxiliary Feedwater (AFW) Addition of Note stating that LCO 3.0.4.b is not applicable.

3.8.1 AC Sources - Operating Addition of Note stating that LCO 3.0.4.b is not applicable to standby emergency power sources.

Enclosure I Page 12 of 12 Table 4 Proposed Changes to the Prairie Island TS Affected TS Description of Change LCO 3.0.4 Addition of risk-informed evaluation of Mode changes.

SR 3.0.4 Clarification of relationship to SR 3.0.3.

3.1.3 Isothermal Temperature Modified Required Action C.1 Note to Coefficient (ITS) make LCO 3.0.4.c applicable 3.3.3 Event Monitoring (EM) Deletion of the Note exempting the Instrumentation LCO ACTIONS from LCO 3.0.4 3.4.11 Pressurizer Power Operated Deletion of the Note exempting the Relief Valves (PORVs) LCO ACTIONS from LCO 3.0.4 3.4.12 Low Temperature Overpressure Addition of Note stating that LCO Protection (LTOP) - Reactor 3.0.4.b is not applicable to LTOP when Coolant System Cold Leg entering MODE 4 Temperature (RCSCLT) >

Safety Injection (SI) Pump Disable Temperature 3.4.13 Low Temperature Overpressure Addition of Note stating that LCO Protection (LTOP) - Reactor 3.0.4.b is not applicable to LTOP when Coolant System Cold Leg entering MODE 4 Temperature (RCSCLT) <

Safety Injection (SI) Pump Disable Temperature 3.4.16 RCS Leakage Detection Deletion of the Note exempting the Instrumentation LCO ACTIONS from LCO 3.0.4 3.4.17 RCS Specific Activity Modified Required Actions Note to make LCO 3.0.4.c applicable 3.5.3 ECCS - Shutdown Addition of Note stating that LCO 3.0.4.b is not applicable to Si 3.6.7 Hydrogen Recombiner Deletion of the Note exempting the LCO ACTIONS from LCO 3.0.4 3.7.3 Main Feedwater Regulation Deletion of the Note exempting the Valves (MFRVs) and MFRV LCO ACTIONS from LCO 3.0.4 Bypass Valves 3.7.4 Steam Generator (SG) Power Deletion of the Note exempting the Operated Relief Valves LCO ACTIONS from LCO 3.0.4 (PORVs) 3.7.5 Auxiliary Feedwater (AFW) Addition of Note stating that LCO System 3.0.4.b is not applicable to AFW 3.8.1 AC Sources - Operating Addition of Note stating that LCO 3.0.4.b is not applicable to diesel generators (DGs)

NUCLEAR MANAGEMENT COMPANY (NMC)

ADOPTION OF CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (CLIIP)

TECHNICAL SPECIFICATION CHANGE TSTF-359, REVISION 9, "INCREASED FLEXIBILITY IN MODE RESTRAINTS" ENCLOSURE II PROPOSED TECHNICAL SPECIFICATION CHANGES (markups)

NUCLEAR MANAGEMENT COMPANY (NMC)

ADOPTION OF CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (CLIIP)

TECHNICAL SPECIFICATION CHANGE TSTF-359, REVISION 9, "INCREASED FLEXIBILITY IN MODE RESTRAINTS' DUANE ARNOLD ENERGY CENTER (DAEC)

TS PAGES (markups)

DAEC LCO Inserts LCO Insert 1 (LCO 3.0.4)

When an LCO is not met, entry into a 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 individual 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.

LCO INSERT 2 (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. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

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 shutdown of the unit.

LCO INSERT 3 (LCO 3.5.1, ECCS - OPERATING)

NOTE -----------------------------------------------

LCO 3.0.4.b is not applicable to HPCI.

DAEC LCO Inserts LCO Insert 4 (LCO 3.5.3, RCIC SYSTEM)

NOTE----------------------------------------------

LCO 3.0.4.b is not applicable to RCIC.

LCO Insert 5 (LCO 3.8.1, AC SOURCES - OPERATING)

NOTE-----------------------------------------------

LCO 3.0.4.b is not applicable to DGs.

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a. MODE 2 within 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ;

b. MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c. MODE 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, and 3.

LCO 3.0.4 When an LCO is not met, entry into a MODE or other LOcntinued epnrtion in thc AMOlDEorlothr shall p e+ be made

/nser i wheen+he ass"ciate "

AChION o emtned permlit Xerox~~~~~~~~~~~~~~~~f wvl 111 Xr WH ATIl .11. oplrvv OfW/~vlI MOD rAr othe specified conditions in the Applicability

+ho+~~~~~~-

_ZS -pi) ,,;h AGT-INSl wtl e+' n-tnp of a shutdown of the unit.

(continued)

DAEC 3.0-1 Awcendment 223TSCR-064

LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 Exeeptions to this Speeification are stated in the (continued) individual Specification-.

LCD 3.0.4 is only applicabic for entry into a MODEorE other specified condition in the Applicability in MODES 1, 2, and 3.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 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 not 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 Specification 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.

When a 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.

(continued)

DAEC 3.0-2 Amendment 234TSCR-064I

LCO Applicability 3.0 3.0 LCO APPLICABILITY (continued)

LCO 3.0.7 Special Operations LCOs in Section 3.10 allow specified Technical Specifications (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Special Operations LCOs is optional. When a Special Operations LCO is desired to be met but is not met, the ACTIONS of the Special Operations LCO shall be met. When a Special Operations LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Specifications.

DAEC 3.0-3 Amendment 223

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other 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 except as provided in SR 3.0.3.

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.

If a Completion Time requires periodic performance on a "once per . . ." basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 246

SR Applicability 3.0 3.0 SR APPLICABILITY (continued) csp ¶J . n a .1--,ALI r.J . I I --- :I - - . .- -nr

- - - - -I-

- _ : r: _i

- -I i

_ _ s I _

I IJl V. -t I II '.4 I IV.V

- - IS I 1 1 I I I.. V kVI IV I I 1 LI. 1-

/Ap plicability of an LCO shall not be made unless the LCO's O Surveillaneez have becn met within their specified LCO Fnr pequency. This provision shail not prevent entry iven Insert2 MODES or other specified conditions in the Applicability shI-- 4 -- ---. . . -- A - . .-'4- L. A f'-rTrKlf' -- 4. L -4. - -- --- 1- -Z MI e 4 aI- :c 9q Utt db J LU t~U;.;j1) y W;0 t.;l tt0tId,

fU . I- F Mmett: l fL pewt fd

4 Qhii: tdlrA A:f th" ni Crl 0 r% A 4. - - , -.- 1-I4-,k I - C- --

T+--Is I4 ' kArfrC' ,--. +,

.1I - -vI.I S 11 j 1/4i.1 r I . - 11/4. I v5 1 J ... 1-d I -154l IAI11/4.

speeified condition in the Applicability in MODES 1, 2, and 3.

DAEC 3.0-5 Amnendme~nt 22-3TSCR-064 I

PAM Instrumentation 3.3.3.1 3.3 INSTRUMENTATION 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3.1 The PAM instrumentation for each Function in Table 3.3.3.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

NOTES------------------------------------

1.LC0 3.0.4 is not applicable.

%rSeparate Condition entry is allowed for each Function. For Function 6, I Separate Condition entry is allowed for each penetration flow path.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required 30 days with one required channel to OPERABLE channel inoperable. status.

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.6.

not met.

C. One or more Functions C.1 Restore one required 7 days with two required channel to OPERABLE channels inoperable. status.

(continued)

DAEC 3.3-21 Amendmlen 223TSCR-064 I

Remote Shutdown System 3.3.3.2 3.3 INSTRUMENTATION 3.3.3.2 Remote Shutdown System LCO 3.3.3.2 The Remote Shutdown System Functions shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

NOTES-----------------------------

1.LC0 3.0.4 is not applicable.

%-Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 30 days Functions inoperable. Function to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Verify each required control circuit and 24 months transfer switch is capable of performing the intended function.

(continued)

DAEC 3.3-25 Amendment 223TSCR-064

LLS Instrumentation 3.3.6.3 3.3 INSTRUMENTATION 3.3.6.3 Low-Low Set (LLS) Instrumentation LCO 3.3.6.3 The LLS valve instrumentation for each Function in Table 3.3.6.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One LLS valve A.1 Restore channel(s) to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable due to OPERABLE status.

inoperable channel(s).

B. One or more Safety B.1- /-NOT-Relief Valves (SRVs) LC 3.0. is n with one Function 3 Apli Le channel inoperable. -- i >

Restore channel(s) to Prior to OPERABLE status. entering MODE 2 or 3 from MODE 4 C. -------- NOTE-------- C.1 Restore at least two 14 days Separate Condition channels per SRV to entry is allowed for OPERABLE status.

each SRV.

One or more SRVs with two or more Function 3 channels inoperable.

(continued)

DAEC 3.3-66 Amendment 223TSCR-064 I

RCS Leakage Detection Instrumentation 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Leakage Detection Instrumentation LCO 3.4.5 The following RCS leakage detection instrumentation shall be OPERABLE:

a. One channel of the Drywell Sump System; and

b. One channel of the Primary Containment Air Sampling System.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required Drywell Sump- - - NO System inoperable. L a cab A.1 Restore required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Drywell Sump System to OPERABLE status.

(continued)

DAEC 3.4-10 Amendment 223TSCR-064 I

RCS Leakage Detection Instrumentation 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Primary NOT Containment Air at a cabi Sampling System ---

inoperable.

B.1 Initiate action to Immediately restore required Primary Containment Air Sampling System to OPERABLE status.

C. Required Drywell Sump C.1 Restore required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months System inoperable. Drywell Sump System to OPERABLE status.

AND OR Required Primary Containment C.2 Restore required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Air Sampling Primary Containment System inoperable. Air Sampling System to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or AND C not met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months DAEC 3.4-11 Ameyndmecnt 2-23TSCR-064 I

RCS Specific Activity 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Specific Activity LCO 3.4.6 The specific activity of the reactor coolant shall be limited to DOSE EQUIVALENT 1-131 specific activity < 0.2 pCi/gm.

APPLICABILITY: MODE 1, MODES 2 and 3 with any main steam line not isolated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor coolant ------ NOTE-----------

specific activity LCO 3.0.4.c is *et

> 0.2 ICi/gm and applicable.

I

< 2.0 pCi/gm DOSE EQUIVALENT 1-131. Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months A.1 Determine DOSE EQUIVALENT I-131.

AND 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months A.2 Restore DOSE EQUIVALENT 1-131 to within limits.

B. Required Action and B.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion EQUIVALENT 1-131.

Time of Condition A not met. AND OR B.2.1 Isolate all main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months steam lines.

Reactor Coolant specific activity > 2.0 OR pCi/gm DOSE EQUIVALENT I-131.

(continued)

DAEC 3.4-13 ~~~24OTSCR-064 I Amendme~~~~~~~~~~~~~

RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES--------------------------

1. Both required RHR shutdown cooling subsystems and recirculation pumps may not be in operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY: MODE 3, with reactor steam dome pressure < the RCIC Steam Supply Line Pressure - Low isolation pressure.

ACTIONS

NTES------------------------

11rn) '

__V _J.

n) A -;,

V . Of IJ

- IVv

.- -F

-- I ;n IS I _UD I

-1 W .

2,.Separate Condition entry is allowed for each RHR shutdown cooling subsystem. I CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Initiate action to Immediately RHR shutdown cooling restore required RHR subsystems inoperable. shutdown cooling subsystem(s) to OPERABLE status.

AND (continued)

DAEC 3.4-15 Amendment 2E34TSCR-064 I

ECCS- Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of four safety/relief valves shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3, except High Pressure Coolant Injection (HPCI) is not required to be OPERABLE with reactor steam dome LCO pressure < 150 psig and ADS valves are not required to insert 3 be OPERABLE with reactor steam dome pressure < 100 psig.

ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. One Residual Heat A.1 Restore RHR pump to 30 Days Removal (RHR) pump OPERABLE status.

inoperable.

B. One low pressure ECCS B.1 Restore low pressure 7 days subsystem inoperable ECCS subsystem to for reasons other than OPERABLE status.

Condition A.

C. One Core Spray C.1 Restore Core Spray 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem inoperable. subsystem to OPERABLE AND status.

One or two RHR pump(s) OR inoperable. C.2 Restore RHR pump(s) 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

D. Both Core Spray D.1 Restore one Core 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystems inoperable. Spray subsystem to OPERABLE status.

(continued)

DAEC 3.5-1 Af~endme~nt 2123TSCR-064 I

RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.

APPLICABILITY: MODE 1, 3 with reactor steam dome pressure > 150 psig.

LCO MODES 2 and Insert 4 ACTIONS A,'

CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System A.1 Verify by Immediately inoperable. administrative means High Pressure Coolant Injection System is OPERABLE.

AND A.2 Restore RCIC System 14 days to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months dome pressure to

< 150 psig.

DAEC 3.5-12 Amcedmcnt 223TSCR-064 1

RHRSW System 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LCO 3.7.1 Two RHRSW subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHRSW pump A.1//-- NO inoperable. L 3.0. is ppli ble.

Restore RHRSW pump to 30 days OPERABLE status.

B. One RHRSW pump in each B.1 Restore one RHRSW 7 days subsystem inoperable. pump to OPERABLE status.

C. One RHRSW subsystem C.1 --------- NOTE--------

inoperable for reasons Enter applicable other than Conditions and Condition A. Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR)

Shutdown Cooling System-Hot Shutdown,"

for RHR shutdown cooling made inoperable by RHRSW System.

Restore RHRSW 7 days subsystem to OPERABLE status.

(continued)

DAEC 3.7-1 Amendment 223TS1R-064 I

CBC System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Control Building Chiller (CBC) System LCO 3.7.5 Two CBC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2. and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During Operations with a Potential for Draining the Reactor Vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CBC subsystem A.1 /- / NO inoperable. LC 3.0./is n picP z le.*

Restore CBC subsystem 30 days to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met in MODE 1, 2, or 3. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued) 2 TV_: : -II - - --- .- - - .- - - -- . -- - - - I- - I nnn

- Ini izsa temperapy a 1 oevancc whic chexpic Fe nH 8R' iY+/-c, +/-k'd- I DAEC 3.7-11 Ame~ndment 725OTSCR-064 I

AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class lE AC Electrical Power Distribution System; and

b. Two diesel generators (DGs).

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS ,/l _________

CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. for OPERABLE offsite circuit. AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter AND A.2 Restore offsite Prior to circuit to OPERABLE entering MODE 2 status. from MODE 3 or 4 (continued)

DAEC 3.8-1 Amend~~~~~~~~flent

~~~~~~~2-23TSCR-064 I

NUCLEAR MANAGEMENT COMPANY (NMC)

ADOPTION OF CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (CLIIP)

TECHNICAL SPECIFICATION CHANGE TSTF-359, REVISION 9,

'INCREASED FLEXIBILITY IN MODE RESTRAINTS" PALISADES NUCLEAR PLANT TS PAGES (markups)

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the plant shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the plant, as applicable, in:

a. MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b. MODE 4 within 31 hours3.587963e-4 days 0.00861 hours 5.125661e-5 weeks 1.17955e-5 months ; and

c. MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

LCO 3.0.4 When an LCO is net fmt, entFinte a MODE cr other specified conditien in the Applicability shall not be maede excpt when the associated ACTIONS to be entered permit continued operation in the MODE or ether specified condition in the Applicability for an unlimited period of time.

This Specification shall net prfcvnt changes in MODES or other specified eOndVAions in the Applieability that ar 1rcuired to comply with ACTIONS.

Exeepticns to this Specification are stated in the individual Specifications.

l See lnsert 1 a Palisades Nuclear Plant 3.0-1 Amendment No. 489,

INSERT 1 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made~not be made exeept when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimitd peried ef time.

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 Individual 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 plant.

Exoeptiens to this Spccifieetien ere stated in the individual Speeiffictions.

SR Applicability 3.0 3.0 SR APPLICABILITY SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall netonly be made Wfees-when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO Is not met due to Surveillances not having been met, entry Into a MODE or other specified condition In the Applicability shall only be made In accordance with LCO 3.0.4.

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 shutdown of the plant.

Palisades Nuclear Plant 3.0-4 Amendment No. 480,

RPS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One Loss of Load trip unit C.1 Restore trip unit and Prior to increasing or associated instrument associated instrument THERMAL POWER channel inoperable. channel to OPERABLE to 2 17% RTP status. following entry into MODE 3 D. One or more ZPM Bypass D.1 Remove the affected Immediately Removal channels ZPM Bypasses.

inoperable.

SOR D.2 Declare affected trip Immediately units inoperable.

E. NOTE----------- NOTE Not applicable to LCO 3.0.4 as net applicablc.

ZPM Bypass Removal Function.

_- --- -- E.1 Place one trip unit in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months One or more Functions AND with two RPS trip units or associated instrument -----------------NOTE-------------------

channels inoperable. Not applicable to High Startup Rate or Loss of Load Functions.

E.2 Restore one trip unit and 7 days associated instrument channel to OPERABLE status.

F. Two power range F.1 Restrict THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months channels inoperable. POWER to < 70% RTP.

Palisades Nuclear Plant 3.3.1 -2 Amendment No. 4-99,

ESF Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Engineered Safety Features (ESF) Instrumentation LCO 3.3.3 Four ESF bistables and associated instrument channels for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: As specified in Table 3.3.3-1.

ACTIONS

NOTE----------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. -------------- NOTE-------------- A.1 Place affected bistable 7 days Not applicable to RAS. in trip.

One or more Functions with one ESF bistable or associated instrument channel inoperable.

B. ---------------NOTE -------------- NOTE Not applicable to RAS. LCO 3.0.4 is not applicable.

One or more Functions with B.1 Place one bistable in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months two ESF bistables or trip.

associated instrument channels inoperable. AND B.2 Restore one bistable 7 days and associated instrument channel to OPERABLE status.

Palisades Nuclear Plant 3.3.3-1 Amendment No. 449,

PAM Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.7 The PAM instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

, rImUC

rd'JI Vft ------ - ------- - --- - ------------ - --------------------

1. LCO 3.0.4 is not soilicbac.

2.-Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required 30 days with one required channel channel to OPERABLE inoperable. status.

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.6.

met.

C. -----------NOTE-------------

Not applicable to hydrogen monitor channels.

One or more Functions C.1 Restore one channel to 7 days with two required channels OPERABLE status.

inoperable.

Palisades Nuclear Plant 3.3.7-1 Amendment No. 449,

Alternate Shutdown System 3.3.8 3.3 INSTRUMENTATION 3.3.8 Alternate Shutdown System LCO 3.3.8 The Alternate Shutdown System Functions in Table 3.3.8-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS j

KlT=C J I P-,

I 1

1. L1O 3.0.4 is not aeolicabIC.

2-.Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A. 1 Restore required 30 days Functions inoperable. Functions to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Palisades Nuclear Plant 3.3.8-1 Amendment No. 489,

Pressurizer PORVs 3.4.11 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES I and 2, MODE 3 with all PCS cold leg temperatures 2 430 0F.

ACTIONS

-nro 4-.Separate Condition entry is allowed for each PORV.

a .

[CO St A4 *q RR* .---nR~RUti.hh ~~~

CONDITION REQUIRED ACTION COMPLETION TIME A. One PORV inoperable. A.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months valve.

AND A.2 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. One block valve B.1 Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. in manual control.

AND B.2 Restore block valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

Palisades Nuclear Plant 3.4.11-1 Amendment No. 4-99,

LTOP System 3.4.12 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with:

a. Both High Pressure Safety Injection (HPSI) pumps incapable of injecting into the PCS, and

- -------- ------ NOTES--------------------------------------

1. LCO 3.4.12.a is only required when any PCS cold leg temperature is < 300 0F.

2. LCO 3.4.12.a does not prohibit the use of the HPSI pumps for emergency addition of makeup to the PCS.

b. One of the following pressure relief capabilities:

1. Two Power Operated Relief Valves (PORVs) with lift settings as specified in Figure 3.4.12-1; or

2. The PCS depressurized and a PCS vent capable of relieving 2 167 gpm at a pressure of 315 psia.

APPLICABILITY: MODE 3 when any PCS cold leg temperature is < 4300 F, MODES 4 and 5, MODE 6 when the reactor vessel head is on.

ACTIONS

NOTE------------------

LCO 3.0.4.b is not applicable to PORVs when entering MODE 4.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two HPSI pumps A.1 Initiate action to verify Immediately capable of injecting into no HPSI pump is the PCS. capable of injecting into the PCS.

Palisades Nuclear Plant 3.4.12-1 Amendment No. 449,

PCS Leakage Detection Instrumentation 3.4.15 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.15 PCS Leakage Detection Instrumentation LCO 3.4.15 Three of the following PCS leakage detection instrumentation channels shall be OPERABLE:

a. One containment sump level indicating channel;

b. One containment atmosphere gaseous activity monitoring channel;

c. One containment air cooler condensate level switch channel;

d. One containment atmosphere humidity monitoring channel.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS NOOTE l60 IS net n 31n4 ;edcable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required leak A.1 Perform SR 3.4.13.1 Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months detection instrument (PCS water inventory channels inoperable. balance).

AND A.2 Restore inoperable 30 days channel(s) to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND I B.2 Be in MODE S. 136 hours0.00157 days 0.0378 hours 2.248677e-4 weeks 5.1748e-5 months Palisades Nuclear Plant 3.4.1 5-1 Amendment No. 4,8,9,

PCS Specific Activity 3.4.16 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.16 PCS Specific Activity LCO 3.4.16 The specific activity of the primary coolant shall be within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with PCS average temperature (Tave) 2 5000F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 -------- NOTE------------------

> 1.0 PCi/gm. LCO 3.0.4.c is notapplicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT 1-131

< 40 pCi/gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

Palisades Nuclear Plant 3.4.16-1 Amendment No. 489,

Hydrogen Recombiners 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Hydrogen Recombiners LCO 3.6.7 Two hydrogen recombiners shall be OPERABLE.

APPLICABLITY: MODES 1 and 2.

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. One hydrogen recombiner NOTE inoperable. LCO 3.0.4 is not applicable.

A.1 Restore hydrogen 30 days recombiner to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Palisades Nuclear Plant 3.6.7-1 Amendment No. 4-89,

ADVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Dump Valves (ADVs)

LCO 3.7.4 One ADV per steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator Is being relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ADV NOTE inoperable. LCO 3.0.4 is not applicbic.

A.1 Restore ADV to 7 days OPERABLE status.

B. Two required ADVs B.1 Restore one ADV to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Inoperable. OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 4 without 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months reliance upon steam generator for heat removal.

Palisades Nuclear Plant 3.7.4-1 Amendment No. 4-89,

AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Two AFW trains shall be OPERABLE.

_ _ _---go------NOTES ---- ------------ a

1. Only one AFW train, which Includes a motor driven pump, is required to be OPERABLE in MODE 4.

2. The steam driven pump is only required to be OPERABLE prior to l making the reactor critical.

3. Two AFW pumps may be placed in manual for testing, for a period of up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator Is relied upon for heat removal.

ACTIONS LCO 3.0.4.b is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AFW A.1 Restore train(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trains Inoperable in OPERABLE status.

MODE 1,2, or 3. I Palisades Nuclear Plant 3.7.5-1 Amendment No. 48, 49G, 200,

AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources- Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class i E AC Electrical Power Distribution System; and

b. Two Diesel Generators (DGs) each capable of supplying one train of the onsite Class I E AC Electrical Power Distribution System.

APPLICABILITY: MODES 1, 2,3, and 4.

ACTIONS

-NOTE.

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One offsite circuit A.1 Perform SR 3.8.1.1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. (offsite source check) for OPERABLE offsite AND circuit.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND thereafter A.2 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

AND 10 days from discovery of failure to meet LCO Palisades Nuclear Plant 3.8.1-1 Amendment No. 489,

NUCLEAR MANAGEMENT COMPANY (NMC)

ADOPTION OF CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (CLIIP)

TECHNICAL SPECIFICATION CHANGE TSTF-359, REVISION 9, INCREASED FLEXIBILITY IN MODE RESTRAINTS" POINT BEACH NUCLEAR PLANT (PBNP)

TS PAGES (markups)

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions In the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

If the LCO Is met or Is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s)

Is not required unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition In which the LCO is not applicable. Action shall be Initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, In:

a. MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b. MODE 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c. MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 Is not required.

LCO 3.0.3 Is only applicable In MODES 1, 2, 3, and 4.

LCO 3.0.4 When an LCO Is not met, entry Into a MODE or other specified condition In the Applicability shall netAnvbe made except when the associated ACTIONS to be entered permit continued operation in the MODE or other spcclfied condition in the Applicability for an unlimited peried of time.;

Point Beach 3.0-1 Unit I - Amendment No. 201 Unit 2 - Amendment No. 206

LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 (continued)

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 addressina Inoperable systems and components. consideration of the determination of the acceptability of entering the Iesults, 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 individual 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.

Exceptions to this Specification arc stated in the individual Speeofeatlensm.

LGO 3.0.4 is only applicable for entry into a MODE or otheF specified conditions in the Applicability on MODES 1, 2 3, I LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be operated under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system operated under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 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 not 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 Specification 5.5.14, "Safety Function Point Beach 3.0-2 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

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 net-iQnybe made unless --wn the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO Is not met due to Surveillances not having been met. entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

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 shutdown of the unit.

SR 3.0.4 is only applicable for entry into a MODE or other specified condition in the Appliabili;ty in MODES 1, 2, 3 and 4.

Point Beach 3.0-5 Unit I - Amendment No. 201 Unit 2 - Amendment No. 206

PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function In Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

.. _rd 1.LO_ .4int__----------- 1U11 Vid te -

N1 ---------------------------- - -- -- ------ - --

1. LCv .0.4 s notapplcabl.

2--Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETIONTIME A. One or more Functions A.1 Restore required 30 days with one required channel to OPERABLE channel Inoperable. status.

B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.6.

met.

C. --------NOTE----- C.1 Restore one channel to 7 days Not applicable to OPERABLE status.

hydrogen monitor channels.

One or more Functions with two required channels inoperable.

(continued)

Point Beach 3.3.3-1 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, MODE 3 with RCS average temperature (Tavg) 2 500 0F.

ACTIONS

NOTES-------------------------------------------------

4-Separate Condition entry is allowed for each PORV and each block valve.

e . e ^ ^ _ _ _. .. - - I .

LLAJ=:i3.U. IF nO ODDIICWaDI CONDITION REQUIRED ACTION CXLETIONTIVE A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable and capable power to associated of being manually block valve.

cycled.

B. One PORV inoperable B.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capable of being valve.

manually cycled.

AND B.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valve.

AND B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

(continued)

Point Beach 3.4.11-1 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

LTOP 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with:

a. A maximum of one Safety Injection (SI) pump capable ofinjecting Into the RCS;

b. Each accumulator Isolated, whose pressure is> the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR, and

c. One of the following pressure relief capabilities:

1. Two power operated relief valves (PORVs) with lift settings within the limits specified Inthe PTLR, or

2. The RCS depressurized and an RCS vent path with venting capability equivalent to or greater than a PORV.

APPLICABILITY: MODE 4 when any RCS cold leg temperature Is< LTOP enabling temperature specified In the PTLR, MODE 5, MODE 6 when the reactor vessel head Is on.

ACTIONS

--- NOTES--

1. While this LCO is not met, entry intoMODE 6, with the reactor vessel head on, from MODE 6, with the reactor vessel head removed, Is not permitted.

2. LCO 3.0.4.b is not applicable when entering MODE 4.

CONDITION I REQUIRED ACTION ICOAMLETONTHE A Two SI pumps capable of A.1 Initiate action to verify a Immediately injecting Into the RCS. maximum of one SI pump Is capable of Injecting into the RCS.

Point Beach 3.4.12-1 Unit I - Amendment No. 201 Unit 2 - Amendment No. 206

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection Instrumentation shall be OPERABLE:

a. One containment sump level alarm; and

b. One containment atmosphere radioactivity monitor (gaseous or particulate).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TiME A. Required containment E----

NOT-NOT sump level alarm LCO 3.0.4 is not applicabic.

inoperable.

NOTE ----------

Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

A.1 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND A.2 Restore required 30 days containment sump monitor to OPERABLE status.

(continued)

Point Beach 3.4.15-1 Unit I - Amendment No. 201 Unit 2 - Amendment No. 206

RCS Leakage Detection Instrumentation 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION cOMPLEnONTIME B. Required containment NOTE atmosphere radioactivity LCO 3.0.4 is not applicable.

monitor inoperable.

B.1.1 Analyze grab samples Once per of the containment 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months atmosphere.

OR

NOTE---------

Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

B.1.2 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.2 Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be In MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. All required monitors D.1 Enter LCO 3.0.3. Immediately and level alarm Inoperable.

Point Beach 3.4.15-2 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS average temperature (Tavg) > 500 0F.

ACTIONS CONDITION REQUIRED ACTION CMPLETIONTIME A. DOSE EQUIVALENT ------------------ Note------

1-131 > 0.8 pCilgm. LCO 3.0.4.c Is not-applicable. I A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT 1-131 within the acceptable region of Figure 3.4.16-1.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

B. Gross specific activityof B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months the reactor coolant not Tavg < 5000 F.

within limit.

(continued)

Point Beach 3.4.16-1 Unit I - Amendment No. 201 Unit 2 - Amendment No. 206

ECCS-Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS-Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.

NOTE----------------------------------------

An RHR train may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned to the ECCS mode of operation.

APPLICABILITY: MODE 4.

ACTIONS NOTE -a LCO 3.0.4.b is not applicable to ECCS high head subsystem.

CONDITION REQUIRED ACTION OOMPLETfONLE A. Required ECCS residual A.1 Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable. subsystem to OPERABLE status.

B. Required ECCS Si B.1 Restore required ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem inoperable. Si subsystem to OPERABLE status.

C. Required Action and C.1 Be In MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months associated Completion Time of Condition B not met.

Point Beach 3.5.3-1 Unit I - Amendment No. 201 Unit 2 - Amendment No. 206

ADV Flowpaths 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Dump Valve (ADV) Flowpaths LCO 3.7.4 Two ADV flowpaths shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator Is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETlONTiME A. One required ADV A.1 N0 flowpath Inoperable. LCO 3.0.4 is not appfleable.

Restore required ADV 7 days flowpath to OPERABLE status.

B. Two required ADV B.1 Restore one ADV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months flowpaths inoperable. flowpath to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be In MODE 4 without 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months reliance upon steam generator for heat removal.

Point Beach 3.7.4-1 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW)

LCO 3.7.5 The AFW System shall be OPERABLE with; one turbine driven AFW pump system and two motor driven AFW pump systems.

NOTE------------------------- --

Only the motor driven AFW pump systems associated with steam generators relied upon for heat removal are required to be OPERABLE In MODE 4.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

NOTE-------------------------------------------

LCO 3.0.4.b is not applicable.

CONDITION REQUIRED ACTION COv LE1ONTIVE A. One steam supply to A.1 Restore steam supply to 7 days turbine driven AFW pump OPERABLE status.

system inoperable. AND 10 days from discovery of failure to meet the LCO B. One turbine driven AFW B.1 Restore turbine driven 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pump system Inoperable in AFW pump system to MODE 1, 2 or 3 for OPERABLE status. AND reasons other than Condition A. 10 days from discovery of failure to meet the LCO (continued)

Point Beach 3.7.5-1 Unit I - Amendment No. 201 Unit 2 - Amendment No. 206

AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a. One circuit between the offsite transmission network and the associated unit's 4.16 kV Class IE safeguards buses, A05 and A06, utilizing the associated unit's 345113.8 kV (X03) transformer or the opposite unit's 345/13.8 kV (X03) transformer with the gas turbine in operation, and the associated unit's 13.8/4.16 kV (X04) transformer;

b. One circuit between the offsite transmission network and the opposite unit' s 4.16 kV Class 1E safeguards buses, A05 and A06; and

c. One standby emergency power source capable of supplying each 4.16 kV/480 V Class 1E safeguards bus.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

NOTF._________________________.

[00 3-0-4-h Is not applinable to standby amperapnn~ Power Soii CONDITION REQUIRED ACTION OIPIETONTIME A. Associated unit A.1 Verify one circuit 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 345/13.8 kV (X03) between the offsite transformer inoperable. transmission network and the associated unit' s OR 4.16 kV Class IE safeguards buses, Gas turbine not in A05 and A06, utilizing operation when utilizing the opposite unit' s opposite unit' s 345/13.8 kV (X03) 345/13.8 kV (X03) transformer.

transformer.

AN12 (continued)

Point Beach 3.8.1-1 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

NUCLEAR MANAGEMENT COMPANY (NMC)

ADOPTION OF CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (CLIIP)

TECHNICAL SPECIFICATION CHANGE TSTF-359, REVISION 9, "INCREASED FLEXIBILITY IN MODE RESTRAINTS" PRAIRIE ISLAND NUCLEAR GENERATING PLANT (PINGP)

TS PAGES (markups)

LCO Applicability 3.0 3.0 LCO APPLICABILITY (continued)

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall n net-be made:

a. When the associated ACTIONS to be entered permit ontinued operation in the MODE or other specified IondidnWin the Applicability forka unlimited period of me;

b. 4fter 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 individual value, barameter, or other Specification.

associated ACTIONS to be entered permit continued operation in the MODE or other speeified conditien in the Applicability for an unlimited period of time.

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.

Exceptions to this Speeification are stated in the indiidual Speeifleatiens.

LCO 3.0.4 is only applicable for entry into a MODE or other specified condifion in the Applicability in MODES 1,2, 3, and 4.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is Prairie Island Unit 1 - Amendment No. 4-58 Units 1 and 2 3.0-2 Unit 2 - Amendment No. 449

LCO Applicability 3.0 3.0 SR APPLICABILITY (continued)

SR 3.0.3 If it 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall nyn be made When unless-the LCO's Surveillances have been met within their specified Frequency:

scept as provided by SR 3.03. When an LCO Is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

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 shutdown of the unit.

SR 3.0.4 is enly applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, 3 and 4.

Prairie Island Unit 1 - Amendment No. 4-58 Units 1 and 2 3.0-6 Unit 2 - Amendment No. 449

ITC 3.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ---- NOTE----- -------- NOTE-------

Required Action C.1 LCO 3.0.4c is not-applicable.

must be completed whenever Condition C is entered. C.1 Re-evaluate core design and Once prior to safety analysis, and reaching the determine that the reactor equivalent of an Projected end of cycle core is acceptable for equilibrium RTP (EOC) ITC not within continued operation. all rods out boron lower limit. concentration of 300 ppm D. Required Action and D.I Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition C not met.

Prairie Island Unit 1 - Amendment No. 4-59 Units 1 and 2 3.1.3-2 Unit 2 - Amendment No. 449

EM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Event Monitoring (EM) Instrumentation LCO 3.3.3 The EM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPICABILflY: MODES 1 and 2.

ACTIONS

,1 ~ ~ ~ ~

b _ _ - _ _- - - - _-_ _

1. LCO 3.0.4 is not applicable.

2.-Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. ------NOTE-------- A.1 Restore required channel 30 days Not applicable to core to OPERABLE status.

exit temperature Function.

One or more Functions with one required channel inoperable.

Prairie Island Unit 1 - Amendment No. 4-5 Units 1 and 2 3.3.3-1 Unit 2 - Amendment No. 449

Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

APPLCABILHIY: MODES 1, 2, and 3.

ACTIONS 1-.Separate Condition entry is allowed for each PORV and each block valve.

2. LCO 3.0.4 is net applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or both PORVs A.1 Close and maintain power 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable and capable to associated block of being manually valve(s).

cycled.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.4.11-1 Unit 2 - Amendment No. 449

LTOP - RCSCLT > SI Pump Disable Temperature 3.4.12 ACTIONS 1 --- ,-

- - l"~~~~~~~..-

- - l - . 1Im~I~. -: I ,I I . I .1 I.... .....I

~C3.O.4.b not applicablewhen ntering ~MODE 4.

CONDITION REQUIRED ACTION COMPLETION TIME A. Two SI pumps capable of A.1 Initiate action to assure a Immediately injecting into the RCS. maximum of one SI pump is capable of injecting into the RCS.

B. An ECCS accumulator B. 1 Isolate affected ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not isolated when the accumulator.

ECCS accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

Prairie Island Unit 1 - Amendment No. 458 Units 1 and 2 3.4.12-2 Unit 2 - Amendment No. 449

LTOP - RCSCLT g SI Pump Disable Temperature 3.4.13 ACTIONS L -- - =t ~ '77 II '-7 '-'.1m-t-~- l CO 3.04.b is not applicable when entering MODE 4.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or both SI pump(s) A. 1 Initiate action to verify no SI Immediately capable of injecting into pump is capable of injecting the RCS. into the RCS.

B. An ECCS accumulator B.1 Isolate affected ECCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not isolated when the accumulator.

ECCS accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

C. Required Action and C.1 Increase RCS cold leg 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion temperature to > the OPPS Time of Condition B not enable temperature specified met. in the PTLR.

OR C.2 Depressurize affected ECCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

Prairie Island Unit 1 - Amendment No. 48 Units I and 2 3.4.13-2 Unit 2 - Amendment No. 449

RCS Leakage Detection Instrumentation 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Leakage Detection Instrumentation LCO 3.4.16 The following RCS leakage detection instrumentation shall be OPERABLE:

a. One containment sump A monitor (pump run time instrumentation);

and

b. One containment radionuclide monitor.

APPLRCABRIHY: MODES 1, 2, 3, and 4.

ACTIONS

- NOTE LCO 3.0.4 i not applic bWl.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required containment A.1 ----------NOTE----

sump monitor inoperable. Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Perform SR 3.4.14.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND Prairie Island Unit 1 - Amendment No. 4;8 Units 1 and 2 3.4.16-1 Unit 2 - Amendment No. 149

RCS Specific Activity 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 RCS Specific Activity LCO 3.4.17 The specific activity of the reactor coolant shall be within limits.

APPUCABRITfY- MODES 1 and 2, MODE 3 with RCS average temperature (Ta) > 5000 F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT ------------- NOTEete--------

I-131 > 1.0 ILCi/gm. _

LCO 3.0.4.c is not-applicable.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months A.1 Verify DOSE EQUIVALENT 1-131 within the acceptable region of Figure 3.4.17-1.

AND 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months A.2 Restore DOSE EQUIVALENT 1-131 to within limit.

Prairie Island Unit 1 - Amendment No. 4-58 Units 1 and 2 3.4.17-1 Unit 2 - Amendment No. 449

ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS - Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.

-NOTE.

An RHR train may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned to the ECCS mode of operation.

APPUCABEHY. MODE 4 when both RCS cold leg temperatures are > SI pump disable temperature specified in PTLR.

ACTIONS LC 73.O.4b` is not aicabe to- CCS safety injection (S) smu system CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS residual A.1 Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable. subsystem to OPERABLE status.

B. Required ECCS safety B.1 Restore required ECCS SI 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months injection (SI) subsystem subsystem to OPERABLE inoperable. status.

Prairie Island Unit 1 - Amendment No. 448 Units 1 and 2 3.5.3-1 Unit 2 - Amendment No. 449

Hydrogen Recombiners 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Hydrogen Recombiners LCO 3.6.7 Two hydrogen recombiners shall be OPERABLE.

APPUCAB1TUIY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One hydrogen A.1 NOTE recombiner inoperable. LCO 3.0.4 is not applicable.

Restore hydrogen 30 days recombiner to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

Prairie Island Unit 1 - Amendment No. 4&9 Units 1 and 2 3.6.7-1 Unit 2 - Amendment No. 449

MFRVs and MFRV Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Regulation Valves (MFRVs) and MFRV Bypass Valves LCO 3.7.3 Two MFRVs and two MFRV bypass valves shall be OPERABLE.

APPUCABII=Y: MODES 1, 2, and 3.

ACTIONS i eyal----NOTE --v------- _________________________________

4-Separate Condition entry is allowed for each valve.

% Y 0"-%l 1% ^ A A_ Ac- nl a 3a. C.U.-I ts limit typtleaute.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or both MFRVs A.1 Close and place in manual 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. or isolate flow through MFRV(s).

AND A.2 Verify MFRV(s) closed and Once per 7 days in manual or flow through MFRV(s) isolated.

Prairie Island Unit 1 - Amendment No. 4-58 Units 1 and 2 3.7.3-1 Unit 2 - Amendment No. 449

SG PORVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Steam Generator (SG) Power Operated Relief Valves (PORVs)

LCO 3.7.4 Two SG PORV lines shall be OPERABLE.

APPUCAB]LITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SG PORV line A.1 NOTE inoperable. LEO 3.0.4 is not appl-e.

7 days Restore SG PORV line to OPERABLE status.

B. Two SG PORV lines B.1 Restore one SG PORV line 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND C.2 Be in MODE 4 without 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reliance upon steam generator for heat removal.

Prairie Island Unit 1 - Amendment No. 458 Units 1 and 2 3.7.4-1 Unit 2 - Amendment No. 449

AFW System 3.7.5 ACTIONS Fr -NOTE --- _ __ _ And 9 LCO 3.0.4.b is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A.1 Restore affected equipment 7 days turbine driven AFW to OPERABLE status.

pump inoperable. AND OR 10 days from discovery of failure to meet the Only applicable if MODE LCO 2 has not been entered following refueling.

One turbine driven AFW pump inoperable in MODE 3 following refueling.

B. One AFW train B. I Restore AFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable in MODE 1, 2, OPERABLE status.

or 3 for reasons other AND than Condition A.

10 days from discovery of failure to meet the LCO Prairie Island Unit 1 - Amendment No. 4-58 Units 1 and 2 3.7.5-2 Unit 2 - Amendment No. 449

AC Sources-Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources-Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

a. Two paths between the offsite transmission grid and the onsite 4 kV Safeguards Distribution System; and

b. Two diesel generators (DGs) capable of supplying the onsite 4 kV Safeguards Distribution System.

APPLKCABLHY: MODES 1, 2, 3, and 4.

ACTIONS NOLi LCO 3.0.4.b is not applicable to DGs.

Prairie Island Unit 1 - Amendment No. 4-58 Units 1 and 2 3.8.1-1 Unit 2 - Amendment No.449

NUCLEAR MANAGEMENT COMPANY (NMC)

ADOPTION OF CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (CLIIP)

TECHNICAL SPECIFICATION CHANGE TSTF-359, REVISION 9, "INCREASED FLEXIBILITY IN MODE RESTRAINTS" ENCLOSURE III PROPOSED TECHNICAL SPECIFICATION CHANGES (typed)

NUCLEAR MANAGEMENT COMPANY (NMC)

ADOPTION OF CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (CLIIP)

TECHNICAL SPECIFICATION CHANGE TSTF-359, REVISION 9, "INCREASED FLEXIBILITY IN MODE RESTRAINTS" lw DUANE ARNOLD ENERGY CENTER (DAEC)

TS PAGES (typed)