Text

Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
	ML22096A221
Person / Time
Site:	Millstone
Issue date:	04/06/2022
From:	Lawrence D; Dominion Energy Nuclear Connecticut
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	22-063
	Download: ML22096A221 (80)
	v • d • e

Dominion Energy Nuclear Connecticut. Inc.

5000 Dominion Boulevard, Glen Allen. VA 23060 Dominion Energy.com April 6, 2022 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNITS 2 AND 3

~

Dominion

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Energye Serial No.

NRA/SS:

Docket No.

License No.22-063 RO 50-336 50-423 DPR-65 NPF-49 APPLICATION FOR TECHNICAL SPECIFICATION CHANGE REGARDING MODE CHANGE LIMITATIONS USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS Pursuant to 10 CFR 50.90, Dominion Energy Nuclear Connecticut, Inc. (DENC) is submitting a license amendment request (LAR) to the Nuclear Regulatory Commission (NRG) to revise the Technical Specifications (TS) for Millstone Power Station Unit 2 (MPS2) and Unit 3 (MPS3). The proposed amendment would modify TS requirements for mode change limitations in TS 3.0.4 and 4.0.4. The proposed changes are consistent with NRG-approved Industry Technical Specification Task Force (TSTF) Standard Technical Specifications change TSTF-359, "Increase Flexibility in Mode Restraints,"

Revision 9 (ADAMS Accession No. ML031190607), which is the equivalent of TSTF-359, Revision 8 (ADAMS Accession No. ML023430260), as modified by the notice in the Federal Register published April 4, 2003 (68 FR 16579). to this letter describes the proposed changes and provides justification for the changes. Attachment 2 provides marked-up MPS2 TS pages showing the proposed changes. provides marked-up MPS2 TS Bases pages showing the proposed changes. Attachment 4 provides marked-up MPS3 TS pages showing the proposed changes. Attachment 5 provides marked-up MPS3 TS Bases pages showing the proposed changes. The TS Bases mark-ups are provided for information only. The changes to the affected TS Bases pages will be incorporated in accordance with the TS Bases Control Program after this LAR is approved. Attachment 6 indicates the regulatory commitments associated with this LAR.

The proposed amendment has been reviewed and approved by the station's Facility Safety Review Committee.

DENC requests approval of this LAR by April 6, 2023, with a 30-day implementation period.

In accordance with 10 CFR 50.91(b), a copy of this LAR is being provided to the State of Connecticut.

Serial No.22-063 Docket Nos. 50-336/423 Page 2 of 3 If you have any questions or require additional information, please contact Mr. Shayan Sinha at (804) 273-4687.

Douglas C. Law ce Vice President - Nuclear Engineering and Fleet Support COMMONWEAL TH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Douglas C. Lawrence, who is Vice President - Nuclear Engineering and Fleet Support of Dominion Energy Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document on behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this ~day of &\\l'fi \\

, 2022.

My Commission Expires:

l -'3 1-2o2 l.f Kathryn Hill Barret Notary Public Commonwealth of Virginia Reg. No. 7905256

~~7.J-,fo~

Notary Public My Commission Expires January 31, 2024 Attachments:

1. Description and Assessment of Proposed Change

2. Marked-up Technical Specification Pages for MPS2

3. Marked-up Technical Specification Bases Pages for MPS2 (for information only)

4. Marked-up Technical Specification Pages for MPS3

5. Marked-up Technical Specification Bases Pages for MPS3 (for information only)

6. List of Regulatory Commitments Commitments made in this letter: See Attachment 6

cc:

U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Richard V. Guzman Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127 Serial No.22-063 Docket Nos. 50-336/423 Page 3 of 3 Serial No.22-063 Docket Nos. 50-336/423 DESCRIPTION AND ASSESSMENT OF PROPOSED CHANGE Dominion Energy Nuclear Connecticut, Inc.

Millstone Power Station Units 2 and 3

1.0

SUMMARY

DESCRIPTION Serial No.22-063 Docket Nos. 50-336/423, Page 1 of 6 Pursuant to 10 CFR 50.90, Dominion Energy Nuclear Connecticut, Inc. (DENG) is submitting a license amendment request (LAR) to the Nuclear Regulatory Commission (NRC) to revise the Technical Specifications (TS) for Millstone Power Station Unit 2 (MPS2) and Unit 3 (MPS3). The proposed amendment would modify TS requirements for mode change limitations in limiting condition for operation (LCO) 3.0.4 and surveillance requirement (SR) 4.0.4. The proposed changes are consistent with NRG-approved Industry Technical Specification Task Force (TSTF) Standard Technical Specifications (STS) change TSTF-359, "Increase Flexibility in Mode Restraints,"

Revision 9 (ADAMS Accession No. ML031190607), which is the equivalent of TSTF-359, Revision 8, as modified by the notice in the Federal Register published April 4, 2003. That Federal Register notice announced the availability of this TS improvement through the consolidated line item improvement process (CLIIP).

2.0 ASSESSMENT

2.1 Applicability of Published Safety Evaluation DENG has reviewed the safety evaluation, dated April 4, 2003, as part of the CLIIP. This review included a review of the NRC staff's evaluation, as well as the supporting information provided to support TSTF-359, Revision

8. DENG has concluded that the justifications presented in the TSTF-359 proposal and the safety evaluation prepared by the NRC staff are applicable to MPS2 and MPS3 and justify this amendment for the incorporation of the changes to the MPS2/3 TS.

2.2 Optional Changes and Variations DENG is proposing the following variations from the TS changes described in the modified TSTF-359 Revision 8 and the NRC staff's model safety evaluation dated April 4, 2003.

1. The MPS2 and MPS3 TS utilize different numbering and titles than NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants," and NUREG-1431, "Standard Technical Specifications, Westinghouse Plants," on which TSTF-359 was based. Additionally, the MPS2/3 TS do not contain all of the TS that were revised by TSTF-359. These differences are administrative and do not affect the applicability of TSTF-359 to the MPS2/3 TS.

2. MPS2 and MPS3 have not converted to the STS from NUREG-1432, and NUREG-1431, respectively. As a result, the MPS2/3 individual SRs do not stipulate the specific time frames and conditions necessary for meeting the SRs to allow entry into the

Serial No.22-063 Docket Nos. 50-336/423, Page 2 of 6 mode or condition of applicability without having performed the SR. Consequently, the existing exceptions to SR 4.0.4 will be retained in the MPS2/3 TS, and the proposed Bases for SR 4.0.4 will not include the paragraph below that is included in TSTF-359 for the Bases of equivalent to STS SR 3.0.4.

The precise requirements for performance of SRs are specified such that exceptions to SR 3. 0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated LCO prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after entering the LCO's Applicability, would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Surveillance may be stated in the form of a Note, as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4, Frequency.

3. TSTF-359 and the model safety evaluation refer to Regulatory Guide (RG) 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." However, RG 1.182 was withdrawn in November 2012 because it was redundant to the inclusion of its information in RG 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." Therefore, the proposed Bases for MPS2/3 LCO 3.0.4 refer to RG 1.160 rather than RG 1.182. This is an administrative variation that does not affect the applicability of TSTF-359 to the MPS2/3 TS.

4. One minor readability change to the TS has been included with insertion of the word "or" between LCO 3.0.4.a and 3.0.4.b to highlight the mutual exclusivity of these elements. This "or" connector was contained in the NRG Notice of Availability published April 4, 2003 (68 FR 16585).

3.0 REGULATORY ANALYSIS

Serial No.22-063 Docket Nos. 50-336/423, Page 3 of 6 3.1 No Significant Hazards Consideration Determination Dominion Energy Nuclear Connecticut, Inc. (DENC) has reviewed the proposed no significant hazards consideration determination (NSHCD) published in the Federal Register as part of the consolidated line item improvement process (CLIIP). DENC has concluded that the proposed NSHCD presented in the Federal Register notice is applicable to Millstone Power Station Unit 2 (MPS2) and Millstone Power Station Unit 3 (MPS3) 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 published in the Federal Register on April 4, 2003 for this TS improvement, plant-specific verifications were performed as follows:

1. DENC has established TS Bases for LCO 3.0.4 and SR 4.0.4 which state that use of the TS mode change limitation flexibility established by LCO 3.0.4 and SR 4.0.4 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.

2. The modification also includes changes to the Bases for LCO 3.0.4 and SR 4.0.4 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

Serial No.22-063 Docket Nos. 50-336/423, Page 4 of 6 LCO 3.0.4.c allows entry into a MODE or other 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.,

Containment Air Temperature, Containment

Pressure, MCPR, Moderator Temperature Coefficient), though it may be applied to other Specifications based on NRG plant-specific approval.

3. 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, NRG Regulatory Guide 1.160, "Monitoring the Effectiveness of Maintenance 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.

4. 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 ACTIONS until the condition is resolved, until the LCO is met, or until the unit is not within the Applicability of the TS. The Bases also state that SR 4.0.4 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 4.0.3. Finally, MPS2 and MPS3 have a Bases Control Program consistent with Section 5.5 of the STS, and the equivalent of STS SR 3.0.1 and associated Bases.

4.0 ENVIRONMENTAL EVALUATION DENG has reviewed the environmental evaluation included in the model safety evaluation dated April 4, 2003 as part of the CLIIP. DENG has concluded that the staff's findings presented in that evaluation are applicable to MPS2 and MPS3 and the evaluation is hereby incorporated by reference for this application.

Serial No.22-063 Docket Nos. 50-336/423, Page 5 of 6 Table of Affected MPS2 Technical Specifications & Bases and Brief Description of Changes Technical Description of the Specification No.

Chanae LCO 3.0.4 Delete current LCO 3.0.4 and replace with TSTF-359 requirements.

SR 4.0.4 Delete current SR 4.0.4 and replace with TSTF-359 requirements.

LCO 3.4.8 Revise Actions to indicate that LCO 3.0.4.c is applicable to Dose Equivalent 1-131 and Xe-133, consistent with TSTF-359.

LCO 3.4.9.3 Delete Action f, which provides an exception to LCO 3.0.4. TSTF-359 removes existing LCO 3.0.4 exceptions. Add new note that LCO 3.0.4.b is not applicable when entering Mode 4, consistent with TSTF-359.

LCO 3.5.3 Add a new note that LCO 3.0.4.b is not applicable to high pressure safety injection subsystem, consistent with TSTF-359.

LCO 3.7.1.2 Add a new note that LCO 3.0.4.b is not applicable, consistent with TSTF-359.

LCO 3.8.1.1 Add a new note that LCO 3.0.4.b is not applicable to diesel generators, consistent with TSTF-359.

Bases for LCO 3.0.4 Replace bases with TSTF-359 bases for Improved Technical Specifications (ITS} LCO 3.0.4.

Bases for SR 4.0.4 Replace bases with TSTF-359 bases for ITS SR 3.0.4.

Bases for LCO 3.4.8 Revise bases to reflect LCO 3.0.4.c allowance consistent with TSTF-359.

Bases for LCO 3.4.9.3 Delete paragraph related to Action f, which provides an exception to LCO 3.0.4. Add discussion concerning the application of LCO 3.0.4.b, consistent with TSTF-359.

Bases for LCO 3.5.3 Add discussion concerning the application of LCO 3.0.4.b, consistent with TSTF-359.

Bases for LCO 3. 7.1.2 Add discussion concerning the application of LCO 3.0.4.b, consistent with TSTF-359.

Bases for LCO 3.8.1.1 Add discussion concerning the application of LCO 3.0.4.b, consistent with TSTF-359.

Serial No.22-063 Docket Nos. 50-336/423, Page 6 of 6 Table of Affected MPS3 Technical Specifications & Bases and Brief Description of Changes Technical Description of the Specification No.

Chanae LCO 3.0.4 Delete current LCO 3.0.4 and replace with TSTF-359 requirements.

SR 4.0.4 Delete current SR 4.0.4 and replace with TSTF-359 requirements.

LCO 3.3.3.5 Delete Action c, which permits entry into an Operational Mode while subject to the Action requirements.

LCO 3.3.3.6 Delete Action g, which permits entry into an Operational Mode while subject to the Action requirements.

LCO 3.4.4 Delete Action e, which permits entry into an Operational Mode while subject to the Action requirements.

LCO 3.4.8 Revise Actions to indicate that LCO 3.0.4.c is applicable to Dose Equivalent 1-131 and Xe-133, consistent with TSTF-359.

LCO 3.4.9.3 Add new note that LCO 3.0.4.b is not applicable when entering Mode 4, consistent with TSTF-359. Delete Action g, which permits entry into an Operational Mode while subject to the Action requirements.

LCO 3.5.3 Add a new note that LCO 3.0.4.b is not applicable to high pressure safety injection subsystem, consistent with TSTF-359.

LCO 3.6.1.3 Delete Action a.4, which permits entry into an Operational Mode while subject to the Action requirements.

LCO 3.7.1.2 Add a new note that LCO 3.0.4.b is not applicable, consistent with TSTF-359.

LCO 3.7.1.6 Delete the last sentence in Action a, which provides an exception to LCO 3.0.4. TSTF-359 removes existing LCO 3.0.4 exceptions.

LCO 3.8.1.1 Add a new note that LCO 3.0.4.b is not applicable to diesel generators, consistent with TSTF-359.

Bases for LCO 3.0.4 Replace bases with TSTF-359 bases for ITS LCO 3.0.4.

Bases for SR 4.0.4 Replace bases with TSTF-359 bases for ITS SR 3.0.4.

Bases for LCO 3.4.8 Revise bases to reflect LCO 3.0.4.c allowance consistent with TSTF-359.

Bases for LCO 3.4.9.3 Add discussion concerning the application of LCO 3.0.4.b, consistent with TSTF-359.

Bases for LCO 3.5.3 Add discussion concerning the application of LCO 3.0.4.b, consistent with TSTF-359.

Bases for LCO 3.7.1.2 Add discussion concerning the application of LCO 3.0.4.b, consistent with TSTF-359.

Bases for LCO 3.8.1.1 Add discussion concerning the application of LCO 3.0.4.b, consistent with TSTF-359.

Serial No.22-063 Docket No. 50-336 MARKED-UP TECHNICAL SPECIFICATIONS PAGES FOR MPS2 Dominion Energy Nuclear Connecticut, Inc.

Millstone Power Station Unit 2

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-336, Page 1 of 13 September 14, 2000 3/4 LIMITING CONDITIONS FOR OPERATION At'ID SURVEILLAt'l"CE REQUIREMENTS 3./4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals, except as provided in LCO 3.0.6. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour ACTION shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

1.

At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time it is identified that a Limiting Condition for Operation is not met. Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODES 5 or 6.

Replace with INSERT 2A

_"""".....,,,.P--Entry into an OPERA.TIONAL MODE or other specified condition shall not be made w n e conditions for the Limiting Condition for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system(s),

subsystem(s), train(s), component(s) and device(s) are OPERABLE, or likewise satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , ACTION shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply by placing it, as applicable, in:

MILLSTONE - UNIT 2 3/4 0-1 AmendmentNos.@,~,B0,249

INSERT 2A Serial No.22-063 Docket No. 50-336, Page 2 of 13 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; or

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.

-FOR INFORMATION ONLY-APPLICABILITY:

LIMIT1NG CONDITION FOR OPERATION (Continued)

1.

At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3.

At least COLD SHUTDOWN within the subsequent 24 homs.

1his specification is not applicable in MODES 5 or 6.

Serial No.22-063 Docket No. 50-336, Page 3 of 13 October 15, 2002 3.0.6 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. 1his is an exception to LCO 3.0.2for the system returned to service tmder administrative control to perform the testing required to demonstrate OPERABILITY.

SURVEILLAi~CE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

Failure to meet a Surveillance, whether such failme is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the Limiting Condition for Operation. Failure to perform a Surveillance within the specified surveillance interval shall be failme to meet the Limiting Condition for Operation except as provided in Specification 4.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance time interval.

4.0.3 If it is discovered that a Surveillance was not performed within its specified surveillance interval, then compliance with the requirement to declare the Limiting Condition for Operation 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 surveillance interval, 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 in1pact shall be managed.

If the Surveillance is not performed within the delay period, the Limiting Condition for Operation must inlmediately 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 Limiting Condition of Operation must inlmediately be declared not met, and the applicable Condition(s) must be entered.

,-;~.'.j..,cr,ntry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been perforn1ed within the stated surveillance interval or as otherwise specified. 1his provision shall not prevent passage through or to OPERATIONAL MODES as required to compl, with ACTION req ir Amendment No. 62-, fG, -l-6l-, ~, 271

INSERT 2B Serial No.22-063 Docket No. 50-336, Page 4 of 13 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 4.0.3.

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.

-FOR INFORMATION ONLY-REACTOR COOLA.t"\\TT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 Tue specific activity of the primary coolant shall be limited to:

a.

0.5 µCi/gram DOSE EQUIVALENT I-131, and

b.

550 µCi/gram DOSE EQUIVALENTXE-133.

APPLICABILITY:

MODES 1, 2, 3, 4.

ACTION:

Serial No.22-063 Docket No. 50-336, Page 5 of 13 August 07, 2020

a.

With the specific activity of the primary coolant> 0.5 µCi/gram DOSE EQUIVALEI\\TT I-131, verify DOSE EQUIVALENT I-131 s 30 µCi/gram once per 4hours.

b.

With the specific activity of the primary coolant > 0.5 µCi/gram DOSE EQUIVALENT I-131 but::; 30 µCi/gram, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT I-131 to within the 0.5 µCi/gram limit. S~

n ~

is l'!M'applicable.

~-

c.

With the specific activity of the primary coolant > 0.5 µCi/gram DOSE EQUIV:.ALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, or> 30 µCi/gram DOSE EQUIVALENT I-131, be in HOT STA1"\\TDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHlITDOWN within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

d With the specific activity of the primary coolant> 550 µCi/gram DOSE EQUIV ALEN1 XE-133, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT XE-133 to within the 550 µCi/gram limit. S ecification ~

is-+ applicable.

3.0.4.c"

e.

With the specific activity of the primary coolant> 550 µCi/gram DOSE EQUIVALENT XE-133 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, be in HOT STA1,1DBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within 36hours.

MILLSTONE - UNIT 2 3/4 4-13 Amendment No. 9, H-l-, !H-, H--1-, !94,

~,~,340

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-336, Page 6 of 13 July l, 1998 REACTOR COOLAt'ff SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 A Low Temperature Overpressure Protection (LTOP) System, as specified below, shall be OPERABLE.

a.

MODE 4, and MODE 5 with all RCS cold leg temperature> 190~F:

l.

Maximum of two charging pumps and one HPSI pump may be capable of injecting into the RCS; and

2.

Two OPERABLE PORVs with a lift setpoint of:5 415 psia.

b.

MODE 5 with any RCS cold leg temperature s 190 °F, and MODE 6 either:

l.

Maximum of one charging pump may be capable of injecting into the RCS; and

2.

Two OPERABLE PORVs with a lift setpoint ofs 415 psia.

OR

3.

Maximum of two charging pumps and one HPSI pump may be capable of injecting into the RCS; and

4.

The RCS is depressurized and an RCS vent of~ 2.2 sq. inches.

APPLICABILITY:

MODE 4 when the temperature of any RCS cold leg is less than or equal to 275°F, MODE 5, and MODE 6 when the head is on the reactor vessel.

ACTION:

a.

b.

C.

d.

e.

f.

1TSERT2C With one required PORVinoperable in MODE 4, restore the inoperable PORVto OPERABLE status within 7 days or depressurize and vent the RCS through a 2: 2.2 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

With one required PORV inoperable in MODES 5 or 6, either restore inoperable PORV to OPERABLE status \\ ithin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or depressurize and vent the RCS through a 2: 2.2 square inch vent within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

With both required PORV s inoperable, depressurize and vent the RCS through a 2: 2.2 square inch vent within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

With more than the maximum allowed pumps capable of injecting into the RCS, take immediate action to comply with 3.4.9.3.

In the event either the PO RVs or the RCS vent(s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PO RVs or RCS vent(s) on the transient, and any corrective action necessary to prevent recurrence.

1bc p1oeisim1s ofSpcci£catiw1 J. B. me not appJ:icM.ilc.

MILLSTONE - UNIT 2 3/4 4-21a Amendment No. §G, B--1-, 8:5-, 218

INSERT 2C Serial No.22-063 Docket No. 50-336, Page 7 of 13

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

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

Serial No.22-063 Docket No. 50-336, Page 8 of 13

-FOR INFORMATION ONLY-EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS* Tavg < 300°F LIMITING CONDITION FOR OPERATION January 29, 2016 3.5.3 One high pressure safety injection subsystem shall be OPERABLE.

- NOTES- -

1.

The provisions of Specifications 3.0.4 and 4.0.4 are not applicable for entry into MODE 4 for the high pressure safety injection pump that is inoperable pursuant to Specification 3.4.9.3 provided the high pressure safety injection pump is restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after entering MODE 4.

2.

In MODE 4, the requirement for OPERABLE safety injection and sump recirculation actuation signals is satisfied by use of the safety injection and sump recirculation trip pushbuttons.

3.

In MODE 4, the OPERABLE HPSI pump is not required to start automatically on a SL<\\S.

Therefore, the pump control switch for this OPERABLE pump may be placed in the pull-to-lock position without affecting the OPERABILITY of this pump.

APPLICABILITY:

MODES 3* and 4.

ACTION:

~

a.

With no high pressure safety injection subsystem OPERABLE, restore at least one high pressure safety injection subsystem to OPERABLE status within one hour or be in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

SURVEILLAi'l"CE REQUIREMENTS

4. 5.3.1 The high pressure safety injection subsystem shall be demonstrated OPERABLE per the applicable portions of Surveillance Requirements 4.5.2.a, 4.5.2.b, 4.5.2.c, 4.5.2.f, 4.5.2.g, 4.5.2.i, 4.5.2.j, and 4.5.2.1.

With pressurizer pressure < 17 50 psi a

.MILLSTONE - UNIT 2 3/4 5-7 Amendment No. 39, ~.,!-16, !.H&,

~. ;!83-, 325

INSERT 2D Serial No.22-063 Docket No. 50-336, Page 9 of 13

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

LCO 3.0.4.b is not applicable to ECCS high pressure safety injection subsystem when entering MODE 4

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-336, Page 10 of 13 January 31, 2007 PLAl'IT SYSTEMS AUXILIARY FEEDWATER PUMPS LIMTT1NG CONDITION FOR OPERATION

3. 7.1.2 At least three steam generator auxiliary feedwater pumps shall be OPERABLE with:

a.

Two feedwater pumps capable of being powered from separate OPERABLE emergency busses, and

b.

One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY:

MODES 1, 2 and 3. ~

ACTION:

~

Inoperable Equipment

a. Turbine-driven auxiliary feedwater pump due to one steam supply being inoperable.

b.

- NOTE - -

Only applicable if MODE 2 has not been entered following REFUELING.

One turbine-driven auxiliary feedwater pump in MODE 3 following REFUELING.

C.

One auxiliary feedwater pump in MODE 1, 2, or 3 for reasons other than a or b. above.

d. Two auxiliary feedwater pumps in MODE 1, 2, or 3.

MILLSTONE - UNIT 2 a

b.

C.

d.

Required ACTION Restore affected equipment to OPERABLE status within 7 days. If these ACTIONS are not met, be in at least HOT STAl'l'DBY within the nell.t 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Restore affected equipment to OPERABLE status within 7 days. If these ACTIONS are not met, be in at least HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Restore the auxiliary feedwater pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . If these ACTIONS are not met, be in at least HOT STA1'\\'DBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Be in at least HOT STAl'IDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3/4 7-4 Amendment No. fil, %, W, :H, ~,

~,297

INSERT 2E Serial No.22-063 Docket No. 50-336, Page 11 of 13

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

LCO 3.0.4.b is not applicable

Serial No.22-063 Docket No. 50-336, Page 12 of 13

-FOR INFORMATION ONLY-3/4.8 ELEC1RICAL POWER SYSTEMS June 24, 2020 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDIDON FOR OPERATION

3. 8.1. l As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

Two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system, and

b.

Two separate and independent diesel generators each with a separate fuel oil supply tank containing a minimum of 12,000 gallons of fuel.

APPLICABILITY:

MODES 1, 2, 3 and 4.

~

ACTION:

J/ -

Inoperable Equipment

a.

One offsite a.I circuit Al'\\Tl) a.2 MID MILLSTONE - UNIT 2 Required ACTION Perform Surveillance Requirement 4.8.1.1.1 for remaining offsite circuit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to or after entering this condition, and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

Restore the inoperable offsite circuit to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (within 10 days* if Required ACTION a.3 is met) or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

3/4 8-1 Amendment No. #, 17, -¥.n, ~.

~. ~

. ;w+, 339

INSERT 2F Serial No.22-063 Docket No. 50-336, Page 13 of 13

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

LCO 3.0.4.b is not applicable to diesel generators Serial No.22-063 Docket No. 50-336 MARKED-UP TECHNICAL SPECIFICATIONS BASES PAGES FOR MPS2 (FOR INFORMATION ONLY)

Dominion Energy Nuclear Connecticut, Inc.

Millstone Power Station Unit 2

-FOR INFORMATION ONLY-APPLICABILITY BASES (Con't)

Serial No.22-063 Docket No. 50-336, Page 1 of 17 Febrnary 26, 1991 The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in the COLD SHUTDOWN MODE when a shutdown is required during the POWER MODE of operation. If the plant is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower !\\JODE of operation applies. However, if a lower MODE of operation is reached in less time than allowed, the total allowance time to reach COLD SHUTDOWN, or other applicable MODE, is not reduced. For example, if HOT STAi'lDBYis reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months . Therefore, if remedial measures are complete-0 that would permit a return to POWER operation, a penalty is not incurred by having to reach a lower.MODE of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into a MODE or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met. If the new specification becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second specification. However, the allowable outage time limits of ACTION requirements for a higher MODE of operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower MODE of operation.

The shutdo,,.,n requirements of Specification 3.0.3 do not apply in MODES 5 and 6, because the ACTION requirements of individual specifications define the remedial measures to be taken.

c* 1cation 3.0.4 establishes limitations on MODE changes when a Limiting Condition for eration is o et. It precludes placing the facility in a higher MODE of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a MODE change. Therefore, in this case, entry into an OPERATIONAL MODE or other specified condition may be made in accordance with the provision of the ACTION requirements.

The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

Replace with INSERT 3A

!\\HLLSTONE - UNIT 2 B 3/4 0-3 Amendment Nos. 62, 151

INSERT 3A Serial No.22-063 Docket No. 50-336, Page 2 of 17 LCO 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an LCO is not met. It allows placing the unit in a MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when unit conditions are such that the requirements of the LCO would not be met, in accordance with LCO 3.0.4.a, LCO 3.0.4.b, or LCO 3.0.4.c.

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. Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions.

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.

The risk assessment may use quantitative, qualitative, or blended approaches, and the risk assessment will be conducted using the plant program, procedures, and criteria in place to implement 10 CFR 50.65(a)(4), which requires that risk impacts of maintenance activities be assessed and managed. The risk assessment, for the purposes of LCO 3.0.4 (b), must take into account all inoperable Technical Specification equipment regardless of whether the equipment is included in the normal 10 CFR 50.65(a)(4) risk assessment scope. The risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." Regulatory Guide 1.160 endorses the guidance in NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases ( establishment of backup success paths or compensatory measures), and determination that the proposed MODE change is acceptable. Consideration should also be given to the probability of completing

Serial No.22-063 Docket No. 50-336, Page 3 of 17 restoration such that the requirements of the LCO would be met prior to the expiration of ACTIONS Completion Times that would require exiting the Applicability.

LCO 3.0.4.b may be used with single, or multiple systems and components unavailable.

NUMARC 93-01 provides guidance relative to consideration of simultaneous unavailability of multiple systems and components.

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. The LCO 3.0.4.b risk assessments do not have to be documented.

The Technical Specifications allow continued operation with equipment unavailable in MODE 1 for the duration of the Completion Time. Since this is allowable, and since in general the risk impact in that particular MODE bounds the risk of transitioning into and through the applicable MODES or other specified conditions in the Applicability of the LCO, the use of the LCO 3.0.4.b allowance should be generally acceptable, as long as the risk is assessed and managed as stated above. However, there is a small subset of systems and components that have been determined to be more important to risk and use of the LCO 3.0.4.b allowance is prohibited. The LCOs governing these system and components contain Notes prohibiting the use of LCO 3.0.4.b by stating that LCO 3.0.4.b is not applicable.

LCO 3.0.4.c allows entry into a MODE or other specified condition in the Applicability with the LCO not met based on a Note in the Specification which states LCO 3.0.4.c is applicable.

These specific allowances permit entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time and a risk assessment has not been performed. This allowance may apply to all the ACTIONS or to a specific Required Action of a Specification. The risk assessments performed to justify the use of LCO 3.0.4.b usually only consider systems and components. For this reason, LCO 3.0.4.c is typically applied to Specifications which describe values and parameters (e.g., Reactor Coolant Specific Activity) and may be applied to other Specifications based on NRC plant-specific approval.

The provisions of this Specification should not 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 Applicability.

The provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability

Serial No.22-063 Docket No. 50-336, Page 4 of 17 associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

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.

Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 4.0.1. Therefore, utilizing LCO 3.0.4 is not a violation of SR 4.0.1 or SR 4.0.4 for any Surveillances that have not been performed on inoperable equipment.

However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO.

-FOR INFORMATION ONLY-APPLICABILITY BASES (Con't)

Serial No.22-063 Docket No. 50-336, Page 5 of 17 LBDCR 04-MP2-016 Febrnary 24, 2005

(11011 a stnndowu is 1equhed to cmnpfy widt itCTfOf:: 1eqtthenrents, dte ptovisions trf Spcci:6:cation 3.8.4 do trot applJ because tbc3 c;ocdd dcl&J phzcing the facility in a Ion ct lciOBE sf epoMtion.

Specification 3.0.5 delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION statements for power sources, when a normal or emergency power source in not OPERABLE. It specifically prohibits operation when one di"ision is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.

The provisions of this specification permit the ACTION statements associated with individual systems, subsystems, trains, components, or devices to be consistent with the ACTION statements of the associated electrical power source. It allows operation to be governed by the time limits of the ACTION statement associated with the Limiting Condition for Operation for the normal or emergency power source, not the individual ACTION statements for each system, subsystem, train, component or device that is determined to be inoperable solely because of the inoperability of its normal emergency power source.

For example, Specification 3.8.1.1 requires in part that two emergency diesel generators be OPERABLE. The ACTION statement provides for a 72-hour out-of-service time when one emergency diesel generator is not OPERABLE. If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source would also be inoperable. This would dictate invoking the applicable ACTION statement for each of the applicable Limiting Conditions for Operation. However, the provisions of Specification 3.0.5 permit the time limits for continued operation to be consistent with the ACTION statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied. In this case, this would mean that the corre.sponding normal power source must be OPERABLE, and all redundant systems, subsystems, trains, components, and devices must be OPERABLE, or otherwise satisfy Specification 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one emergency power source OPERABLE). If they are not satisfied, ACTION is required in accordance with this specification.

As a further example, Specification 3.8. l.1 require.s in part that two physically independent circuits between the offsite transmission network and the onsite Class IE distribution system be OPERABLE. The ACTION statement provides a 24-hour out-of-service time when both required offsite circuits are not OPERABLE. If the definition of OPERABLE were applied without consideration of Specification 3.0.5, all systems, subsystems, trains, components and devices supplied by the inoperable normal power sources, both of the offsi.te circuits, would also be inoperable. This would dictate invoking the applicable ACTION statements for each of the applicable LCOs. However, the provisions of Specification 3.0.5 permit the time limits for continued operation to MILLSTONE - UNIT 2 B 3/40-4 Amendment Nos. -1G, -H, Acknowledged by NRC letter dated 6/28/05

-FOR INFORMATION ONLY-3/4.0 APPLICABILITY BASES (Con't)

~eplace with INSERT 3B Serial No.22-063 Docket No. 50-336, Page 6 of 17 June 19, 2007 LBDCR 07-MP2-014 r-iil!!i~~~~~:t""stablishe.s the requirement that all applicable surveillances must be met before en

mto and OPERATIONAL MODE or other condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be perfonned within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shtndown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower *MODE of operation.

Specification 4.0.5 establishes the requirement that inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of the ASME Code for Operation and ~1aintenance ofNuclear Power Plants (ASME OM Code) and applicable Addenda as required by 10 CFR 50.55a(f). These requirements apply except when relief has been provided in writing by the Commission.

This specification includes a clarification of the.frequencies for performing the inservice testing activities required by the ASME OM Code and applicable Addenda This clarification is provided to ensure consistency in stm*eillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME OM Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIO:'.\\fAL MODE or other specified condition takes precedence over the ASME OM Code provision which allows pumps and valves to be tested up to one week after return to normal operation.

MILLSTONE-UNIT2 B 3/4 0-7 Amendment No. HI-

INSERT 38 Serial No.22-063 Docket No. 50-336, Page 7 of 17 SR 4.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability.

This Specification ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit.

The provisions of this Specification should not 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 Applicability.

A provision is included to allow entry into a MODE or other specified condition in the Applicability when an LCO is not met due to Surveillance not being met in accordance with LCO 3.0.4.

However, in certain circumstances, failing to meet an SR will not result in SR 4.0.4 restricting a MODE change or other specified condition change.

When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 4.0.1, which states that surveillances do not have to be performed on inoperable equipment.

When equipment is inoperable, SR 4.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified Frequency does not result in an SR 4.0.4 restriction to changing MODES or other specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes. SR 4.0.4 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 4.0.3.

The provisions of SR 4.0.4 shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 4.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

-FOR INFORMATION ONLY-REACTOR COOLANT SYSTEM BASES 3/4.4.8 SPECIFIC ACIB1ITY (continued)

ACTIONS

a. and b.

Serial No.22-063 Docket No. 50-336, Page 8 of 17 June 27, 2019 LBDCR 19-MP2-002 With the DOSE EQUIVALENTI-131 greater than the LCO limit, samples at intervals of four hours must be taken to demonstrate that the specific activity is :,; 30 µCi/gm. Four hours is required to obtain and analyze a sample. Sampling is continued every four hours to provide a trend The DOSE EQUIVALENT I-131 must be restored to within limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The completion time of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is acceptable since it is expected that, if there were an iodine spike, the normal coolant iodine concentration would be restored within this time period. Also, there is a low probability of a SLB or SGTR occurring during this time period.

/rstatc111cnt in.. \\:e;;r:18?l k. indicates the pto uisictlb of EfeQ 3.9. -1 we nut applic&elc. 11'.bs

@.,up*ionfo J.,GQ 3.Q.1 p@Mt~o rnlt_. Mi@ the llf'f!li@al!1@) IQQ~E~,,,e1,*mg @It }.0'.flQJ.S It. 1t1ts

b. nbik tire B8SE Ee,BPUmENT I Bl LOO is not met. This

. acceptable due to the si "ficant conservatism incorporated into the RCS specific activity limit, low probability of an ent which is lin1iting due to exceeding this linlit, and the ability to restore nsient-specific acth *ty excursions while the plant remains at, or proceeds to, power operation.

"allowance" "A Note permits the use of provisions ofLCO 3.0.4.c. This allowance permits

c.

entry into the applicable MODE{S) while relying on the ACTIONS."

If the required action and completion time of ACTION b. is not met, or if the DOSE EQUIV.I\\LENT I-131 is> 30 µCi/gm, the reactor must be brought to HOT STANDBY (MODE 3) within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN (MODE 5) within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed completion times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly mamier and without challenging plant systems.

MILLSTONE - UNIT 2 B 3/4 4-4c

-FOR INFORMATION ONLY-REACTOR COOLANT SYSTEM BASES 3/4.4.8 SPECIFIC ACTIVITY (continued)

ACTIONS (continued)

!L Serial No.22-063 Docket No. 50-336, Page 9 of 17 LBDCR 14-MP2-016 September 4, 2014 With the RCS DOSE EQUIVALENTXE-133 greater than the LCO limit, DOSE EQUNALENT XE-133 must be restored to within limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The allowed completion time of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is acceptable since it is expected that, if there were a noble gas spike, the normal coolant noble gas concentration would be restored within this time period. Also, there is a low probability of a SLB or SGTR occurring during this time period.

z'rstatcmcut in 1\\.0HOti el. indicalts tire p10 eisim1S ofL@0 9.8. I me not applicable. Tltb

i111111p&i11Rt11 J,,CQ ~ Q 1 p111i111~B illKJ'5" ill&o ~" 11pplii11M1h } IQQiE~), i;iil,*iRg oR-4 CJ;IQ;)T d 11i1hili, Inc DOSE EE~llPJALENT J(E 133 LOO is not met. This.

is acceptable due to the significant conservatism incorpora e

to the RCS specific activrty * *, the low probability of an event which is limiting due to exceedin

s limit, and the ability to res ansient-specific activity excursions while the plant remains at, o oceeds to, POWER OPERATI

,.,,...:e------,

"A Note permits the use of provisions ofLCO 3.0.4.c. This allowance permits entry into the applicable l\\-10DE(S) while relying on the ACTIONS."

If the required action and completion time of ACTION d. is not met, the reactor must be brought to HOT STAi'lDBY (MODE 3) within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN (MODE 5) within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed completion times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLAl'l'CE REQUIREMENTS Surveillance Requirement 4.4.8.1 re{luires performing a gamma isotopic analysis as a measure of the noble gas specific activity of the reactor coolant. This measurement is the sum of the degassed gamma activities and the gaseous gamma activities in the sample taken. This Surveillance Requirement provides an indication of any increase in the noble gas specific activity. The surveillance frequency is controlled under the Surveillance Frequency Control Program.

Trending the results of this Surveillance Requirement allows proper remedial action to be taken before reaching the LCO limit under normal operating conditions.

MILLSTONE - UNIT 2 B 3/4 4-4d

Serial No.22-063 Docket No. 50-336, Page 1 0 of 17

-FOR INFORMATION ONLY-REACTOR COOLANT SYSTEM BASES LBDCR 05-MP2-003 December 27, 2005 If a loss of RCS inventory or reduction in SHUTDOWN MARGIN event occurs, the appropriate response will be to correct the situation by starting RCS makeup pumps. If the loss of inventory or SHUTDOWN MARGIN is significant, this may necessitate the use of additional RCS makeup pumps that are being maintained not capable of injecting into the RCS in accordance with Technical Specification 3.4.9.3. The use of these additional pumps to restore RCS inventory or SHUTDOWN MARGIN will require entry into the associated ACTION statement. The ACTION statement requires immediate action to comply with the speeification.

The restoration of RCS inventory or SHUTDOWN MARGIN can be considered to be part of the immediate action to restore the additional RCS makeup pumps to a not capable of injecting status.

While recovering RCS inventory or SHUTDOWN MARGIN, RCS pressure will be maintained below the Appendix G limits. After RCS inventory or SHUTDOWN MARGIN has been restored, the additional pumps should be immediately made not capable of injecting and the ACTION statement exited.

!.--IN--rs=ER

=--T--3.... C----.

"' UHtitie& te J:@ehiiteal ilf! uiit1&tie1t HU it, Oil uiituU@r +e@kftiettl ilj!nilt@Mie&

3 4 9 3 to allo1r a pJaet cooldo1rn to a IODli S if one or both PORJ'r art i1aeperablc ~-rODE 5

@e&diiiem; t1ta, ~e n@H!l8-,* ste Hf!8ir th,i PQRVEs).

3/4.4,10 DELETED MJLLSTONE - UNIT 2 B3/44-7c Amendment No. :2-1--&, ~, ~, ~.

Acknowledged by NRC letter dated 12/19/06

INSERT 3C Serial No.22-063 Docket No. 50-336, Page 11 of 17 A Note prohibits the application of LCO 3.0.4.b to inoperable PORVs used for L TOP.

There is an increased risk associated with entering MODE 4 from MODE 5 with PORVs used for L TOP inoperable and the provisions of LCO 3.0.4.b, which allow 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, should not be applied in this circumstance.

-FOR INFORMATION ONLY-3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

BASES:

SERT3D Serial No.22-063 Docket No. 50-336, Page 12 of 17 LBDCR 14-MP2-017 January 8, 2015 The provision in Specification 3.5.3 that Specifications 3.0.4 and 4.0.4 are not applicable for entry into MODE 4 is provided to allow for connecting the HPSI pump breaker to the respective power supply or to remove the tag and open the discharge valve, and perfom1 the subsequent testing necessary to declare the inoperable HPSI pump OPER.ABLE. Specification 3.4.9.3 requires all HPSI pumps to be not capable of injecting into the RCS when RCS temperature is at or below 190°F. Once RCS temperature is above 190°F one HPSI pump can be capable of injecting into the RCS. However, sufficient tin1e may not be available to ensure one HPSI pump is OPERABLE prior to entering MODE 4 as required by Specification 3.5.3. Since Specifications 3.0.4 and 4.0.4 prohibit a MODE change in this situation, this exemption will allow Millstone Unit No. 2 to enter MODE 4, take the steps necessary to make the HPSI pump capable of injecting into the RCS, and then declare the pump OPERABLE. Ifit is nece.ssary to use this exemption during plant heatup, the appropriate ACTION statement of Specification 3.5.3 should be entered as soon as MODE 4 is reached.

3/4.5.4 REFUELING WATER S1DRAGE TANK (RWSD The OPERABILITY of the RWST as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. A minimum usable volume of 370,000 gallons is required for ECCS injection above the earliest or highest level of SRAS initiation accounting for indicator accuracy. The liniits on RWST mininmm volume and boron concentration ensure that 1) sufficient water is available within containment to pennit recirculation cooling flow to the core, and 2) after a LOCA the reactor will remain subcritical in the cold condition following mixing of the RWST and the RCS water volumes. Small break LOCAs asSUllle that all control rods are inserted, except for the control element assembly (CEA) of highest worth, which remains withdrawn from the core. Large break LOCAs assume that all CEAs remain withdrawn from the core.

MILLSTONE - UNIT 2 B 3/4 5-2f Amendment No. j

INSERT 3D Serial No.22-063 Docket No. 50-336, Page 13 of 17 A Note prohibits the application of LCO 3.0.4.b to an inoperable ECCS high pressure safety injection subsystem. There is an increased risk associated with entering MODE 4 from MODE 5 with an inoperable ECCS High Pressure Safety Injection subsystem and the provisions of LCO 3.0.4.b, which allow 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, should not be applied in this circumstance.

3/4 7 PLANT SYSTE~IS BASES 3/4.7.1.2 AUXILI

-FOR INFORMATION ONL y.

Serial No.22-063 Docket No. 50-336, Page 14 of 17 November 10, 2005 LBDCR 04-MP2-013 If the turbine-driven auxiliary feedwater train is inoperable due to an inoperable steam supply in MODES 1, 2, and 3, or if the turbine-driven auxiliary feedwater pump is inoperable while in MODE 3 immediately following REFUELING, action must be taken to restore the inoperable equipment to an OPERABLE status within 7 days. The 7 day allowed outage time is reasonable, based on the following:

a.

For the inoperability of the turbine-driven auxiliary feedwater pump due an inoperable steam supply, the 7 day allowed outage time is reasonable since the auxiliary feedwater system design affords adequate redundancy for the steam supply line for the turbine-driven pump.

b.

For the inoperability of a turbine-driven auxiliary feedwater pump while in MODE 3 immediately subsequent to a refueling, the 7 day allowed outage time is reasonable due to the minimal decay heat levels in this situation.

c.

For both the inoperability of the turbine-driven pump due to an inoperable steam supply and an inoperable turbine-driven auxiliaryfee-dwaterpump while in MODE 3 immediately following a refueling outage, the 7 day allowed outage time is reasonable due to the availability ofredundant OPERABLE motor driven auxiliary feedwater pumps, and due to the low probability of an event requiring the use of the turbine-driven auxiliary feedwater pump.

When one ste.am supply to the turbine-driven auxiliary feedwater pump is inoperable, the turbine-driven amciliary feedwater pump is inoperable. In this case, although the turbine-driven auxiliary feedwater pump with a single operable steam supply is capable of performing its safety function in the absence of a single failure, the turbine-driven auxiliary feedwater pump is considered inoperable due to the lack of redundancy with respect to steam supplies.

The required ACTION dictates that if the 7 day allowed outage time is reached the unit must be in at least HOT STA.t'JDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The allowed time is reasonable, based on operating experience, to reach the required conditions from full power conditions in an orderly manner and without challenging plant systems.

MILLSTONE - UNIT 2 B 3/4 7-2b Amendment No. ~. 61-, 63-, U!-, ~.

~.

INSERT 3E Serial No.22-063 Docket No. 50-336, Page 15 of 17 A Note prohibits the application of LCO 3.0.4.b to an inoperable AFW train. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an AFW train inoperable and the provisions of LCO 3.0.4.b, which allow 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, should not be applied in this circumstance.

Serial No.22-063 Docket No. 50-336, Page 16 of 17

-FOR INFORMATION ONLY-3/4.8 ELECTRICAL POWER SYSTEMS BASES

~

INSERT3F LBDCR 07-MP2-009 March 29, 2007 Technical Specification 3.8. l. l ACTION Statements b and c provide an allowance to avoid unnecessary testing of the other OPERABLE diesel generator. If it can be determined that the cause of the inoperable diesel generator does not exist on the OPERABLE diesel generator, Surveillance Requirement 4.8.l.l.2.a.2 does not have to be performed. If the cause of inoperability exists on the other OPERABLE diesel generator, the other OPERABLE diesel generator would be declared inoperable upon discovery, ACTION Statement e would be entered, and appropriate ACTIONS will be taken. Once the failure is corrected, the common cause failure no longer exists, and the required ACTION Statements (b, c, and e) will be satisfied.

If it cannot be determined that the cause of the inoperable diesel generator does not exist on the remaining diesel generator, performance of Surveillance Requirement 4.8. l. l.2.a.2, within the allowed time period, suffices to provide assurance of continued OPERABILITY of the diesel generator. If the inoperable diesel generator is restored to OPERABLE status prior to the determination of the impact on the other diesel generator, evaluation will continue of the possible common cause failure. This continued evaluation is no longer under the time constraint imposed while in ACTION Statement b or c.

The determination of the existence of a common cause failur.i that would affect the remaining diesel generator will require an evaluation of the current failure and the applicability to the remaining diesel generator. Examples that would not be a common cause failure include, but are not limited to:

1.

Preplanned preventive maintenance or testing, or

2. An inoperable support system with no potential common mode failure for the remaining diesel generator, or

3.

An independently testable component with no potential common mode failure for the r.imaining diesel generator.

If one Millstone Unit No. 2 diesel generator is inoperable in MODES 1 though 4, ACTION Statements b.3 and c.3 require verification that the steam-driven auxiliary feedwater pump is OPERABLE (MODES 1, 2, and 3 only). If the steam-driven auxiliary feedwater pump is inoperable, restoration within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months is required or a plant shutdown to MODE 4 will be necessary. This requirement is intended to provide assurance that a loss of offsite power event will not result in degradation of the auxiliary feedwater safety function to below accident mitigation requirements during the period one of the diesel generators is inoperable. The term verify, as used in this context, means to administratively check by examining logs or other information to determine if the steam-driven auxiliary feedwater pump is out of service for maintenance or other reasons. It does not mean to perform Surveillance Requirements needed to demonstrate the OPERABILITY of the steam-driven auxiliary feedwater pump.

MILLSTONE - UNIT 2 B 3/4 8-3 Amendment No. -l-88, ~. ~

.w8,

u;+,

INSERT 3F Serial No.22-063 Docket No. 50-336, Page 17 of 17 A Note prohibits the application of LCO 3.0.4.b to an inoperable diesel generator. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an inoperable diesel generator and the provisions of LCO 3.0.4.b, which allow 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, should not be applied in this circumstance.

Serial No.22-063 Docket No. 50-423 MARKED-UP TECHNICAL SPECIFICATIONS PAGES FOR MPS3 Dominion Energy Nuclear Connecticut, Inc.

Millstone Power Station Unit 3

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-423, Page 1 of 19 November 15, 2002 3/4 LIMITING CONDffiONS FOR OPE~I\\TION At"\\,ID SURVEILLAt"\\,ICE REOUIREMEI\\TTS 3/4.0 APPLICABILITY LIMmNG CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met, except as provided in Specification 3.0.5.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals, except as provided in Specification 3.0.5. lfthe Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

a.

At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

c.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when e onditions for the Limiting Condition for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified ti.me interval. Entry into an OPERiITIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permit continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual s~cifications.

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 OPERABILTIY or the OPERABILITY of other equipment This is an exception to Specifications 3.0.1 and 3.0.2 for the system returned to service tmder administrative controls to perform the testing required to demonstrate OPERABILITY.

4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. Failure to meet a Surveillance, whether such failure is experienced during the performance MILLSTONE - UN1T 3 3/4 0-1 Amendment-M, -¥1-, -19-, 213

INSERT 4A Serial No.22-063 Docket No. 50-423, Page 2 of 19 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; or

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.

Serial No.22-063 Docket No. 50-423, Page 3 of 19

-FOR INFORMATION ONLY-July 31, 2008 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION of the Surveillance or between performances of the Surveillance, shall be failure to meet the Limiting Condition for Operation. Failure to perform a Surveillance within the specified surveillance interval shall be failure to meet the Limiting Condition for Operation except as provided in Specification 4.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

4.0.3 If it is discovered that a Surveillance was not performed within its specified surveillance interval, then compliance with the requirement to declare the Limiting Condition for Operation 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 surveillance interval, whichever is greater. 1bis delay period is permitted to allow perfonnance 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 Limiting Condition for Operation 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 Limiting Condition for Operation must immediately be declared not met, and theca:"'-'~l;.;ic'-"a"-b;;.;le;.,.-,===-=-==-,

Condition(s) must be entered.

Replace with INSERT 4B 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless e urveillance Requirement( s) associated with the Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through orto OPERATIONAL MODES as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservice testing of ASME Code Class 1, 2, and 3 components shall be performed in accordance with the ASME Code for Operation and Maintenance ofNuclear Power Plants (ASME OM Code) as follows:

a.

Deleted.

b.

Surveillance intervals specified in the ASME OM Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

MILLSTONE - UNIT 3 3/4 0-2 Amendment No. M, -¥1-, 3-&, -¥79, iH-3-,

241

INSERT 48 Serial No.22-063 Docket No. 50-423, Page 4 of 19 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 4.0.3.

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.

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-423, Page 5 of 19 February 25, 2014 INSTRUMENTATION REMOTE SHUTDOWN lNSTRill1ENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The Remote Shutdown Instrumentation transfer switches, power, controls and monitoring instnnnentation channels shown in Table 3.3-9 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

b.

C.

With the number of OPERABLE remote shutdown monitoring channels less than the Minimum Channels OPERABLE as required by Table 3.3-9, restore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With one or more Remote Shutdown Instrumentation transfer switches, power, or control circuits inoperable, restore the inoperable switch(s )/circuit(s) to OPERABLE status within 7 days, or be in HOT STAl'n)BY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

EnhJ isdo mt 8PlsfuYF101iz'Jzh 2,ISBE is pc1111iOcd,,J,_ik subject *o..i,csc

_1,GHQN 2S!J&ii!ll1'Sllt!I.

SURVEILLA.t'l'CE REQUIREMENTS 4.3.3. 5.1 Each required remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBR<\\TION operations at the frequencies shown in Table 4.3-6.

4.3.3.5.2 Each Remote Shutdown Instrumentation transfer switch, power and control circuit including the actuated components, shall be demonstrated OPERABLE at the frequency specified in the Surveillance Frequency Control Program.

MILLSTONE - UNIT 3 3/4 3-53 Amendment No.¥/-, 19, -HlG, 258

Serial No.22-063 Docket No. 50-423, Page 6 of 19

-FOR INFORMATION ONLY-LIMITING CONDITION FOR OPERATION (Continued)

February 25, 2014 action taken, the cause of the inoperability, and the plans and schedule for restoring the channel to OPERABLE status.

f.

With the number of OPERABLE channels for the reactor vessel water level monitor less than the minimum channels OPERABLE requirements of Table 3.3-10, either restore the inoperable cbannel(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months if repairs are feasible without shutting down or:

1.

Initiate an alternate method of monitoring the reactor vessel inventory;

2.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the channel(s) to OPERABLE status; and

3.

Restore the chanuel(s) to OPERABLE status at the next scheduled refueling.

.,trOHO!'t 1cqaitcmcnb.

SURVEILLA1'l"CE REQUIREMENTS 4.3.3.6.1 Each required accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANP-TEL CALIBRATION at the frequencies shown in Table 4.3-7.

4.3.3.6.2 Deleted o-llLLSTONE - UNIT 3 3/4 3-59a Amendment No. 4'.7, ~, ::,6, e, ~,

258

-FOR INFORMATION ONLY*

REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES Lll\\IITING CONDITION FOR OPERATION Serial No.22-063 Docket No. 50-423, Page 7 of 19 March 16, 2006 3.4.4.

Both power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

a.

With one or both PORV(s) inoperable because of excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one-PORV inoperable due to causes other than excessive seat leakage, within I hour either restore the PORV to OPERABLE status or close the associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STAi'l'DBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With both PORV s inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore at least one PORV to OPERABLE status or close its ass0<..--iated block valve and remove power from the block valve and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d.

With one or both block valve(s) inoperable, within I hour restore the block valve(s) to OPERABLE status, or place its associated PORV(s) control switch to "CLOSE." Restore at least one block valve to OPERABLE status within the next hour if both block valves are inoperable; restore any remaining inoperable block valve to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; otherwise, be in at least HOT STAL'l'DBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

C.

Ea1t5 into an QPEiR: 1.+10?'.'zb UQE>Ei is pcaniltcd nhil:e sal,jcet le 11.ese 11zOHB~i 1cqaitt-1ncnts.

MILLSTONE - UNIT 3 3/4 4-12 Amendment No. -¥1-, 8-&, -l-61-, 229

--FOR INFORMATION ONLY-REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVI1Y LIMITING CONDITION FOR OPERATION 3.4.8 Tue specific activity of the reactor coolant shall be liruite.d to:

Serial No.22-063 Docket No. 50-423, Page 8 of 19 October 27, 2008

a.

Less than or equal to 1 microCurie per gram DOSE EQUIVALENT 1-131, and

b.

Less than or equal to 81.2 microCuries per gram DOSE EQUIVALENTXE-133.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

a.

With the specific activity of the reactor coolant greater than 1.0 microCurie per gram DOSE EQUIVALENT 1-131, verify DOSE EQUIVALENT 1-131 less than or equal to 60 microCuries per gram once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

With the specific activity of the reactor coolant greater than 1.0 microCurie per gram DOSE EQUIVALE!\\TT 1-131 but less than or equal to 60 microCuries per gram, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT I-131 to within the 1. 0 microCurie per gram limit.

S ecification.. is -+-applicable.

c.

With the specific activity of the reactor coolant greater than 1.0 microCurie per gram DOSE EQUIVALENT 1-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, or greater than 60 microCuries per gram DOSE EQUIVALENT 1-131, be in HOT STA.i'-IDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within 36hours.

d.

With the specific activity of the reactor coolant greater than 81.2 microCuries per gram DOSE EQUIVALENT :X.'E-133, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT XE-133 to within the 81.2 microCuries per gram limit. Specification.. is M+,applicable.

"3.0.4.c"

e.

With the specific activity of the reactor coolant greater than 81.2 microCuries per gram DOSE EQUIVALE1 T XE-133 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, be in HOT STAl'IDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

ivllLLSTONE - UNIT 3 3/4 4-28 Amendment No. 246

-FOR INFORMATION ONLY-REACTOR COOLA.i"\\IT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION Serial No.22-063 Docket No. 50-423, Page 9 of 19 August 27, 2001 3.4.9.3 Cold Overpressure Protection shall be OPERABLE with a maximum of one centrifugal charging pump* and no Safety Injection pumps capable of injecting into the Reactor Coolant System (RCS) and one of the following pressure relief capabilities:

1.

One power operated relief valve (PORV) with a nominal lift setting established in Figure 3.4-4a and one PORV with a nominal lift setting established in Figure 3.4-4b with no more than one isolated RCS loop, or

2.

Two residual heat removal (RHR) suction relief valves with setpoints;;:: 426.8 psig and:,; 453.2 psig, or

3.

One PORV with a nominal lift setting established in Figure 3.4-4a or Figure 3.4-4b with no more than one isolated RCS loop and one RHR suction relief valve with a setpoint;;:: 426.8 psig and:,; 453.2 psig, or

4.

RCS depressurized with an RCS vent of;;:: 2.0 square inches.

APPLICABILITY:

MODE 4 when any RCS cold leg temperature is:,; 226°F, MODE 5, and MODE 6 when the head is on the reactor vessel.

~

ACTION:

~

a.

With two or more centrifugal charging pumps capable of injecting into the RCS, immediately initiate action to establish that a maximum of one centrifugal charging pump is capable of injecting into the RCS.

b.

With any Safety Injection pump capable of injecting into the RCS, immediately initiate action to establish that no Safety Injection pumps are capable of injecting into the RCS.

c.

With one required relief valve inoperable in MODE 4, restore the required relief valve to OPERABLE status within 7 days, or depressurize and vent the RCS through at least a 2.0 square inch vent within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Two centrifugal charging pumps may be capable of injecting into the RCS for less than one hour, during pump swap operations. However, at no time will two charging pumps be simultaneously out of pull-to-lock during pump swap operations.

MILLSTONE - UNIT 3 3/4 4-38 Amendment No. +8, -¥1-, 8G, -1#, -H-'.7, 197

INSERT 4C Serial No.22-063 Docket No. 50-423, Page 1 O of 19

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

LCO 3.0.4.b is not applicable when entering MODE 4

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-423, Page 11 of 19 August 27, 2001 REACTOR COOLAt"\\/T SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CO:NDIDON FOR OPERATION

d.

e.

f.

With one required relief valve inoperable in MODE 5 or 6, restore the required relief valve to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or depressurize the RCS and establish an RCS vent of~ 2.0 square inches within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With two required relief valves inoperable, depressurize the RCS and establish an RCS vent of~ 2.0 square inches within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1n the event the PORVs, the RHR suction relief valves, ortl1e RCS vent are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs, fue RHR suction relief valves, or RCS vent on the transient, and any corrective action necessary to prevent recurrence.

1\\EWIO~C 1cqai1c1ncnb.

MILLSTONE - UNIT 3 3/4 4-38a Amendment No. -i-8, -¥/-, 00, -143, 1-¥1-,

197

-FOR INFORMATION ONLY-EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T' LESS THAI'!" 350°F LIMITING CONDITION FOR OPERATION Serial No.22-063 Docket No. 50-423, Page 12 of 19 2/12/98 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a.

One OPERABLE centrifugal charging pump,

b.

One OPERABLE RHR heat exchanger,

c.

One OPERABLE RHR pump,

d.

One OPERABLE containment recirculation heat exchanger,

e.

One OPERABLE containment recirculation pump, and

f.

An OPERABLE flow path which, with manual realignment of valves, is capable of discharging to the RCS, taking suction from the refueling water storage tank, and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY:

MODE 4.

ACTION:

~

a.

With no ECCS subsystem OPER..J\\BLE because of the inoperability of the centrifugal charging pump, the containment recirculation pump, the containment recirculation heat exchanger, the flow path from the refueling water storage tank, or the flow path capable of taking suction from the containment sump, restore at least one ECCS subsystem to OPERABLE status within l hour or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b.

With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or RHR pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System Tavg less than 350°F by use of alternate heat removal methods.

c.

In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

MILLSTONE - Ul\\'IT 3 3/4 5-7 Amendment No. 157

INSERT 4D Serial No.22-063 Docket No. 50-423, Page 13 of 19

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

LCO 3.0.4.b is not applicable to ECCS high pressure safety injection subsystem

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-423, Page 14 of 19 May 15, 2002 CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 The containment air lock shall be OPERABLE with:

a.

Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and

b.

An overall air lock leakage rate in accordance with the Containment Leakage Rate Testing Program.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

NOTE Entry and exit through the containment air lock doors is permitted to perform repairs on the affected air lock components.

a.

With only one containment air lock door inoperable:

l.

2.

3.

1.

Verify the OPERABLE air lock door is closed within l hour and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed, Operation may then continue provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days, Otherwise, be in at least HOT STAt'H)BY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , and Eut5 into mt OPER::\\TI@C,1ds ?.1086 is puu1ittcd,,IMc subject to these 21rOiiff0?i 1cquitcmcnhs.

b.

With only the containment air lock interlock mechanism inoperable, verify an OPERABLE air lock door is closed within I hour and lock an OPERABLE air lock door closed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Verify an OPERABLE air lock door is locked closed at least once per 31 days thereafter. Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . (Entry into and exit from containment is permissible under the control of a dedicated individual).

MILLSTONE

UNIT 3 3/4 6-5 Amendment No. ¥1-, ¥.), H4, -l-86, 205

Serial No.22-063 Docket No. 50-423, Page 15 of 19

-FOR INFORMATION ONL y.

February 28, 2007 PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM Lll\\HTING CONDITION FOR OPERATION

3. 7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a.

Two motor-driven auxiliary feedwater pumps, each capable of being powered from separate emergency busses, and

b.

One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE stean1 supply system.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

~

Inoperable Equipment Required ACTION

a. Turbine-driven auxiliary

a. Restore affected equipment to OPERABLE status feedwater pump due to one of the within 7 days. If these ACTIONS are not met, be in two required steam supplies being at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and inoperable.

in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

b. Restore affected equipment to OPERABLE status within 7 days. If these ACTIONS are not met, be in

- - - - - NOTE- -

at least HOT SHUTDOWN within the following 12 Only applicable if MODE 2 has hours.

not been entered following REFUELING.

One turbine-driven auxiliary feedwater pump in MODE 3 following REFUELING.

C. One auxiliary feedwater pump in C. Restore the auxiliary feedwater pump to MODE 1, 2, or 3 for reasons other OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . If these than a. or b. above.

ACTIONS are not met, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. Two auxiliary feedwater pumps in d. Be in at least HOT STA.t'1DBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in MODE 1, 2, or 3.

HOT SHUTDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i\\IlLLSTONE - UNIT 3 3/4 7-4 Amendment No. ¥1-, -l-00, 235

INSERT 4E Serial No.22-063 Docket No. 50-423, Page 16 of 19

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

LCO 3.0.4.b is not applicable

-FOR INFORMATION ONLY-PLANT SYSTEMS STEA.i\\-1 GENERATOR ATMOSPHERIC RELIEF BYPASS LINES LIMITING CONDIDON FOR OPERATION Serial No.22-063 Docket No. 50-423, Page 17 of 19 Febrnary 25, 2014

3. 7.1.6 Each steam generator atmospheric relief bypass valve (SGARBV) line shall be OPERABLE, with the associated main steam atmospheric relief isolation (block) valve in the open position.

APPLICABILITY:

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

ACTIONS:

a.

With one required SGARBV line inoperable, restore required SGARBV line to OPERABLE status within 7 days or be in at least MODE 3 within the neid 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and be in MODE 4 without reliance upon steam generator for heat removal within the nei..1 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months . r.:OO 3.8. I is not applicable.

b.

With two or more required SGARBV lines inoperable, restore all but one required SGARBV line to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least MODE 3 within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and be in.MODE 4 without reliance upon steam generator for heat removal within the nei..1 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

SURVEILLA.i~CE REQUIREMENTS

4. 7.1.6. l Verify one complete cycle of each SGARBV at the frequency specified in the Surveillance Frequency Control Program.

4. 7.1.6.2 Verify one complete cycle of each main steam atmospheric relief isolation (block) valve at the frequency specified in the Surveillance Frequency Control Program.

MILLSTONE - UNIT 3 3/4 7-9a Amendment No. H-1-, 258

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-423, Page 18 of 19 lllan::h 16, 2006 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1. l As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

Two physically independent circuits betwe~n the offsite transmission network and the onstte Class lE Distribution System, and

b.

Two separate and independent diesel generators, each with:

l)

A separate day tank containing a minimum volume of 278 gallons of fuel,

2)

A separate Fuel Storage System containing a minimum volume of32,760 gallons of fuel,

3)

A separate fuel transfer pump,

4)

Lubricating oil storage c-0ntaining a minimum total volume of280 gallons of lubricating oil, and

5)

Capability to transfer lubricating oil from storage to the diesel generator urut.

APPLICABILITY:

MODES 1, 2, 3, and 4.

A.CTION*

Inoperable t:.qutpment Keqmred ACTION

a.

One offsite circuit a.I Perform Surveillance Requirement 4.8.1.1.1.a for remaining offsite cin::uit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to or after entering this condition, and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

A.t'ID a.2 Restore the inoperable offsite circuit to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STA.t'JDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

One diesel generator b.l Pertorm Survetllance Requirement 4.8.1.1.1.a for the offsite circuits within I hour prior to or after entering this condition, and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

A.t'JD b.2 Demonstrate OPERABLE diesel generator is not inoperable due to common cause failure within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or perform Surveillance Requirement 4.8. l.1.2.a5 for the OPERABLE diesel generator within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Ai'ID MILLSTONE - UNIT 3 3/4 8-1 Amendment No. 64, 'Fl-,~,~, 229

INSERT 4F Serial No.22-063 Docket No. 50-423, Page 19 of 19

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

LCO 3.0.4.b is not applicable to diesel generators Serial No.22-063 Docket No. 50-423 MARKED-UP TECHNICAL SPECIFICATIONS BASES PAGES FOR MPS3 (FOR INFORMATION ONLY)

Dominion Energy Nuclear Connecticut, Inc.

Millstone Power Station Unit 3

Replacew 3/4.0 APPLICABILITY BASES

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-423, Page 1 of 15 April 17, 2000 MODE, is not reduced. For example, if HOT STANDBY is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed to reach HOT SHUTDOWN is the nex1 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time to reach HOT SHUTDO\\VN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months . Therefore, if remedial measures are completed that would permit a return to POWER operation, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into a MODE or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met. If the new specification becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second specification. However, the allowable outage time limits of ACTION requirements for a higher MODE of operation may not be used to ell.1end the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower MODE of operation.

The shutdown requirements of Specification 3.0.3 do not apply in MODES 5 and 6, because the cations define the remedial measures to be taken.

blishes limitations on MODE changes when a Limiting C-011dition for

~~~~:§0~1sSZ"osf:~e*1;:1 precludes placing the facility in a high MODE of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a MODE change. Therefore, in this case, entry into an OPERATIONAL MODE or other specified condition may be made in accordance with the provisions of the ACTION requirements.

The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provision of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

Specification 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to Specifications 3.0.1 and 3.0.2 (e.g., to not comply with the applicable Required Actioo(s)) to allow the performance of required testing to demonstrate either:

a.

The OPERABILITY of the equipment being returned to service; or

b.

The OPERABILITY of other equipment.

MILLSTONE

UNIT 3 B 3/4 0-3 Amendment No. -fff, 179

INSERT 5A Serial No.22-063 Docket No. 50-423, Page 2 of 15 LCO 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an LCO is not met. It allows placing the unit in a MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when unit conditions are such that the requirements of the LCO would not be met, in accordance with LCO 3.0.4.a, LCO 3.0.4.b, or LCO 3.0.4.c.

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. Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions.

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.

The risk assessment may use quantitative, qualitative, or blended approaches, and the risk assessment will be conducted using the plant program, procedures, and criteria in place to implement 10 CFR 50.65(a)(4), which requires that risk impacts of maintenance activities be assessed and managed. The risk assessment, for the purposes of LCO 3.0.4 (b), must take into account all inoperable Technical Specification equipment regardless of whether the equipment is included in the normal 10 CFR 50.65(a)(4) risk assessment scope. The risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." Regulatory Guide 1.160 endorses the guidance in NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the proposed MODE change is acceptable. Consideration should also be given to the probability of completing restoration such that the requirements of the LCO would be met prior to the expiration of ACTIONS Completion Times that would require exiting the Applicability.

Serial No.22-063 Docket No. 50-423, Page 3 of 15 LCO 3.0.4.b may be used with single, or multiple systems and components unavailable.

NUMARC 93-01 provides guidance relative to consideration of simultaneous unavailability of multiple systems and components.

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. The LCO 3.0.4.b risk assessments do not have to be documented.

The Technical Specifications allow continued operation with equipment unavailable in MODE 1 for the duration of the Completion Time. Since this is allowable, and since in general the risk impact in that particular MODE bounds the risk of transitioning into and through the applicable MODES or other specified conditions in the Applicability of the LCO, the use of the LCO 3.0.4.b allowance should be generally acceptable, as long as the risk is assessed and managed as stated above. However, there is a small subset of systems and components that have been determined to be more important to risk and use of the LCO 3.0.4.b allowance is prohibited. The LCOs governing these system and components contain Notes prohibiting the use of LCO 3.0.4.b by stating that LCO 3.0.4.b is not applicable.

LCO 3.0.4.c allows entry into a MODE or other specified condition in the Applicability with the LCO not met based on a Note in the Specification which states LCO 3.0.4.c is applicable.

These specific allowances permit entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time and a risk assessment has not been performed. This allowance may apply to all the ACTIONS or to a specific Required Action of a Specification. The risk assessments performed to justify the use of LCO 3.0.4.b usually only consider systems and components. For this reason, LCO 3.0.4.c is typically applied to Specifications which describe values and parameters (e.g., Reactor Coolant Specific Activity) and may be applied to other Specifications based on NRC plant-specific approval.

The provisions of this Specification should not 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 Applicability.

The provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

Serial No.22-063 Docket No. 50-423, Page 4 of 15 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.

Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 4.0.1. Therefore, utilizing LCO 3.0.4 is not a violation of SR 4.0.1 or SR 4.0.4 for any Surveillances that have not been performed on inoperable equipment.

However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO.

3/4 0 APPLICABILITY BASES

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-423, Page 5 of 15 LBDCR No. 07-MP3-009 June 19, 2007

/jReplace with INSERT SB

¢ S ecification 4.0.4 tablishes the requirement that all applicable surveillances must be met liefore e

to an OPERATIONAL MODE or other condition of operation specified in the Applicability statement The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower ]..,[ODE of operation.

Specification 4.0.5 establishes the requirement that inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of the AS1-IE Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as required by 10CFR50.55a(f). These requirements apply except when relief has been provided in writing by the Commission.

This specification includes a clarification of the frequencies for performing the inservice testing activities required by the ASME OM Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the AS.ME OM Code and applicable Addenda. The requirements of Specification 4.0.4 to perfonn surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME OM Code provision which allows pumps and valves to be tested up to one week after return to normal operation.

MILLSTONE - UNIT 3 B 3/4 0-6 Amendment No. -¥1, U3-,

INSERT 58 Serial No.22-063 Docket No. 50-423, Page 6 of 15 SR 4.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability.

This Specification ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit.

The provisions of this Specification should not 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 Applicability.

A provision is included to allow entry into a MODE or other specified condition in the Applicability when an LCO is not met due to Surveillance not being met in accordance with LCO 3.0.4.

However, in certain circumstances, failing to meet an SR will not result in SR 4.0.4 restricting a MODE change or other specified condition change.

When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 4.0.1, which states that surveillances do not have to be performed on inoperable equipment.

When equipment is inoperable, SR 4.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified Frequency does not result in an SR 4.0.4 restriction to changing MODES or other specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes. SR 4.0.4 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 4.0.3.

The provisions of SR 4.0.4 shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 4.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.

REACTOR COOLANT SYSTEM BASES SPECIFIC ACTIVITI (Continued)

ACTIONS

a. and b.

-FOR INFORMATION ONLY-Serial No.22-063 Docket No. 50-423, Page 7 of 15 LBDCRNo. 08-MP3-013 March 18, 2008 With the DOSE EQUIVALENT I-131 greater than the LCO limit, samples at intervals of four hours must be taken to demonstrate that the specific activity is ~ 60 µCi/gm. Four hours is required to obtain and analyze a sample. Sampling is continued every four hours to provide a trend The DOSE EQUfVALENTI-131 must be restored to within limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The completion time of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is acceptable since it is expected that, if there were an iodine spike, the normal coolant iodine concentration would be restored within this time period. Also, there is a low probability of a SLB or SGTR occurring during this time period A s,M@itHIU i1t.'.CTI@l I!. imli@M@!! tihd fl!'!! ieiotto of:bGQ iHU Ill'@ iti!t IIJlflli@ftl!h. +kifi Ui!ilfl&i8e &8 IsCQ ~ Q.1 flii-iw ~

-Hfi8 ~ii &flfllislllilil} IQQl!iEg~, P@':fitt§ 8R r' C1l@Tg a &tts This -N'l!!.ft8tt is acceptable due to the signific conservatism incorporated into the RCS specific activity 1

, he low probability of an event hich is lin1iting due to exceeding this limit, and the aliility to restore ient-specific activity e, ursions while the !ant remains at, or roceeds to POWER OPERATION.

..-,,-all.,..o_w_*~an_c_e_"....,

"A Note permits the use of provisions ofLCO 3.0.4.c. This allowance permits

~

into the applicable MODE(S) while relving on the ACTIONS."

If the required action and completion time of ACTION b. is not met, or if the DOSE EQUIVALENT I-131 is > 60 µCi/gm, the reactor must be brought to HOT STAi'lDBY (MODE 3) within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN (MODE 5) within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed completion times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

With the RCS DOSE EQUfVALENT XE-133 greater than the LCO limit, DOSE EQUIVALENT XE-133 must be restored to within limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The allowed completion time of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is acceptable since it is expected that, if there were a noble gas spike, the nonnal coolant noble gas concentration would be restored within this time period. Also, there is a low probability of a SLB or SGTR occurring during this time period.

_tr sttttcatcnt ht :\\0-HB~C cl. indicates the pto e isiwu of LOB J.B. t me not applicabtc. This cm

a tlrte appHeahle HQ,Ql)~il~, ul, i11~ an.'zQ'.RQ?' ti. A bile 41,t;i-l,il~,l!i,~~µ,1,;~~.. iliM!~8e-M.Q.ot1" -8fo;lttil., This lliiilllfl

table due to the sign to the RCS specific act probability of an event which is exceeding this limit, and the cific activity excursions t remains at, or proceeds to, POWER "allowance" MILLSTONE - UNIT 3 B 3/4 4-6a Amendment No.

"A Note pemiits the use of provisions ofLCO 3.0.4.c. This aUowance pemiits entry into the a licable MODE(S) while relying on the ACTIONS."

-FOR INFORMATION ONLY-REACTOR COOLANT SYSTEM BASES OVERPRESSURE PROTECTION SYSTEMS (continued)

APPLICABILITY Serial No.22-063 Docket No. 50-423, Page 8 of 15 LBDCRNo. 04-MP3-015 February 24, 2005 This LCO is applicable in MODE 4 when any RCS cold leg temperature is :5 226°F, in MODE 5, and in MODE 6 when the head is on the reactor vessel. The Pressurizer safety valves provide RCS overpressure protection in the ductile region (i.e., > 226°F). When the reactor head is off, overpressurization cannot occur.

LCO 3.4.9.1 "Pressure/Temperature Limits" provides the operational PIT limits for all MODES.

LCO 3.4.2, "Safety Valves," requires the OPERABILITY of the Pressurizer safety valves that provide overpressure protection during MODES 1, 2, and 3, and 4 when all RCS cold leg temperatures are> 226°F.

Low temperature overpressure prevention is most critical during shutdown when the RCS is water solid, and a mass or heat input transient can cause a rapid increase in RCS pressure when little or no time exists for operator action to mitigate the event.

AA~C~TI~O~N~S~---------7@SERTSC

-~

~

With two or more centrifugal charging pumps capable of injecting into the RCS, or with any SIH pump capable of injecting into the RCS, RCS overpressurization is possible.

To immediately initiate action to restore restricted mass input capability to the RCS reflects the urgency ofremoving the RCS from this condition.

Required ACTION a is modified by a Note that permits two centrifugal charging pumps capable of RCS injection for :5 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to allow for pump swaps. This is a controlled evolution of short duration and the procedure prevents having two charging pumps simultaneously out ofpull-to-lock while both charging pumps are capable of injecting into the RCS.

In MODE 4 when any RCS cold leg temperature is :5 226°F, with one required relief valve inoperable, the RCS relief valve must be restored to OPERABLE status within an allowed outage time (AOT) of7 days. Two relief valves in any combination of the PORVs and the RHR suction relief valves are required to provide low temperature overpressure mitigation while withstanding a single failure of an active component.

!-.flLLSTONE - UNIT 3 B 3/4 4-23 Amendment No. Hf, -19'.7, Acknowledged by NRC letter dated 08/25/05

INSERT SC Serial No.22-063 Docket No. 50-423, Page 9 of 15 A Note prohibits the application of LCO 3.0.4.b to inoperable Cold Overpressure Protection. There is an increased risk associated with entering MODE 4 from MODE 5 with Cold Overpressure Protection inoperable and the provisions of LCO 3.0.4.b, which allow 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, should not be applied in this circumstance.

-FOR INFORMATION ONLY-EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)

Serial No.22-063 Docket No. 50-423, Page 1 0 of 15 LBDCRNo. 14-MP3-011 January 8, 2015 With less than 4 OPERABLE heaters in either train, the corresponding train of charging is inoperable. This condition will require entry into the applicable ACTION statement for LCOs 3.5.2 and 3.5.3.

--ilNSERT 5D I

~

LCO 3.5.2 ACTION statement "b", and LCO 3.5.3 ACTION statement "c" address special reporting requirements in response to ECCS actuation with water injection to the RCS.

The special report completion is not a requirement for logging out of the ACTION statements that require the reports.

3/4.5.4 REFUELING WATER STORAGE TAl'H<

The OPERABILITY of the refueling water storage tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limits on RWST minimum volume and boron concentration ensure that: (I) sufficient water is available within containment to permit recirculation cooling flow to the core, and (2) the reactor will remain subcritical in the cold condition following a large break (LB)

LOCA, assuming mixing of the RWST, RCS, ECCS water, and other sources of water that may eventually reside in the sump, with all control rods assumed to be out. These assumptions are consistent with the LOCA analyses.

The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.0 and 7.5 for the solution recirculated within containment after a LOCA.

This pH band minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

The minimum and maximum solution temperatures for the RWST in MODES 1, 2, 3 and 4 are based on the following:

The 42°F minimum and 73°F maximum solution temperature values identified within the Technical Specifications include an operational margin of2°F (e.g., me.asurement uncertainties, analytical uncertainties, and design uncertainties) from values used in accident analysis/piping stress analysis. Accident analy-sis/piping stress analysis used 40°F and 75°F for the minimum and maximum RWST solution temperature.

O.HLLSTONE - UNIT 3 B 3/4 5-2f Amendment No.

INSERT 5D Serial No.22-063 Docket No. 50-423, Page 11 of 15 A Note prohibits the application of LCO 3.0.4.b to an inoperable ECCS high pressure safety injection subsystem when entering MODE 4. There is an increased risk associated with entering MODE 4 from MODE 5 with an inoperable ECCS high pressure safety injection subsystem and the provisions of LCO 3.0.4.b, which allow 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, should not be applied in this circumstance.

-FOR INFORMATION ONLY-PLAi~T SYSTEMS BASES AUXILIARY FEEDWATER SYSTEM (Continued)

Serial No.22-063 Docket No. 50-423, Page 12 of 15 LBDCR 14-MP3-006 July 8, 2014 In addition, given the worst case failure, the AFW is designed to supply sufficient makeup water to replace SG inventory loss as the RCS is cooled to less than 350°F at which point the Residual Heat Removal System may be placed into operation.

Motor driven auxiliary feedwater pumps and associated flow paths are OPERABLE in the following alignment during normal operation below l 0% RATED THER.i\\,lAL POWER.

Motor operated isolation valves (3FWA *MOV35A/B/C/D) are open in MODE 1, 2 and 3, Control valves (3FWA*HV31A/B/C/D) may be throttled or closed during alignment, operation and restoration of the associated motor driven AFW pump for steam generator inventory control.

The motor operated isolation valves must remain fully open due to single failure criteria (the valves and associated pump are powered from the opposite electrical trains).

The Turbine Driven Auxiliary Feedwater (TDAFW) pump and associated flow paths are OPERABLE with all control and isolation valves fully open in MODE 1, 2 and 3. Due to High Energy Line Break analysis, the TDAFW pump cannot be used for steam generator inventory control during normal operation below 10% RATED THER.ivl-\\L POWER.

At MPS 3, only two of the three available steam supplies are required to establish an OPERABLE steam supply system. With one of the two required steam supplies inoperable, normally the third steam supply will be used to satisfy the requirement for two OPERABLE steam supplies. If the third steam supply is also inoperable (i.e., only one steam supply to the turbine-driven auxilifil feedwaler pump is OPERABLE), then ACTION a. is entered.

INSERT 5E !

If the turbine-driven auxiliary feedwater pump is inoperable due to one required steam supply being inoperable in MODES 1, 2, and 3, or if a turbine-driven auxiliary feedwater pump is inoperable while in MODE 3 immediately following REFUELING, action must be taken to restore the inoperable equipment to an OPERABLE status within 7 days. The 7 day allowed outage time is reasonable, based on the following reasons:

MILLSTONE - UNIT 3 B 3/4 7-2a Amendment No.~. -89, HO,

INSERT 5E Serial No.22-063 Docket No. 50-423, Page 13 of 15 A Note prohibits the application of LCO 3.0.4.b to an inoperable AFW train. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an AFW train inoperable and the provisions of LCO 3.0.4.b, which allow 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, should not be applied in this circumstance.

-FOR INFORMATION ONLY-3/4.8 ELECTRICAL POWER SYSTEMS BASES Serial No.22-063 Docket No. 50-423, Page 14 of 15 LBDCRNo. 04-MP3-015 Febmary 24, 2005 longer under the time constraint imposed while in ACTION Statements b.2 or c.2.

The determination of the existence of a common cause failure that would affect the remaining diesel generator will require an evaluation of the current failure and the applicability to the remaining diesel generator. Examples that would not be a common cause failure include, but are not limited to:

I.

Preplanned preventative maintenance or testing; or

2.

An inoperable support system with no potential common mode failure for the remaining diesel generator; or

3.

An independently testable component with no potential common mode failure for the remaining diesel generq.,tto

.,,...,r ___ _

(

-!INSERT 5F I When one diesel generator is inoperable, there is an additional ACTION requirement (b.3 and c.3) to verify that all required systems, subsystems, trains, components and devices, that depend on the remaining OPERABLE diesel generator as a source of emergency power, are also OPERABLE, and that the steam-driven auxiliary feedwater pump is OPERABLE. This requirement is intended to provide assurance that a loss-of-offsite power event will not result in a complete loss of safety function of critical systems during the period one of the diesel generators is inoperable. The term, verify, as used in this context means to administratively check by examining logs or other information to determine if certain components are out-of-service for maintenance or other reasons. It does not mean to perform the Surveillance Requirements needed to demonstrate the OPERABILITY of the component.

If one Millstone Unit No. 3 diesel generator is inoperable in MODES 1 through 4, a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months allowed outage time is provided by ACTION Statement b.5 to allow restoration of the diesel generator, provided the requirements of ACTION Statements b.l, b.2, and b.3 are met. This allowed outage time can be extended to 14 days if the additional requirements contained in ACTION Statement b.4 are also met. ACTION Statement b.4 requires verification that the Millstone Unit No. 2 diesel generators are OPERABLE as required by the applicable Millstone Unit No. 2 Teclmical Specification (2 diesel generators in MODES 1 through 4, and 1 diesel generator in !ODES 5 and 6) and the Millstone Unit No. 3 SBO diesel generator is available.

The term verif)', as used in this context, means to administratively check by examining logs or other information to detemune if the required Millstone Unit No. 2 diesel generators and the

Millstone Unit No. 3 SBO diesel generator are out of service for maintenance or other reasons. It does not mean to perform Surveillance Requirements needed to demonstrate the OPERABILITY of the required Millstone Unit No. 2 diesel generators or availability of the Millstone Unit No. 3 SBO diesel generator.

When using the 14 day allowed outage time provision and the Millstone Unit No. 2 diesel generator requirements and/or l\\Iillstone Unit No. 3 SBO diesel generator requirements are not met, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is allowed for restoration of the required Millstone Unit No. 2 diesel generators and the Millstone Unit No. 3 SBO diesel generator. If any of the required Millstone Unit No. 2 diesel generators and/or Millstone Unit No. 3 SBO diesel generator are not restored within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and one Millstone Unit No. 3 diesel generator is still inoperable, Millstone Unit No. 3 is required to shut down.

MILLSTONE - UNIT 3 B 3/4 8-la Amendment No. -l-H, UG, Acknowledged by NRC letter dated 08/25/05

INSERT 5F Serial No.22-063 Docket No. 50-423, Page 15 of 15 A Note prohibits the application of LCO 3.0.4.b to an inoperable diesel generator. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an inoperable diesel generator and the provisions of LCO 3.0.4.b, which allow 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, should not be applied in this circumstance.

LIST OF REGULATORY COMMITMENTS Serial No.22-063 Docket Nos. 50-336/423 Dominion Energy Nuclear Connecticut, Inc.

Millstone Power Station Units 2 and 3

Serial No.22-063 Docket Nos. 50-336/423, Page 1 of 1 REGULATORY COMMITMENTS The following action is committed to by Dominion Energy Nuclear Connecticut, Inc.

(DENG) in this Millstone Power Station Unit 2 (MPS2) and Unit 3 (MPS3) License Amendment Request (LAR).

All other intended or planned actions in the LAR are provided for information only and are not regulatory commitments.

Commitment Scheduled Completion Date DENG will establish the Technical Upon implementation of the license Specification Bases for LCO 3.0.4, and SR amendment.

4.0.4 for MPS2 and MPS3 as adopted with the applicable license amendment.

v t e Letter Sequence Request
EPID:L-2021-LLE-0045, TSTF-359, TSTF-269 (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance... Supplement, Supplement Administration Questions Answers Results Approval, Approval Other: ML22167A059, ML22196A395, ML22199A276, ML22199A277
MONTHYEAR2022-04-19 [Table View]

ML22096A221

Text

SUMMARY

2.0 ASSESSMENT

3.0 REGULATORY ANALYSIS

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