Text

Issuance of Amendment No. 206 TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
	ML21148A274
Person / Time
Site:	Monticello
Issue date:	07/12/2021
From:	Robert Kuntz; Plant Licensing Branch III
To:	Conboy T; Northern States Power Company, Minnesota
	Kuntz R
References
	EPID L-2020-LLA-0062
	Download: ML21148A274 (170)
	v • d • e

July 12, 2021 Mr. Thomas A. Conboy Site Vice President Northern States Power Company - Minnesota Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT - ISSUANCE OF AMENDMENT NO. 206 RE: TSTF-505, REVISION 2, PROVIDE RISK-INFORMED EXTENDED COMPLETION TIMES - RITSTF INITIATIVE 4b (EPID L-2020-LLA-0062)

Dear Mr. Conboy:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 206 to Renewed Facility Operating License No. DPR-22, for the Monticello Nuclear Generating Plant. The amendment consists of changes to the technical specifications (TSs) in response to your application dated March 30, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20090F820), as supplemented by letters dated December 21, 2020 (ADAMS Accession No. ML20356A131), April 20, 2021 (ADAMS Accession No. ML21110A666), and June 30, 2021 (ADAMS Accession No. ML21181A308).

The amendment revises TS requirements to permit the use of risk-informed completion times (RICTs) for actions to be taken when limiting conditions for operation (LCOs) are not met.

The proposed changes are based on Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.

T. Conboy A copy of the Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.

Sincerely,

/RA/

Robert F. Kuntz, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-263

Enclosure:

1. Amendment No. 206 to DPR-22

2. Safety Evaluation cc: Listserv

NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 206 Renewed License No. DPR-22

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Northern States Power Company dated March 30, 2020, as supplemented by letters dated December 21, 2020, April 20, 2021, and June 30, 2021, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

Enclosure 1

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-22 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 206, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 180 days of the date of issuance. The implementation of the amendment shall include the items listed in Table A5-1, RICT Program PRA Implementation Items of the Northern States Power Company letter dated April 20, 2021.

FOR THE NUCLEAR REGULATORY COMMISSION Digitally signed by Nancy Nancy L. L. Salgado Date: 2021.07.12 Salgado 15:24:14 -04'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: July 12, 2021

ATTACHMENT TO LICENSE AMENDMENT NO. 206 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Renewed Facility Operating License No. DPR-22 Replace the following page of the Renewed Facility Operating License No. DPR-22 with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.

INSERT REMOVE Page 3 Page 3 Technical Specifications Replace the following pages of Appendix A, Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

INSERT REMOVE INSERT REMOVE INSERT REMOVE 1.3-11 1.3-11 3.3.4.1-2 3.3.4.1-2 3.5.1-1 3.5.1-1 1.3-12 -------- 3.3.4.1-3 3.3.4.1-3 3.5.1-2 3.5.1-2 3.1.7-1 3.1.7-1 3.3.4.1-4 -------- 3.5.1-3 3.5.1-3 3.1.7-2 3.1.7-2 3.3.5.1-2 3.3.5.1-2 3.5.1-4 3.5.1-4 3.1.7-3 3.1.7-3 3.3.5.1-3 3.3.5.1-3 3.5.1-5 3.5.1-5 3.1.7-4 3.1.7-4 3.3.5.1-4 3.3.5.1-4 3.5.1-6 3.5.1-6 3.1.7-5 3.1.7-5 3.3.5.1-5 3.3.5.1-5 3.5.1-7 3.5.1-7 3.1.7-6 3.1.7-6 3.3.5.1-6 3.3.5.1-6 3.5.1-8 3.5.1-8 3.1.7-7 -------- 3.3.5.1-7 3.3.5.1-7 3.5.1-9 --------

3.3.1.1-1 3.3.1.1-1 3.3.5.1-8 3.3.5.1-8 3.5.3-1 3.5.3-1 3.3.1.1-2 3.3.1.1-2 3.3.5.1-9 3.3.5.1-9 3.6.1.2-3 3.6.1.2-3 3.3.1.1-3 3.3.1.1-3 3.3.5.1-10 3.3.5.1-10 3.6.1.3-1 3.6.1.3-1 3.3.1.1-4 3.3.1.1-4 3.3.5.1-11 3.3.5.1-11 3.6.1.3-2 3.6.1.3-2 3.3.1.1-5 3.3.1.1-5 3.3.5.1-12 3.3.5.1-12 3.6.1.3-3 3.6.1.3-3 3.3.1.1-6 3.3.1.1-6 3.3.5.1-13 -------- 3.6.1.3-4 3.6.1.3-4 3.3.1.1-7 3.3.1.1-7 3.3.5.1-14 -------- 3.6.1.3-5 3.6.1.3-5 3.3.1.1-8 3.3.1.1-8 3.3.5.2-1 3.3.5.2-1 3.6.1.3-6 3.6.1.3-6 3.3.1.1-9 3.3.1.1-9 3.3.5.2-2 3.3.5.2-2 3.6.1.3-7 3.6.1.3-7 3.3.1.1-10 3.3.1.1-10 3.3.6.1-1 3.3.6.1-1 3.6.1.3-8 3.6.1.3-8 3.3.1.1-11 3.3.1.1-11 3.3.6.1-2 3.3.6.1-2 3.6.1.3-9 --------

3.3.1.1-12 -------- 3.3.7.2-1 3.3.7.2-1 3.6.1.3-10 --------

3.3.2.2-1 3.3.2.2-1 3.3.7.2-2 3.3.7.2-2 3.6.1.6-1 3.6.1.6-1 3.3.2.2-2 3.3.2.2-2 3.3.7.2-3 3.3.7.2-3 3.6.1.6-2 3.6.1.6-2 3.3.2.2-3 3.3.2.2-3 3.3.8.1-1 3.3.8.1-1 3.6.1.6-3 --------

3.3.4.1-1 3.3.4.1-1 3.4.3-1 3.4.3-1 3.6.1.7-1 3.6.1.7-1

INSERT REMOVE 3.6.1.8-1 3.6.1.8-1 3.6.1.8-2 3.6.1.8-2 3.6.2.3-1 3.6.2.3-1 3.6.2.3-2 3.6.2.3-2 3.7.1-1 3.7.1-1 3.7.1-2 3.7.1-2 3.7.2-1 3.7.2-1 3.7.2-2 3.7.2-2 3.7.2-3 ---------

3.8.1-1 3.8.1-1 3.8.1-2 3.8.1-2 3.8.1-3 3.8.1-3 3.8.1-4 3.8.1-4 3.8.1-5 3.8.1-5 3.8.1-6 3.8.1-6 3.8.1-7 3.8.1-7 3.8.1-8 3.8.1-8 3.8.1-9 3.8.1-9 3.8.1-10 3.8.1-10 3.8.1-11 ---------

2. Pursuant to the Act and 10 CFR Part 70, NSPM to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operations, as described in the Final Safety Analysis Report, as supplemented and amended, and the licensees filings dated August 16, 1974 (those portions dealing with handling of reactor fuel);

3. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;

4. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NSPM to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and

5. Pursuant to the Act and 10 CFR Parts 30 and 70, NSPM to possess, but not separate, such byproduct and special nuclear material as may be produced by operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission, now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

1. Maximum Power Level NSPM is authorized to operate the facility at steady state reactor core power levels not in excess of 2004 megawatts (thermal).

2. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 206, are hereby incorporated in the license. NSPM shall operate the facility in accordance with the Technical Specifications.

3. Physical Protection NSPM shall implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Amendment No. 206

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore subsystem 7 days subsystem to OPERABLE inoperable. status. OR In accordance with the Risk Informed Completion Time Program B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a subsystem is declared inoperable, Condition A is entered. The 7 day Completion Time may be applied as discussed in Example 1.3-2.

However, the licensee may elect to apply the Risk Informed Completion Time Program which permits calculation of a Risk Informed Completion Time (RICT) that may be used to complete the Required Action beyond the 7 day Completion Time. The RICT cannot exceed 30 days. After the 7 day Completion Time has expired, the subsystem must be restored to OPERABLE status within the RICT or Condition B must also be entered.

The Risk Informed Completion Time Program requires recalculation of the RICT to reflect changing plant conditions. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the plant configuration change, whichever is less.

If the 7 day Completion Time clock of Condition A has expired and subsequent changes in plant condition result in exiting the applicability of the Risk Informed Completion Time Program without restoring the inoperable subsystem to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start.

Monticello 1.3-11 Amendment No. 206

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

If the RICT expires or is recalculated to be less than the elapsed time since the Condition was entered and the inoperable subsystem has not been restored to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable subsystems are restored to OPERABLE status after Condition B is entered, Condition A is exited, and therefore, the Required Actions of Condition B may be terminated.

IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION TIME should be pursued without delay and in a controlled manner.

Monticello 1.3-12 Amendment No. 206

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of sodium A.1 Restore concentration of 7 days pentaborate in solution sodium pentaborate in not within limits of solution to within limits.

Figure 3.1.7-1 and Table 3.1.7-1 Equation 2, but available volume of sodium pentaborate solution is within limits of Table 3.1.7-1 Equation 1.

B. One SLC subsystem B.1 Restore SLC subsystem to 7 days inoperable for reasons OPERABLE status.

other than Condition A. OR In accordance with the Risk Informed Completion Time Program C. Two SLC subsystems C.1 Restore one SLC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for reasons subsystem to OPERABLE other than Condition A. status.

Monticello 3.1.7-1 Amendment No. 206

SLC System 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium pentaborate In accordance solution is within the limits of Figure 3.1.7-1 or with the Equation 1 of Table 3.1.7-1. Surveillance Frequency Control Program SR 3.1.7.2 Verify temperature of sodium pentaborate solution is In accordance within the limits of Figure 3.1.7-2. with the Surveillance Frequency Control Program SR 3.1.7.3 Verify temperature of room in the vicinity of the SLC In accordance pumps is within the solution temperature limits of with the Figure 3.1.7-2 or verify SLC pump suction lines heat Surveillance tracing is OPERABLE. Frequency Control Program SR 3.1.7.4 Verify continuity of explosive charge. In accordance with the Surveillance Frequency Control Program Monticello 3.1.7-2 Amendment No. 206

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.5 Verify the concentration of sodium pentaborate in In accordance solution is within the limits of Figure 3.1.7-1 or within with the the limits of Equation 2 of Table 3.1.7-1. Surveillance Frequency Control Program AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or sodium pentaborate is added to solution AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 SR 3.1.7.6 Verify each SLC subsystem manual valve in the flow In accordance path that is not locked, sealed, or otherwise secured with the in position is in the correct position, or can be Surveillance aligned to the correct position. Frequency Control Program SR 3.1.7.7 Verify each pump develops a flow rate 24 gpm at a In accordance discharge pressure 1275 psig. with the INSERVICE TESTING PROGRAM Monticello 3.1.7-3 Amendment No. 206

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.8 Verify flow through one SLC subsystem from pump In accordance into reactor pressure vessel. with the Surveillance Frequency Control Program SR 3.1.7.9 Verify all heat traced piping between storage tank In accordance and pump suction is unblocked. with the Surveillance Frequency Control Program AND

NOTE-------

Only required if SLC pump suction lines heat tracing is inoperable.

Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after room temperature in the vicinity of the SLC pumps is restored within the solution temperature limits of Figure 3.1.7-2 SR 3.1.7.10 Verify sodium pentaborate enrichment is Prior to addition 55.0 atom percent B-10. to SLC tank Monticello 3.1.7-4 Amendment No. 206

SLC System 3.1.7 Allowed Operation Sodium Pentaborate Concentration (Weight Percent, wt%)

(1167,13.0)

(1404,10.7)

Indicated Tank Volume (Gallons)

Figure 3.1.7-1 (page 1 of 1)

Sodium Pentaborate Solution Volume Versus Concentration Requirements Monticello 3.1.7-5 Amendment No. 206

SLC System 3.1.7 Allowed Operation Measured Solution Temperature (F)

Sodium Pentaborate in Solution (Weight Percent, wt%)

Figure 3.1.7-2 (page 1 of 1)

Sodium Pentaborate Solution Temperature Versus Concentration Requirements Monticello 3.1.7-6 Amendment No. 206

SLC System 3.1.7 Table 3.1.7-1 (page 1 of 1)

Equations for Required Sodium Pentaborate Tank Volume and Concentration Equation 1 71.18 4821 19.8 100 V 1 128 gal 0.0051 C + 0.998 1101 E E C Where:

C = measured boron solution concentration (wt%)

E = measured boron solution enrichment (atom%)

V = indicated boron solution tank volume (gal)

Equation 2 86 19.8 C 8.28 Q E Where:

C = measured boron solution concentration (wt%)

E = measured boron solution enrichment (atom%)

Q = measured pump flow rate (gpm) at 1275 psig Monticello 3.1.7-7 Amendment No. 206

RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.1-1.

ACTIONS

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

1. Separate Condition entry is allowed for each channel.

2. When the Function 2.b and 2.c channels are not within the limit of SR 3.3.1.1.2 due to APRM indication not within limits, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if the APRM is indicating a lower power value than the calculated power, and for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if the APRM is indicating a higher power value than the calculated power.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable.

OR In accordance with the Risk Informed Completion Time Program OR Monticello 3.3.1.1-1 Amendment No. 206

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 --------------NOTE------------- 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Not applicable for Functions 2.a, 2.b, 2.c, 2.d, OR 2.f or 2.g.

In accordance with Place associated trip the Risk Informed system in trip. Completion Time Program B. -----------NOTE------------ B.1 Place channel in one trip 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Not applicable for system in trip.

Functions 2.a, 2.b, 2.c, OR 2.d, 2.f or 2.g.

In accordance with One or more Functions the Risk Informed with one or more Completion Time required channels Program inoperable in both trip systems. OR B.2 Place one trip system in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months trip.

OR In accordance with the Risk Informed Completion Time Program C. One or more Functions C.1 Restore RPS trip capability. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with RPS trip capability not maintained.

Monticello 3.3.1.1-2 Amendment No. 206

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A, B, Table 3.3.1.1-1 for the or C not met. channel.

E. As required by Required E.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Action D.1 and POWER to 40% RTP.

referenced in Table 3.3.1.1-1.

F. As required by Required F.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action D.1 and referenced in AND Table 3.3.1.1-1.

F.2 --------------NOTE-------------

Only applicable to Function 5.

Reduce reactor pressure to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

< 600 psig.

G. As required by Required G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action D.1 and referenced in Table 3.3.1.1-1.

H. As required by Required H.1 Initiate action to fully insert Immediately Action D.1 and all insertable control rods in referenced in core cells containing one or Table 3.3.1.1-1. more fuel assemblies.

Monticello 3.3.1.1-3 Amendment No. 206

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required I.1 Initiate alternate method to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action D.1 and detect and suppress referenced in thermal hydraulic instability Table 3.3.1.1-1. oscillations.

AND I.2 -------------NOTE----------------

LCO 3.0.4 is not applicable Restore required channels 120 days to OPERABLE.

J. As required by Required J.1 Reduce THERMAL 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action D.1 and POWER below the referenced in MELLLA boundary defined Table 3.3.1.1-1. in the COLR.

K. Required Action and K.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to < 20% RTP.

Time of Condition I or J not met.

Monticello 3.3.1.1-4 Amendment No. 206

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.2 --------------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER 25% RTP.

Verify the absolute difference between the average In accordance with power range monitor (APRM) channels and the the Surveillance calculated power is 2% RTP while operating at Frequency Control 25% RTP. Program SR 3.3.1.1.3 --------------------------------NOTE-------------------------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Monticello 3.3.1.1-5 Amendment No. 206

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.4 Perform a functional test of each RPS automatic In accordance with scram contactor. the Surveillance Frequency Control Program SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.7 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Calibrate the trip units. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.9 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.10 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Monticello 3.3.1.1-6 Amendment No. 206

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.11 -------------------------------NOTES------------------------------

1. Neutron detectors are excluded.

2. For Function 1, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

3. For Functions 2.b and 2.f, the recirculation flow transmitters that feed the APRMs are included.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.12 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.13 Verify Turbine Stop Valve - Closure and Turbine In accordance with Control Valve Fast Closure, Acceleration Relay Oil the Surveillance Pressure - Low Functions are not bypassed when Frequency Control THERMAL POWER is > 40% RTP. Program SR 3.3.1.1.14 Verify the RPS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program Monticello 3.3.1.1-7 Amendment No. 206

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.15 -------------------------------NOTES------------------------------

1. For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

2. For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.16 Verify the oscillation power range monitor (OPRM) In accordance with function is not bypassed when APRM Simulated the Surveillance Thermal Power is 25% RTP and drive flow Frequency Control is 60% of rated drive flow. Program Monticello 3.3.1.1-8 Amendment No. 206

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 4)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1. Intermediate Range Monitors

a. Neutron Flux - High 2 3 G SR 3.3.1.1.1 122/125 High SR 3.3.1.1.3 divisions of full SR 3.3.1.1.4 scale SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.14 5(a) 3 H SR 3.3.1.1.1 122/125 SR 3.3.1.1.3 divisions of full SR 3.3.1.1.4 scale SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.14

b. Inop. 2 3 G SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.12 5(a) 3 H SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.12

2. Average Power Range Monitors

a. Neutron Flux - High, 2 3(c) G SR 3.3.1.1.1 20% RTP (Setdown) SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.11 SR 3.3.1.1.15

b. Simulated Thermal 1 3(c) F SR 3.3.1.1.1 0.61W Power - High SR 3.3.1.1.2 + 67.2% RTP(b)

SR 3.3.1.1.4 and 116% RTP SR 3.3.1.1.6 SR 3.3.1.1.11 SR 3.3.1.1.15 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.55 (W - Delta W) + 61.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." The cycle-specific value for Delta W is specified in the COLR.

(c) Each APRM / OPRM channel provides inputs to both trip systems.

Monticello 3.3.1.1-9 Amendment No. 206

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 4)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

c. Neutron Flux - High 1 3(c) F SR 3.3.1.1.1 122% RTP SR 3.3.1.1.2 SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.11(f)(g)

SR 3.3.1.1.15

d. Inop. 1, 2 3(c) G SR 3.3.1.1.4 NA SR 3.3.1.1.15

e. 2-Out-Of-4 Voter 1, 2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.4 SR 3.3.1.1.12 SR 3.3.1.1.14 SR 3.3.1.1.15

f. OPRM Upscale 20% RTP 3(c) I SR 3.3.1.1.1 As specified in SR 3.3.1.1.4 COLR SR 3.3.1.1.6 SR 3.3.1.1.11 SR 3.3.1.1.15 SR 3.3.1.1.16

g. Extended Flow Within EFW 3(c) J SR 3.3.1.1.1 As specified in Window Stability - boundary SR 3.3.1.1.2 COLR High defined in SR 3.3.1.1.4 COLR SR 3.3.1.1.6 SR 3.3.1.1.11 SR 3.3.1.1.15

3. Reactor Vessel Steam 1, 2 2 G SR 3.3.1.1.4 1075 psig Dome Pressure - High SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.14 (c) Each APRM / OPRM channel provides inputs to both trip systems.

(f) If the as-found channel setpoint is not the Nominal Trip Setpoint but is conservative with respect to the Allowable Value, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(g) The instrument channel setpoint shall be reset to the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. The NTSP and the methodology used to determine the NTSP are specified in the Technical Requirements Manual.

Monticello 3.3.1.1-10 Amendment No. 206

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 4)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

4. Reactor Vessel Water 1, 2 2 G SR 3.3.1.1.1 7 inches Level - Low SR 3.3.1.1.4 SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.14

5. Main Steam Isolation 1, 2(d) 8 F SR 3.3.1.1.4 10% closed Valve - Closure SR 3.3.1.1.7 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.14

6. Drywell Pressure - High 1, 2 2 G SR 3.3.1.1.4 2.0 psig SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12

7. Scram Discharge Volume Water Level -

High

a. Resistance 1, 2 2 G SR 3.3.1.1.4 56.0 gallons Temperature SR 3.3.1.1.7 Detector SR 3.3.1.1.9 SR 3.3.1.1.12 5(a) 2 H SR 3.3.1.1.4 56.0 gallons SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12

b. Float Switch 1, 2 2 G SR 3.3.1.1.4 56.0 gallons SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12 5(a) 2 H SR 3.3.1.1.4 56.0 gallons SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(d) With reactor pressure 600 psig.

Monticello 3.3.1.1-11 Amendment No. 206

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 4 of 4)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

8. Turbine Stop Valve - > 40% RTP 4 E SR 3.3.1.1.4 10% closed Closure SR 3.3.1.1.7 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.14

9. Turbine Control Valve > 40% RTP 2 E SR 3.3.1.1.4 167.8 psig Fast Closure, SR 3.3.1.1.7 Acceleration Relay Oil SR 3.3.1.1.9 Pressure - Low SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.14

10. Reactor Mode Switch - 1, 2 1 G SR 3.3.1.1.10 NA Shutdown Position SR 3.3.1.1.12 5(a) 1 H SR 3.3.1.1.10 NA SR 3.3.1.1.12

11. Manual Scram 1, 2 1 G SR 3.3.1.1.5 NA SR 3.3.1.1.12 5(a) 1 H SR 3.3.1.1.5 NA SR 3.3.1.1.12 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

Monticello 3.3.1.1-12 Amendment No. 206

Feedwater Pump and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater Pump and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 Four channels of Feedwater Pump and Main Turbine High Water Level Trip Instrumentation shall be OPERABLE.

APPLICABILITY: THERMAL POWER 25% RTP.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more feedwater A.1 Place channel in trip. 7 days pump and main turbine high water level trip OR channels inoperable.

In accordance with the Risk Informed Completion Time Program B. Feedwater pump and B.1 Restore feedwater pump 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months main turbine high water and main turbine high water level trip capability not level trip capability.

maintained.

Monticello 3.3.2.2-1 Amendment No. 206

Feedwater Pump and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 ----------NOTE-------------------

associated Completion Only applicable if Time not met. inoperable channel is the result of inoperable feedwater pump breaker or main turbine stop valve.

Remove affected feedwater 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months pump(s) and main turbine valve(s) from service.

OR C.2 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 25% RTP.

SURVEILLANCE REQUIREMENTS

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

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided feedwater pump and main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.2.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Monticello 3.3.2.2-2 Amendment No. 206

Feedwater Pump and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.2.3 Calibrate the trip units. In accordance with the Surveillance Frequency Control Program SR 3.3.2.2.4 Perform CHANNEL CALIBRATION. The Allowable In accordance with Value shall be 49 inches. the Surveillance Frequency Control Program SR 3.3.2.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST In accordance with including valve and breaker actuation. the Surveillance Frequency Control Program Monticello 3.3.2.2-3 Amendment No. 206

ATWS-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)

Instrumentation LCO 3.3.4.1 Two channels per trip system for each ATWS-RPT instrumentation Function listed below shall be OPERABLE:

a. Reactor Vessel Water Level - Low Low; and

b. Reactor Vessel Steam Dome Pressure - High.

APPLICABILITY: MODE 1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 14 days inoperable. OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program OR Monticello 3.3.4.1-1 Amendment No. 206

ATWS-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 ---------------NOTE--------------

Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in trip. 14 days OR In accordance with the Risk Informed Completion Time Program B. One Function with B.1 Restore ATWS-RPT trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ATWS-RPT trip capability.

capability not maintained.

C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS-RPT trip capability for one Function.

capability not maintained.

D. Required Action and D.1 ---------------NOTE--------------

associated Completion Only applicable if Time not met. inoperable channel is the result of an inoperable breaker.

Remove the affected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months recirculation pump from service.

OR D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Monticello 3.3.4.1-2 Amendment No. 206

ATWS-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS

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

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 --------------------------------NOTE-------------------------------

Not required for the time delay portion of the Reactor Vessel Water Level - Low Low Function.

Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.4.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.4.1.3 Calibrate the trip units. In accordance with the Surveillance Frequency Control Program SR 3.3.4.1.4 Perform CHANNEL CALIBRATION of Reactor In accordance with Vessel Water Level - Low Low time delay relays. the Surveillance The Allowable Value shall be 6 seconds and Frequency Control 8.6 seconds. Program Monticello 3.3.4.1-3 Amendment No. 206

ATWS-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.1.5 Perform CHANNEL CALIBRATION. The Allowable In accordance with Values shall be: the Surveillance Frequency Control

a. Reactor Vessel Water Level - Low Low Program

-48 inches; and

b. Reactor Vessel Steam Dome Pressure - High 1155 psig.

SR 3.3.4.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST In accordance with including breaker actuation. the Surveillance Frequency Control Program Monticello 3.3.4.1-4 Amendment No. 206

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2 ---------------NOTE--------------

Only applicable for Functions 3.a and 3.b.

Declare High Pressure 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery Coolant Injection (HPCI) of loss of HPCI System inoperable. initiation capability AND B.3 Place channel in trip. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR

NOTE----------

Not applicable when a loss of function occurs.

In accordance with the Risk Informed Completion Time Program C. As required by Required C.1 --------------NOTE-------------

Action A.1 and Only applicable for referenced in Functions 1.c, 1.d, 1.e, 1.f, Table 3.3.5.1-1. 2.c, 2.d, 2.e, 2.i, 2.j, 2.l, and 2.m.

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery feature(s) inoperable when of loss of initiation its redundant feature ECCS capability for initiation capability is feature(s) in both inoperable. divisions AND Monticello 3.3.5.1-2 Amendment No. 206

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR

NOTE----------

Not applicable when a loss of function occurs.

In accordance with the Risk Informed Completion Time Program D. As required by Required D.1 ---------------NOTE--------------

Action A.1 and Only applicable if HPCI referenced in pump suction is not aligned Table 3.3.5.1-1. to the suppression pool.

Declare HPCI System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery inoperable. of loss of HPCI initiation capability AND D.2.1 Place channel in trip. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR

NOTE----------

Not applicable when a loss of function occurs.

In accordance with the Risk Informed Completion Time Program OR Monticello 3.3.5.1-3 Amendment No. 206

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.2.2 Align the HPCI pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months suction to the suppression pool.

E. As required by Required E.1 --------------NOTE-------------

Action A.1 and Only applicable for referenced in Function 2.g.

Table 3.3.5.1-1. ------------------------------------

Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery feature(s) inoperable when of loss of initiation its redundant feature capability for ECCS initiation capability is subsystems in both inoperable. divisions AND E.2 Restore channel to 7 days OPERABLE status.

OR

NOTE---------

Not applicable when a loss of function occurs.

In accordance with the Risk Informed Completion Time Program Monticello 3.3.5.1-4 Amendment No. 206

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required F.1 Declare Automatic 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery Action A.1 and Depressurization System of loss of ADS referenced in (ADS) valves inoperable. initiation capability in Table 3.3.5.1-1. both trip systems AND F.2 Place channel in trip. -----------NOTE---------

Risk Informed Completion Time Program not applicable to loss of function.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable AND 8 days or in accordance with the Risk Informed Completion Time Program G. As required by Required G.1 Declare ADS valves 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery Action A.1 and inoperable. of loss of ADS referenced in initiation capability in Table 3.3.5.1-1. both trip systems AND Monticello 3.3.5.1-5 Amendment No. 206

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G.2 Restore channel to -----------NOTE---------

OPERABLE status. Risk Informed Completion Time Program not applicable to loss of function.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months or in accordance with the Risk Informed Completion Time Program from discovery of inoperable channel concurrent with HPCI or RCIC inoperable AND 8 days or in accordance with the Risk Informed Completion Time Program H. Required Action and H.1 Declare associated Immediately associated Completion supported feature(s)

Time of Condition B, C, inoperable.

D, E, F, or G not met.

Monticello 3.3.5.1-6 Amendment No. 206

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c and 3.f; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.3 Calibrate the trip unit. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.5 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.6 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program Monticello 3.3.5.1-7 Amendment No. 206

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.5.1.7 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.8 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.9 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Monticello 3.3.5.1-8 Amendment No. 206

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Core Spray System

a. Reactor Vessel 1, 2, 3 4(a) B SR 3.3.5.1.1 -48 inches Water Level - Low SR 3.3.5.1.2 Low SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

b. Drywell Pressure - 1, 2, 3 4(a) B SR 3.3.5.1.2 2 psig High SR 3.3.5.1.4 SR 3.3.5.1.8

c. Reactor Steam 1, 2, 3 2 C SR 3.3.5.1.2 397 psig and Dome Pressure - SR 3.3.5.1.4(b)(c) 440 psig Low (Injection SR 3.3.5.1.8 Permissive)

d. Reactor Steam 1, 2, 3 2 C SR 3.3.5.1.2 397 psig Dome Pressure SR 3.3.5.1.4(b)(c)

Permissive - Low SR 3.3.5.1.8 (Pump Permissive)

e. Reactor Steam 1, 2, 3 2 C SR 3.3.5.1.7 18 minutes Dome Pressure SR 3.3.5.1.8 Permissive - Bypass Timer (Pump Permissive)

(a) Also required to initiate the associated emergency diesel generator (EDG).

(b) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the Technical Requirements Manual (TRM).

Monticello 3.3.5.1-9 Amendment No. 206

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Core Spray System

f. Core Spray Pump 1, 2, 3 1 per pump C SR 3.3.5.1.7 15.86 Start - Time Delay SR 3.3.5.1.8 seconds Relay

2. Low Pressure Coolant Injection (LPCI) System

a. Reactor Vessel 1, 2, 3 4 B SR 3.3.5.1.1 -48 inches Water Level - Low SR 3.3.5.1.2 Low SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

b. Drywell Pressure - 1, 2, 3 4 B SR 3.3.5.1.2 2 psig High SR 3.3.5.1.4 SR 3.3.5.1.8

c. Reactor Steam 1, 2, 3 2 C SR 3.3.5.1.2 397 psig and Dome Pressure - SR 3.3.5.1.4(b)(c) 440 psig Low (Injection SR 3.3.5.1.8 Permissive)

d. Reactor Steam 1, 2, 3 2 C SR 3.3.5.1.2 397 psig Dome Pressure SR 3.3.5.1.4(b)(c)

Permissive - Low SR 3.3.5.1.8 (Pump Permissive)

(b) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.

Monticello 3.3.5.1-10 Amendment No. 206

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. LPCI System

e. Reactor Steam 1, 2, 3 2 C SR 3.3.5.1.7 18 minutes Dome Pressure SR 3.3.5.1.8 Permissive - Bypass Timer (Pump Permissive)

f. Low Pressure 1, 2, 3 4 per pump B SR 3.3.5.1.7 Coolant Injection SR 3.3.5.1.8 Pump Start - Time Delay Relay Pumps A, B 5.33 seconds Pumps C, D 10.59 seconds

g. Low Pressure 1, 2, 3 1 per pump E SR 3.3.5.1.2 360 gpm and Coolant Injection SR 3.3.5.1.7 745 gpm Pump Discharge SR 3.3.5.1.8 Flow - Low (Bypass)

h. Reactor Steam 1, 2, 3 4 B SR 3.3.5.1.2 873.6 psig Dome Pressure - SR 3.3.5.1.7 and Low (Break SR 3.3.5.1.8 923.4 psig Detection)

i. Recirculation Pump 1, 2, 3 4 per pump C SR 3.3.5.1.2 63.5 inches Differential Pressure SR 3.3.5.1.7 wc

- High (Break SR 3.3.5.1.8 Detection)

j. Recirculation Riser 1, 2, 3 4 C SR 3.3.5.1.2 100.0 inches Differential Pressure SR 3.3.5.1.7(b)(c) wc

- High (Break SR 3.3.5.1.8 Detection)

(b) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.

Monticello 3.3.5.1-11 Amendment No. 206

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. LPCI System

k. Reactor Steam 1, 2, 3 2 B SR 3.3.5.1.7 2.97 seconds Dome Pressure - SR 3.3.5.1.8 Time Delay Relay SR 3.3.5.1.9 (Break Detection)

l. Recirculation Pump 1, 2, 3 2 C SR 3.3.5.1.7 0.75 seconds Differential Pressure SR 3.3.5.1.8

- Time Delay Relay SR 3.3.5.1.9 (Break Detection)

m. Recirculation Riser 1, 2, 3 2 C SR 3.3.5.1.7 0.75 seconds Differential Pressure SR 3.3.5.1.8

- Time Delay Relay SR 3.3.5.1.9 (Break Detection)

3. High Pressure Coolant Injection (HPCI) System

a. Reactor Vessel 1, 2(d), 3(d) 4 B SR 3.3.5.1.1 -48 inches Water Level - Low SR 3.3.5.1.2 Low SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

b. Drywell Pressure - 1, 2(d), 3(d) 4 B SR 3.3.5.1.2 2 psig High SR 3.3.5.1.4 SR 3.3.5.1.8

c. Reactor Vessel 1, 2(d), 3(d) 2 C SR 3.3.5.1.1 48 inches Water Level - High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

d. Condensate Storage 1, 2(d), 3(d) 2 D SR 3.3.5.1.7 29.3 inches Tank Level - Low SR 3.3.5.1.8

e. Suppression Pool 1, 2(d), 3(d) 2 D SR 3.3.5.1.5 3.0 inches Water Level - High SR 3.3.5.1.6 SR 3.3.5.1.8

f. High Pressure 1, 2(d), 3(d) 1 E SR 3.3.5.1.5 362 gpm and Coolant Injection SR 3.3.5.1.6 849 gpm Pump Discharge SR 3.3.5.1.8 Flow - Low (Bypass)

(d) With reactor steam dome pressure > 150 psig.

Monticello 3.3.5.1-12 Amendment No. 206

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 -48 inches Water Level - Low SR 3.3.5.1.2 Low SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

b. Automatic 1, 2(d), 3(d) 1 G SR 3.3.5.1.7 120 seconds Depressurization SR 3.3.5.1.8 System Initiation Timer

c. Core Spray Pump 1, 2(d), 3(d) 2 G SR 3.3.5.1.2 75 psig and Discharge Pressure SR 3.3.5.1.4(b)(c) 125 psig

- High SR 3.3.5.1.8

d. Low Pressure 1, 2(d), 3(d) 4 G SR 3.3.5.1.2 75 psig and Coolant Injection SR 3.3.5.1.4(b)(c) 125 psig Pump Discharge SR 3.3.5.1.8 Pressure - High

5. ADS Trip System B

a. Reactor Vessel 1, 2(d), 3(d) 2 F SR 3.3.5.1.1 -48 inches Water Level - Low SR 3.3.5.1.2 Low SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

b. Automatic 1, 2(d), 3(d) 1 G SR 3.3.5.1.7 120 seconds Depressurization SR 3.3.5.1.8 System Initiation Timer (b) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.

(d) With reactor steam dome pressure > 150 psig.

Monticello 3.3.5.1-13 Amendment No. 206

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 6 of 6)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQUIRED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

5. ADS Trip System B

c. Core Spray Pump 1, 2(d), 3(d) 2 G SR 3.3.5.1.2 75 psig and Discharge Pressure SR 3.3.5.1.4(b)(c) 125 psig

- High SR 3.3.5.1.8

d. Low Pressure 1, 2(d), 3(d) 4 G SR 3.3.5.1.2 75 psig and Coolant Injection SR 3.3.5.1.4(b)(c) 125 psig Pump Discharge SR 3.3.5.1.8 Pressure - High (b) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.

(d) With reactor steam dome pressure > 150 psig.

Monticello 3.3.5.1-14 Amendment No. 206

RCIC System Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.2 The RCIC System instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable. referenced in Table 3.3.5.2-1 for the channel.

B. As required by Required B.1 Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery Action A.1 and inoperable. of loss of RCIC referenced in initiation capability Table 3.3.5.2-1.

AND B.2 Place channel in trip. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR

NOTE----------

Not applicable when a loss of function occurs.

In accordance with the Risk Informed Completion Time Program Monticello 3.3.5.2-1 Amendment No. 206

RCIC System Instrumentation 3.3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. As required by Required C.1 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Action A.1 and OPERABLE status.

referenced in Table 3.3.5.2-1.

D. As required by Required D.1 ---------------NOTE-------------

Action A.1 and Only applicable if RCIC referenced in pump suction is not aligned Table 3.3.5.2-1. to the suppression pool.

Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery inoperable. of loss of RCIC initiation capability AND D.2.1 Place channel in trip. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR

NOTE---------

Not applicable when a loss of function occurs.

In accordance with the Risk Informed Completion Time Program OR D.2.2 Align RCIC pump suction 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the suppression pool.

E. Required Action and E.1 Declare RCIC System Immediately associated Completion inoperable.

Time of Condition B, C, or D not met.

Monticello 3.3.5.2-2 Amendment No. 206

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.1-1.

ACTIONS

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

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or in channels inoperable. accordance with the Risk Informed Completion Time Program for Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or in accordance with the Risk Informed Completion Time Program for Functions other than Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b B. One or more Functions B.1 Restore primary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with primary containment isolation containment isolation capability.

capability not maintained.

Monticello 3.3.6.1-1 Amendment No. 206

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A Table 3.3.6.1-1 for the or B not met. channel.

D. As required by Required D.1 Isolate associated main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action C.1 and steam line (MSL).

referenced in Table 3.3.6.1-1. OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. As required by Required E.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and referenced in Table 3.3.6.1-1.

F. As required by Required F.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and penetration flow path(s).

referenced in Table 3.3.6.1-1.

G. As required by Required G.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Action C.1 and penetration flow path(s).

referenced in Table 3.3.6.1-1.

H. As required by Required H.1 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and standby liquid control referenced in (SLC) subsystem Table 3.3.6.1-1. inoperable.

OR H.2 Isolate the Reactor Water 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Cleanup System.

Monticello 3.3.6.1-2 Amendment No. 206

Mechanical Vacuum Pump Isolation Instrumentation 3.3.7.2 3.3 INSTRUMENTATION 3.3.7.2 Mechanical Vacuum Pump Isolation Instrumentation LCO 3.3.7.2 Four channels of the Main Steam Line Tunnel Radiation - High Function for the mechanical vacuum pump isolation shall be OPERABLE.

APPLICABILITY: MODES 1 and 2 with the mechanical vacuum pump in service and any main steam line not isolated.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable. OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program OR A.2 --------------NOTE---------------

Not applicable if inoperable channel is the result of an inoperable mechanical vacuum pump breaker or isolation valve.

Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR In accordance with the Risk Informed Completion Time Program Monticello 3.3.7.2-1 Amendment No. 206

Mechanical Vacuum Pump Isolation Instrumentation 3.3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Mechanical vacuum B.1 Restore mechanical vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months pump isolation capability pump isolation capability not maintained.

C. Required Action and C.1 Isolate the mechanical 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion vacuum pump.

Time not met.

OR C.2 Isolate the main steam lines. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR C.3 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS

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

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains mechanical vacuum pump isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.7.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.2.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program Monticello 3.3.7.2-2 Amendment No. 206

Mechanical Vacuum Pump Isolation Instrumentation 3.3.7.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.7.2.3 Perform CHANNEL CALIBRATION. The Allowable In accordance with Value Shall be 6.9 R/hour. the Surveillance Frequency Control Program SR 3.3.7.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST, In accordance with including mechanical vacuum pump breaker and the Surveillance isolation valves actuation. Frequency Control Program Monticello 3.3.7.2-3 Amendment No. 206

LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3 ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

OR

NOTE----------

Not applicable when a loss of function occurs.

In accordance with the Risk Informed Completion Time Program B. Required Action and B.1 Declare associated EDG Immediately associated Completion inoperable.

Time not met.

Monticello 3.3.8.1-1 Amendment No. 206

S/RVs 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety/Relief Valves (S/RVs)

LCO 3.4.3 The safety function of seven S/RVs shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Restore the required S/RVs 14 days S/RVs inoperable. to OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Three or more required S/RVs inoperable.

Monticello 3.4.3-1 Amendment No. 206

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

APPLICABILITY: MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.

ACTIONS

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

LCO 3.0.4.b is not applicable to HPCI.

CONDITION REQUIRED ACTION COMPLETION TIME A. One LPCI pump A.1 Restore LPCI pump to 30 days inoperable. OPERABLE status.

B. One LPCI subsystem B.1 Restore low pressure 7 days inoperable for reasons ECCS injection/spray other than Condition A. subsystem to OPERABLE OR status.

OR In accordance with the Risk Informed One Core Spray Completion Time subsystem inoperable. Program Monticello 3.5.1-1 Amendment No. 206

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One LPCI pump in both C.1 Restore one LPCI pump to 7 days LPCI subsystems OPERABLE status.

inoperable. OR In accordance with the Risk Informed Completion Time Program D. Two LPCI subsystems D.1 Restore one LPCI 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable for reasons subsystem to OPERABLE other than Condition C status. OR or G.

In accordance with the Risk Informed Completion Time Program E. One Core Spray E.1 Restore Core Spray 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem inoperable. subsystem to OPERABLE status. OR AND In accordance with the Risk Informed One LPCI subsystem Completion Time inoperable. Program OR OR One or two LPCI E.2 Restore LPCI subsystem to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pump(s) inoperable. OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program OR Monticello 3.5.1-2 Amendment No. 206

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.3 Restore LPCI pump(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program F. Required Action and F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, AND C, D, or E not met.

F.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. Two LPCI subsystems G.1 Isolate the RHR intertie 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months inoperable due to open line.

RHR intertie return line isolation valve(s).

H. Required Action and H.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition G not met.

Monticello 3.5.1-3 Amendment No. 206

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. HPCI System I.1 Verify by administrative Immediately inoperable. means RCIC System is OPERABLE.

AND I.2 Restore HPCI System to 14 days OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program J. HPCI System J.1 Restore HPCI System to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

OR AND In accordance with Condition A, B, or C the Risk Informed entered. Completion Time Program OR J.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ECCS injection/spray subsystem(s) to OR OPERABLE status.

In accordance with the Risk Informed Completion Time Program K. One ADS valve K.1 Restore ADS valve to 14 days inoperable. OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program Monticello 3.5.1-4 Amendment No. 206

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. Required Action and L.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition I, J, AND or K not met.

L.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR dome pressure to 150 psig.

One ADS valve inoperable and Condition A, B, C, D, or G entered.

OR Two or more ADS valves inoperable.

OR HPCI System inoperable and Condition D, E, or G entered.

M. Two or more low M.1 Enter LCO 3.0.3. Immediately pressure ECCS injection/spray subsystems inoperable for reasons other than Condition C, D, E, or G.

OR HPCI System and one or more ADS valves inoperable.

Monticello 3.5.1-5 Amendment No. 206

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, In accordance with locations susceptible to gas accumulation are the Surveillance sufficiently filled with water. Frequency Control Program SR 3.5.1.2 --------------------------------NOTE-------------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each ECCS injection/spray subsystem In accordance with manual, power operated, and automatic valves in the the Surveillance flow path, that is not locked, sealed, or otherwise Frequency Control secured in position, is in the correct position. Program SR 3.5.1.3 Verify ADS pneumatic pressure is as follows for In accordance with each required ADS pneumatic supply: the Surveillance Frequency Control

a. S/RV Accumulator Bank header pressure Program 88.3 psig; and

b. Alternate Nitrogen System pressure is 1060 psig.

SR 3.5.1.4 --------------------------------NOTE-------------------------------

Only required to be met in MODE 1.

Verify the RHR System intertie return line isolation In accordance with valves are closed. the Surveillance Frequency Control Program SR 3.5.1.5 Verify correct breaker alignment to the LPCI swing In accordance with bus. the Surveillance Frequency Control Program Monticello 3.5.1-6 Amendment No. 206

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.6 Verify each recirculation pump discharge valve In accordance with cycles through one complete cycle of full travel or is the INSERVICE de-energized in the closed position. TESTING PROGRAM SR 3.5.1.7 Verify the following ECCS pumps develop the In accordance with specified flow rate against a system head the INSERVICE corresponding to the specified reactor to TESTING containment pressure. PROGRAM System Head Corresponding to a Reactor to No. of Containment System Flow Rate Pumps Pressure of Core Spray 2835 gpm 1 130 psi LPCI 3870 gpm 1 20 psi SR 3.5.1.8 --------------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor steam dome pressure In accordance with 1025.3 psig and 950 psig, the HPCI pump can the INSERVICE develop a flow rate 2700 gpm against a system TESTING head corresponding to reactor pressure. PROGRAM Monticello 3.5.1-7 Amendment No. 206

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.9 --------------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the HPCI In accordance with pump can develop a flow rate 2700 gpm against a the Surveillance system head corresponding to reactor pressure. Frequency Control Program SR 3.5.1.10 --------------------------------NOTE-------------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem In accordance with actuates on an actual or simulated automatic the Surveillance initiation signal. Frequency Control Program SR 3.5.1.11 --------------------------------NOTE-------------------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated In accordance with automatic initiation signal. the Surveillance Frequency Control Program SR 3.5.1.12 --------------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam flow is adequate to perform the test.

Verify each ADS valve is capable of being opened. In accordance with the INSERVICE TESTING PROGRAM Monticello 3.5.1-8 Amendment No. 206

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.13 Verify automatic transfer capability of the LPCI In accordance with swing bus power supply from the normal source to the Surveillance the backup source. Frequency Control Program Monticello 3.5.1-9 Amendment No. 206

RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

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

LCO 3.0.4.b is not applicable to the RCIC System.

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

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

OR In accordance with the Risk Informed Completion Time Program B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months dome pressure to 150 psig.

Monticello 3.5.3-1 Amendment No. 206

Primary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.3 ---------------NOTE--------------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify an OPERABLE door Once per 31 days is locked closed.

C. Primary containment air C.1 Initiate action to evaluate Immediately lock inoperable for primary containment overall reasons other than leakage rate per Condition A or B. LCO 3.6.1.1, using current air lock test results.

AND C.2 Verify a door is closed. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.6.1.2-3 Amendment No. 206

PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3 Monticello 3.6.1.3-1 Amendment No. 206

PCIVs 3.6.1.3 ACTIONS

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

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment,"

when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for Only applicable to penetration flow path by main steam line penetration flow paths use of at least one closed with two PCIVs. and de-activated automatic OR

valve, closed manual valve, blind flange, or check valve In accordance with One or more penetration with flow through the valve the Risk Informed flow paths with one secured. Completion Time PCIV inoperable for Program reasons other than AND Condition D or E. AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main steam line OR In accordance with the Risk Informed Completion Time Program Monticello 3.6.1.3-2 Amendment No. 206

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2 --------------NOTES------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is following isolation for isolated. isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment Monticello 3.6.1.3-3 Amendment No. 206

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE------------ B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two PCIVs. and de-activated automatic

valve, closed manual valve, or blind flange.

One or more penetration flow paths with two PCIVs inoperable for reasons other than Condition D or E.

C. ------------NOTE------------ C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for Only applicable to penetration flow path by excess flow check penetration flow paths use of at least one closed valves (EFCVs) and with only one PCIV. and de-activated automatic penetrations with a

valve, closed manual closed system valve, or blind flange.

One or more AND penetration flow paths with one PCIV 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for EFCVs inoperable. and penetrations with a closed system AND Monticello 3.6.1.3-4 Amendment No. 206

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2 --------------NOTES------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is following isolation for isolated. isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment Monticello 3.6.1.3-5 Amendment No. 206

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration D.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months flow paths with one or penetration flow path by more 18 inch primary use of at least one closed OR containment purge and and de-activated automatic vent valves not within valve, closed manual valve, -----------NOTE----------

purge and vent valve or blind flange. Not applicable when leakage limits. a loss of function occurs.

In accordance with the Risk Informed Completion Time Program AND D.2 --------------NOTES------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is following isolation for isolated. isolation devices outside containment Monticello 3.6.1.3-6 Amendment No. 206

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more MSIVs E.1 Restore leakage rate to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months with leakage rate not within limits.

within limits.

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

F.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.6.1.3-7 Amendment No. 206

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 --------------------------------NOTE-------------------------------

Not required to be met when the 18 inch primary containment purge and vent valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 18 inch primary containment purge and In accordance with vent valve is closed. the Surveillance Frequency Control Program SR 3.6.1.3.2 -------------------------------NOTES------------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual In accordance with valve and blind flange that is located outside primary the Surveillance containment and not locked, sealed, or otherwise Frequency Control secured and is required to be closed during accident Program conditions is closed.

Monticello 3.6.1.3-8 Amendment No. 206

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.3 -------------------------------NOTES------------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual isolation Prior to entering valve and blind flange that is located inside primary MODE 2 or 3 from containment and not locked, sealed, or otherwise MODE 4 if secured and is required to be closed during accident primary conditions is closed. containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe (TIP) In accordance with shear isolation valve explosive charge. the Surveillance Frequency Control Program SR 3.6.1.3.5 Verify the isolation time of each power operated In accordance with automatic PCIV, except for MSIVs, is within limits. the Surveillance Frequency Control Program SR 3.6.1.3.6 Verify the isolation time of each MSIV is In accordance with 3 seconds and 9.9 seconds. the Surveillance Frequency Control Program SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation In accordance with position on an actual or simulated isolation signal. the Surveillance Frequency Control Program Monticello 3.6.1.3-9 Amendment No. 206

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV In accordance with actuates on a simulated instrument line break to the Surveillance restrict flow to 2 gpm. Frequency Control Program SR 3.6.1.3.9 Verify each 18 inch primary containment purge and In accordance with vent valve is blocked to restrict the valve from the Surveillance opening > 40°. Frequency Control Program SR 3.6.1.3.10 Remove and test the explosive squib from each In accordance with shear isolation valve of the TIP System. the Surveillance Frequency Control Program SR 3.6.1.3.11 Perform leakage rate testing for each 18 inch primary In accordance with containment purge and vent valve with resilient seals. the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify leakage rate through each MSIV is: In accordance with the Primary (a) 100 scfh when tested at 44.1 psig (Pa); or Containment (b) 75.3 scfh when tested at 25 psig. Leakage Rate Testing Program SR 3.6.1.3.13 Verify leakage rate through the main steam pathway In accordance with is: the Primary Containment (a) 200 scfh when tested at 44.1 psig (Pa); or Leakage Rate (b) 150.6 scfh when tested at 25 psig. Testing Program Monticello 3.6.1.3-10 Amendment No. 206

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 3.6 CONTAINMENT SYSTEMS 3.6.1.6 Reactor Building-to-Suppression Chamber Vacuum Breakers LCO 3.6.1.6 Each reactor building-to-suppression chamber vacuum breaker shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each line.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more lines with A.1 Close the open vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months one reactor building-to- breaker.

suppression chamber vacuum breaker not closed.

B. One or more lines with B.1 Close one open vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months two reactor building-to- breaker.

suppression chamber vacuum breakers not closed.

C. One line with one or C.1 Restore the vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months more reactor building- breaker(s) to OPERABLE to-suppression chamber status. OR vacuum breakers inoperable for opening. In accordance with the Risk Informed Completion Time Program Monticello 3.6.1.6-1 Amendment No. 206

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two lines with one or D.1 Restore all vacuum 1 Hour more reactor building- breakers in one line to to-suppression chamber OPERABLE status.

vacuum breakers inoperable for opening.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.6.1.6-2 Amendment No. 206

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1 -------------------------------NOTES------------------------------

1. Not required to be met for vacuum breakers that are open during Surveillances.

2. Not required to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is closed. In accordance with the Surveillance Frequency Control Program SR 3.6.1.6.2 Perform a functional test of each vacuum breaker. In accordance with the Surveillance Frequency Control Program SR 3.6.1.6.3 Verify the opening setpoint of each vacuum breaker In accordance with is 0.5 psid. the Surveillance Frequency Control Program Monticello 3.6.1.6-3 Amendment No. 206

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 3.6 CONTAINMENT SYSTEMS 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers LCO 3.6.1.7 Seven suppression chamber-to-drywell vacuum breakers shall be OPERABLE for opening.

AND Eight suppression chamber-to-drywell vacuum breakers shall be closed.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required A.1 Restore one vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months suppression chamber-to- breaker to OPERABLE drywell vacuum breaker status. OR inoperable for opening.

In accordance with the Risk Informed Completion Time Program B. One suppression B.1 Close the open vacuum 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months chamber-to-drywell breaker.

vacuum breaker not closed.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.6.1.7-1 Amendment No. 206

RHR Drywell Spray 3.6.1.8 3.6 CONTAINMENT SYSTEMS 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray LCO 3.6.1.8 Two RHR drywell spray subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR drywell spray A.1 Restore RHR drywell spray 7 days subsystem inoperable. subsystem to OPERABLE status. OR In accordance with the Risk Informed Completion Time Program B. Two RHR drywell spray B.1 Restore one RHR drywell 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months subsystems inoperable. spray subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.6.1.8-1 Amendment No. 206

RHR Drywell Spray 3.6.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.8.1 Verify each RHR drywell spray subsystem manual In accordance with and power operated valve in the flow path that is not the Surveillance locked, sealed, or otherwise secured in position is in Frequency Control the correct position or can be aligned to the correct Program position.

SR 3.6.1.8.2 Verify each drywell spray header and nozzle is 10 years unobstructed.

SR 3.6.1.8.3 Verify RHR drywell spray subsystem locations In accordance with susceptible to gas accumulation are sufficiently filled the Surveillance with water. Frequency Control Program Monticello 3.6.1.8-2 Amendment No. 206

RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 Two RHR suppression pooling cooling subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression A.1 Restore RHR suppression 7 days pool cooling subsystem pool cooling subsystem to inoperable. OPERABLE status. OR In accordance with the Risk Informed Completion Time Program B. Two RHR suppression B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months pool cooling subsystems suppression pool cooling inoperable. subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.6.2.3-1 Amendment No. 206

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling In accordance with subsystem manual and power operated valve in the the Surveillance flow path that is not locked, sealed, or otherwise Frequency Control secured in position is in the correct position or can be Program aligned to the correct position.

SR 3.6.2.3.2 Verify each required RHR pump develops a flow In accordance with rate 3870 gpm through the associated heat the INSERVICE exchanger while operating in the suppression pool TESTING cooling mode. PROGRAM SR 3.6.2.3.3 Verify RHR suppression pool cooling subsystem In accordance with locations susceptible to gas accumulation are the Surveillance sufficiently filled with water. Frequency Control Program Monticello 3.6.2.3-2 Amendment No. 206

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

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHRSW subsystem A.1 ---------------NOTE--------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown," for RHR shutdown cooling made inoperable by RHRSW System.

Restore RHRSW 7 days subsystem to OPERABLE status. OR In accordance with the Risk Informed Completion Time Program Monticello 3.7.1-1 Amendment No. 206

RHRSW System 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Both RHRSW B.1 ---------------NOTE--------------

subsystems inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.7 for RHR shutdown cooling made inoperable by RHRSW System.

Restore one RHRSW 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify each RHRSW manual, power operated, and In accordance with automatic valve in the flow path, that is not locked, the Surveillance sealed, or otherwise secured in position, is in the Frequency Control correct position or can be aligned to the correct Program position.

Monticello 3.7.1-2 Amendment No. 206

ESW System and UHS 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Emergency Service Water (ESW) System and Ultimate Heat Sink (UHS)

LCO 3.7.2 Two ESW subsystems and UHS shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ESW subsystem A.1 --------------NOTE--------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown," for RHR shutdown cooling made inoperable by ESW.

Restore the ESW 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem to OPERABLE status. OR In accordance with the Risk Informed Completion Time Program Monticello 3.7.2-1 Amendment No. 206

ESW System and UHS 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Both ESW subsystems inoperable.

OR UHS inoperable.

Monticello 3.7.2-2 Amendment No. 206

ESW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in the intake structure is In accordance with 899 ft mean sea level. the Surveillance Frequency Control Program SR 3.7.2.2 Verify the average water temperature of UHS is In accordance with 90°F. the Surveillance Frequency Control Program SR 3.7.2.3 --------------------------------NOTE-------------------------------

Isolation of flow to individual components does not render ESW System inoperable.

Verify each ESW subsystem manual and automatic In accordance with valve in the flow paths servicing safety related the Surveillance systems or components, that is not locked, sealed, Frequency Control or otherwise secured in position, is in the correct Program position.

SR 3.7.2.4 Verify each ESW subsystem actuates on an actual In accordance with or simulated initiation signal. the Surveillance Frequency Control Program Monticello 3.7.2-3 Amendment No. 206

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 Restore required offsite 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuit to OPERABLE status. OR In accordance with the Risk Informed Completion Time Program B. One EDG inoperable. B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE required offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.2 Declare required feature(s), 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from supported by the inoperable discovery of EDG, inoperable when the Condition B redundant required concurrent with feature(s) are inoperable. inoperability of redundant required feature(s)

AND B.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months EDG is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE EDG.

AND Monticello 3.8.1-2 Amendment No. 206

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.4 Restore EDG to 7 days OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program C. Two required offsite C.1 Declare required feature(s) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from circuits inoperable. inoperable when the discovery of redundant required Condition C feature(s) are inoperable. concurrent with inoperability of redundant required feature(s)

AND C.2 Restore one required offsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months circuit to OPERABLE status. OR In accordance with the Risk Informed Completion Time Program Monticello 3.8.1-3 Amendment No. 206

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One required offsite --------------------NOTE-------------------

circuit inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.7, AND "Distribution Systems - Operating,"

when Condition D is entered with no One EDG inoperable. AC power source to any division.

D.1 Restore required offsite 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuit to OPERABLE status. OR In accordance with the Risk Informed Completion Time Program OR D.2 Restore EDG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

OR In accordance with the Risk Informed Completion Time Program E. Two EDGs inoperable. E.1 Restore one EDG to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OPERABLE status.

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

F.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. Three or more required G.1 Enter LCO 3.0.3. Immediately AC sources inoperable.

Monticello 3.8.1-4 Amendment No. 206

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated In accordance with power availability for each required offsite circuit. the Surveillance Frequency Control Program SR 3.8.1.2 ------------------------------NOTES-------------------------------

1. All EDG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

2. A modified EDG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer.

Verify each EDG starts from standby conditions and In accordance with achieves steady state voltage 3975 V and the Surveillance 4400 V and frequency 58.8 Hz and 61.2 Hz. Frequency Control Program Monticello 3.8.1-5 Amendment No. 206

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.3 -------------------------------NOTES------------------------------

1. EDG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one EDG at a time.

4. This SR shall be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.2.

Verify each EDG is synchronized and loaded and In accordance with operates for 60 minutes at a load 2250 kW and the Surveillance 2500 kW. Frequency Control Program SR 3.8.1.4 Check for and remove accumulated water from each In accordance with day tank and base tank. the Surveillance Frequency Control Program SR 3.8.1.5 Verify the fuel oil transfer system operates to In accordance with transfer fuel oil from the storage tank to the day the Surveillance tanks and from each day tank to the associated Frequency Control base tank. Program Monticello 3.8.1-6 Amendment No. 206

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.6 --------------------------------NOTE-------------------------------

This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

In accordance with Verify automatic and manual transfer of unit power the Surveillance supply from the normal offsite circuit to the alternate Frequency Control offsite circuit. Program SR 3.8.1.7 -------------------------------NOTES------------------------------

1. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

2. If performed with EDG synchronized with offsite power, it shall be performed within the power factor limit. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each EDG rejects a load greater than or equal In accordance with to its associated single largest post-accident load, the Surveillance and following load rejection, the frequency is Frequency Control 67.5 Hz. Program Monticello 3.8.1-7 Amendment No. 206

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.8 --------------------------------NOTE-------------------------------

This Surveillance shall not normally be performed in MODE 1 or 2. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated Emergency Core In accordance with Cooling System (ECCS) initiation signal, the Surveillance permanently connected loads remain energized Frequency Control from the offsite power system and emergency loads Program are auto-connected through the time delay relays from the offsite power system.

SR 3.8.1.9 -------------------------------NOTES------------------------------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

3. If part b is performed with EDG synchronized with offsite power, it shall be performed within the power factor limit. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each EDG operates for 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s: In accordance with the Surveillance

a. For 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2625 kW and Frequency Control 2750 kW; and Program

b. For the remaining hours of the test loaded 2250 kW and 2500 kW.

Monticello 3.8.1-8 Amendment No. 206

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.10 -------------------------------NOTES------------------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the EDG after the EDG has operated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 2250 kW and 2500 kW.

Momentary transients outside of load range do not invalidate this test.

2. All EDG starts may be preceded by an engine prelube period.

Verify each EDG starts and achieves: In accordance with the Surveillance

a. In 10 seconds, voltage 3975 V and Frequency Control frequency 58.8 Hz; and Program

b. Steady state voltage 3975 V and 4400 V and frequency 58.8 Hz and 61.2 Hz.

SR 3.8.1.11 --------------------------------NOTE-------------------------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify each EDG: In accordance with the Surveillance

a. Synchronizes with offsite power source while Frequency Control loaded with emergency loads upon a simulated Program restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

Monticello 3.8.1-9 Amendment No. 206

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.12 -------------------------------NOTES------------------------------

1. All EDG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify, on an actual or simulated loss of offsite In accordance with power signal in conjunction with an actual or the Surveillance simulated ECCS initiation signal: Frequency Control Program

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. EDG auto-starts from standby condition and:

1. Energizes permanently connected loads in 10 seconds;

2. Energizes auto-connected emergency loads through time delay relays;

3. Achieves steady state voltage 3975 V and 4400 V;

4. Achieves steady state frequency 58.8 Hz and 61.2 Hz; and

5. Supplies permanently connected and auto-connected emergency loads for 5 minutes.

Monticello 3.8.1-10 Amendment No. 206

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.13 --------------------------------NOTE-------------------------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify interval between each sequenced load block In accordance with is greater than or equal to the minimum design load the Surveillance interval. Frequency Control Program Monticello 3.8.1-11 Amendment No. 206

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 The Division 1 and Division 2 125 VDC and 250 VDC electrical power subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore battery terminal 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months battery chargers on voltage to greater than or Division 1 or Division 2 equal to the minimum inoperable. established float voltage.

AND A.2 Verify battery float current Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2 amps for 250 VDC batteries and 1 amp for 125 VDC batteries.

AND A.3 Restore required Division 1 7 days or Division 2 battery charger(s) to OPERABLE OR status.

In accordance with the Risk Informed Completion Time Program B. One Division 1 or B.1 Restore Division 1 or 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Division 2 DC electrical Division 2 DC electrical power subsystem power subsystem to OR inoperable for reasons OPERABLE status.

other than Condition A. In accordance with the Risk Informed Completion Time Program Monticello 3.8.4-1 Amendment No. 206

Distribution Systems - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems - Operating LCO 3.8.7 Division 1 and Division 2 AC and DC electrical power distribution subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC --------------------NOTE-------------------

electrical power Enter applicable Conditions and distribution subsystems Required Actions of LCO 3.8.4, "DC inoperable. Sources - Operating," for DC divisions made inoperable by inoperable power distribution subsystems.

A.1 Restore AC electrical power 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months distribution subsystem(s) to OPERABLE status. OR In accordance with the Risk Informed Completion Time Program B. One or more DC B.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power power distribution distribution subsystems subsystem(s) to OR inoperable. OPERABLE status.

In accordance with the Risk Informed Completion Time Program Monticello 3.8.7-1 Amendment No. 206

Distribution Systems - Operating 3.8.7 ACTIONS (continued)

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

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Two or more electrical D.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct breaker alignments and voltage to In accordance with required AC and DC electrical power distribution the Surveillance subsystems. Frequency Control Program Monticello 3.8.7-2 Amendment No. 206

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Spent Fuel Pool Boral Monitoring Program The program provides routine monitoring and actions to ensure that the condition of Boral in the spent fuel pool racks is appropriately monitored to ensure that the Boral neutron attenuation capability described in the criticality safety analysis of USAR Section 10.2.1 is maintained. The program shall include the following:

a. Periodic physical examination of representative Boral coupons or in situ storage racks at a frequency defined by observed trends or calculated projections of Boral degradation. The measurement will be performed to ensure that average thickness of the coupon (or average thickness of a representative area of the in situ storage rack) does not exceed the nominal design thickness of the coupon (or storage rack) plus the 0.055-inch dimension assumed for the analyzed blister.

b. Neutron attenuation testing of a representative Boral coupon or in situ storage rack shall be performed prior to December 31, 2015, and thereafter at a frequency of not more than 10 years, or more frequently based on observed trends or calculated projections of Boral degradation. The acceptance criterion for minimum boron areal density will be that value assumed in the criticality safety analysis (0.013 gm/cm2).

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

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

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

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

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

Monticello 5.5-13 Amendment No. 206

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Risk Informed Completion Time Program This program provides controls to calculate a Risk Informed Completion Time (RICT) and must be implemented in accordance with NEI 06-09-A, Revision 0, "Risk-Managed Technical Specifications (RMTS) Guidelines." The program shall include the following:

a. The RICT may not exceed 30 days;

b. A RICT may only be utilized in MODE 1, 2;

c. When a RICT is being used, any change to the plant configuration, as defined in NEI 06-09-A, Appendix A, must be considered for the effect on the RICT.

1. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration.

2. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the plant configuration change, whichever is less.

3. Revising the RICT is not required if the plant configuration change would lower plant risk and would result in a longer RICT.

d. For emergent conditions, if the extent of condition evaluation for inoperable structures, systems, or components (SSCs) is not complete prior to exceeding the Completion Time, the RICT shall account for the increased possibility of common cause failure (CCF) by either:

1. Numerically accounting for the increased possibility of CCF in the RICT calculation; or

2. Risk Management Actions (RMAs) not already credited in the RICT calculation shall be implemented that support redundant or diverse SSCs that perform the function(s) of the inoperable SSCs, and, if practicable, reduce the frequency of initiating events that challenge the function(s) performed by the inoperable SSCs.

e. The risk assessment approaches and methods shall be acceptable to the NRC. The plant PRA shall be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant, as specified in Regulatory Guide 1.200, Revision 2. Methods to assess the risk from extending the Completion Times must be PRA methods used to support this license amendment, or other methods approved by the NRC for generic use; and any change in the PRA methods to assess risk that are outside these approval boundaries require prior NRC approval.

Monticello 5.5-14 Amendment No. 206

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 206 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-22 NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263

1.0 INTRODUCTION

By application dated March 30, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20090F820), as supplemented by letters dated December 21, 2020 (ADAMS Accession No. ML20356A131), April 20, 2021 (ADAMS Accession No. ML21110A666), and June 30, 2021 (ADAMS Accession No. ML21181A308) Northern States Power Company, doing business as Xcel Energy (NSPM, the licensee) submitted a license amendment request (LAR) for Monticello Nuclear Generating Plant (MNGP).

The amendment would revise technical specification (TS) requirements to permit the use of risk-informed completion times (RICTs) for actions to be taken when limiting conditions for operation (LCOs) are not met. The proposed changes are based on Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, dated July 2, 2018 (ADAMS Package Accession No. ML18183A493). The U.S. Nuclear Regulatory Commission (NRC or the Commission) issued a final model safety evaluation (SE) approving TSTF-505, Revision 2, on November 21, 2018 (ADAMS Package Accession No. ML18269A041).

The LAR proposed variations from the TS changes described in TSTF-505, Revision 2. The variations are described in Section 2.2.4 of this SE.

The supplemental letters provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no significant hazards consideration determination as published in the Federal Register (FR) on May 19, 2020 (85 FR 29985).

Enclosure 2

2.0 REGULATORY EVALUATION

2.1 Description of Risk Informed Completion Time (RICT) Program The TS LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO is not met, the licensee must shut down the reactor or follow any remedial or required action (e.g., testing, maintenance, or repair activity) permitted by the TSs until the condition can be met. The remedial actions (i.e., ACTIONS) associated with an LCO contain Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times (CTs). The CTs are referred to as the front stops in the context of this SE. For certain Conditions, the TS require exiting the Mode of Applicability of an LCO (i.e., shutdown the reactor).

The Nuclear Energy Institute (NEI) Topical Report (TR) NEI 06-09-A, Revision 0, Risk Informed Technical Specifications Initiative 4b: Risk Managed Technical Specifications (RMTS), dated November 2006 (NEI 06-09 A) (ADAMS Accession No. ML122860402) provides a methodology for extending existing CTs and thereby delaying exiting the operational mode of applicability or taking Required Actions if risk is assessed and managed within the limits and programmatic requirements established by a RICT program.

2.2 Description of TS Changes The amendment requested approval to add a RICT program to the Administrative Controls section of the TS and to modify selected CTs to permit extending the CTs, provided risk is assessed and managed as described in NEI 06-09-A. The LAR proposed to use NEI 06-09-A and included documentation regarding the technical adequacy of the probabilistic risk assessment (PRA) models for the RICT program, consistent with the guidance of Regulatory Guide (RG) 1.200, Revision 2, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk informed Activities, March 2009 (ADAMS Accession No. ML090410014).

2.2.1 TS 1.0, Use and Application Example 1.3-8 would be added to TS 1.3, Completion Times, and reads as follows:

EXAMPLE 1.3-8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore subsystem 7 days subsystem to OPERABLE inoperable. status. OR In accordance with the Risk Informed Completion Time Program B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and associated AND Completion Time not B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

When a subsystem is declared inoperable, Condition A is entered.

The 7 day Completion Time may be applied as discussed in Example 1.3-2. However, the licensee may elect to apply the Risk Informed Completion Time Program which permits calculation of a Risk Informed Completion Time (RICT) that may be used to complete the Required Action beyond the 7 day Completion Time.

The RICT cannot exceed 30 days. After the 7 day Completion Time has expired, the subsystem must be restored to OPERABLE status within the RICT or Condition B must also be entered.

The Risk Informed Completion Time Program requires recalculation of the RICT to reflect changing plant conditions. For planned changes, the revised RICT must be determined prior to implementation of the change in configuration. For emergent conditions, the revised RICT must be determined within the time limits of the Required Action Completion Time (i.e., not the RICT) or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the plant configuration change, whichever is less.

If the 7 day Completion Time clock of Condition A has expired and subsequent changes in plant condition result in exiting the applicability of the Risk Informed Completion Time Program without restoring the inoperable subsystem to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start.

If the RICT expires or is recalculated to be less than the elapsed time since the Condition was entered and the inoperable subsystem has not been restored to OPERABLE status, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable subsystems are restored to OPERABLE status after Condition B is entered, Conditions A and B are exited, and therefore, the required actions of Condition B may be terminated.

2.2.2 TS 5.5.16 - Risk informed Completion Time Program TS 5.5.16, which describes the RICT program, would be added to the TS and reads as follows:

Risk Informed Completion Time Program This program provides controls to calculate a Risk Informed Completion Time (RICT) and must be implemented in accordance with NEI 06-09-A, Revision 0, Risk-Managed Technical Specifications (RMTS) Guidelines. The program shall include the following: