Text

Technical Specifications, Unit 1, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant
	ML11172A020
Person / Time
Site:	Prairie Island
Issue date:	06/27/2011
From:	; Office of Nuclear Reactor Regulation
To:	; Northern States Power Co
	Regner L
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ML11147A141	List: ML11147A123; ML11147A137; ML11147A139; ML11147A140; ML11172A020; ML11172A022; NRC-2009-0507, Prairie Island Nuclear Generating Plant, Units 1 and 2 Notice of Issuance of Renewed Facility Operating License Nos. DPR-42 and DPR-60 for an Additional 20-Year Period Record of Decision;
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APPENDIX A TECHNICAL SPECIFICATIONS PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 FACILITY OPERATNG LICENSE NOS. DPR-42 AND DPR-60 NORTHERN STATES POWER COMPANY - MINNESOTA DOCKET NOS. 50-282 AND 50-306

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

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

N-------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

ACTUATION An ACTUATION LOGIC TEST shall be the application of various LOGIC simulated or actual input combinations in conjunction with each mESr possible interlock logic state required for OPERABILITY of a logic circuit and the verification of the required logic output.

AXIALFL'UX AFD shall be the difference in normalized flux signals between the DFFERENCE top and bottom halves of a two section excore neutron detector.

(AFD)

CHANNEL A CHANNEL CALIBRATION shall be the adjustment, as CALIBRATlON necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 1.1-1 Unit 2 - Amendment No. 149

Definitions 1.1 1.1 Definitions (continued)

CHANNEL A CHANNEL CHECK shall be the qualitative assessment, by CHECK observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL A COT shall be the injection of a simulated or actual signal into OPERATIONAL the channel as close to the sensor output as practicable to verify TEST(COT) OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps.

CORE CORE ALTERATION shall be the movement of any fuel, sources, ALTERATION or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE The COLR is the unit specific document that provides cycle specific OPERATING parameter limits for the current reload cycle. These cycle specific LIMITS parameter limits shall be determined for each reload cycle in REPORT accordance with Specification 5.6.5. Plant operation within these (COLR) limits is addressed in individual Specifications.

DOSE DOSE EQUIVALENT I-13 1 shall be that concentration of I-131 EQUIVALENT (microcuries/gram) that alone would produce the same thyroid dose 1-131 as the quantity and isotopic mixture of I-131, 1-132, 1-133, 1-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites".

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 1.1-2 Unit 2 - Amendment No. 149

Definitions 1.1 1.1 Definitions (continued)

E -AVERAGE E shall be the average (weighted in proportion to the concentration DISINTEGRATION of each radionuclide in the reactor coolant at the time of sampling)

ENERGY of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total noniodine activity in the coolant.

LEAKAGE LEAKAGE from the Reactor Coolant System (RCS) shall be:

a. Identified LEAKAGE I. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; or

3. RCS LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE);

b. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE;

c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

Prairie Island Unit 1 - Amendment No. 4-18 177 Units I and 2 1.1-3 Unit 2 - Amendment No. 449 167

Definitions 1.1 1.1 Definitions (continued)

MASTER A MASTER RELAY TEST shall consist of energizing all RELAY master relays in the channel required for channel OPERABILITY TEST and verifying the OPERABILITY of each required master relay.

The MASTER RELAY TEST shall include a continuity check of each associated required slave relay. The MASTER RELAY TEST may be performed by means of any series of sequential, overlapping, or total steps.

MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

OPERABLE - A system, subsystem, train, component, or device shall be OPERABILITY OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling-and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS PHYSICS TESTS shall be those tests performed to measure the TESTS fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:

a. Described in Appendix J of the USAR, Pre-Operational and Startup Tests;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

Prairie Island Unit I -Amendment No. 158 Units 1 and 2 1.1-4 Unit 2 - Amendment No. 149

Definitions 1.1 1.1 Definitions (continued)

PRESSURE AND The PTLR is the unit specific document that provides the reactor lEMPERATURE vessel pressure and temperature limits, including heatup and LIMITS cooldown rates, and the OPPS arming temperature for the current REPORT reactor vessel fluence period. These pressure and temperature limits (PILR) shall be determined for each fluence period in accordance with Specification 5.6.6. Plant operation within these operating limits is addressed in LCO 3.4.3, "RCS Pressure and Temperature (PIT)

Limits," LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP) -Reactor Coolant System Cold Leg Temperature (RCSCLT)

> Safety Injection (SI) Pump Disable Temperature," and LCO 3.4.13, "Low Temperature Overpressure Protection (LTOP)

- Reactor Coolant System Cold Leg Temperature (RCSCLT)

~ Safety Injection (SI) Pump Disable Temperature."

QUADRANT QPTR shall be the ratio of the maximum upper excore detector POWER1ll..T calibrated output to the average of the upper excore detector RATIO (QPIR) calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater.

RATED RTP shall be a total reactor core heat transfer rate to the reactor THERMAL coolant of 1677 MWt.

POWER (RTP)

REACTOR The RTS RESPONSE TIME shall be that time interval from when TRIP the monitored parameter exceeds its RTS trip setpoint at the channel SYSTEM (RTS) sensor output until opening of a reactor trip breaker. The response RESPONSE time may be measured by means of any series of sequential, TIME overlapping, or total steps so that the entire response time is measured.

Prairie Island Unit 1 - Amendment No. -l-§.& 197 Units 1 and 2 1.1-5 Unit 2 - Amendment No. -l-49 186

Definitions 1.1 1.1 Definitions (continued)

SHUTDOWN SDM shall be the instantaneous amount of reactivity by which:

MARGIN (SDM) a. The reactor is subcritical; or

b. The reactor would be subcritical from its present condition assuming all rod cluster control assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM. In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal zero power design temperature.

SLAVE A SLAVE RELAY TEST shall consist of energizing all slave relays RELAY in the channel required for channel OPERABILITY and verifying TEST the OPERABILITY of each required slave relay. The SLAVE shall include a continuity check of associated required testable actuation devices. The SLAVE RELAY TEST may be performed by means of any series of sequential, overlappping, or total steps.

STAGGERED A STAGGERED TEST BASIS shall consist of the testing of one of TEST the systems, subsystems, channels, or other designated components BASIS during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

Prairie Island Unit I -Amendment No. 158 Units I and 2 1.1-6 Unit 2 - Amendment No. 149

Definitions 1.1 1.1 Definitions (continued)

THERMAL THERMAL POWER shall be the total reactor core heat transfer POWER rate to the reactor coolant.

TRIP A TADOT shall consist of operating the trip actuating device and ACTJATING verifying the OPERABILITY of all devices in the channel DEVICE required for trip actuating device OPERABILITY. The TADOT OPERATIONAL shall include adjustment, as necessary, of the trip actuating device TEST so that it actuates at the required setpoint within the necessary (TADOT) accuracy. The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps.

Prairie Island Unit I - Amendment No. 158 Units I and 2 1.1-7 Unit 2 - Amendment No. 149

Definitions 1.1 Table 1.1-1 (page I of 1)

MCDES MODE TITLE REACTIVITY % RATED AVERAGE CONDITION THERMAL REACTOR (kff) POWER(a) COOLANT TEMPERATURE (OF) 1 Power Operation 2 0.99 > 5 NA 2 Startup 2 0.99

5 NA 3 Hot Standby < 0.99 NA Ž 350 4 Hot Shutdown(b) < 0.99 NA 350 > TaVg > 200 5 Cold Shutdown(b) < 0.99 NA s 200 6 Refueling(c) NA NA NA (a) Excludirn, decay heat.

(b) All reactor vessel head closure bolts fully tensioned.

(c) One or more reactor vessel head closure bolts less than fully tensioned.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 1.1-8 Unit 2 - Amendment No. 149

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action.

The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

Prairie Island Unit I -Amendment No. 158 Units I and 2 1.2-1 Unit 2 - Amendment No. 149

Logical Connectors 1.2 1.2 Logical Connectors (continued)

EXAMPLES The following examples illustrate the use of logical connectors.

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify ...

AND A.2 Restore...

In this example the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

Prairie Island Unit I - Amendment No. 158 Units I and 2 1.2-2 Unit 2 - Amendment No. 149

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not A. I Trip ...

met.

OR A.2.1 Verify...

AND A.2.2.1 Reduce ...

OR A.2.2.2 Perform...

OR A.3 Align ...

This example represents a more complicated use of logical connectors. Required Actions A. l, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement.

Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.I and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Prairie Island Unit I - Amendment No. 158 Units I and 2 1.2-3 Unit 2 - Amendment No. 149

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met.

Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time.

An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCO Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent trains, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry Prairie Island Unit I - Amendment No. 158 Units I and 2 1.3-1 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times DESCRIPTION into the Condition, unless specifically stated. The Required Actions (continued) of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

However, when a subsequent train, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. The Completion Time extension cannot be used to extend the stated Completion Time for the first inoperable train, subsystem, component, or variable. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours1 days 0.143 weeks 0.0329 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 1.3-2 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times DESCRIPTION The above Completion Time extension does not apply to a (continued) Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours0.333 days 0.0476 weeks 0.011 months ,"

where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery. . ."

Example 1.3-3 illustrates one use of this type of Completion Time.

The 10 day Completion Time specified for Conditions A and B in Example 1.3-3 may not be extended. An example of a modified "time zero" with the Completion Time expressed as "once per 8 hours0.333 days 0.0476 weeks 0.011 months " is illustrated in Example 1.3-6, Condition A. In this example, the Completion Time may not be extended.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 1.3-3 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times (continued)

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 6 hours0.25 days 0.0357 weeks 0.00822 months AND in MODE 5 within 36 hours1.5 days 0.214 weeks 0.0493 months . A total of 6 hours0.25 days 0.0357 weeks 0.00822 months is allowed for reaching MODE 3 and a total of 36 hours1.5 days 0.214 weeks 0.0493 months (not 42 hours1.75 days 0.25 weeks 0.0575 months ) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours0.125 days 0.0179 weeks 0.00411 months , the time allowed for reaching MODE 5 is the next 33 hours1.375 days 0.196 weeks 0.0452 months because the total time allowed for reaching MODE 5 is 36 hours1.5 days 0.214 weeks 0.0493 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 5 is the next 36 hours1.5 days 0.214 weeks 0.0493 months .

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 1.3-4 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One train A. I Restore train to 7 days inoperable. OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated AND Completion Time not met. B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months When a train is declared inoperable, Condition A is entered. If the train is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B. 1 and B.2 start. If the inoperable train is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

When a second train is declared inoperable while the first train is still inoperable, Condition A is not re-entered for the second train.

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable train. The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 1.3-5 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

While in LCO 3.0.3, if either of the inoperable trains is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition A.

While in LCO 3.0.3, if either of the inoperable trains is restored to OPERABLE status and the Completion Time for Condition A has expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.

Upon restoring either of the trains to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first train was declared inoperable. This Completion Time may be extended if the train restored to OPERABLE status was the first inoperable train. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second train being inoperable for > 7 days.

Prairie Island Unit ] - Amendment No. 158 Units I and 2 1.3-6 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.I Restore Function X 7 days Function X train to train OPERABLE status. AND inoperable.

10 days from discovery of failure to meet the LCO B. One B.I Restore Function Y 72 hours3 days 0.429 weeks 0.0986 months Function Y train to train OPERABLE status. AND inoperable.

10 days from discovery of failure to meet the LCO Prairie Island Unit 1 -Amendment No. 158 Units I and 2 1.3-7 Unit 2 - Amendment-No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS C. One C.1 Restore Function X 72 hours3 days 0.429 weeks 0.0986 months Function X train to train OPERABLE status.

inoperable.

OR AND C.2 Restore Function Y 72 hours3 days 0.429 weeks 0.0986 months One train to Function Y OPERABLE status.

train inoperable.

When one Function X train and one Function Y train are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.l has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected train was declared inoperable (i.e., initial entry into Condition A).

Prairie Island Unit 1-Amendment No. 158 Units I and 2 1.3-8 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

The Completion Times of Conditions A and B are modified by a logical connector with a separate 1O day Completion Time measured from the time it was discovered the LCO was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. The separate Completion Time modified by'the phrase "from discovery of failure to meet the LCO" is designed to prevent indefinite continued operation while not meeting the LCO.

This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock". In this instance, the Completion Time "time zero" is specified as commencing at the time the LCO wvas initially not met, instead of at the time the associated Condition was entered.

Prairie Island Unit I -Amendment No. 158 Units I and 2 1.3-9 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A. I Restore valve(s) to 4 hours0.167 days 0.0238 weeks 0.00548 months valves OPERABLE inoperable. status.

B. Required B.I Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated AND Completion Time not B.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months met.

A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours0.167 days 0.0238 weeks 0.00548 months provided this does not result in any subsequent valve being inoperable for > 4 hours0.167 days 0.0238 weeks 0.00548 months .

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 1.3-10 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

If the Completion Time of 4 hours0.167 days 0.0238 weeks 0.00548 months (plus the extension) expires while one or more valves are still inoperable, Condition B is entered.

EXAMPLE 1.3-5 ACTIONS NOTE Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A. 1 Restore valve to 4 hours0.167 days 0.0238 weeks 0.00548 months valves OPERABLE inoperable, status.

B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated AND Completion Time not B.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months met.

The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

Prairie Island Unit 1 - Amendment No. 4-58 180 Units ! and 2 !.3-1! Unit 2 - Amendment No. IA-9 170

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 1.3-12 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-6 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A. I Perform Once per 8 hours0.333 days 0.0476 weeks 0.011 months inoperable. SR 3.x.x.x.

OR A.2 Reduce 8 hours0.333 days 0.0476 weeks 0.011 months THERMAL POWER to

50% RTP.

B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated Completion Time not met.

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A. 1 has a "once per" Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A. 1 must be complete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A. 1 is followed, and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2), Condition B is entered. If Required Prairie Island Unit 1 -Amendment No. 158 Units I and 2 1.3-13 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-6 (continued)

Action A.2 is followed and the Completion Time of 8 hours0.333 days 0.0476 weeks 0.011 months is not met, Condition B is entered.

If after entry into Condition B, Required Action A. I or A.2 is met, Condition B is exited and operation may then continue in Condition A.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 1.3-14 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verifyaffected I hour subsystem subsystem isolated.

inoperable. AND Once per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter AND A.2 Restore subsystem 72 hours3 days 0.429 weeks 0.0986 months to OPERABLE status.

B. Required B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action and associated AND Completion Time not B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months met.

Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter" interval begins upon performance of Required Action A.1.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 1.3-15 Unit 2 - Amendment No. 149

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

If after Condition A is entered, Required Action A. I is not met within either the initial I hour or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2),

Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

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

TIME Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 1.3-16 Unit 2 - Amendment No. 149

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR) Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, Prairie Island Unit I - Amendment No. 158 Units I and 2 1.4-1 Unit 2- Amendment No. 149

Frequency 1.4 1.4 Frequency DESCRIPTION even without a Surveillance specifically being "performed,"

(continued) constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.

Some Surveillances contain notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these Surveillances, the MODE-entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:

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

b. The Surveillance is required to be met in the MODE or other specified condition to be entered, but has been performed within the specified Frequency (i.e., it is current) and is known not to be failed; or

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

Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discuss these special situations.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is MODES 1, 2, and 3.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 1.4-2 Unit 2 - Amendment No. 149

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours0.5 days 0.0714 weeks 0.0164 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours0.5 days 0.0714 weeks 0.0164 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Example 1.4-3), then SR 3.0.3 becomes applicable.

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE'or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable. The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered-not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.

Prairie Island Unit 1 - Amendment No. 4- 185 Units l and 2 1.4-3 Unit 2 - Amendment No. 449 175

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours0.5 days 0.0714 weeks 0.0164 months after 2 25% RTP I AND 24 hours1 days 0.143 weeks 0.0329 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level < 25% RTP to 2 25% RTP, the Surveillance must be performed within 12 hours0.5 days 0.0714 weeks 0.0164 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND"). This type of Frequency does not qualify for the 25%

extension allowed by SR 3.0.2. "Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

Prairie Island Unit I -Amendment No. 158 Units I and 2 1.4-4 Unit 2 - Amendment No. 149

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after 2 25% RTP.

Perform channel adjustment. 7 days The interval continues, whether or not the unit operation is

< 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours0.5 days 0.0714 weeks 0.0164 months after power reaches 2 25% RTP to perform the Surveillance. The Surveillance is still considered to be performed within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was < 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours0.5 days 0.0714 weeks 0.0164 months with power a 25% RTP.

Once the unit reaches 25% RTP, 12 hours0.5 days 0.0714 weeks 0.0164 months would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

Prairie Island Unit I - Amendment No. 158 Units I and 2 1.4-5 Unit 2 - Amendment No. 149

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-4 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours1 days 0.143 weeks 0.0329 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE l. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2),

but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1.

Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 1.4-6 Unit 2 - Amendment No. 149

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-5 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be performed in MODE 1.

Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MODE 1, 2, or 3 (the assumed Applicability of the associated LCO) between performances.

As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the "specified Frequency."

Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance. The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to entering MODE 1. Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1.

Once the unit reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance were not performed prior to entering MODE 1, there would then be a Prairie Island Unit 1 -Amendment No. 158 Units l and 2 1.4-7 Unit 2 - Amendment No. 149

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-5 (continued) failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY NOTE-----------------------

Not required to be met in MODE 3.

Verify parameter is within limits. 24 hours1 days 0.143 weeks 0.0329 months Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met while the unit is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1, 2, and 3). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 3, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satisfying the SR.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 1.4-8 Unit 2 - Amendment No. 149

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR and the following SLs shall not be exceeded:

2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained> 1.17 for WRB-1 DNB correlation.

2.1.1.2 The peak fuel centerline temperature shall be maintained as follows:

a) <5080 of, decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing U02; b) <<5080 OF minus 6.75 OF per wlo Gdz0 3 ), decreasing by 58 OF per 10,000 MWDIMTU bUffiup, for fuel containing gadolinia; 2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained

s 2735 psig.

2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

Prairie Island Unit 1 - Amendment No. ~ ~ 192 Units land 2 2.0-1 Unit 2 - Amendment No. -l-49 BJ. 181 Revised hy letter dated Septe~her 15, 200Q

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

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5, LCO 3.0.6 and LCO 3.0.8.

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

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

a. MODE 3 within 7 hours0.292 days 0.0417 weeks 0.00959 months ;

b. MODE 4 within 13 hours0.542 days 0.0774 weeks 0.0178 months ; and

c. MODE 5 within 37 hours1.542 days 0.22 weeks 0.0507 months .

Exceptions to this Specification are stated in the individual Specifications.

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

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

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.0-1 Unit 2 - Amendment No. 149

LCO Applicability 3.0 3.0 LCO APPLICABILITY (continued)

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

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

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

c. When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

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

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered.

Only the support system LCO ACTIONS are required to be entered.

\.J Prairie Island Unit I - Amendment No. 4-5b, 167 Units I and 2 3.0-2 Unit 2 - Amendment No. 4I49, 157

LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.6 This is an exception to LCO 3.0.2 for the supported system. In this (continued) event, an evaluation shall be performed in accordance with Specification 5.5.13, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCOs 3.1.8 and 3.4.18 allow specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

LCO 3.0.8 When a Technical Specification supported system LCO is not met solely due to the inoperability of a non-Technical Specification support system listed below, the Technical Specification supported system LCO is considered to be met unless the associated delay time of the non-Technical Specification support system has expired. This is an exception to LCO 3.0.2 for the Technical Specification. Upon expiration of the non-Technical Specification support system delay time, the Technical Specification supported system shall be declared inoperable and the applicable Conditions and Required Actions for the Technical Specifications supported system shall be entered in accordance with LCO 3.0.2.

K\.> Prairie Island Unit I - Amendment No. 4-&5, 167 Units I and 2 3.0-3 Unit 2 - Amendment No. 149, 157

LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.8 Non-Technical Specification Support System Delav Time (continued)

Snubbers 72 hours3 days 0.429 weeks 0.0986 months LCO 3.0.9 Unless specifically noted, all the information provided in the LCO including the associated ACTION requirements shall apply to each unit individually. Whenever certain portions of a specification refer to systems, components, operating parameters, setpoints, etc., which are different for each unit, this will be identified in parentheses or notes or in the Applicability section as appropriate.

<12I Prairie Island Unit I - Amendment No. 4&5, 167 Units I and 2 3.0-4 Unit 2 - Amendment No. 149, 1571

SR Applicability I 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO.

Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met, except for SRs with a specified Frequency of 24 months, if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

The specified Frequency is met for each SR with a specified Frequency of 24 months if the Surveillance is performed within 24 months, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension (1.25 times the interval specified) does not apply.

If a Completion Time requires periodic performance on a "once per . . ." basis, the interval extension (1.25 times the interval specified) applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

Prairie Island Unit 1 - Amendment No. 4 176 Units 1 and 2 3.0-5 Unit 2 - Amendment No. 449 166

SR Applicability 3.0 3.0 SR APPLICABILITY (continued)

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours1 days 0.143 weeks 0.0329 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours1 days 0.143 weeks 0.0329 months and the risk impact shall be managed.

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

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

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

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

Prairie Island Unit 1 - Amendment No. 4-54 4-67 176 Units l and 2 3.0-6 Unit 2 - Amendment No. 4-49 4-5q 166

SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be 'within the limits provided in the COLR APPLICABILITY: MODE 2 with k < 1.0, MODES 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM is within limits. 24 hours1 days 0.143 weeks 0.0329 months Prairie Island Unit I -Amendment No. 158 Units I and 2 3.1.1-1 Unit 2 - Amendment No. 149

Core Reactivity 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Core Reactivity LCO 3.1.2 The measured core reactivitv shall be within +/- 1% Ak/k of predicted values.

APPLICABILITY: MODE I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core reactivity A.] Re-evaluate core design and 7 days not within limit. safety analysis, and determine that the reactor core is acceptable for continued operation.

AND A.2 Establish appropriate 7 days operating restrictions and SRs.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.1.2-1 Unit 2 - Amendment No. 149

Core Reactivity 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify measured core reactivity is within +/- 1% Ak/k Prior to entering of predicted values. MODE I after each refueling SR 3.1.2.2 ----------------------------NOTES --------------------------

1. Only required to be performed after 60 effective full power days (EFPD).

2. The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel bumup of 60 EFPD after each fuel loading.

Verify measured core reactivity is within I % Ak/k 31 EFPD of predicted values.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.1.2-2 Unit 2 - Amendment No. 149

ITC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Isothermal Temperature Coefficient (ITC)

LCO 3.1.3 The ITC shall be maintained within the limits specified in the COLR.

The maximum COLR upper limit shall be:

a. < 5 pcm/IF for power levels

70% RTP; and

b. < 0 pcm/IF for power levels > 70% RTP.

APPLICABILITY: MODE I and MODE 2 with ke¢f 2 1.0 for the upper ITC limit, MODES 1, 2, and 3 for the lower ITC limit.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ITC not within upper A.1 Establish administrative 24 hours1 days 0.143 weeks 0.0329 months limit. withdrawal limits for control banks to maintain ITC within limit.

B. Required Action and B.1 Be in MODE 2 with 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion kcfr < 1.0.

Time of Condition A not met.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.1.3-1 Unit 2 - Amendment No. 149

ITC 3.1.3 ACTIONS (continued)

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

Required Action C.1 LCO 3.0.4.c is applicable. I must be completed whenever Condition C is entered. C. 1 Re-evaluLate core design and Once prior to safety analysis, and reaching the determine that the reactor equivalent of an Projected end of cycle core is acceptable for equilibrium RTP (EOC) ITC not within continued operation. all rods out boron lower limit. concentration of 300 ppm D. Required Action and D. I Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition C not met.

Prairie Island Unit 1- Amendment No. 4g, 167 Units I and 2 3.1.3-2 Unit 2 - Amendment No. 4-9, 157

ITC 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify ITC is within upper limit. Once prior to entering MODE I after each refueling SR 3.1.3.2 Verify ITC will be within limits specified in the Once after each COLR at 70% RTP. refueling prior to THERMAL POWER exceeding 70%

RTP SR 3.1.3.3 Verify that ITC will be within limits at EOC. Once after each refueling prior to THERMAL POWER exceeding 70%

RTP Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.1.3-3 Unit 2 - Amendment No. 149

Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits.

LCO 3.1.4 All shutdown and control rods shall be OPERABLE.

AND Individual actual rod positions shall be within 24 steps of their group step counter demand position when the demand position is between 30 and 215 steps, or within 36 steps of their group step counter demand position when the demand position < 30 steps, or > 215 steps.

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

Individual RPIs may be outside their limits for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months following substantial rod movement.

APPLICABlLTIY: MODES 1 and 2.

ACTIONS .. _.-

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rod(s) A.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. limits provided in the COLR.

OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND A.2 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Prairie Island Unit I -Amendment No. H8, 160 Units I and 2 3.1.4-1 Unit 2 - Amendment No. 149, 151

Rod Group Alignment Limits 3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One rod not within B.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months alignment limits. limits provided in the COLR.

OR B.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND B.2.1.1 Perform SR 3.2.1.1 and 8 hours0.333 days 0.0476 weeks 0.011 months SR 3.2.1.2.

AND B.2.1.2 Perform SR 3.2.2.1. 8 hours0.333 days 0.0476 weeks 0.011 months OR B.2.2 Reduce High Neutron 8 hours0.333 days 0.0476 weeks 0.011 months Flux Trip Setpoint to s 85% RTP.

AND B.3 Verify SDM is within the Once per limits provided in the 12 hours0.5 days 0.0714 weeks 0.0164 months COLR.

AND I ______________________

I Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.1.4-2 Unit 2 - Amendment No. 149

Rod Group Alignment Limits 3.1.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.4 Re-evaluate safety 30 days analyses and determine the THERMAL POWER for which the results remain valid for duration of operation under these conditions.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition B not met.

D. More than one rod not D.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within alignment limit. limits provided in the COLR.

OR D.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required SDM to within limit.

AND D.2 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.1.4-3 Unit 2 - Amendment No. 149

Rod Group Alignment Limits 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within alignment 12 hours0.5 days 0.0714 weeks 0.0164 months limit.

SR 3.1.4.2 Verify rod freedom of movement (trippability) by 92 days moving each rod, not fully inserted in the core,

> 10 steps in either direction.

SR 3.1.4.3 Verify rod drop time of each rod, from the fully Prior to reactor withdrawn position, is < 1.8 seconds from the criticality after beginning of decay of stationary gripper coil voltage each removal of to dashpot entry, with: the reactor head

a. Tavg> 500'F; and

b. Both reactor coolant pumps operating.

Prairie Island Unit 1 - Amendment No. 4-54 180

~21A A -I,,:.I 2 ANo. r-ý* ~ ,r 1-4% 170 Units I and 2 I.)IL -- Cg- lkl *Sh nALI.tl L q.

Shutdown Bank Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 Each shutdown bank shall be within insertion limits specified in the COLR.

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

This LCO is not applicable while performing SR 3.1.4.2.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more shutdown A.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months banks not within limits. limits provided in the COLR.

OR A.1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND A.2 Restore shutdown banks to 2 hours0.0833 days 0.0119 weeks 0.00274 months within limits.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.1.5-1 Unit 2 - Amendment No. 149

Shutdown Bank Insertion Limits 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each shutdown bank is within the limits 12 hours0.5 days 0.0714 weeks 0.0164 months specified in the COLR.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.1.5-2 Unit 2 - Amendment No. 149

Control Bank Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Control Bank Insertion Limits LCO 3.1.6 Control banks shall be within the insertion, sequence, and overlap limits specified in the COLR.

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

This LCO is not applicable while performing SR 3.1.4.2.

APPLICABILITIY: MODE 1, MODE 2 with kef- 2 1.0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control bank insertion A.1.1 Verify SDM is within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limits not met. limits provided in the COLR.

OR A. 1.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND A.2 Restore control bank(s) to 2 hours0.0833 days 0.0119 weeks 0.00274 months within limits.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.1.6-1 Unit 2 - Amendment No. 149

Control Bank Insertion Limits 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Control bank sequence or B.1.1 Verify SDM is within the I hour overlap limits not met. limits provided in the COLR.

OR B.l.2 Initiate boration to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDM to within limit.

AND B.2 Restore control bank 2 hours0.0833 days 0.0119 weeks 0.00274 months sequence and overlap to within limits.

C. Required Action and C.1 Be in MODE 2 with kff 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion < 1.0.

Time not met.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.1.6-2 Unit 2-Amendment No. 149

Control Bank Insertion Limits 3.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify estimated critical control bank position is Prior to within the limits specified in the COLR. achieving criticality SR 3.1.6.2 Verify each control bank insertion is within the limits 12 hours0.5 days 0.0714 weeks 0.0164 months specified in the COLR.

SR 3.1.6.3 Verify sequence and overlap limits specified in the 12 hours0.5 days 0.0714 weeks 0.0164 months COLR are met for control banks not fully withdrawn from the core.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.1.6-3 Unit 2 - Amendment No. 149

Rod Position Indication 3.1.7 3.1 REACTrvITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Rod Position Indication (RPI) System and demand position indication shall be OPERABLE.

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

Individual RPIs may be outside their limits for::: 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months following substantial rod movement.

APPLlCABlllIY: MODES 1 and 2.

ACTIONS

NOTE----------------------------------.--------------

Separate Condition entry is allowed for each inoperable rod position indicator and each demand position indicator.

CONDITION REQUIRED ACTION COMPLETION TIME A. One RPI per group Al Verify the position of the Oncc per 8 hours0.333 days 0.0476 weeks 0.011 months inoperable for one or rod(s) with inoperable more groups. position indicators by using core power distribution measurement information.

OR A2 Reduce THERMAL 8 hours0.333 days 0.0476 weeks 0.011 months POWER to::: 50% RTP.

Prairie Island Unit I - Amendment No. ~,M() 2011 Units 1 and 2 3.1.7-1 Unit 2 Amendment No. -M9, +.s-1 Ip~{ll

Rod Position Indication 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. More than one RPI per B.1 Monitor and record demand Once per hour group inoperable for one position indication for rods or more groups. with inoperable RPI.

B.2 Monitor and record reactor Once per hour coolant system average temperatUre.

B.3 Verify, using core power Once per 4 hours0.167 days 0.0238 weeks 0.00548 months distribution measurement information, position of rods with inoperable RPls which have been moved in excess of 24 steps in one direction since last determination of their position.

B.4 Restore inoperable RPls to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status such that a maximum of one RPI per group is inoperable.

Prairie Island Un~t 1 Amendment No. M& 20~ I Units 1 and 2 Umt 2 - Amendment No . .f.49 leu

Rod Position Indication 3.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Indication for one C. 1.1 Verify by administrative Once per 8 hours0.333 days 0.0476 weeks 0.011 months demand position per bank means all RPIs for the inoperable for one or affected bank(s) are more banks. OPERABLE.

AND C.1.2 Verify the rod position Once per 8 hours0.333 days 0.0476 weeks 0.011 months indication of the most withdrawn rod and the least withdrawn rod of the affected bank(s) are

12 steps apart.

OR C.2 Reduce THERMAL 8 hours0.333 days 0.0476 weeks 0.011 months POWER to s 50% RTP.

D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.1.7-3 Unit 2 - Amendment No. 149

Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify each RPI agrees within 12 steps of the group Once prior to demand position between 30 and 215 steps, or within criticality after 24 steps of the group demand position when the each removal of demand position is 2 215 steps or < 30 steps. the reactor head Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.1.7-4 Unit 2 - Amendment No. 149

PHYSICS TESTS Exceptions -MODE 2 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions-MODE 2 LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of LCO 3.1.3, "Isothermal Temperature Coefficient (ITC)";

LCO 3.1.4, "Rod Group Alignment Limits";

LCO 3.1.5, "Shutdown Bank Insertion Limits";

LCO 3.1.6, "Control Bank Insertion Limits"; and LCO 3.4.2, "RCS Minimum Temperature for Criticality" may be suspended and the number of required channels for LCO 3.3.1, "RTS Instrumentation," Functions 2, 3, 6, and 16.e may be reduced to I "3" required channels, provided:

a. RCS lowest loop average temperature is > 5350 F;

b. SDM is within the limits provided in the COLR; and

c. THERMAL POWER is < 5% RTP.

APPLICABILlTY: During PHYSICS TESTS initiated in MODE 2.

ACTIONS .

CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore 15 minutes SDM to within limit.

AND A.2 Suspend PHYSICS TESTS I hour exceptions.

Prairie Island Unit 1 - Amendment No. 162 Units I and 2 3.1.8-1 Unit 2 - Amendment No. 153

PHYSICS TESTS Exceptions - MODE 2 3.1.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. THERMAL POWER not B.1 Open reactor trip breakers. Immediately within limit.

C. RCS lowest loop average C.1 Restore RCS lowest loop 15 minutes temperature not within average temperature to limit. within limit.

D. Required Action and D.1 Be in MODE 3. 15 minutes associated Completion Time of Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Perform a CHANNEL OPERATIONAL TEST on Prior to initiation power range and intermediate range channels per of PHYSICS SR 3.3.1.7, SR 3.3.1.8, and Table 3.3.1-1. TESTS SR 3.1.8.2 Verify the RCS lowest loop average temperature is 30 minutes

Ž 535°F.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.1.8-2 Unit 2 - Amendment No. 149

PHYSICS TESTS Exceptions - MODE 2 3.1.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.8.3 Verify THERMAL POWER is

5% RTP. 30 minutes SR 3.1.8.4 Verify SDM is within the limits provided in the 24 hours1 days 0.143 weeks 0.0329 months COLR.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.1.8-3 Unit 2 - Amendment No. 149

F Q(Z) 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

LCO 3.2.1 F Q(Z), as approximated by F I (Z) and F Q(Z), shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.------- NOTE----------- A.1 Reduce THERMAL 15 minutes after Required Action A.4 POWER 2 1% RTP for each each F I (Z) shall be completed 1% Fc(Z) exceeds limit. determination whenever this Condition is entered. AND A.2 Reduce Power Range 72 hours3 days 0.429 weeks 0.0986 months after FQ(Z) not within limit. Neutron Flux-High trip each FQ(Z) setpoints 2 1% for each determination 1% Fc(Z) exceeds limit.

AND A.3 Reduce Overpower AT trip 72 hours3 days 0.429 weeks 0.0986 months after setpoints> 1% for each 1% each Fc (Z)

Fc(Z) exceeds limit. determination AND Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.2.1-1 Unit 2 - Amendment No. 149

FQ(Z) 3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Perform SR 3.2.1.1 and Prior to increasing SR 3.2.1.2. THERMAL POWER above the limit of Required Action A. I B. ----------- NOTE ----------- B.1 Reduce AFD limits>1% for 4 hours0.167 days 0.0238 weeks 0.00548 months after Required Action B.4 each 1%F (Z) exceeds each F I(Z) shall be completed limit. determination whenever this Condition is entered. AND B.2 Reduce Power Range 72 hours3 days 0.429 weeks 0.0986 months after FQ (Z) not within limits. Neutron Flux-High trip each F (Z) setpoints > 1% for each 1% determination that the maximum allowable power of the AFD limit is reduced.

AND B.3 Reduce Overpower AT trip 72 hours3 days 0.429 weeks 0.0986 months after setpoints > 1% for each 1% each F ' (Z) that the maximum allowable d power of the AFD limit is determination reduced.

AND Prairie Island Unit I - Amendment No. 162 Units 1 and 2 3.2.1-2 Unit 2 - Amendment No. 153

FQ(Z) 3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.4 Perform SR 3.2.1.1 and Prior to SR 3.2.1.2. increasing THERMAL POWER above the maximum allowable power of the AFD limits C. Required Action and C.1 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

Prairie Island Unit I - Amendment No. 162 Units 1 and 2 3.2.1-3 Unit 2 - Amendment No. 153

FQ(Z) 3.2.1 SURVEILLANCE REQUIREMENTS

.----------------.---w--------------------N()ll~--------------------------------------------------

During power escalation at the beginning of each cycle, llH~RMAL P()WER may be increased until an equilibrium power level has been achieved, at which a power distribution measurement is obtained.

SURV~ILLANC~ FREQUENCY SR 3.2.1.1 Verify Fg(Z) is within limit. ()nce after each refueling prior to llH~RMAL P()WER exceeding 75% RllP

()nce within 12 hours0.5 days 0.0714 weeks 0.0164 months after achieving equilibrium conditions after exceeding, by

> 10% RllP, the llI-IERMAL P()W~R at which F g(Z) was last verified 31 effective full power days

(~FPD) thereafter Prairie Island Unit 1 - Amendment No. +S-& ~01 I Units 1 and 2 3.2.1-4 Unit 2 - Amendment No. M-9 188

F Q(Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued SURVEILLANCE FREQUENCY SR 3.2.1.2 ----------------------------N O'fE---------------------------

If measurements indicate that the maximum overz [~gl]

has increased since the previous evaluation of F ~ (Z):

a. Increase F ~ (Z) by an appropriate factor specified in the COLR and reverify F ~ (Z) is within limits; or

b. Repeat SR 3.2.1.2 once per 7 EFPD until either a.

above is met or two successive power distribution measurements indicate that the maximum over z [ ~gll has not increased.

Verify F ~ (Z) is within limit. Once within 12 hours0.5 days 0.0714 weeks 0.0164 months after achieving eqUilibrium conditions after each refueling after THERMAL POWER exceeds 75%RTP Prairie Island Unit 1 - Amendment No. B-8 2011 Units 1 and 2 3.2.1-5 Unit 2 - Amendment No. +49 188

FQ(Z) 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.2 (continued) Once within 12 hours0.5 days 0.0714 weeks 0.0164 months after achieving equilibrium conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which F W(Z) was last verified AND 31 EFPD thereafter Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.2.1-6 Unit 2- Amendment No. 149

3N22 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FmN )

LCO 3.2.2 FN,, shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.-------- NOTE----------- A.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months Required Actions A.2 POWER to < 50% RTP.

and A.4 must be completed whenever AND Condition A is entered.

- A.2 Perform SR 3.2.2.1. 24 hours1 days 0.143 weeks 0.0329 months F not within limit. AND A.3 Reduce Power Range 72 hours3 days 0.429 weeks 0.0986 months Neutron Flux-High trip setpoints to

55% RTP.

AND Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.2.2-1 Unit 2 - Amendment No. 149

3N22 3.2.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 -------------NOTE-------------

THERMAL POWER does not have to be reduced to comply with this Required Action.

Perform SR 3.2.2.1. Prior to THERMAL POWER exceeding 50% RTP AND Prior to THERMAL POWER exceeding 75% RTP AND 24 hours1 days 0.143 weeks 0.0329 months after THERMAL POWER reaching

Ž95% RTP B. Required Action and B.1 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.2.2-2 Unit 2 - Amendment No. 149

2N 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify FAN, is within limits specified in the COLR. Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND 31 EFPD thereafter Prairie Island Unit I -Amendment No. 158 Units 1 and 2 3.2.2-3 Unit 2 - Amendment No. 149

AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD)

LCO 3.2.3 The AFD in % flux difference units shall be maintained within the limits specified in the COLR.

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

The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits.

APPLICABRITfY: MODE I with THERMAL POWER > 50% RTP.

ACTIONS =

CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits. A.1 Reduce THERMAL 30 minutes POWER to < 50% RTP.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD within limits for each OPERABLE 7 days excore channel.

Prairie Island Unit 1 - Amendment No. 162 Units I and 2 3.2.3-1 Unit 2 - Amendment No. 153

QPTR 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)

LCO 3.2.4 The QPTR shall be

1.02.

APPLICABILlTY: MODE I with THERMAL POWER > 50% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPTR not within limit. A.l Reduce THERMAL 2 hours0.0833 days 0.0119 weeks 0.00274 months after each POWER 2 3% from RTP QPTR for each 1% of QPTR determination

> 1.00.

AND A.2 Perform SR 3.2.4.1. Once per 12 hours0.5 days 0.0714 weeks 0.0164 months AND Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.2.4-1 Unit 2 - Amendment No. 149

QPTR 3.2.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 Perform SR 3.2.1. 1, SR 24 hours1 days 0.143 weeks 0.0329 months after 3.2.1.2 and SR 3.2.2.1. achieving equilibrium conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter.

AND A.4 Re-evaluate safety analyses Prior to and confirm results remain increasing valid for duration of THERMAL operation under this POWER above condition. the limit of Required Action A.1 AND Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.2.4-2 Unit 2 - Amendment No. 149

QPTR 3.2.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.5 ------------- NOTES------------

1. Perform Required Action A.5 only after Required Action A.4 is completed.

2. Required Action A.6 shall be completed when Required Action A.5 is performed.

Normalize excore detectors Prior to to restore QPTR to within increasing limits. THERMAL POWER above the limit of Required Action A.1 AND Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.2.4-3 Unit 2 - Amendment No. 149

QPTR 3.2.4 ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.6 ------------ NOTE-------------

Perform Required Action A.6 only after Required Action A.5 is completed.

Perform SR 3.2.1.1, SR Within 24 hours1 days 0.143 weeks 0.0329 months 3.2.1.2 and SR 3.2.2.1. after achieving equilibrium conditions at RTP not to exceed 48 hours2 days 0.286 weeks 0.0658 months after increasing THERMAL POWER above the limit of Required Action A.1 B. Required Action and B.1 Reduce THERMAL 4 hours0.167 days 0.0238 weeks 0.00548 months associated Completion POWER to s 50% RTP.

Time not met.

Prairie Island Unit I -Amendment No. 158 Units I and 2 3.2.4-4 Unit 2 - Amendment No. 149

QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 -------------------------N()TES-----------------------------

1. With input from one Power Range Neutron Flux channel inoperable and THERMAL P()WER

s 85% RTP, the remaining three power range channels can be used for calculating QPTR.

2. SR 3.2.4.2 may be performed in lieu of this Surveillance.

VerifY QPTR is within limit by calculation. 7 days SR 3.2.4.2 --------------------------N()TE-----------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL P()WER

> 85%RTP.

VerifY QPTR is within limit using core power 12 hours0.5 days 0.0714 weeks 0.0164 months distribution measurement information.

Prairie Island Unit 1 - Amendment No . .J-.§..8 2011 Units 1 and 2 3.2.4-5 Unit 2 - Amendment No. -l49 '188

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILHY: According to Table 3.3.1-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A. 1 Enter the Condition Immediately with one or more referenced in Table 3.3.1-1 required channels or for the channel(s) or train(s).

trains inoperable.

B. One Manual Reactor B.1 Restore channel to 48 hours2 days 0.286 weeks 0.0658 months Trip channel OPERABLE status.

inoperable.

OR B.2 Be in MODE 3. 54 hours2.25 days 0.321 weeks 0.074 months Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.3.1-1 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One channel or train C.1 Restore channel or train to 48 hours2 days 0.286 weeks 0.0658 months inoperable. OPERABLE status.

OR C.2.1 Initiate action to fully insert 48 hours2 days 0.286 weeks 0.0658 months all rods.

AND C.2.2 Place the Rod Control 49 hours2.042 days 0.292 weeks 0.0671 months System in a condition incapable of rod withdrawal.

D. One Power Range ---------------- NOTE---------------

Neutron Flux channel The inoperable channel may be inoperable. bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing and setpoint adjustment of other channels.

D.I.1 Place channel in trip. 6 hours0.25 days 0.0357 weeks 0.00822 months AND Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.1-2 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued) D.1.2 ------------ NOTE------------

Only required to be performed when THERMAL POWER is

> 85% RTP and the Power Range Neutron Flux input to QPTR is inoperable.

Perform SR 3.2.4.2. Once per 12 hours0.5 days 0.0714 weeks 0.0164 months OR D.2 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months E. One channel inoperable. ---------------- NOTE---------------

The inoperable channel may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing of other channels.

E.1 Place channel in trip. 6 hours0.25 days 0.0357 weeks 0.00822 months OR E.2 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.3.1-3 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME F. One Intermediate Range F. 1 Reduce THERMAL 24 hours1 days 0.143 weeks 0.0329 months Neutron Flux channel POWER to < P-6.

inoperable.

OR F.2 Increase THERMAL 24 hours1 days 0.143 weeks 0.0329 months POWER to > P-1 0.

G. Two Intermediate Range G.1 ------------ NOTE------------

Neutron Flux channels Limited plant cooldown or inoperable. boron dilution is allowed provided the change is accounted for in the calculated SDM.

Suspend operations Immediately involving positive reactivity additions.

AND G.2 Reduce THERMAL 2 hours0.0833 days 0.0119 weeks 0.00274 months POWER to < P-6.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.3.1-4 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. One Source Range H.l ----- NOTE------------

Neutron Flux channel Limited plant cooldown or inoperable. boron dilution is allowed provided the change is accounted for in the calculated SDM.

Suspend operations Immediately involving positive reactivity additions.

I. Two Source Range I.1 Open Reactor Trip Breakers Immediately Neutron Flux channels (RTBs).

inoperable.

J. One Source Range J.1 Restore channel to 48 hours2 days 0.286 weeks 0.0658 months Neutron Flux channel OPERABLE status.

inoperable.

OR J.2.1 Initiate action to fully insert 48 hours2 days 0.286 weeks 0.0658 months all rods.

AND J.2.2 Place the Rod Control 49 hours2.042 days 0.292 weeks 0.0671 months System in a condition incapable of rod withdrawal.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.3.1-5 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME K. One channel inoperable. ----------------- NOTE----------------

The inoperable channel may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing of other channels.

K.1 Place channel in trip. 6 hours0.25 days 0.0357 weeks 0.00822 months OR K.2 Reduce THERMAL 12 hours0.5 days 0.0714 weeks 0.0164 months POWER to < P-7 and P-8.

L. One or both channel(s) ----------------- NOTE ----------------

inoperable on one bus. One inoperable channel may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing of other channels.

L.1 Place channel(s) in trip. 6 hours0.25 days 0.0357 weeks 0.00822 months OR L.2 Reduce THERMAL 12 hours0.5 days 0.0714 weeks 0.0164 months POWER to < P-7 and P-8.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.3.1-6 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME M. One Reactor Coolant M.1 Restore channel to 48 hours2 days 0.286 weeks 0.0658 months Pump Breaker Open OPERABLE status.

channel inoperable.

OR M.2 Reduce THERMAL 54 hours2.25 days 0.321 weeks 0.074 months POWER to < P-7 and P-8.

N. One Turbine Trip ----------------- NOTE ----------------

channel inoperable The inoperable channel may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing of other channel(s).

N. 1 Place channel in trip. 6 hours0.25 days 0.0357 weeks 0.00822 months OR N.2 Reduce THERMAL 12 hours0.5 days 0.0714 weeks 0.0164 months POWER to < P-9.

Prairie Island Unit I -Amendment No. 158 Units I and 2 3.3.1-7 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

0. One train inoperable. ----------------- NOTE----------------

One train may be bypassed for up to 8 hours0.333 days 0.0476 weeks 0.011 months for surveillance testing provided the other train is OPERABLE.

0.1 Restore train to 6 hours0.25 days 0.0357 weeks 0.00822 months OPERABLE status.

OR 0.2 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months P. One RTB train ---------------- NOTES---------------

inoperable. 1. One train may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing, provided the other train is OPERABLE.

2. One RTB may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for maintenance on undervoltage or shunt trip mechanisms, provided the other train is OPERABLE.

P.1 Restore train to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE status.

OR P.2 Be in MODE 3. 7 hours0.292 days 0.0417 weeks 0.00959 months Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.1-8 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Q. One or more channels Q.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit conditions.

OR Q.2 Be in MODE 3. 7 hours0.292 days 0.0417 weeks 0.00959 months R. One or more channels R.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit conditions.

OR R.2 Be in MODE 2. 7 hours0.292 days 0.0417 weeks 0.00959 months S. One trip mechanism S.1 Restore inoperable trip 48 hours2 days 0.286 weeks 0.0658 months inoperable for one RTB. mechanism to OPERABLE status.

OR S.2 Be in MODE 3. 54 hours2.25 days 0.321 weeks 0.074 months Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.3.1-9 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1- 1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.1.2 --------------------------- NOTES----------------------------

1. Adjust NIS channel if absolute difference is

>2%.

2. Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after THERMAL POWER is Ž 15% RTP.

Compare results of calorimetric heat balance 24 hours1 days 0.143 weeks 0.0329 months calculation to Nuclear Instrumentation System (NIS) channel output.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.3.1-10 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued SURVEILLANCE FREQUENCY SR 3.3.1.3 -.-------------------------NOTES--------------------------

1. Adjust NIS channel if absolute difference is

>2%.

2. Not required to be performed until 72 hours3 days 0.429 weeks 0.0986 months after THERMAL POWER is 2: 15% RTP.

Compare results of the core power distribution 31 effective full measurements to NfS AFD. power days (EFPD)

SR 3.3.1.4 -----------------------r----NOTE--------------------------

This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.

Perform T ADOT. 31 days on a STAGGERED TEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS Prairie Island Unit 1 Amendment No. .g.g 2011 Units 1 and 2 3.3.1-11 Unit 2 - Amendment No. +49 188

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS continued)

SURVEILLANCE FREQUENCY SR 3.3.1.6 ----------------------------NOTE---------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after THERMAL POWER is ~ 75% RTP.

Calibrate excore channels to agree with core power 92 EFPD distribution measurements.

SR 3.3.1. 7 ---------------------------NOTE---------------------------

Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours0.167 days 0.0238 weeks 0.00548 months after entry into MODE 3.

Perfonn COT.

92 da s Prairie Island Unit 1 Amendment No . .g.g 201 1 Units 1 and 2 Unit 2 - Amendment No. i49 188

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE IFREQUENCY SR 3.3.1.8 ---------------------------- NOTES-------------------------- ------- NOTE------

1. This Surveillance shall include verification that Only required interlocks P-6 and P-1 0 are in their required state when not for existing unit conditions. performed within previous 92 days

2. Not required to be performed for intermediate and source range instrumentation prior to reactor startup following shutdown - 48 hours2 days 0.286 weeks 0.0658 months .

Perform COT. Prior to reactor startup AND Twelve hours after reducing power below P-10 for power and intermediate range instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND Every 92 days thereafter Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.1-13 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.9 --------------------- NOTE----------------------------

Verification of setpoint is not required.

Perform TADOT. 92 days SR 3.3.1.10 --------------------------- NOTE-----------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.11 -------------------------- NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 24 months Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.1-14 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued) .

SURVEILLANCE FREQUENCY SR 3.3.1.12 ---------------------------- NOTE----------------------------

This Surveillance shall include verification of Reactor Coolant System resistance temperature detector bypass loop flow rate.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.13 Perform COT. 24 months SR 3.3.1.14 ---------------------------- NOTE----------------------------

Verification of setpoint is not required.

Perform TADOT. 24 months SR 3.3.1.15 ---------------------------- NOTE----------------------------

Verification of setpoint is not required.

Perform TADOT. Prior to exceeding the P-9 interlock whenever the unit has been in MODE 3, if not performed within the previous 31 days Prairie Island Unit I -Amendment No. 158 Units I and 2 3.3.1-15 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.16 ---------------------------- NNOTE----------------------------

Neutron detectors are excluded from response time testing.

Verify RTS RESPONSE TIME is within limits. 24 months Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.3.1-16 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 Table3.3.1-1 (page I of 8)

Reactor Trip Syrtem Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

1. Manual Reactor 1,2 2 B SR 3.3.1.14 NA Trip 3 (a), 4 (a), 5 (a) 2 C SR 3.3.1.14 NA

2. Power Range Neutron Flux

a. High 1,2 4 D SR 3.3.1.1 s 110%RTP SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16

b. Low 4 D SR 3.3.1.1 s 40% RTP SR 3.3.1.8 SR 3.3.1.1 1 SR 3.3.1.16

3. Power Range Neutron Flux Rate

a. High Positive 1,2 4 D SR 3.3.1.7 s 6% RTP with Rate SR 3.3.1.11 time constant SR 3.3.1.16 2 2 sec

b. High 1,2 4 D SR 3.3.1.7 s 8% RTP with Negative Rate SR 3.3.1.11 time constant SR 3.3.1.16 2 2 sec

4. Intermediate 2 F, G SR 3.3.1.1 s 40% RTP 1 (b) 2(c)

Range Neutron SR 3.3.1.8 Flux SR 3.3.1.11 (a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(b) Below the P-1 0 (Power Range Neutron Flux) interlocks.

(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.3.1-17 Unit 2 - Amendment No. 149

RTS Instnimentation 3.3.1 Table 3.3.1-1 (page 2 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE S. Source Range 2 (d) 2 HI SR 3.3.1.1 < L.0E6 cps Neutron Flux SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16 3 (a), 4 (a), 5 (a) 2 1,3 SR 3.3.1.1 < 1.0E6 cps SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16

6. Overtemperature AT 1,2 4 E SR 3.3.1.1 Refer to Note I SR 3.3.1.3 (Page 3.3.1-23)

SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.12 SR 3.3.1.16

7. Overpower AT 1,2 4 E SR 3.3.1.1 Refer to SR 3.3.1.7 Note 2 (Page SR 3.3.1.12 3.3.1-24)

I SR 3.3.1.16

8. Pressurizer Pressure

a. Low I(e) 4 K SR 3.3.1.1 > 1845 psig SR 3.3.1.7 SR 3.3.1.10

b. High 1,2 3 E SR 3.3.1.1 < 2400 psig SR 3.3.1.7 SR 3.3.1.10 (a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(e) Above the P-7 (Low Power Reactor Trips Block) interlock.

Prairie Island Unit 1 - Amendment No. 162 Units I and 2 3.3.1-18 Unit 2 - Amendment No. 153

RTS Instrumentation 3.3.1 Table 3.3.1-I (page 3 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

9. Pressurizer Water l(e) 3 K SR 3.3.1.1 s 90%

Level - High SR 3.3.1.7 SR 3.3.1.10

10. ReactorCoolant l(f) 3per loop K SR 3.3.1.1 > 91%

Flow- Low SR 3.3.1.7 SR 3.3.1.10

11. Loss of Reactor Coolant Pump (RCP)

a. RCP Breaker (f) I per RCP M SR 3.3.1.14 NA Open

b. Under- I(f) 2 per bus L SR 3.3.1.9 2 58.2 Hz frequency SR 3.3.1.10

,)

4 kV Buses 11 and 12 (21 and 22)

12. Undervoltage on l(e) 2 per bus L SR 3.3.1.9 2 76% rated 4 kV Buses 11 SR 3.3.1.10 bus voltage and 12 (21 and 22) 1,2 3 per SG E SR 3.3.1.1

13. Steam SR 3.3.1.7 2 11.3%

Generator (SG) SR 3.3. 1.10 Water Level -

Low Low (e) Above the P-7 (Low Power Reactor Trips Block) interlock.

(I Above the P-8 (Power Range Neutron Flux) or P-7 (Low Power Reactor Trips Block) interlocks.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 .3.3.1-19 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

14. Turbine Trip

a. LowAutostopOil l(g) 3 N SR3.3.1. I0 45psig Pressure SR 3.3.1.15

b. Turbine Stop l(g) 2 N SR3.3.1.10 Closed Valve Closure SR 3.3.1.15

15. Safetylnjection(SI) 1,2 2trains 0 SR3.3.1.14 NA Input from Engineered Safety Feature Actuation System (ESFAS)

(g) Above the P-9 (Power Range Neutron Flux) interlock.

Prairie Island Unit I -Amendment No. 158 Units I and 2 3.3.1-20 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 8)

Reactor Trip Syrtem Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

16. Reactor Trip System Interlocks

a. Intermediate 2 (d) 2 Q SR 3.3.1.11 z 1.OE-10 amp Range Neutron SR 3.3.1.13 Flux, P-6

b. Low Power Reactor Trips Block, P-7 1.PowerRange 1 4 R SR 3.3.1.11 s 12%RTP Neutron Flux SR 3.3.1.13

2. Turbine Impulse 1 2 R SR 3.3.1.7 s 12% Full Pressure SR 3.3.1.10 Load

c. Power Range 1 4 R SR 3.3.1.11 ll%RTP Neutron Flux, P-S SR 3.3.1.13

d. Power Range 1 4 R SR 3.3.1.11 s 12%RTP Neutron Flux, P-9 SR 3.3.1.13

e. Power Range 1,2 4 Q SR 3.3.1.1 1 k 9% RTP Neutron Flux, P-1I SR 3.3.1.13

17. ReactorTrip 1,2 2trains P SR3.3.1.4 NA Breakers(h) (RTBs) 3 (a), 4(a), 5 (a) 2 trains C SR 3.3.1.4 NA (a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(h) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.1-21 Unit 2 - Amendment No. 149

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

18. ReactorTripBreaker 1,2 1 each per S SR 3.3.1.4 NA Undervoltage and Shunt RTB Trip Mechanisms 3 (a),4(a), 5 (a) l each per C SR 3.3.1.4 NA RTB

19. Automatic Trip Logic 1,2 2 trains 0 SR 3.3.1.5 NA 3(a),4(a) (a) 2 trains C SR 3.3.1.5 NA (a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.3.1-22 Unit 2 - Amendment No. 149

RTS Instrimentation 3.3.1 Table 3.3.1-1 (page 7 of 8)

Reactor Trip System Instrumentation Note 1: Overtemperature AT The Overtemperature AT Function Allowable Value is defined by the following Trip Setpoint.

AT < ATo{K1 -K 2 (T- T')[( 1 +ris) + K 3 (P - P') - f(AI)}

Where: AT is measured Reactor Coolant System (RCS) AT, 'F.

ATo is the indicated AT at RTP, 'F.

s is the Laplace transform operator, see-'.

T is the measured RCS average temperature, OF.

T' is the nominal Tavg at RTP, = *OF.

P is the measured pressurizer pressure, psig P'is the nominal RCS operating pressure,

psig Ki <

K 2 = */'F K3 = */psig T =

sec 2=

sec f(AI) =*{* + (qt - qb)} when q, - qb < *% RTP

% of RTP when *% RTP < qt - qb <*% RTP

{(qt - qb) - *}when qt - qb > *% RTP Where q, and qb are percent RTP in the upper and lower halves of the core, respectively, and q, + qb is the total THERMAL POWER in percent RTP.

As specified in the COLR.

Prairie Island Unit I - Amendment No. 162 Units l and 2 3.3.1-23 Unit 2 - Amendment No. 153

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 8 of 8)

Reactor Trip System Instrumentation Note 2: Overmower AT The Overpower AT Function Allowable Value is defined by the following Trip Setpoint.

I AT* ATo{K 4 - K 5 1+T3 s _ K6(T-T')}

Where: AT is measured RCS AT, IF.

ATo is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec' .

T is the measured RCS average temperature, OF.

T' is the nominal Tavg at RTP, = *'F. I I

K5 = */'F for increasing Tavg

= */'F for decreasing Tavg I K6 = */'F when T > T'

*/'F when T < T' yr3

sec I I

I

As specified in the COLR.

Prairie Island Unit 1 - Amendment No. 162 Units 1 and 2 3.3.1-24 Unit 2 - Amendment No. 153

ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILflY: According to Table 3.3.2-1.

ACTIONS

NOTE--------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.2-1 required channels or for the channel(s) or trains inoperable. train(s).

B. One channel or train B.l Restore channel or train to 48 hours2 days 0.286 weeks 0.0658 months inoperable. OPERABLE status.

OR B.2.1 Be in MODE 3. 54 hours2.25 days 0.321 weeks 0.074 months AND B.2.2 Be in MODE 5. 84 hours3.5 days 0.5 weeks 0.115 months Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.3.2-1 Unit 2 - Amendment No. 149

ESFAS Instrumentation 3.3.2 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable. ----------------- NOTE ----------------

One train may be bypassed for up to 8 hours0.333 days 0.0476 weeks 0.011 months for surveillance testing provided the other train is OPERABLE.

C.1 Restore train to 6 hours0.25 days 0.0357 weeks 0.00822 months OPERABLE status.

OR C.2.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months AND C.2.2 Be in MODE 5. 42 hours1.75 days 0.25 weeks 0.0575 months D. One channel inoperable. ----------------- NOTE----------------

The inoperable channel may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing of other channels.

D.1 Place channel in trip. 6 hours0.25 days 0.0357 weeks 0.00822 months OR D.2.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months AND D.2.2 Be in MODE 4. 18 hours0.75 days 0.107 weeks 0.0247 months Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.2-2 Unit 2 - Amendment No. 149

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more ----------------- NOTE----------------

Containment Pressure One channel may be bypassed for channel(s) inoperable. up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing.

E.].1 Place inoperable 6 hours0.25 days 0.0357 weeks 0.00822 months channel(s) in trip.

AND E.1.2 Verify one channel per 6 hours0.25 days 0.0357 weeks 0.00822 months pair OPERABLE.

OR E.2.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months AND E.2.2 Be in MODE 4. 18 hours0.75 days 0.107 weeks 0.0247 months Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.2-3 Unit 2 - Amendment No. 149

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. One channel or train F. 1 Restore channel or train to 48 hours2 days 0.286 weeks 0.0658 months inoperable. OPERABLE status.

OR F.2.1 Be in MODE 3. 54 hours2.25 days 0.321 weeks 0.074 months AND F.2.2 Be in MODE 4. 60 hours2.5 days 0.357 weeks 0.0822 months

4-G. One train inoperable. ----------------- NOTE----------------

One train may be bypassed for up to 8 hours0.333 days 0.0476 weeks 0.011 months for surveillance testing provided the other train is OPERABLE.

G.1 Restore train to 6 hours0.25 days 0.0357 weeks 0.00822 months OPERABLE status.

OR G.2.1 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months AND G.2.2 Be in MODE 4. 18 hours0.75 days 0.107 weeks 0.0247 months Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.3.2-4 Unit 2 - Amendment No. 149

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. One channel ------------------NOTE----------------

inoperable. The inoperable channel may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing of other channels.

H.1 Place channel in trip. 6 hours0.25 days 0.0357 weeks 0.00822 months OR H.2 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months I. One or both channel(s) ----------------- NOTE----------------

inoperable on one bus. One inoperable channel may be bypassed for up to 4 hours0.167 days 0.0238 weeks 0.00548 months for surveillance testing of other channels.

I.1 Place channel(s) in trip. 6 hours0.25 days 0.0357 weeks 0.00822 months OR 1.2 Be in MODE 3. 12 hours0.5 days 0.0714 weeks 0.0164 months Prairie Island Unit I -Amendment No. 158 Units I and 2 3.3.2-5 Unit 2 - Amendment No. 149

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. One train inoperable. ----------------- NOTE----------------

One train may be bypassed for up to 8 hours0.333 days 0.0476 weeks 0.011 months for surveillance testing provided the other train is OPERABLE.

J.1 Enter applicable Immediately Condition(s) and Required Action(s) for Auxiliary Feedwater (AFW) train made inoperable by ESFAS instrumentation.

K. One channel inoperable. K.1 Enter applicable Immediately Condition(s) and Required Action(s) for Auxiliary Feedwater (AFW) pump made inoperable by ESFAS instrumentation.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.3.2-6 Unit 2 - Amendment No. 149

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.

SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.2.2 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.2.3 Perform COT. 92 days SR 3.3.2.4 --------------------------- NOTE----------------------------

Verification of setpoint not required.

Perform TADOT. 24 months Prairie Island Unit I - Amendment No. 158 Units I and 2 3.3.2-7 Unit 2 - Amendment No. 149

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.5 ---------------------- NOTE----------------------------

Verification of setpoint not required.

Perform TADOT. 24 months on a STAGGERED TEST BASIS SR 3.3.2.6 ---------------------------- NOTE----------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.2.7 Perform MASTER RELAY TEST. 24 months SR 3.3.2.8 Perform SLAVE RELAY TEST. 24 months Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.2-8 Unit 2 - Amendment No. 149

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 4)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

1. Safety Injection

a. Manual 1,2,3,4 2 B SR 3.3.2.5 NA Initiation

b. Automatic 1,2,3,4 2 trains C SR 3.3.2.2 NA Actuation SR 3.3.2.8 Relay Logic

c. High 1,2,3 3 D SR 3.3.2.1 s4.0psig Containment SR 3.3.2.3 Pressure SR 3.3.2.6

d. Pressurizer 1 ,2 , 3 (a) 3 D SR 3.3.2.1 2 1760 psig Low Pressure SR 3.3.2.3 SR 3.3.2.6

e. Steam Line 1,2, 3 (a) 3 per steam D SR 3.3.2.1 2 S00(b)psig Low Pressure line SR 3.3.2.3 SR 3.3.2.6

2. Containment Spray

a. Manual 1,2,3,4 2 B SR 3.3.2.4 NA Initiation

b. Automatic 1,2,3,4 2trains C SR 3.3.2.2 NA Actuation SR 3.3.2.8 Relay Logic (a) Pressurizer Pressure 2 2000 psig.

(b) Time constants used in the lead/lag controller are t1 2 12 seconds and t2 s 2 seconds.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.3.2-9 Unit 2 - Amendment No. 149

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 4)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

2. Containment Spray (continued)

c. High-High 1,2,3 3 sets of 2 E SR 3.3.2.1 %23 psig Containment SR 3.3.2.3 Pressure SR 3.3.2.6

3. Containment Isolation

a. Manual 1,2,3,4 2 B SR 3.3.2.4 NA Initiation

b. Automatic 1,2,3,4 2 trains C SR 3.3.2.2 NA Actuation SR 3.3.2.8 Relay Logic

c. Safety Refer to Function I (Safety Injection) for all initiation functions and requirements.

Injection

4. Steam Line Isolation

a. Manual I, 2(c), 3(c) I/loop F SR 3.3.2.4 NA Initiation

b. Automatic 1, 2(c), 3(c) 2 trains G SR 3.3.2.2 NA Actuation SR 3.3.2.7 Relay Logic

c. High-High 1, 2(c), 3(c) 3 D SR 3.3.2.1 s 17psig Containment SR 3.3.2.3 Pressure SR 3.3.2.6 (c) Except when both Main Steam Isolation Valves (MSIVs) are closed.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.3.2-10 Unit 2-Amendment No. 149

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 4)

Engineered Safety Feature Actuation System Instrumentation-APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE' FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

4. Steam Line Isolation (continued)

d. High Steam 1, 2(c), 3(c)(d) 2 per steam D SR 3.3.2.1 < 9.18E5 lb/hr at Flow line SR 3.3.2.3 1005 psig SR 3.3.2.6 Coincident Refer to Function I (Safety Injection) for all initiation functions and requirements.

with Safety Injection and.

Coincident 1, 2(c), 3(c)(d) 4 D SR 3.3.2.1 2 5360 F with Low-Low SR 3.3.2.3 Tzvg SR 3.3.2.6

e. High High I, 2(c), 3(c) 2 per steam .D SR 3.3.2.1 s 4.5E6 lb/hr at Steam Flow line SR 3.3.2.3 735 psig SR 3.3.2.6 Coincident Refer to Function I (Safety Injection) for all initiation functions and requirements.

with Safety Injection

5. Feedwater Isolation

a. Automatic I ,2 (e), 3 (e) 2 trains G SR 3.3.2.2 NA Actuation SR 3.3.2.7 Relay Logic

b. High- High 1, 2 (e) 3 per SG H SR 3.3.2.1 &90%

Steam SR 3.3.2.3 Generator (SG) SR 3.3.2.6 WVater Level (c) Except when both MSIVs are closed.

(d) Reactor Coolant System (RCS) T., 2: 5207F (e) Except when all Main Feedwater Regulation Valves (MFRVs) and MFRV bypass valves are closed and de-activated or isolated by a closed manual valve.

Prairie Island Unit I -Amendment No. 158 Units I and 2 3.3.2-11 Unit 2 - Amendment No. 149

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 4)

Engineered Safety Featur: %ctuzition System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

5. Feedwater Isolation (continued)

c. Safety Refer to Function I (Safety Injection) for all initiation functions and requirements.

Injection

6. Auwiliarv Feedwater

a. Automatic 1,2,3 2 trains J SR 3.3.2.2 NA Actuation Relay Logic

b. Low-LowSG 1,2,3 3perSG D SR 3.3.2.1 k 11.3%

Water Level SR 3.3.2.3 SR 3.3.2.6

c. Safety Refer to Function I (Safety Injection) for all initiation functions and requirements.

Injection

d. Undervoltage 1, 2 2 per bus I SR 3.3.2.4 2 76% rated bus on 4 kV Buses SR 3.3.2.6 voltage II and 12 (21 and 22)(f)

e. Trip of both 1, 2(g) 2 per pump IK SR 3.3.2.4 NA Main Feedwater Pumps (f) Start of Turbine Driven Pump only.

(g) This Function may be bypassed during alignment and operation of the AFW System for SG level control.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.3.2-12 Unit 2 - Amendment No. 149

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

APPLICABILITY: MODES I and 2.

ACTIONS

NOTE---------

Separate Condition entry is allowed for each Function.

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

exit temperature Function.

One or more Functions with one required channel inoperable.

Prairie Island Unit 1 - Amendment No. 4548, 167l Units I and 2 3.3.3-1 Unit 2 - Amendment No. 449, 1571

EM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more required B.l Restore required CET 30 days Core Exit Thermocouple channel(s) to OPERABLE (CET) channel(s) status.

inoperable.

AND At least 4 CET channels OPERABLE in the center region of the core.

AND At least one CET channel OPERABLE in each quadrant of the outside core region.

C. Required Action and C. I Initiate action in Immediately associated Completion accordance with Time of Condition A or B Specification 5.6.8.

not met.

D . ---------- NOTE ------------ D.l Restore one channel to 7 days Not applicable to CET OPERABLE status.

channels.

One or more Functions with two required channels inoperable.

Prairie Island Unit 1 - Amendment No. 44S 163 Units I and 2 3.3.3-2 Unit 2 - Amendment No. 449 154

EM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Three or more required E. 1 Restore required channels 7 days CET channels inoperable to OPERABLE status.

in one or more quadrants.

AND Less than four CETs OPERABLE in the center region of the core.

F. Three or more required F. 1 Restore required channels 7 days CET channels inoperable to OPERABLE status.

in one or more quadrants.

AND Less than one CET OPERABLE in each quadrant of the outside core region.

G. Required Action and G.1 Enter the Condition Immediately associated Completion referenced in Table 3.3.3-1 Time of Condition D, E, for the channel.

or F not met.

Prairie Island Unit I -AmendmentNo. 4-54 163 Units I and 2 3.3.3-3 Unit 2 - Amendment No. 44911 154

EM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. As required by Required H.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Action G.1 and referenced in Table 3.3.3-1.

I. As required by Required L.1 Initiate action in Immediately Action G.1 and accordance with referenced in Specification 5.6.8.

Table 3.3.3-1.

Prairie Island Unit I - Amendment No. 4-5& 163 Units I and 2 3.3.3-4 Unit 2 - Amendment No. 449 1154

EM Instrumentation 3.3.3 SURVEILLANCE REQUIREMENTS

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

SR 3.3.3.1 and SR 3.3.3.2 apply to each EM instrumentation Function in Table 3.3.3-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.3.2 -------------------------NOTE---------------------------- I Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 24 months Prairie Island Unit I - Amendment No. 459 163 Units I and 2 3.3.3-5 Unit 2 - Amendment No. 449 154

EM Instnimentation 3.3.3 Table 3.3.3-1 (page I of 1)

Event Monitoring Instrumentation CONDbT -ON REFERENCED FROM FUNCTION REQUIRED REQUIRED ACTION CHANNELS G.1

1. Power Range Neutron Flux (Logarithmic Scale) 2 H

2. Source Range Neutron Flux (Logarithmic Scale) 2 H

3. Reactor Coolant System (RCS) Hot Leg Temperature 2 H

4. RCS Cold Leg Temperature 2 H

5. RCS Pressure (Wide Range) 2 H

6. Reactor Vessel Water Level 2 I

7. Containment Sump Water Level (Wide Range) 2 H

8. Containment Pressure (Wide Range) 2 H

9. Penetration Flow Path Automatic Containment 2 per penetration flow H Isolation Valve Position path(a)(b)

10. Containment Area Radiation (High Range) 2 I

11. Not used

12. Pressurizer Level 2 H4 I

13. Steam Generator Water Level (Wide Range) 2 per steam generator H I

14. Condensate Storage Tank Level 2 H I

15. Core Exit Temperature 4 per quadrant(C) H I

16. Refueling Water Storage Tank Level 2 H I (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of one core exit thermocouple (CET).

Prairie Island Unit 1- Amendment No. 445 1 163 Units I and 2 3.3.3-6 Unit 2 - Amendment No. 449 1-154

4 kV Safeguards Bus Voltage Instrumentation 3.3.4 3.3 INSTRUMENTATION 3.3.4 4 kV Safeguards Bus Voltage Instrumentation LCO 3.3.4 The following 4 kV safeguards bus voltage instrumentation Functions shall be OPERABLE:

a. Four channels per bus of the undervoltage Function;

b. Four channels per bus of the degraded voltage Function; and

c. One automatic load sequencer per bus.

APPLICABILITY MODES 1, 2, 3, and 4, When associated Diesel Generator (DG) is required to be OPERABLE by LCO 3.8.2, "AC Sources-Shutdowm."

ACTIONS

NOT] r.--------------------------

Separate Condition entry is allowed for each Fi CONDITION REQUIRED ACTION COMPLETION TIME A. ------------ NOTE----------- A.1 Place channel in bypass. 6 hours0.25 days 0.0357 weeks 0.00822 months Only applicable to Functions a and b.

One or more Functions with one channel per bus inoperable.

Prairie Island Unit I -Amendment No. 158 Units 1 and 2 3.3.4-1 Unit 2 - Amendment No. 149

4 kAV Safeguards Bus Voltage Instrumentation 3.3.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.---------- NOTE--------- B.1 Place one channel in bypass 6 hours0.25 days 0.0357 weeks 0.00822 months Only applicable to and place one channel in Functions a and b. trip.

AND One or more Functions with two channels per B.2 Verify all channels 6 hours0.25 days 0.0357 weeks 0.00822 months bus inoperable. associated with redundant load sequencer are OPERABLE.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.4-2 Unit 2 - Amendment No. 149

4 kV Safeguards Bus Voltage Instrumentation 3.3.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ------------NOTE ------ C.l Perform SR 3.3.4.2 for 6 hours0.25 days 0.0357 weeks 0.00822 months Only applicable in OPERABLE automatic MODE 1, 2, 3, or 4. load sequencer. AND Once per 24 hours1 days 0.143 weeks 0.0329 months Required Action and thereafter associated Completion Time of Condition A or B AND not met.

C.2 Establish offsite paths block 8 hours0.333 days 0.0476 weeks 0.011 months OR loading capability for associated 4 kV safeguards Function a or b or both bus.

with three channels per AND bus inoperable.

C.3 Verify offsite paths for 8 hours0.333 days 0.0476 weeks 0.011 months OR associated 4kV safeguards bus OPERABLE. AND One required automatic load sequencer Once per 8 hours0.333 days 0.0476 weeks 0.011 months inoperable. thereafter AND C.4 Declare required feature(s) 4 hours0.167 days 0.0238 weeks 0.00548 months from supported by the affected discovery of inoperable DG inoperable Condition C when its required redundant concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)

AND C.5 Restore automatic load 7 days sequencer to OPERABLE status.

Prairie Island Unit I -Amendment No. 158 Units 1 and 2 3.3.4-3 Unit 2 - Amendment No. 149

4 kV Safeguards Bus Voltage Instrumentation 3.3.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition C not AND met.

D.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months E.------- NOTE----------- E.1 Enter applicable Immediately Only applicable in Condition(s) and Required MODES 5 or 6. Action(s) of LCO 3.8.2, "AC Sources - Shutdown" Required Action and for the DG made inoperable associated Completion from inoperable 4 kV Time of Condition A or safeguards bus voltage B not met. instrumentation.

OR Function a or b or both with three channels per bus inoperable.

OR One required automatic load sequencer inoperable.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.3.4-4 Unit 2 - Amendment No. 149

4 kV Safeguards Bus Voltage Instrumentation 3.3.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform COT on each undervoltage and degraded 31 days voltage channel.

SR 3.3.4.2 Perform ACTUATION LOGIC TEST on each 31 days automatic load sequencer.

SR 3.3.4.3 Perform CHANNEL CALIBRATION on 24 months undervoltage and degraded voltage channels with Allowable Value as follows:

a. Undervoltage Allowable Value 2 3016 V and

5 3224 V with an undervoltage time delay of 4 + 1.5 seconds.

b. Degraded voltage Allowable Value 2 3944 V and s 4002 V with a degraded voltage time delay of 8 +/- 0.5 seconds and degraded voltage DG start time delay of 7.5 to 63 seconds.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.4-5 Unit 2 - Amendment No. 149

Not Used 3.3.5 3.3 INSTRUMENTATION 3.3.5 Not used Prairie Island Unit 1 - Amendment No. ~ 191 Units I and 2 3.3.5-1 Unit 2 - Amendment No. -l-49 180

CRSVS Actuation Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Control Room Special Ventilation System (CRSVS) Actuation Instrumentation LCO0 3.3.6 The CRSVS actuation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6-1.

ACTIONS

NOTE---------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Place one CRSVS train in 7 days with one channel operation and close the inoperable. opposite train outside air dampers.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.3.6-1 Unit 2 - Amendment No. 149

CRSVS Actuation Instrumentation 3.3.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions B.l Enter applicable Immediately with two channels Conditions and Required inoperable. Actions for two CRSVS trains made inoperable by inoperable CRSVS actuation instrumentation.

OR B.2 Place both trains in Immediately operation.

C. Required Action and C.] Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time for Condition A AND or B not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months D. Required Action and D.1 Suspend movement of Immediately associated Completion irradiated fuel assemblies.

Time for Condition A or B not met during movement of irradiated fuel assemblies.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.3.6-2 Unit 2 - Amendment No. 149

CRSVS Actuation Instrumentation 3.3.6 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.6-1 to determine which SRs apply for each CRSVS Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.6.2 Perform COT. 92 days SR 3.3.6.3 ---------------------- NOTE----------------------

Verification of setpoint is not required.

Perform TADOT. 24 months SR 3.3.6.4 Perform CHANNEL CALIBRATION. 24 months Prairie Island Unit 1-Amendment No. 158 Units I and 2 3.3.6-3 Unit 2 - Amendment No. 149

CRSVS Actuation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of I)

CRSVS Actuation Instrumentation APPLICABLE MODES OR OTHER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION SPECIFIED CONDITIONS CHANNELS REQUIREMENTS VALUE

1. Manual Initiation 1,2,3,4 2 SR 3.3.6.3 NA (a)

2. Control Room 1,2,3,4 2 SR 3.3.6.1 5 times Radiation - (a) SR 3.3.6.2 background Atmosphere SR 3.3.6.4

3. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function I, for all initiation functions and requirements.

(a) During movement of irradiated fuel assemblies.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.6-4 Unit 2 - Amendment No. 149

SFPSVS Actuation Instrumentation 3.3.7 3.3 INSTRUMENTATION 3.3.7 Spent Fuel Pool Special Ventilation System (SFPSVS) Actuation Instrumentation LCO 3.3.7 The SFPSVS actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.7-1.

ACTIONS

NOT]E--------------------

LCO 3.0.3 .is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable. A.1 Place one SFPSVS train in 7 days operation.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.3.7-1 Unit 2 - Amendment No. 149

SFPSVS Actuation Instrumentation 3.3.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two channels inoperable. B.1.1 Place one SFPSVS train Immediately in operation.

AND B.I.2 Enter applicable Immediately Conditions and Required Actions of LCO 3.7.13, "Spent Fuel Pool Special Ventilation System (SFPSVS)," for one train made inoperable by inoperable actuation instrumentation.

OR B.2 Place both trains in Immediately operation.

C. Required Action and C.1 Suspend movement of Immediately associated Completion irradiated fuel assemblies Time for Condition A in the fuel pool enclosure.

or B not met during movement of irradiated fuel assemblies in the fuel pool enclosure.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.3.7-2 Unit 2 - Amendment No. 149

SFPSVS Actuation Instrumentation 3.3.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.3.7.2 Perform COT. 92 days SR 3.3.7.3 Perform CHANNEL CALIBRATION. 24 months Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.3.7-3 Unit 2 - Amendment No. 149

SFPSVS Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page I of i)

SFPSVS Actuation Instrumentation APPLICABLE MODES OR SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE I. Fuel Pool (a) I per train SR 3.3.7.1 (b)

Enclosure SR 3.3.7.2 Radiation SR 3.3.7.3 (a) During movement of irradiated fuel assemblies in the fuel pool encbsure.

(b) This value provided by the ODCM.

Prairie Island Unit 1 - Amendment No. 4-58 180 Units i and 2 I) I '7_A Unit 2 - A. endment No. 4.49 170

RCS Pressure, Temperature, and Flow - DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow -Departure from Nucleate Boiling (DNB)

Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified below:

a. Pressurizer pressure 2 the limit specified in the COLR;

b. RCS average temperature < the limit specified in the COLR; and

c. RCS total flowv rate 2 the value specified in the COLR.

APPLICABILITY: MODE 1.

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

Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute; or

b. THERMAL POWER step> 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB A.1 Restore RCS DNB 2 hours0.0833 days 0.0119 weeks 0.00274 months parameters not within parameter(s) to within limit.

limits.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.4.1-1 Unit 2 - Amendment No. 149

RCS Pressure, Temperature, and Flow - DNB Limits 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.11 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1 .1 Verify pressurizer pressure is greater than or equal 12 hours0.5 days 0.0714 weeks 0.0164 months to the limit specified in the COLR.

SR 3.4.1.2 Verify RCS average temperature is less than or 12 hours0.5 days 0.0714 weeks 0.0164 months equal to the limit specified in the COLR.

SR 3.4.1.3 -------------------------- NOTE--------------------------

Required to be performed within 72 hours3 days 0.429 weeks 0.0986 months after

>90%RTP.

Verify RCS total flow rate is within the limit 24 months specified in the COLR.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.4.1-2 Unit 2 - Amendment No. 149

RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 Each RCS loop average temperature (Tayg) shall be ; 540'F.

APPLICABILflY: MODE 1, MODE 2 with kff Ž 1.0.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tavg in one or more RCS A. I Be in MODE 2 with 30 minutes loops not within limit. kerr < 1.0.

SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tayg in each loop 2 540TF. 12 hours0.5 days 0.0714 weeks 0.0164 months Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.4.2-1 Unit 2 - Amendment No. 149

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure,-RCS temperature, and RCS beatup and cooldowvn rates shall be maintained within the limits specified in the PTLR.

APPLICABILITY: At all times.

ACTIONS .

CONDITION REQUIRED ACTION COMPLETION TIME A. ----------- NOTE----------- A.1 Restore parameter(s) to 30 minutes Required Action A.2 within limits.

shall be completed whenever this Condition AND is entered.

-A.2 Determine RCS is 72 hours3 days 0.429 weeks 0.0986 months acceptable for continued Requirements of LCO operation.

not met in MODE 1, 2, 3,or4.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5 with RCS 36 hours1.5 days 0.214 weeks 0.0493 months pressure < 500 psig.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.4.3-1 Unit 2 - Amendment No. 149

RCS P/T Limits 3.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIMF C.------- NOTE----------- C.1 Initiate action to restore Immediately Required Action C.2 parameter(s) to within shall be completed limits.

whenever this Condition is entered. AND C.2 Determine RCS is Prior to entering Requirements of LCO acceptable for continued MODE 4 not met any time in other operation.

than MODE 1, 2, 3, or 4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 ----------------------- NOTE-----------------------

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and RCS 30 minutes heatup and cooldown rates are within the limits specified in the PTLR.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.4.3-2 Unit 2 - Amendment No. 149

RCS Loops - MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops - MODES I and 2 LCO 3.4.4 Two RCS loops shall be OPERABLE and in operation.

APPLICABIlTY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of LCO not A.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.4.4-1 Unit 2 - Amendment No. 149

RCS Loops - MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops - MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE, and either:

a. Two RCS loops shall be in operation when the Rod Control System is capable of rod withdrawal; or

b. One RCS loop shall be in operation when the Rod Control System is not capable of rod withdrawal.

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

Both reactor coolant pumps may be de-energized for

12 hours0.5 days 0.0714 weeks 0.0164 months to perform preplanned work activities provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 100 F below saturation temperature.

APPLICABILITY: MODE 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RCS loop A.1 Restore inoperable RCS 72 hours3 days 0.429 weeks 0.0986 months inoperable. loop to OPERABLE status.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.4.5-1 Unit 2 - Amendment No. 149

RCS Loops - MODE 3 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion Time of Condition A not met.

C. One RCS loop not in C.1 Restore required RCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months operation with loop to operation.

Rod Control System capable of rod OR withdrawal.

C.2 Place the Rod Control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months System in a condition incapable of rod withdrawal.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.4.5-2 Unit 2 - Amendment No. 149

RCS Loops - MODE 3 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two RCS loops D.l Place the Rod Control Immediately inoperable. System in a condition incapable of rod OR withdrawal.

Required RCS loop AND not in operation.

D.2 Suspend operations that Immediately would cause introduction into the RCS, coolant with boron concentration less than required to meet SDM of LCO 3.1.1.

AND D.3 Initiate action to restore Immediately one RCS loop to OPERABLE status and operation.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.4.5-3 Unit 2 - Amendment No. 149

RCS Loops - MODE 3

- 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.4.5.2 Verify required steam generator capable of 12 hours0.5 days 0.0714 weeks 0.0164 months removing decay heat.

SR 3.4.5.3 -------------------------- NOTE-------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after a required pump is not in operation.

Verify correct breaker alignment and indicated 7 days power are available to each required pump.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.4.5-4 Unit 2 - Amendment No. 149

RCS Loops - MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops - MODE 4 LCO 3.4.6 Two loops consisting of any combination of RCS loops and residual heat removal (RIR) loops shall be OPERABLE, and one loop shall be in operation.

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

1. All reactor coolant pumps (RCPs) and RHR pumps may be de-energized for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 100 F below saturation temperature.

2. No RCP shall be started with any RCS cold leg temperature < the Over Pressure Protection System (OPPS) enable temperature specified in the PTLR unless:

a. The secondary side water temperature of each steam generator (SG) is < 50'F above each of the RCS cold leg temperatures; or

b. There is a steam or gas bubble in the pressurizer.

APPLICABILITY: MODE 4.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.4.6-1 Unit 2 - Amendment No. 149

RCS Loops - MODE 4 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required loop A.1 Initiate action to restore a Immediately inoperable. second loop to OPERABLE status.

AND A.2 ------------- NOTE------------

Only required if RHR loop is OPERABLE.

Be in MODE 5. 24 hours1 days 0.143 weeks 0.0329 months B. Both loops inoperable. B.1 Suspend operations that Immediately would cause introduction OR into the RCS, coolant with boron concentration less Required loop not in than required to meet SDM operation. of LCO 3.1.1.

AND B.2 Initiate action to restore one Immediately loop to OPERABLE status and operation.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.4.6-2 Unit 2 - Amendment No. 149

RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify required RHR or RCS loop is in 12 hours0.5 days 0.0714 weeks 0.0164 months operation.

SR 3.4.6.2 Verify required SG capable of removing decay 12 hours0.5 days 0.0714 weeks 0.0164 months heat.

SR 3.4.6.3 -------------------------- NOTE--------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after a required pump is not in operation.

Verify correct breaker alignment and indicated 7 days power are available to each required pump.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.4.6-3 Unit 2 - Amendment No. 149

RCS Loops - MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops -MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) loop shall be OPERABLE and in operation, and either:

a. One additional RHR loop shall be OPERABLE; or

b. One steam generator (SG) shall be capable of removing decay heat.

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

1. The RHR pump of the loop in operation may be de-energized for

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 10F below saturation temperature.

2. One required RHR loop may be inoperable for

2 hours0.0833 days 0.0119 weeks 0.00274 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

3. No reactor coolant pump shall be started with one or more RCS cold leg temperatures

the Over Pressure Protection System (OPPS) enable temperature specified in the PTLR unless:

a. The secondary side water temperature of each SG is < 50'F above each of the RCS cold leg temperatures; or

b. There is a steam or gas bubble in the pressurizer.

4. Both RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

/ Prairie Island Unit 1 -Amendment No. 158 Units l and 2 3.4.7-1 Unit 2-Amendment No. 149

RCS Loops-MODE 5, Loops Filled

3.4.7 APPLICABIlITY

MODE 5 with RCS loops filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RHR loop A.1 Initiate action to restore a Immediately inoperable. second RHR loop to OPERABLE status.

AND OR One RHR loop OPERABLE. A.2 Initiate action to restore Immediately required SG capable to remove decay heat.

B. One or more SGs not B.1 Initiate action to restore a Immediately capable of decay heat second RHR loop to removal. OPERABLE status.

AND OR One RHR loop B.2 Initiate action to restore a Immediately OPERABLE. required SG capable to remove decay heat.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.4.7-2 Unit 2 - Amendment No. 149

RCS Loops-MODE S, Loops Filled 3.4.7 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME C. No required RHR loops C.I Suspend operations that Immediately OPERABLE. would cause introduction into the RCS, coolant with OR boron concentration less than required to meet SDM Required RHR loop not of LCO 3.1. 1.

in operation.

AND C.2 Initiate action to restore Immediately one RHR loop to OPERABLE status and operation.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.4.7-3 Unit 2 - Amendment No. 149

RCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS .

SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required RHR loop is in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.4.7.2 Verify required SG capable of removing decay 12 hours0.5 days 0.0714 weeks 0.0164 months heat.

SR 3.4.7.3 -------------------------- NOTE --------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after a required pump is not in operation.

Verify correct breaker alignment and indicated 7 days power are available to each required RHR pump.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.4.7-4 Unit 2 - Amendment No. 149

RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.

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

1. All RHR pumps may be de-energized for

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1;

b. The core outlet temperature is maintained > 10F below saturation temperature; and

c. No draining operations to further reduce the RCS water volume are permitted.

2. One RHR loop may be inoperable for < 2 hours0.0833 days 0.0119 weeks 0.00274 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 5 with RCS loops not filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RHR loop A.1 Initiate action to restore Immediately inoperable. RHR loop to OPERABLE status.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.4.8-1 Unit 2 - Amendment No. 149

RCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No required RHR loop B.1 Suspend operations that Immediately OPERABLE. would cause introduction into the RCS, coolant with OR boron concentration less than required to meet SDM Required RHR loop not in of LCO 3. 1.1.

operation.

AND

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

A Safety Injection pump may be run as required to maintain adequate core cooling and RCS inventory.

B.2 Initiate action to restore one Immediately RHR loop to OPERABLE status and operation.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.4.8-2 Unit 2 - Amendment No. 149

RCS Loops - MODE 5, Loops Not Filled 3.4.8 SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify required RHR loop is in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.4.8.2 -------------------------- NOTE----------------------------

Not required to be performed until 24 hours1 days 0.143 weeks 0.0329 months after a required pump is not in operation.

Verify correct breaker alignment and indicated 7 days powver are available to each required RHR pump.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.4.8-3 Unit 2 - Amendment No. 149

Pressurizer 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:

a. Pressurizer water level

90%; and

b. Two groups of pressurizer heaters OPERABLE with the capacity of each group > 100 kW and capable of being powered from an emergency power supply.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level A.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months not within limit.

AND A.2 Fully insert all rods. 6 hours0.25 days 0.0357 weeks 0.00822 months AND A.3 Place Rod Control System 6 hours0.25 days 0.0357 weeks 0.00822 months in a condition incapable of rod withdrawal.

AND A.4 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.4.9-1 Unit 2 - Amendment No. 149

Pressurizer 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One group of pressurizer B.1 Restore group of pressurizer 72 hours3 days 0.429 weeks 0.0986 months heaters inoperable. heaters to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition B AND not met.

C.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is

90%. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.4.9.2 Verify capacity of each required group of 24 months pressurizer heaters is > 100 kW.

SR 3.4.9.3 Verify required pressurizer heaters are 24 months capable of being powered from an emergency power supply.

Prairie Island Unit I - Amendment No. 158 Units l and 2 3.4.9-2 Unit 2 - Amendment No. 149

Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Pressurizer Safety Valves LCO 3.4.10 Two pressurizer safety valves shall be OPERABLE with lift settings

> 2410 psig and s 2560 psig.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures > the Over Pressure Protection System (OPPS) enable temperature specified in the PTLR.

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

The lift settings are not required to be within the LCO limits during MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 36 hours1.5 days 0.214 weeks 0.0493 months following entry into MODE 3 provided a preliminary cold setting wvas made prior to heatup.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.4.10-1 Unit 2 - Amendment No. 149

Pressurizer Safety Valves 3.4.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.] Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND OR B.2 Be in MODE 4 with any 24 hours1 days 0.143 weeks 0.0329 months RCS cold leg temperature Both pressurizer safety

the OPPS enable valves inoperable. temperature specified in the PTLR.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is In accordance OPERABLE in accordance with the Inservice with the Testing Program. Following testing, lift settings Inservice Testing shall be within +/- 1% (2460 to 2510 psig). Program Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.4.10-2 Unit 2 - Amendment No. 149

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

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

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

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

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

cycled.

Prairie Island Unit 1 - Amendment No. 4.5, 167 l Units 1 and 2 3.4.11-1 Unit 2 - Amendment No. 449, 157

Pressurizer PORVs 3.4.11 ACTIONS (continued)

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

manually cycled.

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

AND B.3 Restore PORV to 72 hours3 days 0.429 weeks 0.0986 months OPERABLE status.

C. One block valve --------------- NOTE----------------

inoperable. Required Actions C.1 and C.2 do not apply when block valve is inoperable solely as a result of complying with Required Actions B.2 or E.2 C.1 Place associated PORV in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months manual control.

AND C.2 Restore block valve to 72 hours3 days 0.429 weeks 0.0986 months OPERABLE status.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.4.11-2 Unit 2 - Amendment No. 149

Pressurizer PORVs 3.4.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A, B, AND or C not met.

D.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months E. Both PORVs inoperable E. 1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not capable of being valves.

manually cycled.

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

AND E.3 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months AND E.4 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months F. Both block valves ----------------- NOTE----------------

inoperable. Required Action F.1 does not apply when block valve is inoperable solely as a result of complying with Required Actions B.2 or E.2 F.1 Restore one block valve to 2 hours0.0833 days 0.0119 weeks 0.00274 months OPERABLE status.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.4.11-3 Unit 2 - Amendment No. 149

Pressurizer PORVs 3.4.11 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition F not AND met.

G.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 --------------------------- NOTES --------------------------

1. Not required to be performed with block valve closed in accordance with the Required Actions of this LCO.

2. Only required to be performed in MODES I and 2.

Perform a complete cycle of each block valve. 92 days SR 3.4.11.2 --------------------------- NOTE---------------------------

Only required to be performed in MODES 1 and 2.

Perform a complete cycle of each PORV. 24 months Prairie Island Unit I -Amendment No. 158 Units 1 and 2 3.4.11-4 Unit 2 - Amendment No. 149

LTOP - RCSCLT > SI Pump Disable Temperature 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) -Reactor Coolant System Cold Leg Temperature (RCSCLT) > Safety Injection (SI) Pump Disable Temperature LCO 3.4.12 LTOP shall be provided with:

a. A maximum of one SI pump capable of injecting into the RCS;

b. The emergency core cooling system (ECCS) accumulators isolated;

c. An OPERABLE Over Pressure Protection System (OPPS) with lift setting within the limits specified in the PTLR; and

d. Two OPERABLE pressurizer power operated relief valves (PORVs).

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

1. Both SI pumps may be run for s 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months while conducting SI system testing providing there is a steam or gas bubble in the pressurizer and at least one isolation valve between the SI pump and the RCS is shut.

2. ECCS accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.

APPLICABILITY: MODE 4 when any RCS cold leg temperature is

the OPPS enable temperature specified in the PTLR and > the SI pump disable temperature specified in the PTLR.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.4.12-1 Unit 2 - Amendment No. 149

LTOP - RCSCLT > SI Pump Disable Temperature 3.4.12 ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION

._ _TIME A. Two SI pumps capable of A.1 Initiate action to assure a Immediately injecting into the RCS. maximum of one SI pump is capable of injecting into the RCS.

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

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

Prairie Island Unit 1 - Amendment No. 458, 167l Units 1 and 2 3.4.12-2 Unit 2 - Amendment No. 449, 1571

LTOP - RCSCLT > SI Pump Disable Temperature 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Increase RCS cold leg 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion temperature to > the OPPS Time of Condition B not enable temperature met. specified in the PTLR.

OR C.2 Depressurize affected 12 hours0.5 days 0.0714 weeks 0.0164 months ECCS accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

D. One required PORV D. 1 Restore required PORV to 7 days inoperable. OPERABLE status.

E. Two PORVs inoperable. E.I Be in MODE 5. 8 hours0.333 days 0.0476 weeks 0.011 months OR AND Required Action and E.2 Depressurize RCS and 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion establish RCS vent of > 3 Time of Condition A, C, square inches.

or D not met.

OR OPPS inoperable.

Prairie Island Unit I - Amendment No. 4-US, 167 Units 1 and 2 3.4.12-3 Unit 2 - Amendment No. 449, 157

LTOP - RCSCLT > SI Pump Disable Temperature 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximum of one SI pump is capable of 12 hours0.5 days 0.0714 weeks 0.0164 months injecting into the RCS.

SR 3.4.12.2 Verify each ECCS accumulator is isolated. Once within 12 hours0.5 days 0.0714 weeks 0.0164 months and every 12 hours0.5 days 0.0714 weeks 0.0164 months thereafter SR 3.4.12.3 Verify PORV block valve is open for each 72 hours3 days 0.429 weeks 0.0986 months required PORV.

SR 3.4.12.4 ---------------------- NOTE--------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after decreasing RCS cold leg temperature to s the OPPS enable temperature specified in the PTLR.

Perform a COT on OPPS. 31 days SR 3.4.12.5 Perform CHANNEL CALIBRATION for each 24 months OPPS actuation channel.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.4.12-4 Unit 2 - Amendment No. 149

LTOP - RCSCLT

SI Pump Disable Temperature 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 Low Temperature Overpressure Protection (LTOP) - Reactor Coolant System Cold Leg Temperature (RCSCLT) < Safety Injection (SI) Pump Disable Temperature LCO 3.4.13 LTOP shall be provided with: 1) no SI Pumps capable of injecting into the RCS; 2) the emergency core cooling system (ECCS) accumulators isolated; and 3) one of the following pressure relief capabilities:

a. An Over Pressure Protection System (OPPS) shall be OPERABLE with two pressurizer power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR; or

b. The RCS depressurized and an RCS vent of 2 3 square inches.

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

1. Both safety injection (SI) pumps may be run for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months while conducting SI system testing provided there is a steam or gas bubble in the pressurizer, the reactor vessel head is on, and at least one isolation valve between the SI pump and the RCS is shut.

2. During reduced inventory conditions an SI pump may be run as required to maintain adequate core cooling and RCS inventory.

3. ECCS accumulator may be unisolated when ECCS accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.

APPLICABILITY: MODE 4 when any RCS cold leg temperature is

the SI Pump disable temperature specified in the PTLR, MODE 5 when the steam generator (SG) primary system manway and pressurizer manway are closed and secured in position, MODE 6 when the reactor vessel head is on and the SG primary system manway and pressurizer manways are closed and secured in position.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.4.13-1 Unit 2 - Amendment No. 149

LTOP - RCSCLT

SI Pump Disable Temperature 3.4.13 ACTIONS

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

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

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

B. An ECCS accumulator B.I Isolate affected ECCS I hour not isolated when the accumulator.

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

C. Required Action and C.] Increase RCS cold leg 12 hours0.5 days 0.0714 weeks 0.0164 months associated Completion temperature to > the OPPS Time of Condition B not enable temperature specified met. in the PTLR.

OR C.2 Depressurize affected ECCS 12 hours0.5 days 0.0714 weeks 0.0164 months accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

Prairie Island Unit I - Amendment No. 445 , 167 Units I and 2 3.4.13-2 Unit 2 - Amendment No. 449, 157

LTOP - RCSCLT s SI Pump Disable Temperature 3.4.13 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. ---------- NOTE--------- D.1 Restore required PORV to 24 hours1 days 0.143 weeks 0.0329 months Only applicable in LCO OPERABLE status.

3.4.13.a.

One required PORV inoperable.

E. Two required PORVs E.1 Depressurize RCS and 8 hours0.333 days 0.0476 weeks 0.011 months inoperable for LCO establish RCS vent of 2 3 3.4.13.a. square inches.

OR.

Required Action and associated Completion Time of Condition A, C, or Dnot met.

OR OPPS inoperable.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.4.13-3 Unit 2 - Amendment No. 149

LTOP - RCSCLT

SI Pump Disable Temperature 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 Verify no SI pumps are capable of injecting into 12 hours0.5 days 0.0714 weeks 0.0164 months the RCS.

SR 3.4.13.2 Verify each ECCS accumulator is isolated. Once within 12 hours0.5 days 0.0714 weeks 0.0164 months and every 12 hours0.5 days 0.0714 weeks 0.0164 months thereafter SR 3.4.13.3 ------------------------- NOTE----------------------------

Only required to be performed when complying with LCO 3.4.13.b.

Verify required RCS vent 2 3 square inches open. 12 hours0.5 days 0.0714 weeks 0.0164 months for unlocked open vent valve(s)

AND 31 days for other vent path(s)

SR 3.4.13.4 Verify PORV block valve is open for each 72 hours3 days 0.429 weeks 0.0986 months required PORV.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.4.13-4 Unit 2 - Amendment No. 149

LTOP - RCSCLT

SI Pump Disable Temperature 3.4.13 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.13.5 --------------------------- NOTE--------------------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after decreasing RCS cold leg temperature to

the OPPS enable temperature specified in the PTLR.

Perform a COT on OPPS. 31 days SR 3.4.13.6 Perform CHANNEL CALIBRATION for OPPS 24 months actuation channel.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.4.13-5 Unit 2 - Amendment No. 149

RCS Operational LEAKAGE 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Operational LEAKAGE LCO 3.4.14 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 10gpm identified LEAKAGE; and

d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS unidentified A.1 Reduce LEAKAGE to 4 hours0.167 days 0.0238 weeks 0.00548 months LEAKAGE not within within limits.

limit.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2.1 Identify LEAKAGE. 54 hours2.25 days 0.321 weeks 0.074 months OR B.2.2 Be in MODE 5. 84 hours3.5 days 0.5 weeks 0.115 months Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.4.14-1 Unit 2 - Amendment No. 149

RCS Operational LEAKAGE 3.4.14 ACTIONS (continued)

-CONDITION REQUIREDACTION--------

-.. -- COMPLETION TIME C. RCS identified C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months LEAKAGE not within limit for reasons other AND than pressure boundary LEAKAGE or primary to C.2.1 Reduce LEAKAGE to 14 hours0.583 days 0.0833 weeks 0.0192 months secondary LEAKAGE. within limits.

OR C.2.2 Be in MODE 5. 44 hours1.833 days 0.262 weeks 0.0603 months D. Pressure boundary D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months LEAKAGE exists.

AND OR D.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Primary to secondary LEAKAGE not within limit.

Prairie Island Unit I - Amendment No. 4-58 177 Units 1 and 2 3.4.14-2 Unit 2 - Amendment No. 449 167

RCS Operational LEAKAGE 3.4.14 SURVEILLANCE REQUIREMENTS

-SURVEILLANCE -FREQUENCY SR 3.4.14.1 -------------- NOTES --------------------------

1. Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after establishment of steady state operation.

2. Not applicable to primary to secondary LEAKAGE.

Verify RCS operational LEAKAGE within limits 24 hours1 days 0.143 weeks 0.0329 months by performance of RCS water inventory balance.

SR 3.4.14.2 ----------------- NOTE ----------------

Not required to be performed until 12 hours0.5 days 0.0714 weeks 0.0164 months after establishment of steady state operation.

Verify primary to secondary LEAKAGE is 72 hours3 days 0.429 weeks 0.0986 months

< 150 gallons per day through any one SG.

Prairie Island Unit 1 - Amendment No. 4-58 177 Units I and 2 3.4.14-3 Unit 2 - Amendment No. 4-49 167

RCS PIV Leakage 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.15 Leakage from each RCS PIV shall be within limit.

APPLICABILiT.Y: MODES 1, 2, 3, and 4.

ACTIONS

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

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.4.15-1 Unit 2 - Amendment No. 149

RCS PIV Leakage 3.4.15 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths ---------------- NOTE-----------------

with leakage from one or Each valve used to satisfy more RCS PIVs not Required Action A. l must have within limit. been verified to meet SR 3.4.15.1 and be in the high pressure portion of the system.

A.1 Isolate the high pressure 4 hours0.167 days 0.0238 weeks 0.00548 months portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AND A.2 Restore RCS PIV to within 72 hours3 days 0.429 weeks 0.0986 months limits.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.4.15-2 Unit 2 - Amendment No. 149

RCS PIV Leakage 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 --------------------------- NOTE---------------------------

Not required to be performed in MODES 3 and 4.

Verify leakage from each RCS PIV is equivalent to In accordance

< 0.5 gpm per nominal inch of valve size up to a with the maximum of 5 gpm at an RCS pressure 2 2215 psig Inservice Testing and s 2255 psig. Program, and 24 months AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.4.15-3 Unit 2 - Amendment No. 149

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

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

and

b. One containment radionuclide monitor.

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

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

sump monitor inoperable. Not required until 12 hours0.5 days 0.0714 weeks 0.0164 months after establishment of steady state operation.

Perform SR 3.4. 14. 1. Once per 24 hours1 days 0.143 weeks 0.0329 months AND Prairie Island Unit I - Amendment No. I-4Q, 167 Units I and 2 3.4.16-1 Unit 2 - Amendment No. 449, 1571

RCS Leakage Detection Instrumentation 3.4.16 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Restore required 30 days containment sump monitor to OPERABLE status.

B. Required containment B.1.1 Analyze grab samples of Once per 24 hours1 days 0.143 weeks 0.0329 months radionuclide monitor the containment inoperable. atmosphere.

OR B.1.2 ------------ NOTE------------

Not required until 12 hours0.5 days 0.0714 weeks 0.0164 months after establishment of steady state operation.

Perform SR 3.4.14.1. Once per 24 hours1 days 0.143 weeks 0.0329 months AND B.2 Restore required 30 days containment radionuclide monitor to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.4.16-2 Unit 2 - Amendment No. 149

RCS Leakage Detection Instrumentation 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. All required monitors D.I Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Perform CHANNEL CHECK of the required 12 hours0.5 days 0.0714 weeks 0.0164 months containment radionuclide monitor.

SR 3.4.16.2 Perform COT of the required containment 92 days radionuclide monitor.

SR 3.4.16.3 Perform CHANNEL CALIBRATION of the 24 months required containment sump monitor.

SR 3.4.16.4 Perform CHANNEL CALIBRATION of the 24 months required containment radionuclide monitor.

Prairie Island Unit I -Amendment No. 158 Units 1 and 2 3.4.16-3 Unit 2 - Amendment No. 149

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

APPLJCABILTIY: MODES 1 and 2, MODE 3 with RCS average temperature (Tavg ) ~ 500°F.

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

1-131 > 0.5 /lCi/gm. LCO 3.0.4.c is applicable.

A.I Verify DOSE Once per 4 hours0.167 days 0.0238 weeks 0.00548 months EQUIVALENT 1-131 within the acceptable region of Figure 3.4.17-1.

A.2 Restore DOSE 48 hours2 days 0.286 weeks 0.0658 months EQUIVALENT 1-131 to within limit.

Prairie Island Unit 1 - Amendment No. m M+ 1911 Units] and 2 3.4.]7-] Unit 2 - Amendment No. -l49 -H+ 180

RCS Specific Activity 3.4.17 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Gross specific activity -B.1 Be in MODE 3 with 6 hours0.25 days 0.0357 weeks 0.00822 months of the reactor coolant Tavg < 500'F.

not within limit.

C. Required Action and C.1 Be in MODE 3 with 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Tavg < 5000F.

Time of Condition A not met.

OR DOSE EQUIVALENT 1-131 in the unacceptable region of Figure 3.4.17-1.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify reactor coolant gross specific activity 7 days s1 00/E yCi/gm.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.4.17-2 Unit 2 - Amendment No. 149

RCS Specific Activity 3.4.17 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.17.2 ---------------------------NOTE-----------------------.-

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 14 days 1-131 specific activity:S 0.5 llCi/gm.

Between 2 and 6 hours0.25 days 0.0357 weeks 0.00822 months after a THERMAL POWER change of~ 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period SR 3.4. 17.3 ---------------------------NOTE-------------------------

Not required to be performed until 3 I days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for ~ 48 hours2 days 0.286 weeks 0.0658 months .

DetermineE from a sample taken in MODE I after 184 days a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for ~ 48 hours2 days 0.286 weeks 0.0658 months .

Prairie Island Unit I - Amendment No. -l-§.& 191 Units I and 2 3.4.17-3 Unit 2 - Amendment No. -l49 180

Res Specific Activity 3.4.17 250 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 3.4.17-1 (page 1 of 1)

Reactor Coolant DOSE EQUIVALENT 1-131 Specific Activity Limit Versus Percent of RATED THERMAL POWER Prairie Island Unit 1 - Amendment No.lj& 191 Units 1 and 2 3.4.17-4 Unit 2 - Amendment No. +49 180

RCS Loops -Test Exceptions 3.4.18 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.18 RCS Loops-Test Exceptions LCO 3.4.18 The requirements of LCO 3.4.4, "RCS Loops- MODES I and 2," may be suspended, with THERMAL POWER < P-7.

APPLICABILlTY: MODES 1 and 2 during startup and PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. THERMAL POWER A.1 Open reactor trip breakers. Immediately 2 P-7.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.18.1 Verify THERMAL POWER is <P-7. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.4.18.2 Perform a COT for each power range neutron Prior to initiation flux - low and intermediate range neutron flux of startup and channel and P-7. PHYSICS TESTS Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.4.18-1 Unit 2 - Amendment No. 149

SG Tube Integrity 3.4.19 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.19 Steam Generator (SG) Tube Integrity LCO 3.4.19 SG tube integrity shall be maintained.

AND All SG tubes satisfying the tube repair criteria shall be plugged or repaired in accordance with the Steam Generator Program APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

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

Separate Condition entry is allowed for each SG tube.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes A. l Verify tube integrity of the 7 days satisfying the tube repair affected tube(s) is criteria and not plugged maintained until the next or repaired in accordance refueling outage or SG with the Steam inspection.

Generator Program.

AND A. 2 Plug or repair the affected Prior to entering tube(s) in accordance with MODE 4 the Steam Generator following the Program. -next refueling outage or SG tube inspection Prairie Island Unit 1 - Amendment No. 177 Units I and 2 3.4.19-1 Unit 2 - Amendment No. 167

SG Tube Integrity 3.4.19 ACTIONS (continued)

CONDITION ..... REQUIRED-ACTION -- COMPLETION-TIME B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months OR SG tube integrity not maintained.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.19.1 Verify SG tube integrity in accordance with the In accordance Steam Generator Program. with the Steam Generator Program SR 3.4.19.2 Verify that each inspected SG tube that satisfies the Prior to entering tube repair criteria is plugged or repaired in MODE 4 accordance with the Steam Generator Program. following an SG tube inspection Prairie Island Unit 1 - Amendment No. 177 Units 1 and 2 3.4.19-2 Unit 2 - Amendment No. 167

Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators LCO 3.5.1 Two ECCS accumulators shall be OPERABLE.

APPLICABILITY: MODES I and 2, MODE 3 with RCS pressure> 1000 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator A.1 Restore boron 72 hours3 days 0.429 weeks 0.0986 months inoperable due to boron concentration to within concentration not within limits.

limits.

B. One accumulator B.1 Restore accumulator to 24 hours1 days 0.143 weeks 0.0329 months inoperable for reasons OPERABLE status.

other than Condition A.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A AND or B not met.

C.2 Reduce RCS pressure to 12 hours0.5 days 0.0714 weeks 0.0164 months

< 1000 psig.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.5.1-1 Unit 2 - Amendment No. 149

Accumulators 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two accumulators D.l Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully 12 hours0.5 days 0.0714 weeks 0.0164 months open.

SR 3.5.1.2 Verify borated water volume in each accumulator 12 hours0.5 days 0.0714 weeks 0.0164 months is::: 1250 cubic feet (25%) and c 1290 cubic feet (91 %).

SR 3.5.1.3 Verify nitrogen cover pressure in each 12 hours0.5 days 0.0714 weeks 0.0164 months accumulator is ::: 710 psig and :s 770 psig.

SR 3.5.1.4 Verify boron concentration in each accumulator is 31 days

2300 ppm.

SR 3.5.1.5 Verify power is removed from each accumulator 31 days isolation valve operator when RCS pressure is

2000 psig.

Prairie Island Unit 1 - Amendment No.~ 1192 Units 1 and 2 3.5.1-2 Unit 2 - Amendment No. +49 181

ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.

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

In MODE 3, both safety injection (SI) pump flow paths may be isolated by closing the isolation valves for up to 2 hours0.0833 days 0.0119 weeks 0.00274 months to perform pressure isolation valve testing per SR 3.4.15.1.

APPLICABILiTY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more trains A.1 Restore train(s) to 72 hours3 days 0.429 weeks 0.0986 months inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months C. Less than 100% of the C.1 Enter LCO 3.0.3. Immediately ECCS flow equivalent to a single OPERABLE ECCS train available.

Prairie Island Unit I -Amendment No. 158 Units 1 and 2 3.5.2-1 Unit 2 - Amendment No. 149

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the listed position. 12 hours0.5 days 0.0714 weeks 0.0164 months Westing-Unit I house Valve Valve Number Number Position Function 32070 8801A OPEN SI Injection to RCS Cold Leg A 32068 8801B OPEN SI Injection to RCS Cold Leg B 32073 8806A OPEN SI Cold Leg Injection Line 32206 8816A CLOSED SI Pump Suction from RHR 32207 8816B CLOSED SI Pump Suction from RHR Westing-Unit 2 house Valve Valve Number Number Position Function 32173 8801 A OPEN SI Injection to RCS Cold Leg A 32171 8801B OPEN SI Injection to RCS Cold Leg B 32176 8806A OPEN SI Cold Leg Injection Line 32208 8816A CLOSED SI Pump Suction from RHR 32209 8816B CLOSED SI Pump Suction from RHR SR 3.5.2.2 Verify each ECCS manual, power operated, and 31 days automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.2.3 Verify power to the valve operator has been removed 31 days for each valve listed in SR 3.5.2.1.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.5.2-2 Unit 2 - Amendment No. 149

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.4 Verify each ECCS pump's developed head at thetest In accordance flow point is greater than or equal to the required with the Inservice developed head. Testing Program SR 3.5.2.5 Verify each ECCS automatic valve in the flow path 24 months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.5:2.6 Verify each ECCS pump starts automatically on an 24 months actual or simulated actuation signal.

SR 3.5.2.7 Verify each ECCS throttle valve listed below is in the 24 months correct position.

Unit 1 Valve Number Unit 2 Valve Number SI-15-6 2SI-15-6 SI-15-7 2S1-15-7 SI-15-8 2SI-15-8 SI-15-9 2SI-15-9 SR 3.5.2.8 Verify, by visual inspection, each ECCS train 24 months containment sump suction inlet is not restricted by debris and the suction inlet strainers show no evidence I of structural distress or abnormal corrosion.

Prairie Island Units 1 and 2 3.5.2-3 Unit I - Amendment No. 4 182 Unit 2 - Amendment No. -149 172 I

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

NOTES

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

2. An SI train may be considered OPERABLE when the pump is capable of being manually started from the control room.

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

ACTIONS

.NOTE LCO 3.0.4.b is not applicable to ECCS safety injection (SI) subsystem.

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

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

Prairie Island Unit 1 - Amendment No. 4-58 4-67 183 Units I and 2 3.5.3-1 Unit 2 - Amendment No. 449 447 173

ECCS - Shutdown 3.5.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 5. 24 hours1 days 0.143 weeks 0.0329 months associated Completion Time of Condition B not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all equipment In accordance required to be OPERABLE: with applicable SRs SR 3.5.2.1 SR 3.5.2.7 SR 3.5.2.3 SR 3.5.2.8 SR 3.5.2.4 Prairie Island Unit I - Amendment No. 44&, 167 Units 1 and 2 3.5.3-2 Unit 2 - Amendment No. 449, 157

RWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Refueling Water Storage Tank (RWST)

LCO 3.5.4 The RWST shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RWST boron A.I Restore RWST to 8 hours0.333 days 0.0476 weeks 0.011 months concentration not within OPERABLE status.

limits.

B. RWST borated water B.l Restore RWST to I hour volume not within limits. OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit I - Amendment No. 158 Units I and 2 3.5.4-1 Unit 2 - Amendment No. 149

RWST.

3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 Verify RWST borated water volume is 7 days

> 265,000 gallons (90%). I SR 3.5.4.2 Verify RWST boron concentration is > 2600 ppm and 7 days

< 3500 ppm.

Prairie Island Unit 1 - Amendment No. 4 182 Units I and 2 3.5.4-2 Unit 2 - Amendment No. 449 172

Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment inoperable. A.1 Restore containment to I hour OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.6.1-1 Unit 2 - Amendment No. 149

Containment 3.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1 .1 Perform required visual examinations and leakage In accordance rate testing except for containment air lock testing, in with the accordance with the Containment Leakage Rate Containment Testing Program. Leakage Rate Testing Program SR 3.6.1.2 Verify containment average air temperature

440 F Prior to entering above shield building average air temperature. MODE 4 from MODE 5 SR 3.6.1.3 Verify containment shell temperature 2 30'F. Prior to entering MODE 4 from MODE 5 Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.6.1-2 Unit 2 - Amendment No. 149

Containment Air Locks 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Air Locks LCO 3.6.2 Two containment air locks shall be OPERABLE.

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

ACTIONS

N--------NOTES------------------------------------------------

1. Entry and exit is permissible to perform repairs on the affected air lock components.

2. Separate Condition entry is allowed for each air lock.

3. Enter applicable Conditions and Required Actions of LCO 3.6.1, "Containment,"

when air lock leakage results in exceeding the overall containment leakage rate acceptance criteria.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.6.2-1 Unit 2 - Amendment No. 149

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more ---------------- NOTES---------------

containment air locks 1. Required Actions A. 1, A.2, with one containment air and A.3 are not applicable lock door inoperable. if both doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls if both air locks are inoperable.

A.1 Verify the OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock.

AND A.2 Lock the OPERABLE door 24 hours1 days 0.143 weeks 0.0329 months closed in the affected air lock.

AND Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.6.2-2 Unit 2 - Amendment No. 149

Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3 ---------- NOTE-------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify the OPERABLE Once per 31 days door is locked closed in the affected air lock.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.6.2-3 Unit 2 - Amendment No. 149

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more ------------ NOTES---------------

containment air locks 1. Required Actions B. l, B.2, with containment air and B.3 are not applicable lock interlock if both doors in the same air mechanism inoperable. lock are inoperable and Condition C is entered.

2. Entry and exit of containment is permissible under the control of a dedicated individual.

B. I Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock.

AND B.2 Lock an OPERABLE door 24 hours1 days 0.143 weeks 0.0329 months closed in the affected air lock.

AND B.3 ------------- NOTE------------

Air lock doors in high radiation areas may be verified locked closed by administrative means.

Verify an OPERABLE Once per 31 days door is locked closed in the affected air lock.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.6.2-4 Unit 2 - Amendment No. 149

Containment Air Locks 3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more C. 1 Initiate action to evaluate Immediately containment air locks overall containment leakage inoperable for reasons rate per LCO 3.6. 1.

other than Condition A or B. AND C.2 Verify a door is closed in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the affected air lock.

AND C.3 Restore air lock to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.6.2-5 Unit 2 - Amendment No. 149

Containment Air Locks 3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I-SR 3.6.2.1 -------------------------- NOTES---------------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.

Perform required air lock leakage rate testing in In accordance accordance with the Containment Leakage Rate with the Testing Program. Containment Leakage Rate Testing Program SR 3.6.2.2 Verify only one door in the air lock can be opened at 24 months a time.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.6.2-6 Unit 2 - Amendment No. 149

Containment Isolation Valves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO 3.6.3 Each containment isolation valve shall be OPERABLE.

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

ACTIONS

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

1. Penetration flow path(s) except for 36-inch containment purge and 18-inch inservice purge system 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 containment isolation valves.

4. Enter applicable Conditions and Required Actio~s ofLCO 3.6.1, "Containment,"

when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.

Prairie Island Unit 1 - Amendment No. m 191 Units 1 and 2 3.6.3-1 Unit 2 - Amendment No. +49 180

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE----------- A.1 Isolate the affected 4 hours0.167 days 0.0238 weeks 0.00548 months Only applicable to penetration flow paths by penetration flow paths use of at least one closed with two containment and de-activated or isolation valves. mechanically blocked power operated valve, closed manual valve, blind One or more penetration flange, or check valve with flow paths with one flow through the valve containment isolation secured.

valve inoperable for reasons other than AND Condition D.

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 paths is for isolation isolated. devices outside containment AND Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.6.3-2 Unit 2 - Amendment No. 149

Containment Isolation Valves 3.6.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 (continued) Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment B. ----- NOTE--------- B.1 Isolate the affected I hour Only applicable to penetration flow path(s) by penetration flow paths use of at least one closed with two containment and de-activated power isolation valves. operated valve, closed manual valve, or blind flange.

One or more penetration flow paths with two containment isolation valves inoperable for reasons other than Condition D.

Prairie Island Unit I -Amendment No. 158 Units ] and 2 3.6.3-3 Unit 2 - Amendment No. 149

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ------------ NOTE------ C.1 Isolate the affected 72 hours3 days 0.429 weeks 0.0986 months Only applicable to penetration flow paths by penetration flow paths use of at least one closed with only one and de-activated power containment isolation operated valve, closed valve and a closed manual valve, or blind system. flange.

AND One or more penetration flow paths with one C.2 ----------- NOTES ------------

containment isolation 1. Isolation devices in valve inoperable. 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 paths is isolated.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.6.3-4 Unit 2 - Amendment No. 149

Containment Isolation Valves 3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more secondary D.l Restore leakage within 4 hours0.167 days 0.0238 weeks 0.00548 months containment bypass limit.

leakage not within limit.

E. Containment purge blind E.} Restore leakage within } hour flange or inservice purge limit.

blind flange leakage not within limit.

F. Required Action and F.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND F.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit} - Amendment No. ~ 191 Units 1 and 2 3.6.3-5 Unit 2 - Amendment No. -l49 180

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 Verify each 36-inch containment purge penetration Prior to entering blind flange is installed. MODE 4 from MODES SR 3.6.3.2 Verify each I8-inch containment inservice purge Prior to entering penetration blind flange is installed. MODE 4 from MODES SR 3.6.3.3 ----------------------------NOTE---------------------------

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

Verify each containment isolation manual valve and 92 days blind flange that is located outside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

SR 3.6.3.4 ----------------------------NOTE---------------------------

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

Verify each containment isolation manual valve and Prior to entering blind flange that is located inside containment and MODE 4 from not locked, sealed, or otherwise secured and required MODE 5 ifnot to be closed during accident conditions is closed, perfonned within except for containment isolation valves that are open the previous under administrative controls. 92 days Prairie Island Unit I - Amendment No. m 191 Units I and 2 3.6.3-6 Unit 2 - Amendment No. +49 180

Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.3.5 VerifY the isolation time of each automatic power In accordance operated containment isolation valve is within limits. with the Inservice Testing Program SR 3.6.3.6 Not Used SR 3.6.3.7 VerifY each automatic containment isolation valve 24 months that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

SR 3.6.3.8 VerifY the combined leakage rate for all secondary In accordance containment bypass leakage paths is in accordance with the with the Containment Leakage Rate Testing Program. Containment Leakage Rate Testing Program Prairie Island Unit 1 - Amendment No. -M-8 191 Units I and 2 3.6.3-7 Unit 2 - Amendment No. -l49 180

Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be s 2.0 psig.

APPLICABI=1Y: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure not A. I Restore containment 8 hours0.333 days 0.0476 weeks 0.011 months within limits. pressure to within limits.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within limits. 12 hours0.5 days 0.0714 weeks 0.0164 months Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.6.4-1 Unit 2 - Amendment No. 149

Containment Spray and Cooling Systems 3.6.5 3.6 CONTAINMENT SYSTEMS 3.6.5 Containment Spray and Cooling Systems LCO 3.6.5 T wo containment spray trains and two containment cooling trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment spray 72 hours3 days 0.429 weeks 0.0986 months train inoperable. train to OPERABLE status.

AND 10 days from discovery of failure to meet the LCO B. Required Action and B.I Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 84 hours3.5 days 0.5 weeks 0.115 months Prairie Island Unit I -Amendment No. 158 Units I and 2 3.6.5-1 Unit 2 - Amendment No. 149

Containment Spray and Cooling Systems 3.6.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or both containment C.1 Restore containment 7 days cooling fan coil unit(s) cooling FCU(s) to (FCU) in one train OPERABLE status. AND inoperable.

10 days from discovery of failure to meet the LCO D. One containment cooling D.1 Initiate action to isolate Immediately FCU in each train both inoperable FCUs.

inoperable.

AND D.2 Restore all FCUs to 7 days OPERABLE status.

AND 10 days from discovery of failure to meet the LCO E. Required Action and E.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition C or D AND not met.

E.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 - Amendment No. 4-59 173 Units 1 and 2 3.6.5-2 Unit 2 - Amendment No. 449 163 1 Revised by letter dated August29, 2006.

Containment Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify each containment spray manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.5.2 Operate each containment fan coil unit on low motor 31 days I speed for > 15 minutes.

I SR 3.6.5.3 Verify cooling water flow rate to each containment 24 months fan coil unit is > 900 gpm.

SR 3.6.5.4 Verify each containment spray pump's developed In accordance head at the flow test point is greater than or equal to with the the required developed head. Inservice Testing Program SR 3.6.5.5 Verify each automatic containment spray valve in the 24 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.5.6 Verify each containment spray pump starts 24 months automatically on an actual or simulated actuation signal.

Prairie Island Unit 1 - Amendment No. 4 173 Units 1 and 2 3.6.5-3 Unit 2 - Amendment No. 449 163 Revised by letter dated August 29, 2006.

Containment Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.5.7 Verify each containment cooling train starts 24 months automatically on an actual or simulated actuation signal.

SR 3.6.5.8 Verify each spray nozzle is unobstructed. Following maintenance which could result in nozzle blockage Prairie Island Unit 1 - Amendment No. m 190 Units I and 2 3.6.5-4 Unit 2 - Amendment No. +49 179

Spray Additive System 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Spray Additive System LCO 3.6.6 The Spray Additive System shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spray Additive System A. 1 Restore Spray Additive 24 hours1 days 0.143 weeks 0.0329 months inoperable. System to OPERABLE status.

B. Required Action and B.I Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 84 hours3.5 days 0.5 weeks 0.115 months Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.6.6-1 Unit 2 - Amendment No. 149

Spray Additive System 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each spray additive manual, power operated, 31 days and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.6.6.2 Verify spray additive tank solution volume 184 days is 2 2590 gal (89%).

SR 3.6.6.3 Verify spray additive tank NaOH solution 184 days concentration is > 9% and < 11% by weight.

SR 3.6.6.4 Verify each spray additive automatic valve in the 24 months flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

Prairie Island Unit I -Amendment No. 158 Units 1 and 2 3.6.6-2 Unit 2 - Amendment No. 149

Not Used l 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Not Used I I

Prairie Island Unitl-AmendmentNo. 4 1 163 Units I and 2 3.6.7-1 Unit 2- Amendment No. 449 l 154

Vacuum Breaker System 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Vacuum Breaker System LCO 3.6.8 Two vacuum breaker trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Vacuum relief function of A.1 Restore vacuum breaker 7 days one or both valves in one train to OPERABLE status.

vacuum breaker train inoperable.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.6.8-1 Unit 2 - Amendment No. 149

Vacuum Breaker System 3.6.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Verify each vacuum breaker train opens on an actual 92 days or simulated containment vacuum equal to or less than 0.5 psi and closes on an actual or simulated containment isolation signal.

SR 3.6.8.2 Perform CHANNEL CALIBRATION. 24 months Prairie Island Unit 1 - Amendment No. 158

.Units I and 2 3.6.8-2 Unit 2 - Amendment No. 149

SBVS 3:6..9 3.6 CONIAINMENT.SYSTEMS 3 6.9 Shield Building Ventilation System (SBVS)

LCO 36.9 Two SBVS trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4 ACIIONS *_.

CONDITION REQUIRED ACTION COMPLETION,

.TIME A. One SBVS train A 1 Restore SBVS train to .7 days inoperable.. OPERABLE status..

B.. Required Action and B.1I Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met., AND B2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FIREQUENCY SR 3.6-9. 1 Operate each SBVS train for> 15 minutes with 31 days heaters operating.

7/_ _ __ _ _ _

/?

I Prairie Island Unit I - Amendment No 4-51& 186 Units I and 2 3 6.9-1 Unit 2 -Amendment No. 49 176

SBVS 3.6.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.9.2 Perform required SBVS filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.6.9.3 Verify each SBVS train actuates on an actual or 24 months simulated actuation signal.

SR 3.6.9.4 Verify SBVS isolation dampers actuate on an actual 24 months or simulated signal.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.6.9-2 Unit 2 - Amendment No. 149

Shield Building 3.6.10 3.6 CONTAINMENT SYSTEMS 3.6.10 Shield Building LCO 3.6.10 The shield building shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Shield building A.1 Restore shield building to 24 hours1 days 0.143 weeks 0.0329 months inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.6.10-1 Unit 2 - Amendment No. 149

Shield Building 3.6.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.10.1 Verify one shield building access door in each 31 days access opening is closed.

SR 3.6.10.2 Verify each Shield Building Ventilation System 31 days (SBVS) train OPERABLE and produces a pressure equal to or more negative than -2.00 inches water gauge and maintains a pressure equal to or more negative than -1.82 inches water gauge in the annulus.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.6.10-2 Unit 2 - Amendment No. 149

MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)

LCO 3.7.1 Five MSSVs per steam generator shall be OPERABLE.

APPLICABILflY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSSV inoperable. A.1 Restore inoperable MSSV 4 hours0.167 days 0.0238 weeks 0.00548 months to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.7.1-1 Unit 2 - Amendment No. 149

MSSVs 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 ------------------------- NOT ----------------------------

Only required to be performed in MODES I and 2.

Verify each MSSV lift setpoint per Table 3.7.1-1 in In accordance accordance with the Inservice Testing Program. with the Following testing, lift setting shall be within +/- 1%. Inservice Testing Program Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.7.1-2 Unit 2 - Amendment No. 149

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

Main Steam Safety Valve Lift Settings VALVE NUMBER Unit 1 Unit 2 LIFT SETTING Steam Generator: Steam Generator: (psig +/- 3%)

11 #12 #21 #22 RS-21-1 RS-21-6 RS-21-11 RS-21-16 1077 RS-21-2 RS-21-7 RS-21-12 RS-21-17 1093 RS-21-3 RS-21-8 RS-21-13 RS-21-18 1110 RS-21-4 RS-21-9 RS-21-14 RS-21-19 1120 RS-21-5 RS-21-10 RS-21-15 RS-21-20 1131 Prairie Island Unit I - Amendment No. 158 Units I and 2 3.7.1-3 Unit 2- Amendment No. 149

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 Two MSIVs shall be OPERABLE.

APPLICABILrIY: MODE 1, MODES 2 and 3 except when both MSIVs are closed.

ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in A.1 Restore MSIV to 8 hours0.333 days 0.0476 weeks 0.011 months MODE 1. OPERABLE status.

B. Required Action and B.1 Be in MODE 2. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not met.

C. -----------NOTE ---------- C.1 Close MSIV. 8 hours0.333 days 0.0476 weeks 0.011 months Separate Condition entry is allowed for each AND MSIV.

- -C.2 Verify MSIV is closed. Once per 7 days One or more MSIVs inoperable in MODE 2 or 3.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.7.2-1 Unit 2 - Amendment No. 149

MSIVs 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D. Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition C not AND met.

D.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 ---------------------------- NOTE ----------------------------

Only required to be performed in MODES I.and 2.

Verify the isolation time of each MSIV is within In accordance limits. with the Inservice Testing Program SR 3.7.2.2 ---------------------------- NOTE ----------------------------

Only required to be performed in MODES 1 and 2.

Verify each MSIV actuates to the isolation position 24 months on an actual or simulated actuation signal.

Prairie Island Unit I - Amendment No. 4-58 1f81l Units i and 2 ,.J. I .Z--, Unit 2 - Amendment No. 449171

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

APPLICABILITY- MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or both MFRVs A. I Close and place in manual 72 hours3 days 0.429 weeks 0.0986 months inoperable. or isolate flow through MFRV(s).

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

Prairie Island Unit I - Amendment No. 4155, 167 Units I and 2 3.7.3-1 Unit 2 - Amendment No. I44, 157

MFRVs and MFRV Bypass Valves 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or both MFRV B.1 Close and place in manual 72 hours3 days 0.429 weeks 0.0986 months bypass valves inoperable. or isolate flow through bypass valve(s).

AND B.2 Verify bypass valve(s) Once per 7 days closed and in manual or flow through valve(s) isolated.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the isolation time of each MFRV and MFRV In accordance bypass valve is within limits. with the Inservice Testing Program SR 3.7.3.2 Verify each MFRV and MFRV bypass valve actuates 24 months to the isolation position on an actual or simulated actuation signal.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.7.3-2 Unit 2 - Amendment No. 149

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

LCO 3.7.4 Two SG PORV lines shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SG PORV line A.1 Restore SG PORV line to 7 days I inoperable. OPERABLE status.

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

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND C.2 Be in MODE 4 without 12 hours0.5 days 0.0714 weeks 0.0164 months reliance upon steam generator for heat removal.

Prairie Island Unit I - Amendment No. 4I9, 167 Units 1 and 2 3.7.4-1 Unit 2 - Amendment No. 149, 157

SG PORVs 3.7.4 SURVEILLANCE REQUIREMENTS .

SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each SG PORV. In accordance with the Inservice Testing Program SR 3.7.4.2 Verify one complete manual cycle of each SG PORV 24 months block valve.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.7.4-2 Unit 2 - Amendment No. 149

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

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

1. AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation.

2. Only the AFW train which includes the motor driven pump is required to be OPERABLE in MODE 4.

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

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.7.5-1 Unit 2 - Amendment No. 149

AFW System 3.7.5 ACTIONS

NOTE.

LCO 3.0.4.b is not applicable.

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

pump inoperable. AND OR 10 days from discovery of

NOTE----------- failure to meet the Only applicable if MODE LCO 2 has not been entered following refueling.

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

B. One AFW train B.1 Restore AFW train to 72 hours3 days 0.429 weeks 0.0986 months inoperable in MODE 1, 2, OPERABLE status.

or 3 for reasons other AND than Condition A.

10 days from discovery of failure to meet the LCO Prairie Island Unit I - Amendment No. 4-5A, 167 Units I and 2 3.7.5-2 Unit 2 - Amendment No. 449, 157

AFW System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C. 1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time for Condition A AND or B not met.

C.2 Be in MODE 4. 12 hours0.5 days 0.0714 weeks 0.0164 months D. Two AFW trains D.1 ------------- NOTE------------

inoperable in MODE 1, 2, LCO 3.0.3 and all other or 3. LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to restore Immediately one AFW train to OPERABLE status.

E. Required AFW train E.1 Initiate action to restore Immediately inoperable in MODE 4. AFW train to OPERABLE status.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.7.5-3 Unit 2 - Amendment No. 149

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 ---------------------------- NOT N ----------------------------

AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control if it is capable of being manually realigned to the AFW mode of operation.

Verify each AFW manual, power operated, and 31 days automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

+

SR 3.7.5.2 ---------------------------- NOTE---------------------------

Not required to be performed for the turbine driven AFW pump until prior to exceeding 10% RTP or within 72 hours3 days 0.429 weeks 0.0986 months after RCS temperature > 350'F.

Verify the developed head of each AFW pump at the In accordance flow test point is greater than or equal to the required with the Inservice developed head. Testing Program Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.7.5-4 Unit 2 - Amendment No. 149

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.3 ---------------------------- NOT ----------------------------

AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation.

Verify each AFW automatic valve that is not locked, 24 months sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.5.4 ---------------------------- NOTES----------------------------

1. Not required to be performed for the turbine driven AFW pump until prior to exceeding 10% RTP or within 72 hours3 days 0.429 weeks 0.0986 months after RCS temperature > 350TF.

2. AFW train(s) may be considered OPERABLE during alignment and operation for steam generator level control, if it is capable of being manually realigned to the AFW mode of operation.

Verify each AFW pump starts automatically on an 24 months actual or simulated actuation signal.

Prairie Island Unit 1-Amendment No. 158 Units I and 2 3.7.5-5 Unit 2 - Amendment No. 149

CSTs 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tanks (CSTs)

LCO 3.7.6 The CSTs shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CSTs inoperable. A.1 Verify by administrative 4 hours0.167 days 0.0238 weeks 0.00548 months means OPERABILITY of backup water supply. AND Once per 12 hours0.5 days 0.0714 weeks 0.0164 months thereafter AND A.2 Restore CSTs to 7 days OPERABLE status.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.7.6-1 Unit 2 - Amendment No. 149

CSTs 3.7.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND B.2 Be in MODE 4, without 12 hours0.5 days 0.0714 weeks 0.0164 months reliance on steam generator for heat removal.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify CSTs useable contents 2 100,000 gal per 12 hours0.5 days 0.0714 weeks 0.0164 months operating unit.

Prairie Island Unit I -Amendment No. 158 Units 1 and 2 3.7.6-2 Unit 2-Amendment No. 149

CC System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CC) System LCO 3.7.7 Two CC trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CC train inoperable. A.I ------------- NOTE------------

Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops -

MODE 4," for residual heat removal loops made inoperable by CC.

Restore CC train to 72 hours3 days 0.429 weeks 0.0986 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit I - Amendment No. 158 Units I and 2 3.7.7-1 Unit 2 - Amendment No. 149

CC System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 --------------------------- NOTE ------------------------

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

Verify each CC manual, power operated, and 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.7.2 ----------------------------NOT ----------------------------

This SR only applies to those valves required to align CC System to support the safety injection or recirculation phase of emergency core cooling.

Verify each CC automatic valve in the flow path that 24 months

is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.7.3 Verify each CC pump starts automatically on an 24 months actual or simulated actuation signal.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.7.7-2 Unit 2 - Amendment No. 149

CL System 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Cooling Water (CL) System LCO 3.7.8 Two CL trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No safeguards CL pumps ----------------- NOTES ----------------

OPERABLE for one 1. Unit 1 enter applicable train. Conditions and Required Actions of LCO 3.8.1, "AC Sources-MODES 1, 2, 3, and 4," for emergency diesel generator made inoperable by CL System.

2. Both units enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4," for residual heat removal loops made inoperable by CL System.

3. This Condition may not exist

> 7 days in any consecutive 30 day period.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.7.8-1 Unit 2 - Amendment No. 149

CL System 3.7.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A. I Restore one safeguards CL 7 days pump to OPERABLE status.

AND 10 days from discovery of failure to meet the LCO B. One CL supply header -----------------NOTES ----------------

inoperable. I. Unit 1 enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources-MODES 1, 2, 3, and 4," for emergency diesel generator made inoperable by CL System.

2. Both units enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4," for residual heat removal loops made inoperable by CL System.

B.1 Verify vertical motor driven 4 hours0.167 days 0.0238 weeks 0.00548 months CL pump OPERABLE.

AND Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.7.8-2 Unit 2 - Amendment No. 149

CL System 3.7.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Verify opposite train diesel 4 hours0.167 days 0.0238 weeks 0.00548 months driven CL pump OPERABLE.

AND B.3 Restore CL supply header to 72 hours3 days 0.429 weeks 0.0986 months OPERABLE status.

AND 10 days from discovery of failure to meet the LCO C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months D. Diesel driven CL pumps D.1 Restore fuel oil supply to 48 hours2 days 0.286 weeks 0.0658 months stored fuel oil supply within limits.

< 19,500 gal and AND

> 17,000 gal.

9 days from discovery of failure to meet the LCO Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.7.8-3 Unit 2- Amendment No. 149

CL System 3.7.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Diesel driven CL pumps E. 1 Declare diesel driven CL Immediately stored fuel oil supply pumps inoperable.

< 17,000 gal.

OR Required Action and associated Completion Time of Condition D not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 ------------------ NOTE ----------------

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

Verify each CL System manual, power operated, and 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.8.2 Verify each required diesel driven CL pump starts 31 days and assumes -load within one minute.

Prairie Island Unit 1 - Amendment No. 4-5-9 175 Units 1 and 2 3.7.8-4 Unit 2 - Amendment No. 449 165

CL System 3.7.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.8.3 Verify stored diesel driven CL pumps fuel oil supply 31 days

> 19,500 gal.

SR 3.7.8.4 Verify OPERABILITY of required vertical motor 92 days driven CL pump.

SR 3.7.8.5 Verify each CL System automatic valve required to 24 months mitigate accidents that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.8.6 Verify the required diesel driven and required 24 months vertical motor driven CL pumps start automatically on an actual or simulated actuation signal.

Prairie Island Unit 1- Amendment No. 4 175 Units 1 and 2 3.7.8-5 Unit 2 - Amendment No. 4 165

Emergency CL Supply 3.7.9 3.7 PLANT SYSTEMS 3.7.9 Emergency Cooling Water (CL) Supply LCO 3.7.9 The Emergency CL supply shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One safeguards traveling A.I -------- NOTE-------------

screen inoperable. Not applicable during periods of testing for s 24 hours1 days 0.143 weeks 0.0329 months .

Verify one emergency bay 4 hours0.167 days 0.0238 weeks 0.00548 months sluice gate open.

AND A.2 Restore safeguards traveling 90 days screen to OPERABLE status.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.7.9-1 Unit 2 - Amendment No. 149

Emergency CL Supply 3.7.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Both safeguards traveling B.1 Verify one emergency bay 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months screens inoperable. sluice gate open.

AND B.2 Restore one safeguards 7 days traveling screen to OPERABLE status.

C. Emergency CL Line C. I Verify one emergency bay 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. sluice gate open.

AND C.2 Restore Emergency CL 7 days Line to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.7.9-2 Unit 2 - Amendment No. 149

Emergency CL Supply 3.7.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify safeguards traveling screens OPERABLE. 92 days Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.7.9-3 Unit 2 - Amendment No. 149

CRSVS 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Special Ventilation System (CRSVS)

LCO 3.7.10 Two CRSVS trains shall be OPERABLE.

N()TE----------------------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILllY: M()OES I, 2, 3, and 4, During movement of irradiated fuel assemblies.

ACTI()NS C()NDITI()N REQUIRED ACTION C()MPLETI()N TIME A. One CRSVS train A.I Restore CRSVS train to 7 days inoperable for reasons OPERABLE status.

other than Condition B.

Prairie Island Unit I - Amendment No. m 195 Units 1 and 2 3:7.1 0-1 Unit 2 - Amendment No. +49 184

CRSVS 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more CRSVS B.l Initiate action to Immediately trains inoperable due to implement mitigating inoperable CRE boundary actions.

in MODES l, 2, 3, or 4.

AND B.2 Verify mitigating actions ensure CRE occupant 24 hours1 days 0.143 weeks 0.0329 months radiological exposures will not exceed limits, and CRE occupants are protected from chemical and smoke hazards.

AND B.3. Restore CRE boundary to OPERABLE status. 90 days C. Required Action and C.l Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1- Amendment No. M& 195 Units 1 and 2 3.7.10-2 Unit 2 - Amendment No. +49184

CRSVS 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and 0.1 Place OPERABLE CRSVS Immediately associated Completion train in operation.

Time of Condition A not met during movement of OR irradiated fuel assemblies.

D.2 Suspend movement of Immediately irradiated fuel assemblies.

E. Two CRSVS trains E.l Suspend movement of Immediately inoperable during irradiated fuel assemblies.

movement of irradiated fuel assemblies.

OR I

One or more CRSVS trains inoperable due to an inoperable CRE boundary during movement of irradiated fuel assemblies.

F. Two CRSVS trains F.l Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, .

3. or 4 for reasons other than Condition B.

Prairie Island Unit I - Amendment No. ~ +W 195 Units I and 2 3.7.10-3 Unit 2 - Amendment No. M9++G184

CRSVS 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CRSVS train? 15 minutes. 31 days SR 3.7.10.2 Perform required CRSVS filter testing in In accordance accordance with the Ventilation Filter Testing with VFTP Program (VFTP).

SR 3.7.10.3 Verify each CRSVS train actuates on an actual or 24 months simulated actuation signal.

SR 3.7.10.4 Verify each CRSVS train in the Emergency Mode 24 months on a delivers 3600 to 4400 cfm through the associated STAGGERED CRSVS filters. TEST BASIS SR 3.7.10.5 Perform required CRE unfiltered air inleakage In accordance testing in accordance with the Control Room with the Control Envelope Habitability Program. Room Envelope Habitability Program Prairie Island Unit 1 - Amendment No. H& +&Gi95 Units 1 and 2 3.7.10-4 Unit 2 - Amendment No. -l-49 -l-19184

SCwS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Safeguards Chilled Water System (SCWS)

LCO 3.7.11 Two SCWS loops shall be OPERABLE.

APPLICABILUTY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SCWS loop A.1 Restore SCWS loop to 30 days inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A not AND met in MODE 1, 2, 3, or 4. B.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.7.11-1 Unit 2 - Amendment No. 149

SCwS 3.7.11 ACTIONS (continued) _ _.

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Place OPERABLE SCWS Immediately associated Completion loop in operation.

Time of Condition A not met during movement of OR irradiated fuel assemblies.

C.2 Suspend movement of Immediately irradiated fuel assemblies.

D. Two SCWS loops D.1 Suspend movement of Immediately inoperable during irradiated fuel assemblies.

movement of irradiated fuel assemblies.

E. Two SCWS loops E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.7.11-2 Unit 2 - Amendment No. 149

SCwS 3.7.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify each SCWS loop actuates on an actual or 24 months on a simulated actuation signal. STAGGERED TEST BASIS SR 3.7.11.2 Verify SCWS components OPERABLE in In accordance accordance with the Inservice Testing Program. with the Inservice Testing Program Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.7.11-3 Unit 2 - Amendment No. 149

ABSVS 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Auxiliary Building Special Ventilation System (ABSVS)

LCO 3.7.12 Two ABSVS trains shall be OPERABLE.

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

The ABSVS boundary may be opened under administrative control.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ABSVS train A.1 Restore ABSVS train to 7 days inoperable. OPERABLE status.

B. Two ABSVS trains B. 1 Restore ABSVS boundary 24 hours1 days 0.143 weeks 0.0329 months inoperable due to to OPERABLE status.

inoperable ABSVS boundary.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.7.12-1 Unit 2 - Amendment No. 149

ABSVS 3 7.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.- Required Action and C 1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND.

C.2 Be in MODE 5.. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE...REQUIREMENIS SURVEILLANCE FREQUENCY SR 3.7 .12.1 Operate each ABSVS train for> 15 minutes with 31 days the heaters operating.

SR 3.7.12.2 Perform required ABSVS filter testing in In accordance accordance with the Ventilation Filter-Testing with the VFTP Program (VFIP). "

SR -.3.7 12.3 Verify each ABSVS train can produce a negative 92 days pressure within 6 minutes after initiation.

SR 3.7.12.4 Verify each ABSVS train actuates. on an actual or 24 months simulated actuation signal.,

Prairie Island Unit 1 - Amendment No. 4 186 Units 1 and 2 3.7.12-2 Unit 2 - Amendment No 449 176

SFPSVS 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Spent Fuel Pool Special Ventilation System (SFPSVS)

LCO 3.7.13 Two SFPSVS trains shall be OPERABLE.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel pool enclosure.

ACTIONS xTNTD111 r--------------------------------------------------

--- ------ --- ---- --- --- ---- --- --- 1INL1.1 LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One SFPSVS train A.1 Restore SFPSVS train to 7 days inoperable. OPERABLE status.

B. Required Action and B.1 Place OPERABLE SFPSVS Immediately associated Completion train in operation.

Time of Condition A not met. OR B.2 Suspend movement of Immediately irradiated fuel assemblies in the spent fuel pool enclosure.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.7.13-1 Unit 2 - Amendment No. 149

SF PSVS 3.7113 ACTIONS (continued)

CONDITION, REQUIRED ACTION -COMPLETION TIME C. Both SFPSVS trains C.1 Suspend movement of' Immediately.

inoperable, irradiated fuiel assemblies in the spent fuiel pool enclosure.

SURVEILLANCE REQUIREMENT S SURVEILLANCE FREQUENCY SR 3 7.13.1 Operate each SFPSVS train for-> 15 minutes with 31 days the heaters operating.

SR 317,13.2 Perform required SFPSVS filter testing in In accoidance accordance with the Ventilation Filter Testing . with the VI IP Program (VFTP),,

SR 3.7 13,.3 Verify each SIFPSVS train actuates on an actual or 24 months simulated actuation signal.

SR 37.13.4 Verify the SFPSVS fdn in each train delivers 4680. 24 months on a to 5720 cfrn.. STAGGERED TEST BASIS Prairie Island. Unit 1 - Amendment No. + 186 Units 1 and 2 3.7.13-2 Unit 2 - Amendment No., 449 176

Secondary Specific Activity 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Secondary Specific Activity LCO 3.7.14 The specific activity of the secondary coolant shall be s 0.10 yCi/gm DOSE EQUIVALENT I-131.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not A.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months within limit.

AND A.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Verify the specific activity of the secondary coolant 31 days is s 0.10 pCi/gm DOSE EQUIVALENT I-13 1.

Prairie Island Unit 1 - Amendment No. 158 Units l and 2 3.7.14-1 Unit 2 - Amendment No. 149

Spent Fuel Storage Pool Water Level 3.7.15 3.7 PLANT SYSTEMS 3.7.15 Spent Fuel Storage Pool Water Level LCO 3.7.15 The spent fuel'storage pool water level shall be 2 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage pool A.1 --------- NOTE-------------

water level not within LCO 3.0.3 is not applicable.

limit.

Suspend movement of Immediately irradiated fuel assemblies in the spent fuel storage pool.

SURVEILLANCE REQUIREMENTS, SURVEILLANCE FREQUENCY SR 3.7.15.1 Verify the spent fuel storage pool water level is 7 days z 23 ft above the top of the irradiated fuel assemblies seated in the storage racks.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.7.15-1 Unit 2 - Amendment No. 149

Spent Fuel Storage Pool Boron Concentration 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Spent Fuel Storage Pool Boron Concentration LCO 3.7.16 The spent fuel storage pool boron concentration shall be 2 1800 ppm.

APPLICABILITY: When fuel assemblies are stored in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage pool ------------------ NOTE-----------------

boron concentration not LCO 3.0.3 is not applicable.

within limit.

A.1 Suspend movement of fuel Immediately assemblies in the spent fuel storage pool.

AND A.2 Initiate action to restore spent Immediately fuel storage pool boron concentration to within limit.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.7.16-1 Unit 2 - Amendment No. 149

Spent Fuel Storage Pool Boron Concentration 3.7.16 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the spent fuel storage pool boron 7 days concentration is within limit.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.7.16-2 Unit 2 - Amendment No. 149

Spent Fuel Pool Storage 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Spent Fuel Pool Storage LCO 3.7.17 The combination of initial enrichment, burnup and decay time of each fuel assembly stored in the spent fuel pool shall be within the Unrestricted Region of Figure 3.7.17-1 or in accordance with Specification 4.3.1.1.

APPLICABILflY: Whenever any fuel assembly is stored in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A. 1 ------------- NOTE-------------

not met. LCO 3.0.3 is not applicable.

Initiate action to move the Immediately noncomplying fuel assembly to an acceptable location.

Prairie Island Unit 1 - Amendment No. 4-58, 172 Units I and 2 3.7.17-1 Unit 2 - Amendment No. 449, 1621

Spent Fuel Pool Storage 3.7.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify by administrative means the initial Prior to storing enrichment, burnup and decay time of the fuel or moving the assembly is in accordance with Figure 3.7.17-1 or fuel assembly Specification 4.3. 1.1. I SR 3.7.17.2 Verify spent fuel pool inventory. Within 7 days after completion of a spent fuel pool fuel handling campaign Prairie Island Unit I - Amendment No. 158, 172 Units 1 and 2 3.7.17-2 Unit 2 - Amendment No. I4, 162

Spent Fuel Pool Storage 3.7.17

-o years

-5 years 35000 -10 year

-15 year!

-20 year.

30000 25000 E 20000 15000

~ ---4--K t - - 1 <r; 10000 I------.-.-

l . ..-

I..l..j --- 1 RESTRICTED 1*

7TF iM - -

5000 0

1 2 3 4 5 InMtial Enrichment (%U235)

Figure 3.7.17-1 Spent Fuel Pool Unrestricted Region Burnup and Decay Time Requirements Prairie Island Unit I - Amendment No. 4148 172 Units 1 and 2 3.7.17-3 Unit 2 - Amendment No. 149, 162

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

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

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

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

ACTIONS

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

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required path A. 1 Perform SR 3.8.1.1 for the I hour inoperable. OPERABLE path.

AND Once per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter AND Prairie Island Unit 1 - Amendment No. 4-5g 4-6-7 175 Units I and 2 3.8.1-1 Unit 2- AmendmentNo. 44-9-4-5-7 165

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Restore path to 7 days OPERABLE status.

AND 21 days from discovery of failure to meet LCO B. One DG inoperable. B. 1 Perform SR 3.8.1.1 for the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months paths.

AND Once per 8 hours0.333 days 0.0476 weeks 0.011 months thereafter AND B.2 Declare required feature(s) 4 hours0.167 days 0.0238 weeks 0.00548 months from supported by the discovery of inoperable DG inoperable Condition B when its required concurrent with redundant feature(s) is inoperability of inoperable, redundant required feature(s)

AND Prairie Island Unit 1 - Amendment No. 1-5, 4-6-7 178 Units 1 and 2 3.8.1-2 Unit 2 - Amendment No. 449 4-5-7168

AC Sources-Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3.1 Determine OPERABLE 24 hours1 days 0.143 weeks 0.0329 months DG is not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for 24 hours1 days 0.143 weeks 0.0329 months OPERABLE DG.

AND B.4 Restore DG to 14 days OPERABLE status.

AND 21 days from discovery of failure to meet LCO Prairie Island Unit 1 - Amendment No. 4-5' 4-6-7 17 Units 1 and 2 3.8.1-3 Unit 2 -Amendment No. 449 4-5-7 161

AC Sources-Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two paths inoperable. C. l Declare required feature(s) 12 hours0.5 days 0.0714 weeks 0.0164 months from inoperable when its discovery of redundant required Condition C feature(s) is inoperable. concurrent with inoperability of redundant required features AND C.2 Restore one path to 24 hours1 days 0.143 weeks 0.0329 months OPERABLE status.

D. One path inoperable. ----------------- NOTE ----------------

Enter applicable Conditions and AND Required Actions of LCO 3.8.9, "Distribution Systems-One DG inoperable. Operating," when Condition D is entered with no AC power source to either train.

D.l Restore path to 12 hours0.5 days 0.0714 weeks 0.0164 months OPERABLE status.

OR D.2 Restore DG to 12 hours0.5 days 0.0714 weeks 0.0164 months OPERABLE status.

Prairie Island Unit I - Amendment No. 4US, 167 Units I and 2 3.8.1-4 Unit 2 - Amendment No. 449, 157

AC Sources-Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two DGs inoperable. E. 1 Restore one DG to 2 hours0.0833 days 0.0119 weeks 0.00274 months OPERABLE status.

F. Required Action and F.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time of Condition A, B, AND C, D, or E not met.

F.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months G. Two DGs inoperable and G.1 Enter LCO 3.0.3. Immediately one or more paths inoperable.

OR One DG inoperable and two paths inoperable.

Prairie Island Unit I - Amendment No. 4-Y , 167 Units I and 2 3.8.1-5 Unit 2- Amendment No. 4.49, 157

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated 7 days power availability for each required path.

SR 3.8.1.2 ------------------ NOTES ---------------

1. Performance of SR 3.8.1.6 satisfies this SR.

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

3. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR in consideration of manufacturer's recommendations. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.6 must be met.

Verify each DG starts from standby conditions and 31 days achieves steady state voltage > 3740 V and

< 4580 V, and frequency > 58.8 Hz and < 61.2 Hz.

Prairie Island Unit 1 - Amendment No. 448 175 Units 1 and 2 3.8.1-6 Unit 2 - Amendment No. 449 165

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

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

1. DG loadings may include gradual loading in consideration of manufacturer's recommendations.

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

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

4. This SR shall be preceded by and immediately follow without shutdown a successful performance of SR 3.8.1.2 or SR 3.8.1.6.

Verify each DG is synchronized and loaded and 31 days operates for > 60 minutes at a load:

a. Unit 1; > 2500 kW; and

b. Unit 2; >5100kW and_<5300 kW.

SR 3.8.1.4 Verify fuel oil level above lower limit switch in each 31 days day tank.

SR 3.8.1.5 Verify the fuel oil transfer system operates to transfer 31 days fuel oil from storage tank to the day tank.

Prairie Island Unit I - Amendment No. 4-58 4-7-4187 Units I and 2 3.8.1-7 Unit 2 - Amendment No. 4-49 165

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

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

All DG starts may be preceded by an engine prelube period.

Verify each DO starts from standby condition and 184 days achieves:

a. In.:::: 10 seconds, voltage ~ 3740 V and frequency ~ 58.8 Hz; and

b. Steady state voltage ~ 3740 V and.:::: 4580 V, and frequency ~ 58.8 Hz and.:::: 61.2 Hz.

SR 3.8.1.7 Verify each DG does not trip during and following a 24 months load rejection of:

1. Unit I ~ 650 kW; and

2. Unit 2 ~ 860 kW.

SR 3.8.1.8 Verify each DO's automatic trips are bypassed on an -------NOlLE-----

actual or simulated safety injection signal except: SR 3.0.2 interval extension (1.25

a. Engine overspeed; times the interval) applies

b. Generator differential current; and to this SR

c. Ground fault (Unit 1 only).

24 months Prairie Island Unit I - Amendment No. H-8 194 Units 1 and 2 3.8.1-8 Unit 2 - Amendment No. +49 183

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9 ----------------------------NOTES-------------------------

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

2. If performed with DG synchronized with offsite power, it shall be performed at a power factor

0.85. 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 practicabIe.

24 months Verify each DG operates for > 24 hours1 days 0.143 weeks 0.0329 months :

a. For 2: 2 hours0.0833 days 0.0119 weeks 0.00274 months loaded:

Unit I 2: 2832 kW, and

3000 kW Unit 2 ::: 5400 kW, and

5940 kW; and

b. For the remaining hours of the test loaded:

Unit 1 2:: 2500 kW, and Unit 2::: 4860 kW; and

c. Achieves steady state voltage y 3740 V and::: 4580 V; and frequency j 58.8 Hz and < 61.2 Hz.

Prairie Island Unit 1 - Amendment No. m -l-89 1961 Units I and 2 3.8.1-9 Unit 2 - Amendment No. +49 -l-+& 185

AC Sources-Operating 3.S.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.S.1.1 0 ----------------------------N OTES--------------------------

1. All DG starts may be preceded by an engine pre1ube period.

2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4.

3. 12 Battery Charger not required to be energized in SR 3.S.1.1O(c) until completion of this SR during Unit 1 2011 refueling outage.

24 months Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated safety injection actuation signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and energizes emergency loads in 5. 60 seconds.

SR 3.S.1.11 ----------------------------NOTE---------------------------

All DG starts may be preceded by an engine prelube period.

Verify on an actual or simulated loss of offsite power 24 months signal that the DG auto-starts from standby condition.

A modification will be installed during or prior to the Unit 1 2011 refueling outage to assure the 12 Battery Charger is automatically powered from its normal bus within 60 seconds. Compliance with this SR will be demonstrated after implementation of the modification.

Prairie Island Unit 1 Amendment No. H&.f-9&' 2001 Units 1 and 2 Unit 2 - Amendment No. 149

AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One path between the offsite transmission grid and the onsite 4 kV Safeguards Distribution System required by LCO 3.8.10, "Distribution Systems-Shutdown "; and

b. One diesel generator (DG) capable of supplying one train of the onsite 4 kV Safeguards Distribution System required by LCO 3.8.10.

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

LCO 3.8.2 may not be applicable for a period of 8 hours0.333 days 0.0476 weeks 0.011 months during the performance of SR 3.8.1. 10.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

I NOT E-------------------

LCO 3.0.3 not applicable.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.8.2-1 Unit 2 - Amendment No. 149

AC Sources - Shutdown 3.8.2 ACTIONS (continued).

CONDITION REQUIRED ACTION COMPLETION TIME A. Required path inoperable. ------------------ NOTE---------------

Enter applicable Conditions and Required Actions of LCO 3.8.10, with one required train de-energized as a result of Condition A.

A.1 Suspend CORE Immediately ALTERATIONS.

AND A.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.4 Initiate action to restore Immediately required path to OPERABLE status.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.8.2-2 Unit 2 - Amendment No. 149

AC Sources -Shutdown 3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One required DG B.1 Suspend CORE Immediately inoperable. ALTERATIONS.

AND B.2 Suspend movement of Immediately irradiated fuel assemblies.

AND B1.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND B.4 Initiate action to restore Immediately required DG to OPERABLE status.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.8.2-3 Unit 2 - Amendment No. 149

AC Sources - Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 --------------------------- NOTE-----------------------------

The following SRs are not required to be performed:

SR 3.8.1.2, SR 3.8.1.3, and SR 3.8.1.7 through SR 3.8.1.10.

For AC sources required to be OPERABLE, the SRs In accordance of Specification 3.8.1, "AC Sources-Operating," are with applicable applicable. SRs Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.8.2-4 Unit 2 - Amendment No. 149

Diesel Fuel Oil 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil LCO 3.8.3 The stored diesel generator (DG) fuel oil supply shall be within limits.

APPLICABILITY: When the DG(s) is required to be OPERABLE.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Stored DG fuel oil A.1 Restore fuel oil supply to 48 hours2 days 0.286 weeks 0.0658 months supply: within limits.

Unit 1 < 42,000 gal and

> 36,000 gal; Unit 2 < 75,000 gal and

> 65,000 gal.

B. One or more required DG B.1 Restore fuel oil tank(s) 7 days fuel oil tank(s) with properties to within limit(s).

stored fuel oil not within limit(s).

C. Required Action and C.1 Isolate the associated DG 2 hours0.0833 days 0.0119 weeks 0.00274 months associated Completion fuel oil tank(s).

Time of Condition B not met.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.8.3-1 Unit 2 - Amendment No. 149

Diesel Fuel Oil 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Stored DG fuel oil ----------------- NOTE----------------

supply: Enter applicable Conditions and Required Actions of LCO 3.7.8, Unit 1 < 36,000 gal; "CL System" for CL train(s) made inoperable as a result of Unit 2 < 65,000 gal. stored fuel oil properties not within limits.

OR Required Action and D. I Declare DGs inoperable. Immediately associated Completion Time of Conditions A or C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify stored DG fuel oil supply contains: 31 days Unit 1 2 42,000 gal; and Unit 2 2 75,000 gal of fuel.

SR 3.8.3.2 Verify fuel oil properties of new and stored fuel oil In accordance are tested in accordance with, and maintained within with the Diesel the limits of, the Diesel Fuel Oil Testing Program. Fuel Oil Testing Program Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.8.3-2 Unit 2 - Amendment No. 149

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 The Train A and Train B DC electrical power subsystems shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One battery charger A.1 Verify its associated battery 2 hours0.0833 days 0.0119 weeks 0.00274 months inoperable. is OPERABLE.

AND A.2 Verify the other train 2 hours0.0833 days 0.0119 weeks 0.00274 months battery charger is OPERABLE.

AND A.3 Verify the diesel generator 2 hours0.0833 days 0.0119 weeks 0.00274 months and safeguards equipment on the other train are OPERABLE.

AND A.4 Restore battery charger to 8 hours0.333 days 0.0476 weeks 0.011 months OPERABLE status.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.8.4-1 Unit 2 - Amendment No. 149

DC Sources - Operating 3.8.4 ACTIONS (continued) :-

CONDITION REQUIRED ACTION . COMPLETION TIME B. One battery B.] Verify associated battery 2 hours0.0833 days 0.0119 weeks 0.00274 months inoperable. charger is OPERABLE.

AND B.2 Verify other train battery is 2 hours0.0833 days 0.0119 weeks 0.00274 months OPERABLE.

AND B.3 Verify other train battery 2 hours0.0833 days 0.0119 weeks 0.00274 months charger is OPERABLE.

AND B.4 Restore battery to 8 hours0.333 days 0.0476 weeks 0.011 months OPERABLE status.

C. One DC electrical C.l Restore DC electrical 2 hours0.0833 days 0.0119 weeks 0.00274 months power subsystem power subsystem to inoperable for reasons OPERABLE status.

other than Condition A or B.

D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months Associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.8.4-2 Unit 2 - Amendment No. 149

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or 7 days equal to the minimum established float voltage.

SR 3.8.4.2 Verify each battery charger supplies 2 250 amps at 24 months greater than or equal to the minimum established float voltage for 2 4 hours0.167 days 0.0238 weeks 0.00548 months .

OR Verify each battery charger can recharge the battery to the fully charged state within 24 hours1 days 0.143 weeks 0.0329 months while supplying the demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

SR 3.8.4.3 -------------------------- NOTES----------------------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3.

2. This Surveillance shall not normally be performed in MODE 1, 2, 3, or 4. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.

Verify battery capacity is adequate to supply, and 24 months maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.8.4-3 Unit 2 - Amendment No. 149

DC Sources-Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources-Shutdown LCO 3.8.5 One DC electrical power subsystem shall be OPERABLE.

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

Service Building DC electrical power subsystem components may be used to replace safeguards DC electrical power subsystem components when the required safeguards DC electrical power subsystem is inoperable due to testing, maintenance, or replacement.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

--NOTE-LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required battery A.1 Restore battery charger to 8 hours0.333 days 0.0476 weeks 0.011 months charger inoperable. OPERABLE status.

Prairie Island Unit I -Amendment No. 158 Units I and 2 3.8.5-1 Unit 2 - Amendment No. 149

DC Sources-Shutdown 3.8.5 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME B. One required DC B.1 Suspend CORE Immediately electrical power ALTERATIONS.

subsystem inoperable for reasons other than AND Condition A.

B.2 Suspend movement of Immediately OR irradiated fuel assemblies.

Required Action and AND associated Completion Time of Condition A not B.3 Suspend operations Immediately met. involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND B.4 Initiate action to restore Immediately required DC electrical power subsystems to OPERABLE status.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.8.5-2 Unit 2 - Amendment No. 149

DC Sources-Shutdown 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 --------------------------- NOTE---------------------------

The following SRs are not required to be performed: SR 3.8.4.2 and SR 3.8.4.3.

For DC sources required to be OPERABLE, the In accordance following SRs are applicable: with applicable SRs SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.8.5-3 Unit 2 - Amendment No. 149

Battery Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Parameters LCO 3.8.6 Battery parameters for Train A and Train B batteries shall be within limits.

APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.

ACTIONS

NOT' '---

Separate Condition entry is allowed for each be CONDITION REQUIRED ACTION COMPLETION TIME A. One battery with one or A.l Perform SR 3.8.4.1. 8 hours0.333 days 0.0476 weeks 0.011 months more battery cells float voltage < 2.07 V. AND A.2 Perform SR 3.8.6.1. 8 hours0.333 days 0.0476 weeks 0.011 months AND A.3 Restores affected cell 24 hours1 days 0.143 weeks 0.0329 months voltage 2 2.07 V.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.8.6-1 Unit 2 - Amendment No. 149

Battery Parameters 3.8.6 ACTIONS (continued) _ _

CONDITION REQUIRED ACTION COMPLETION TIME B. One battery with float B.1 Perform SR 3.8.4.1. 8 hours0.333 days 0.0476 weeks 0.011 months current > 2 amps.

AND B.2 Restore battery float 24 hours1 days 0.143 weeks 0.0329 months current to

2 amps.

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

Required Action C.2 shall be Required Actions C. 1 and C.2 are completed if electrolyte level only applicable if electrolyte level was below the top of plates. was below the top of plates.

C. One battery with one or C. I Restore electrolyte level to 8 hours0.333 days 0.0476 weeks 0.011 months more cells electrolyte above top of plates.

level less than minimum established design limits. AND C.2 Verify no evidence of 12 hours0.5 days 0.0714 weeks 0.0164 months leakage.

AND C.3 Restore electrolyte level to 31 days greater than or equal to minimum established design limits.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.8.6-2 Unit 2 - Amendment No. 149

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One battery with pilot D.1 Restore battery pilot cell 12 hours0.5 days 0.0714 weeks 0.0164 months cell electrolyte temperature to 2 minimum temperature less than established design limits.

minimum established design limits.

E. Battery parameters in E.1 Restore battery parameters 8 hours0.333 days 0.0476 weeks 0.011 months both trains not within for battery in one train to limits. within limits.

F. Required Action and F.1 Declare associated battery Immediately associated Completion inoperable.

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

OR One battery with one or more battery cells float voltage < 2.07 V and float current > 2 amps.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.8.6-3 Unit 2 - Amendment No. 149

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 --------------------------- NOTE---------------------------

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is

2 amps. 7 days SR 3.8.6.2 Verify each battery pilot cell voltage is 2 2.07 V. 31 days SR 3.8.6.3 Verify each battery connected cell electrolyte level is 31 days greater than or equal to minimum established design limits.

SR 3.8.6.4 Verify each battery pilot cell temperature is greater 31 days than or equal to minimum established design limits.

SR 3.8.6.5 Verify each battery connected cell voltage 92 days is 2 2.07 V.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.8.6-4 Unit 2 - Amendment No. 149

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.6 -----------------------------NOTE -----------------------

This Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is 2 80% of the 60 months manufacturer's-rating when subjected to a performance discharge test or a modified AND performance discharge test.

12 months when battery shows degradation, or has reached 85%

of the expected life with capacity

< 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity 2 100% of manufacturer's rating Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.8.6-5 Unit 2 - Amendment No. 149

Inverters-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters-Operating LCO 3.8.7 Four Reactor Protection Instrument AC inverters shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Reactor Protection A.1 Verify Reactor Protection 2 hours0.0833 days 0.0119 weeks 0.00274 months Instrument AC inverter Instrument AC panel with inoperable. inoperable inverter is powered from Panel 117 (Unit 2 - Panel 217).

OR A.2 Verify Reactor Protection 2 hours0.0833 days 0.0119 weeks 0.00274 months Instrument AC panel with inoperable inverter is powered from its inverter bypass source.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.8.7-1 Unit 2 - Amendment No. 149

Inverters-Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two required Reactor - ------------- NOTE----------------

Protection Instrument AC Enter applicable Conditions and inverters inoperable. Required Actions of LCO 3.8.9, "Distribution Systems-Operating" with any Reactor Protection Instrument AC panel de-energized.

B.1 Verify no more than one 2 hours0.0833 days 0.0119 weeks 0.00274 months Reactor Protection Instrument AC panel is powered from Panel 117 (Unit 2 - Panel 217).

AND B.2 Verify one or both Reactor 2 hours0.0833 days 0.0119 weeks 0.00274 months Protection Instrument AC panel(s) is powered from an inverter bypass source.

AND B.3 Restore one inverter to 8 hours0.333 days 0.0476 weeks 0.011 months OPERABLE status.

C. Required Action and C.l Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.8.7-2 Unit 2 - Amendment No. 149

Inverters-Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage and alignment to 7 days required Reactor. Protection Instrument AC panels.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.8.7-3 Unit 2 - Amendment No. 149

Inverters-Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters-Shutdown LCO 3.8.8 One Reactor Protection Instrument AC inverter shall be OPERABLE.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

N( .--

LCO 3.0.3 not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required inverter A.1 Suspend CORE Immediately inoperable. ALTERATIONS.

AND A.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND Prairie Island Unit I -Amendment No. 158 Units 1 and 2 3.8.8-1 Unit 2 - Amendment No. 149

Inverters-Shutdowvn 3.8.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Initiate action to restore Immediately required inverter to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage and alignment to 7 days required Reactor Protection Instrument AC panel.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.8.8-2 Unit 2 - Amendment No. 149

Distribution Systems-Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems-Operating LCO 3.8.9 Train A and Train B safeguards AC and DC, and Reactor Protection Instrument AC electrical power distribution subsystems shall be OPERABLE.

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

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

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

A.l Restore safeguards AC 8 hours0.333 days 0.0476 weeks 0.011 months electrical power distribution subsystems to AND OPERABLE status.

16 hours0.667 days 0.0952 weeks 0.0219 months from discovery of failure to meet LCO Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.8.9-1 Unit 2 - Amendment No. 149

Distribution Systems-Operating 3.8.9 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more safeguards B.1 Restore safeguards DC 2 hours0.0833 days 0.0119 weeks 0.00274 months DC electrical power electrical power distribution subsystems distribution subsystems to AND inoperable. OPERABLE status.

16 hours0.667 days 0.0952 weeks 0.0219 months from discovery of failure to meet LCO C. One Reactor Protection C.1 Restore Reactor Protection 2 hours0.0833 days 0.0119 weeks 0.00274 months Instrument AC panel Instrument AC panel to inoperable. OPERABLE status. AND 16 hours0.667 days 0.0952 weeks 0.0219 months from discovery of failure to meet LCO D. Required Action and D.1 Be in MODE 3. 6 hours0.25 days 0.0357 weeks 0.00822 months associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours1.5 days 0.214 weeks 0.0493 months Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.8.9-2 Unit 2 - Amendment No. 149

Distribution Systems-Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two trains with E.1 Enter LCO 3.0.3. Immediately inoperable distribution subsystems that result in a loss of safety function.

OR Two or more Reactor Protection Instrument AC panels inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker and switch alignments and 7 days voltage to safeguards AC, DC, and Reactor Protection Instrument AC electrical power distribution subsystems.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.8.9-3 Unit 2 - Amendment No. 149

Distribution Systems-Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems-Shutdown LCO 3.8.10 The necessary portion of safeguards AC, DC, and Reactor Protection Instrument AC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately safeguards AC, DC, or supported required Reactor Protection feature(s) inoperable.

Instrument AC electrical power distribution OR subsystems inoperable.

A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.8.10-1 Unit 2 - Amendment No. 149

Distribution Systems-Shutdown 3.8.10 ACTIONS (continued) .

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.4 Initiate actions to restore Immediately required safeguards AC, DC, and Reactor Protection Instrument AC electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required residual heat removal subsystem(s) inoperable and not in operation.

Prairie Island Unit I -Amendment No. 158 Units I and 2 3.8.10-2 Unit 2 - Amendment No. 149

Distribution Systems-Shutdown 3.8.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker and switch alignments and 7 days voltage to required safeguards AC, DC, and Reactor Protection Instrument AC electrical power distribution subsystems.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.8.10-3 Unit 2 - Amendment No. 149

Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System and the refueling cavity shall be maintained within the limits specified in the COLR.

APPLICABILITY: MODE 6.

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

Only applicable to the refueling cavity when connected to the RCS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration A.1 Suspend CORE Immediately not within limits. ALTERATIONS.

AND A.2 Suspend positive reactivity Immediately additions.

AND A.3 Initiate action to restore Immediately boron concentration to within limits.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.9.1-1 Unit 2 - Amendment No. 149

Boron Concentration 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limits 72 hours3 days 0.429 weeks 0.0986 months specified in COLR.

Prairie Island Unit 1 -Amendment No. 158 Units 1 and 2 3.9.1-2 Unit 2 - Amendment No. 149

Refueling Cavity Water Level 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refueling Cavity Water Level LCO 3.9.2 Refueling cavity water level shall be maintained 2 23 ft above the top of reactor vessel flange.

APPLICABILl=Y: During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water A.1 Suspend movement of Immediately level not within limit. irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify refueling cavity water level is 2 23 ft above 24 hours1 days 0.143 weeks 0.0329 months the top of reactor vessel flange.

Prairie Island Unit 1 -Amendment No. 158 Units I and 2 3.9.2-1 Unit 2 - Amendment No. 149

Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Nuclear Instrumentation LCO 3.9.3 Two core subcritical neutron flux monitors shall be OPERABLE.

AND One core subcritical neutron flux monitor audible count rate circuit shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required core A.1 Suspend CORE Immediately subcritical neutron flux ALTERATIONS.

monitor inoperable.

AND A.2 Suspend operations that Immediately would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.9.3-1 Unit 2 - Amendment No. 149

Nuclear Instrumentation 3.9.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Two required core B.1 Initiate action to restore Immediately subcritical neutron flux one core subcritical monitors inoperable. neutron flux monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1. Once per 12 hours0.5 days 0.0714 weeks 0.0164 months C. Required core subcritical C.1 Initiate action to isolate Immediately neutron flux monitor unborated water sources.

audible count rate circuit inoperable. AND C.2 Suspend CORE Immediately ALTERATIONS.

Prairie Island Unit I - Amendment No. 158 Units 1 and 2 3.9.3-2 Unit 2 - Amendment No. 149

k Nuclear Instrumentation 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform CHANNEL CHECK of required channels. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.9.3.2 ------------------ NOTE ---------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION of required 24 months channels.

Prairie Island Unit 1 - Amendment No. 4- 175 Units 1 and 2 3.9.3-3 Unit 2 - Amendment No. -149 165

Containment Penetrations 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Containment Penetrations LCO 3.9.4 The containment penetrations shall be in the following status:

a. The equipment hatch closed and held in place by four bolts;

b. One door in each air lock closed, and

c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere closed by a manual or automatic isolation valve, blind flange, or equivalent.

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

Penetration flow path(s) providing access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls.

APPLICABI11Y: During movement of recently irradiated fuel assemblies within I containment.

Prairie Island Unit I - Amendment No. 41-5 166 Units 1 and 2 3.9.4-1 Unit 2 - Amendment No. 149 156

Containment Penetrations 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A. 1 Suspend movement of Immediately penetrations not in recently irradiated fuel required status. assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify each required containment penetration is in 7 days the required status.

Prairie Island Unit 1 - Amendment No. 4--48 166 Units I and 2 3.9.4-2 Unit 2 - Amendment No. 449 156

RHR and Coolant Circulation-High Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation-High Water Level LCO 3.9.5 One RHR loop shall be OPERABLE and in operation.

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

The required RHR loop may be removed from operation for

I hour per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would cause introduction into the Reactor Coolant System, coolant with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9. 1.

APPLICABILITY: MODE 6 with the water level 2 20 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RHR loop requirements A.1 Suspend operations that Immediately not met. would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND A.2 Suspend loading irradiated Immediately fuel assemblies in the core.

AND Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.9.5-1 Unit 2 - Amendment No. 149

RHR and Coolant Circulation-High Water Level 3.9.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION

._ TIME A. (continued) A.3 Initiate action to satisfy Immediately RHR loop requirements.

IAND IA.4 Close equipment hatch and 4 hours0.167 days 0.0238 weeks 0.00548 months secure with four bolts.

AND A.5 Close one door in each 4 hours0.167 days 0.0238 weeks 0.00548 months airlock.

AND A.6. 1 Close each penetration 4 hours0.167 days 0.0238 weeks 0.00548 months providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, or blind flange.

OR A.6.2 Verify each penetration is 4 hours0.167 days 0.0238 weeks 0.00548 months capable of being closed by an OPERABLE Containment Ventilation Isolation System.

Prairie Island Unit I - Amendment No. 158 Units I and 2 3.9.5-2 Unit 2 - Amendment No. 149

RHR and Coolant Circulation-High Water Level 3.9.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months Prairie Island Unit I - Amendment No. 158 Units I and 2 3.9.5-3 Unit 2 - Amendment No. 149

RHR and Coolant Circulation-Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

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

1. Both RHR pumps may be de-energized for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided:

a. The core outlet temperature is maintained > 10 degrees F below saturation temperature;

b. No operations are permitted that would cause a reduction of the Reactor Coolant System (RCS) boron concentration; and

c. No draining operations to further reduce RCS water volume are permitted.

2. One required RHR loop may be inoperable for up to 2 hours0.0833 days 0.0119 weeks 0.00274 months for surveillance testing, provided that the other RHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 6 with the water level < 20 ft above the top of reactor vessel flange.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.9.6-1 Unit 2 - Amendment No. 149

RHR and Coolant Circulation-Low Water Level 3.9.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loop(s) to OPERABLE. OPERABLE status.

OR A.2 Initiate action to establish Immediately

Ž 20 ft of water above the top of reactor vessel flange.

B. No RHR loop in B.1 Suspend operations that Immediately operation. would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND B.2 Initiate action to restore one Immediately RHR loop to operation.

AND B.3 Close equipment hatch and 4 hours0.167 days 0.0238 weeks 0.00548 months secure with four bolts.

AND B.4 Close one door in each air 4 hours0.167 days 0.0238 weeks 0.00548 months lock.

AND Prairie Island Unit 1 - Amendment No. 158 Units I and 2 3.9.6-2 Unit 2 - Amendment No. 149

RHR and Coolant Circulation-Low Water Level 3.9.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.5.1 Close each penetration 4 hours0.167 days 0.0238 weeks 0.00548 months providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, or blind flange.

OR B.5.2 Verify each penetration is 4 hours0.167 days 0.0238 weeks 0.00548 months capable of being closed by an OPERABLE Containment Ventilation Isolation System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation. 12 hours0.5 days 0.0714 weeks 0.0164 months SR 3.9.6.2 Verify correct breaker alignment and indicated power 7 days available to the required RHR pump that is not in operation.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 3.9.6-3 Unit 2 - Amendment No. 149

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The site for the Prairie Island Nuclear Generating Plant is located on the west bank ofthe Mississippi River, approximately 6 miles northwest of the city of Red Wing, Minnesota. The site exclusion area boundary has a minimum radius of 715 meters from the center line of either reactor.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 121 fuel assemblies. Each assembly shall consist ofa matrix ofZircaloy, ZIRLO', or Optimized ZIRLO' fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 29 control rod assemblies. The control material shall be silver indium cadmium as approved by the NRC.

Prairie Island Unit 1 - Amendment No. ~ 199 Units 1 and 2 Unit 2 - Amendment No. +49 187

Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;

b. kerr < 1.0 if fully flooded with unborated water, which includes an allowance for uncertainties as described in USAR Section 10.2;

c. kerr::: 0.95 if fully flooded with water borated to 730 ppm, which includes an allowance for uncertainties as described in USAR Section 10.2;

d. A nominal 9.5 inch center to center distance between fuel assemblies placed in the fuel storage racks;

e. New or spent fuel assemblies with a combination of discharge burnup, initial enrichment and decay time in the "unrestricted range" of Figure 3.7.17-1 may be allowed unrestricted storage in the fuel storage racks; and

f. New or spent fuel assemblies with a combination of discharge burnup, initial enrichment and decay time in the "restricted range" of Figure 3.7.17-1 will be stored in compliance with Figures 4.3.1-1 through 4.3.1-4.

Prairie Island Unit 1 - Amendment No. 158 1721192 Units 1 and 2 4.0-2 Unit 2 - Amendment No. 149.162 181

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;

b. keff < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in USAR Section 10.2;

c. keff ~ 0.98 if accidentally filled with a low density moderator which resulted in optimum low density moderation conditions; and

d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

4.3.1.3 Fuel will not be inserted into a TN-40 spent fuel cask in the pool unless a minimum boron concentration of 1800 ppm is present.

The 1800 ppm will ensure that ketf for the spent fuel cask, including statistical uncertainties, will be ~ 0.95 for all postulated arrangements of fuel within the cask. The criticality analyses for the TN-40 spent fuel storage cask were based on fresh fuel enriched to 3.85 weight percent U-235.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 727' 4" (Mean Sea Level).

Prairie Island Unit 1 - Amendment No. ~ 192 Units 1 and 2 4.0-3 Unit 2 - Amendment No. -l49 181

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1386 fuel assemblies not including those assemblies which can be returned to the reactor. The southeast comer of the small pool serves as the spent fuel cask lay down area. To facilitate plant evolutions, four additional storage racks, with a combined capacity of 196, may be temporarily installed in the cask lay down area to provide a total of 1582 storage locations (USAR Section 10.2).

Prairie Island Unit 1 - Amendment No . .J..=R +W 1192 Units 1 and 2 4.0-4 Unit 2 - Amendment No. ~ -l-+Q 181

Design Features 4.0 I IX E Fresh Fuel: Must be less than or equal to Nominal 4.95 w/o 235U No restrictions on burnup Assemblies with GAD shall have a minimum of 4 fuel rods with a minimum concentration of 4.0 w/o Gd 2O3.

[I Burned Fuel: Must satisfy minimum burnup requirements of Figures 4.3.1-3 or 4.3.1-4 depending on presence of GAD rods in fresh fuel Figure 4.3.1-1 Spent Fuel Pool Burned/Fresh Checkerboard Cell Layout Prairie Island Unit 1 - Amendment No. 4-58, 1721 Units 1 and 2 4.0-5 Unit 2 - Amendment No. 449, 1621

Design Features 4.0 Interface I

Fresh Fuel: Must be less than or equal to nominal 4.95 w/o 235U No restrictions on burnup Burned Fuel: 3x3 Checkerboard Region Must satisfy minimum burnup requirements of Figure 4.3.1-3 or 4.3.1-4 I Burned Fuel: All Cell Unrestricted Region Must satisfy minimum burnup requirements of Figure 3.7.17-1 I Figure 4.3.1-2 Spent Fuel Pool Checkerboard Interface Requirements Prairie Island Unit 1 - Amendment No. 45, 172l Units 1 and 2 4.0-6 Unit 2 - Amendment No. 4141, 16

Design Features 4.0 7iI7-----'-

- J- ----

-- - -Z 1- -F-I-A-

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-jfI 0.

2 3 4 5 Initial Enrli.hment (%U235)

Figure 4.3.1-3 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements

- No GAD Prairie Island Unit 1 - Amendment No. +-l 17,2 Units 1 and 2 4.0-7 Unit 2 - Amendment No. 4-9, 162

Design Features 4.0 45000 T

X Fl KFI § V- T -0 years

- 5 years IO-1years I -I 15 years 40000

_-20 years 35000 4 4+ I 0 .......... EP ACC S _T___ j [i . -! //4 -

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Figure 4.3.1-4 Spent Fuel Pool Checkerboard Region Burnup and Decay Time Requirements - Fuel with GAD Prairie Island Unit 1 - Amendment No. 5,172 Units l and 2 4.0-8 Unit 2 - Amendment No. 44 162

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.

5.1.2 The shift supervisor (SS) shall be responsible for the control room command function. During any absence of the SS from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with an active senior reactor operator (SRO) license shall be designated to assume the control room command function. During any absence of the SS from the control room while the unit is in MODE 5 or 6, an individual with an active SRO license or reactor operator (RO) license shall be designated to assume the control room command function.

Prairie Island Unit 1 - Amendment No. 158 Units I and 2 5.0-1 Unit 2 - Amendment No. 149

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for plant operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements, including the plant specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Updated Safety Analysis Report (USAR);

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

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

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

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 5.0-2 Unit 2 - Amendment No. 149

Organization 5.2 5.2 Organization (continued) 5.2.2 Plant Staff The plant staff organization shall include the following:

a. An operator to perform non-licensed duties shall be assigned to each reactor containing fuel and one additional operator to perform non licensed duties shall be assigned when either or both reactors are operating in MODES 1,2,3, or 4.

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to ex(:eed 2 hours0.0833 days 0.0119 weeks 0.00274 months in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c. An individual qualified in radiation protection procedures shall be on site when fuel is in a reactor. The position may be vacant for not more than 2 hours0.0833 days 0.0119 weeks 0.00274 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. Not Used.

Prairie Island Unit 1 - Amendment No. ~ 193 Units 1 and 2 5.0-3 Unit 2 - Amendment No. -l49 182

Organization 5.2 5.2 Organization 5.2.2 Plant Staff (continued)

e. The operations manager or assistant operations manager shall hold an SRO license. In addition, the duty shift manager shall hold an SRO license.

f. In MODES 1,2,3, and 4, the shift technical advisor shall provide advisory technical support to the unit operations shift crew in the areas ofthennal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

Prairie Island Unit I - Amendment No. H& +84 193 Units I and 2 5.0-4 Unit 2 - Amendment No. +49 H4 182

Plant Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Plant Staff Qualifications 5.3. i Each member of the plant staff shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 1, September 1975 except for (I) the operations manager who shall meet the requirements of ANSI N 18.1-1971, except that NRC license requirements are as specified in TS 5.2.2.e, and (2) the education and experience eligibility requirements for operator license applicants, and changes thereto, shall be those previously reviewed and approved by the NRC, specifically those referenced in NMC'* I letter dated March 19, 2003.

5.3.2 For the purpose of 10 CFR 55.4, a licensed senior reactor operator (SRO) and a licensed reactor operator (RO) are those individuals who, in addition to meeting-the requirements of TS 5.3.1, perform the functions described in i0 CFR 50.54(m).

" NMC is maintained as historical information I

Unit I - Amendment No. 4-584-9*5-84188 Utilts I ind 2 5)-5 lUnit 2 - A\mnendment No. 449 4-- 44--4177

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

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

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

c. Quality control for effluent and environmental monitoring;

d. Fire Protection Program implementation; and

e. All programs specified in Specification 5.5.

Prairie Island Unit I - Amendment No. 158 Units I and 2 5.0-6 Unit 2 - Amendment No. 149

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

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

b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Monitoring, and Radioactive Effluent Reports required by Specification 5.6.2 and Specification 5.6.3.

Changes to the ODCM:

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

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

2. a determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix 1, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b. Shall become effective after the approval by a member of plant management designated by the plant manager; and Prairie Island Unit 1 - Amendment No. 158 Units l and 2 5.0-7 Unit 2 - Amendment No. 149

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) (continued)

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed. The date (i.e., month and year) the change was implemented shall be indicated.

5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practical. The systems include portions of the Residual Heat Removal and Safety Injection Systems. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at refueling cycle intervals or less.

5.5.3 Post Accident Sampling This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions.

The program shall include the following:

a. Training of personnel;

b. Procedures for sampling and analysis; and

c. Provisions for maintenance of sampling and analysis equipment.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 5.0-8 Unit 2 - Amendment No. 149

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.

This program shall allocate releases equally to each unit. The liquid radwaste treatment system, waste gas treatment system, containment purge release vent, and spent fuel pool vent are shared by both units. Experience has also shown that contributions from both units are released from each auxiliary building vent. Therefore, all releases will be allocated equally in determining conformance to the design objectives of 10 CFR 50, Appendix 1.

The program shall be contained in the ODCM. shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

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

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402;

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

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix 1; Prairie Island Unit I - Amendment No. 158 Units 1 and 2 5.0-9 Unit 2 - Amendment No. 149

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM.

Determination of projected dose contributions for radioactive effluents in accordance with the methodology in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days from the liquid effluent releases would exceed 0.12 mrem to the total body or 0.4 mrem to any organ; or from the gaseous effluent releases would exceed 0.4 mrad for gamma air dose, 0.8 mrad for beta air dose, or 0.6 mrem organ dose;

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

1. for noble gases: a dose rate < 500 mrem/yr to the whole body and a dose rate < 3000 mrem/yr to the skin, and

2. for iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate

1500 mrem/yr to any organ;

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

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and Prairie Island Unit 1 - Amendment No. 4-55& 176 Units l and 2 5.0-10 Unit 2 - Amendment No. 449 166

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

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

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the USAR, Section 4.1.4, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Reactor Coolant Pumo Flywheel Inspection Proaram This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. In lieu of Position C.4.b(1) and C.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT or PT) of exposed surfaces of the removed flywheels may be conducted at 20 intervals.

Inservice Testing, Proram This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

Prairie Island Unit 1 - Amendment No. 4-54 4-70 185 Units I and 2 5.0-11 Unit 2 - Amendment No. 449 4-60 175

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Inservice Testing Program (continued)

a. Testing frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASMEOM Code) and applicable Addenda as follows:

ASME OM Code and applicable Addenda terminology for Required Frequencies inservice testing for performing inservice activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Semiquarterly At least once per 46 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as less than 2 years in the Inservice Testing (IST) Program for performing inservice testing activities. As an exception to SR 3.0.2, IST Program testing with the Frequency specified as 2 years (24 months) is met if the test is performed within 30 months (1.25 times the interval specified in the Frequency);

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.

Prairie Island Unit 1 - Amendment No. 4-58 185 Units 1 and 2 5.0-12 Unit 2 - Amendment No. 44-9 175

Programs and Manuals 5.5 5.5 Progrars and Manuals (continued) -

5.5.8 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained. In addition, the Steam Generator Program shall include the following provisions:

a. Provisions for condition monitoring assessments. Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging or repair of tubes. Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected, plugged, or repaired to confirm that the performance criteria are being met.

b. Performance criteria for SG tube integrity. SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE.

1. Structural integrity performance criterion: All in-service steam generator tubes shall retain structural integrity over the full range of normal operating conditions (including startup, operation in the power range, hot standby, and cool down and all anticipated transients included in the design specification) and design basis accidents. This includes retaining a safety factor of 3.0 against burst under normal steady state full power operation primary-to-secondary pressure differential and, except for flaws addressed through application of the alternate repair criteria discussed in Specification 5.5.8.c.2(c), a safety factor of 1.4 against burst applied to uti design basis accident primary-to-secondary pressure differentials. Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design and licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse.

Prairie Island Unit 1 - Amendment No. 54 177 Units I and 2 5.0-13 Unit 2 - Amendment No. 4-49 167

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued)

In the assessment of tube integrity, those loads that do significantly affect burst or collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads. For Unit 2, when alternate repair criteria discussed in Specification 5.5.8.c.2(c) are applied to axially oriented outside diameter stress corrosion cracking indications at the tube support plate locations, the probability that one or more of these indications in an SG will burst under postulated main steam line break conditions shall be less than IE-02.

2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. For Unit 1, leakage is not to exceed I gpm per SG. For Unit 2, leakage from all sources, excluding the leakage attributed to the degradation associated with implementation of the voltage-based repair criteria discussed in Specification 5.5.8.c.2(c), is not to exceed 1 gpm per SG.

3. The operational LEAKAGE performance criterion is specified in LCO 3.4.14, "RCS Operational LEAKAGE."

c. Provisions for SG tube repair criteria:

1. Unit I steam generator tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal tube wall thickness shall be plugged.

2 Unit 2 steam generator tubes- found by inservice inspection to contain flaws shall be dispositioned as follows:

Prairie Island Unit 1 - Amendment No. 4-5g 177 Units l and 2 5.0-14 Unit 2 - Amendment No. 449 167

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued)

(a) Depth Based Criteria:

(1) Tubes found by inservice inspection containing a flaw in a non-sleeved region with a depth equal to or exceeding 50% of the nominal tube wall thickness shall be plugged or repaired except if permitted to remain in service through application of the alternate tube repair criteria discussed in Specification 5.5.8.c.2(b) or in Specification 5.5.8.c.2(c). If significant general tube thinning occurs, this criterion is reduced to 40% wall penetration.

(2) Tubes found by inservice inspection containing a flaw in the pressure boundary region of any sleeve exceeding 25% of the nominal sleeve wall thickness shall be plugged.

(3) Tubes with a flaw in a sleeve to tube joint that occurs in the original tube wall of the joint shall be plugged.

(b) The following F* or EF* Alternate Repair Criteria may be applied to the hot-leg of the tubesheet as an alternative to the depth based criteria in Specification 5.5.8.c.2(a)(1):

(1) F* Criterion: If the bottom of the uppermost hardroll transition in the tubesheet is below the midplane of the tubesheet, then all flaws located below 1.07 inches from the bottom of this uppermost hardroll transition (not including eddy current uncertainty) may be allowed to remain in service provided the tube does not contain any flaws within this 1.07-inch span (not including eddy current uncertainty).

This 1.07-inch span (increased for measurement uncertainty) is referred to as the F* region. If flaws are contained within the F* region, the tube shall be plugged or repaired.

Prairie Island Unit 1 - Amendment No. 4-59 177 Units 1 and 2 5.0-15 Unit 2 - Amendment No. 449 167

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Steam Generator (SG) Program (continued)

(2) EF* Criterion: If the bottom of the uppermost hardroll transition in the tubesheet is above the midplane of the tubesheet but at least 2.0 inches below the top of the secondary face of the tubesheet, then all flaws located below 1.67 inches from the bottom of the uppermost hardroll transition (not including eddy current uncertainty) may be allowed to remain in service provided the tube does not contain any flaws within this 1.67-inch span (not including eddy current uncertainty). This 1.67-inch span (increased for measurement uncertainty) is referred to as the EF* region. If flaws are contained within the EF* region, the tube shall be plugged or repaired.

(c) The following Alternate Tube Support Plate Voltage-Based Repair Criteria may be applied as an alternative to the depth based criteria in Specification 5.5.8.c.2(a)(1): For regions of the tube affected by predominately axially oriented outside diameter stress corrosion cracking confined within the thickness of tube support plates the plugging or repair limit is as follows:

(1) If the bobbin voltage associated with the indication is less than or equal to 2.0 Volts, the indication is allowed to remain in service.

(2) If the bobbin voltage associated with the indication is greater than 2.0 Volts, the tube shall be plugged or repaired unless the voltage is less than or equal to the upper voltage repair limit (calculated according to the methodology in GL 95-05 as supplemented) and a rotating pancake coil (or comparable examination technique) does not detect a flaw.

- In this latter-case, the indication may remain in service.

Prairie Island Unit 1 - Amendment No. 4-51177 Units l and 2 5.0-16 Unit 2- Amendment No. 449 167

Programs and Manuals 5.5 5.5 __ Programs and Manuals- -..

5.5.8 Steam Generator (SG) Program (continued) 3 If an unscheduled mid-cycle inspection is performed, the following mid-cycle repair limits apply instead of the limits in Specifications 5.5.8.c.2(c)(1) and 5.5.8.c.2(c)(2) above. The mid-cycle repair limits are determined from the following equations:

VMURL= VSL.

1.0 + NDE + GrKL -At) kCL)

VMLRL=VMURL-(VURL-2 .0) (CL -At)

Where:

VURL = upper voltage repair limit VLRL = lower voltage repair limit VMURL = mid-cycle upper voltage repair limit based on time into cycle VMLRL = mid-cycle lower voltage repair limit based on VMURL and time into cycle At = length of time since last scheduled inspection during which Vup, and VLRL were implemented Prairie Island Unit 1 - Amendment No. 14-8 177 Units 1 and 2 5.0-17 Unit 2 - Amendment No. 449 167

Programs and Manuals 5.5 5.5 . Programs-and Manuals -_...

5.5.8 Steam Generator (SG) Program (continued)

CL = cycle length (time between two scheduled steam generator inspections)

VSL = structural limit voltage Gr = average growth rate per cycle length NDE = 95 percent cumulative probability allowance for nondestructive examination uncertainty (i.e., a value of 20 percent has been approved by the NRC)

Implementation of these mid-cycle repair limits should follow the same approach as described in Specifications 5.5.8.c.2(c)(1) and 5.5.8.c.2(c)(2) above.

Note: The upper voltage repair limit is calculated according to the methodology in GL 95-05 as supplemented.

d. Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tube-to-tubesheet weld at the tube outlet, and that may satisfy the applicable tube repair criteria. In tubes repaired by sleeving, the portion of the original tube wall between the sleeve's joints is not an area requiring re-inspection. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.1, d.2, d.3 and d.4 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is maintained until the Prairie Island Unit 1 - Amendment No. 4--5 177 Units 1 and 2 5.0-18 Unit 2 - Amendment No. 449 167

Programs and Manuals 5.5

.5.5 __...Programs andManuals---------............ .. --

5.5.8 Steam Generator (SG) Program (continued) next SG inspection. An assessment of degradation shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations.

1. Inspect 100% of the tubes in each SG during the first refueling outage following SG replacement.

2. For Unit I SGs, inspect 100% of the tubes at sequential periods of 144, 108, 72, and, thereafter, 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs. In addition, inspect 50% of the tubes by the refueling outage nearest the midpoint of the period and the remaining 50% by the refueling outage nearest the end of the period. No SG shall operate for more than 72 effective full power months or three refueling outages (whichever is less) without being inspected.

3. For Unit 2 SGs, inspect 100% of the tubes at sequential periods of 60 effective full power months. The first sequential period shall be considered to begin after the first inservice inspection of the SGs.

No SG shall operate more than 24 effective full power months or one refueling outage (whichever is less) without being inspected.

(a) During each Unit 2 SG inspection (every 24 effective full power months (EFPM) or one refueling outage (whichever is less)), all tubes within that SG which have had the F* or EF*

criteria applied will be inspected in the F* and EF* regions of the roll expanded region. The region of these tubes below the F* and EF* regions do not need to be inspected, unless there is a sleeve (or portion of a sleeve) that extends below the F* or EF* region.

Prairie Island Unit 1 - Amendment No. 1- 177 Units l and 2 5.0-19 Unit 2 - Amendment No. 44-9 167

Programs and Manuals 5.5 5.5 Program s-and M an uals .. .. ... .. . .... . ..... .. . .. . . . .. .... . .

5.5.8 Steam Generator (SG) Program (continued)

(b) Implementation of the SG tube alternate repair criteria discussed in Specification 5.5.8.c.2(c) requires a 100 percent bobbin coil inspection for hot leg and cold leg tube support plate intersections down to the lowest cold leg tube support plate with known outside diameter stress corrosion cracking (ODSCC) indications. The determination of the lowest cold leg tube support plate intersections having ODSCC indications shall be based on the performance of at least a 20 percent random sampling of tubes inspected over their full length.

(c) SG tube indications left in service as a result of application of the alternate repair criteria discussed in Specification 5.5.8.c.2(c) shall be inspected by bobbin coil probe every 24 EFPM or one refueling outage (whichever is less).

4. If crack indications are found in any SG tube, then the next inspection for each SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever is less). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack.

e. Provisions for monitoring operational primary to secondary LEAKAGE.

f. Provisions for SG tube repair methods. Steam generator tube repair methods shall provide the means to reestablish the RCS pressure boundary integrity of SG tubes without removing the tube from service. For the purposes of these Specifications, tube plugging is not a repair. All acceptable tube repair methods are listed below.

1. There are no approved SG tube repair methods -for the Unit I SGs.

Prairie Island Unit 1 - Amendment No. 9-8 177 Units 1 and 2 5.0-20 Unit 2 - Amendment No. 449 167

Programs and Manuals 5.5

-5.5 ... Program s-and-M anuals--- .. ..- . . .. .. . .....- ............ ....- ...- ..-...- ..

5.5.8 Steam Generator (SG) Program (continued)

2. For Unit 2, the following are approved repair methods:

(a) Alloy 690 tungsten inert gas welded sleeves in accordance with CEN-629-P, Revision 03-P, "Repair of Westinghouse Series 44 and 51 Steam Generator Tubes Using Leak Tight Sleeves".

(b) Hardroll expanding non-sleeved portions of tubes in the tubesheet in order to apply the F* and EF* criteria.

Prairie Island Unit 1 - Amendment No. 4--58 177 Units I and 2 5.0-21 Unit 2 - Amendment No. 449 167

Programs and Manuals 5.5 5.5 .... Programs and -Manuals -(continued)---------------------------..

This page retained for page numbering I Prairie Island Unit I - Amendment No. 4-48 177 Units I and 2 5.0-22 Unit 2 - Amendment No. 4-49 167

Programs and Manuals 55 5.5 Programs and Manuals (continued) 5.5.9 Ventilation Filtei Iesting Program (VFIP)

A program shall be established to implement the following required testing of the Control Room Special Ventilation System (CRSVS), Auxiliary Building Special Ventilation System (ABSVS), Shield Building Ventilation System (SBVS), and the Spent Fuel Pool Special and Inservice Purge Ventilation System (SFPSIPVS) at least once each 24 months.

Demonstrate for the ABSVS, SBVS, CRSVS, and SFPSIPVS systems that:

a. An inplace DOP test of'the high efficiency particulate air (HEPA)

filters shows a penetration and system bypass < 0.05% (for DOP, particles having a mean diameter of' 0.7 microns);

b A htlo-gen-nated-ftydrocaibon test of the inpiiace chat-coal adsorbei shows a penetration and system bypass < 0_05%;

c A laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1 52, Revision 2, shows the methyl iodide penetration less than: 1) 15% penetration fbr ABSVS, 2) 15%

.penetration for SBVS, 3) 7.5% penetration for the SFPSIPVS, and 4) 2.5% penetration for the CRSVS when tested in accordance with, ASTM D3803-1989 at a temperature of 30°C and 95% relative humidity (RH);

d The pressure drop across the combined HEPA filters and the charcoal adsorbers is less than 6 inches of water at the system flowrate + 10%;

and

e. A laboratory test of a sample of the charcoal adsorber shall have filter test face velocities greater than or equal to the fbllowing values for each system: 1) 54 fpm fbt the CRSVS, 2) 72 fpm for the ABSVS, 3) 47 fpm for the SBVS, and 4) 47 fpm for the SEPSIPVS.

Prairie Island Unit I - Amendment No. 9 4 186 Units I and 2 5.0-23 Unit 2 - Amendment No 4-49 4-5 176

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Ventilation Filter Testing Program (VFTP) (continued)

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test Frequencies.

5.5.10 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the waste gas holdup system, the quantity of radioactivity contained in gas storage tanks, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks.

The program shall include:

a. The limits for concentrations of oxygen in the waste gas holdup system and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria;

b. A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than or equal to 78,800 Curies of noble gas (considered as dose equivalent Xe-133); and

c. A surveillance program to ensure that the quantity of radioactivity contained in each of the following tanks shall be limited to 10 Curies, excluding tritium and dissolved or entrained noble gases:

Condensate storage tanks Outside temporary tanks The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance Frequencies.

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 5.0-24 Unit 2 - Amendment No. 149

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.11 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with the limits specified in Table I of ASTM D975-77 when checked for viscosity, water, and sediment. Acceptability of new fuel oil shall be determined prior to addition to the safeguards storage tanks.

Testing of diesel fuel oil stored in the safeguards storage tanks shall be performed at least every 31 days.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test Frequencies.

5.5.12 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

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

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

1. a change in the TS incorporated in the license, or

2. a change to the USAR or Bases that requires NRC approval pursuant to 10 CFR 50.59;

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the USAR; and Prairie Island Unit 1 - Amendment No. 158 Units l and 2 5.0-25 Unit 2-Amendment No. 149

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Technical Specifications (TS) Bases Control Program (continued)

d. Proposed changes that meet the criteria of Specification 5.5.12 b above shall be reviewed and approved by the NRC prior to implementation.

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with USAR updates.

5.5.13 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate action~s taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate actions may be taken as a result of the support system inoperability and corresponding exception to entering supported system Conditions and Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following:

a. Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

Prairie Island Unit 1 - Amendment No. 158 Units l and 2 5.0-26 Unit 2 -Amendment No. 149

Programs and Manuals 5.5 5.5 Proarams and Manuals 5.5.13 Safety Function Determination Program (SFDP) (continued)

A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power or no concurrent loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to the system(s) supported by the inoperable support system is also inoperable; or

b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or

c. A required system redundant to the inoperable support system(s) for the supported systems (a) and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

Prairie Island Unit I - Amendment No. 4I5.g, 165 Units 1 and 2 5.0-27 Unit 2 - Amendment No. -1.49

Programs andManuals 5.5 5.5 Programs and Manuals (continued) 5.5.14 Containment Leakage Rate Testing Program

a. A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exceptions:

1. Unit I is excepted from post-modification integrated leakage rate testing requirements associated with steam generator replacement.

2. Exception to NEI 94-01, "Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J", Section 9.2.3, to allow the following:

(i). The first Unit 1 Type A test performed after December 1, 1997 shall be performed by December 1, 2012.

(ii). The first Unit 2 Type A test performed after March 7, 1997 shall be performed by March 7, 2012.

b. The peak calculated containment internal pressure for the design basis loss of coolant accident is less than the containment internal design pressure, Pa, of 46 psig.

c. The maximum allowable primary containment leakage rate, La, at Pa, shall be 0.25% of primary containment air weight per day. For pipes connected to systems that are in the auxiliary building special ventilation zone, the total leakage shall be less than 0.1% of primary containment air weight per day at pressure Pa. For pipes connected to systems that are exterior to both the shield building and the auxiliary building special ventilation zone, the total leakage past isolation valves shall be less than 0.01% of primary containment air weight per day at pressure Pa.

Prairie Island Unit 1 - Amendment No. 158 165 174 Units 1 and 2 5.0-28 Unit 2 - Amendment No. 449 164

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Containment Leakage Rate Testing Program (continued)

d. Leakage Rate acceptance criteria are:

1. Primary containment leakage rate acceptance criterion is S 1.0 La.

Prior to unit startup, following testing in accordance with the program, the combined leakage rate acceptance criteria are S 0.60 La for all components subject to Type B and Type C tests and S 0.75 La for Type A tests.

2. Air lock testing acceptance criteria are:

a) Overall air lock leakage rate is S 0.05 La when tested at:::: 46 psig.

b) For each door intergasket test, leakage rate is S 0.01 La when pressurized to:::: 10 psig.

e. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

f. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix 1.

5.5.15 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance of the 125V plant safeguards batteries and service building batteries, which may be used instead of the safeguards batteries during shutdown conditions in accordance with manufacturer's recommendations, as follows:

a. Actions to restore battery cells with float voltage < 2.13 V will be in accordance with manufacturer's recommendations, and

b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit Prairie Island Unit 1 - Amendment No. ~ -lM- 195 Units 1 and 2 5.0-29 Unit 2 - Amendment No. -l49 184

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Special Ventilation System (CRSVS),

CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem whole body or its equivalent to any part of the body, or 5 rem total effective dose equivalent (TEDE), as applicable, for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining the CRE boundary in its design conditions including configuration control and preventive maintenance.

c. Requirements for (i) determining the unfiltered air in-leakage past the CRE boundary into the eRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," 'Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, Revision O.

d. Licensee controlled programs that will be used to verify the integrity of the CRE boundary. Conditions that generate relevant information from those programs will be entered into the corrective action process and shall be trended and used as part of the periodic assessments of the CRE boundary.

Prairie 1sland Unit 1 - Amendment No. -l-SS -m 195 Units I and 2 i 5.0;.30 Unit 2 - Amendment No. i49 m 184

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Control Room Envelope Habitability Program (continued)

e. The quantitative limits on unfiltered air in-leakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered in-leakage measured by the testing described in paragraph c.

The unfiltered air in-leakage limit for radiological challenges is the in leakage flow rate assumed in the licensing basis analysis of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions of the licensing basis.

f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability and determining CRE unfiltered in-leakage as required by paragraph c.

Prairie Island Unit I - Amendment No. m m 195 Units 1 and 2 5.0-31 Unit 2 - Amendment No. -l49 M+ 184

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

LCO 3.2.1, "Heat Flux Hot Channel Factor (FQ(Z))";

LCO 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor (FH)";

LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)";

LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation" Overtemperature AT and Overpower AT Parameter Values for Table 3.3.1-1; LCO 3.4.1, "RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling (DNB) Limits"; and LCO 3.9.1, "Boron Concentration".

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, -

specifically those described in the following documents:

1. NSPNAD-8101-A, "Qualification of Reactor Physics Methods for Application to PI Units" (latest approved version);

2. NSPNAD-8102-PA, "Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units" (latest approved version);

3. NSPNAD-97002-PA, "Northern States Power Company's "Steam Line Break Methodology", (latest approved version);

4. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology";

5. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code";

6. Deleted;

7. WCAP-10924-P-A, "Westinghouse Large Break LOCA Best Estimate Methodology";

Prairie Island Unit 1 - Amendment No. 4-62 468 176 Units l and 2 5.0-34 Unit 2 - Amendment No. 4-5-3 4 166

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

8. XN-NF-77-57 (A), XN-NF-77-57, Supplement 1 (A), "Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II";

9. WCAP-13677-P-A, "10 CFR 50.46 Evaluation Model Report:

W-COBRA/TRAC 2-Loop Upper Plenum Injection Model Update to Support ZIRLOTM Cladding Options";

10. NSPNAD-93003-A, "Transient Power Distribution Methodology",

(latest approved version);

11. NAD-PI-003, "Prairie Island Nuclear Power Plant Required Shutdown Margin During Physics Tests",;

12. NAD-PI-004, "Prairie Island Nuclear Power Plant Fv (Z) Penalty

'With Increasing [Fc (Z) / K(Z)] Trend";

13. WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control/ FQ Surveillance Technical Specification";

14. WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions";

15. WCAP-I 1397-P-A, "Revised Thermal Design Procedure";

16. WCAP-14483-A, "Generic Methodology for Expanded Core Operating Limits Report";

17. WCAP-7588 Rev. 1-A, "An Evaluation of the Rod Ejection Accident in Westinghouse Pressurized Water Reactors Using Spatial Kinetics Methods";

Prairie Island Unit 1- Amendment No. 4-62 4-68 176 Units 1 and 2 5.0-35 Unit 2 - Amendment No. 4-5-3 4-5=, 166

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

18. WCAP-7908-A, "FACTRAN -A FORTRAN IV Code for Thermal Transients in a U0 2 Fuel Rod";

19. WCAP-7907-P-A, "LOFTRAN Code Description";

20. WCAP-7979-P-A, "TWINKLE - A Multidimensional Neutron Kinetics Computer Code";

21. WCAP-I0965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code";

22. WCAP-I1394-P-A, "Methodology for the Analysis of the Dropped Rod Event";

23. WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores";

24. WCAP-12910 Rev. I-A, "Pressurizer Safety Valve Set Pressure Shift";

25. WCAP-14565-P-A, "VIPRE-OI Modeling and Qualification for pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis";

26. WCAP-14882-P-A, "RETRAN-02 Modeling and Qualification for Westinghouse Pressurized Water Reactor Non-LOCA Safety Analyses";

27. WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM)";

28. Caldon Engineering Report ER-80P, "Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM System";

Prairie Island Lnit I - Amendment No. m -l-9+ 199 Units I and 2 5.0-36 I nit 2 - Amendment No. -l-69 +86 187

Reporting Requirements .

5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

29. Caldon Engineering Report ER-157P, "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM or LEFM CheckPlus System";

30. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report"; and

31. WCAP-12610-P-A and CENPD-404-P-A, Addendum I-A, "Optimized ZIRLO TM".

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

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

Prairie Island Unit I - Amendment No. +6& 91199 Units 1 and 2 5.0-37 Unit 2 - Amendment No. m -1,%187

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heat-up, cooldown, low temperature operation, criticality, and hydrostatic testing, OPPS arming, PORV lift settings and Safety Injection Pump Disable Temperature as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

LCO 3.4.3, "RCS Pressure and Temperature (PIT) Limits";

LCO 3.4.6, "RCS Loops - MODE 4";

LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled";

LCO 3.4.10, "Pressurizer Safety Valves";

LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP)

Reactor Coolant System Cold Leg Temperature (RCSCLT) > Safety Injection (SI) Pump Disable Temperature";

LCO 3.4.13, "Low Temperature Overpressure Protection (LTOP)

Reactor Coolant System Cold Leg Temperature

s (RCSCLT) Safety Injection (SI) Pump Disable Temperature"; and LCO 3.5.3, "ECCS - Shutdown".

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

WCAP-14040-NP-A, Revision 2, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves" (includes any exemption granted by NRC to ASME Code Case N-514).

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

Changes to the curves, setpoints, or parameters in the PTLR resulting from new or additional analysis of beltline material properties shall be submitted to the NRC prior to issuance of an updated PTLR.

Prairie Island Unit 1 - Amendment No. +6& m J 99 Units 1 and 2 5.0-38 Unit 2 - Amendment No. -l-§.& -l-61 187

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.7 Steam Generator Tube Inspection Report

a. A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.8, Steam Generator (SG)

Program. The report shall include:

1. The scope of inspections performed on each SG,

2. Active degradation mechanisms found,

3. Nondestructive examination techniques utilized for each degradation mechanism,

4. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

5. Number of tubes plugged or repaired during the inspection outage for each active degradation mechanism,

6. Total number and percentage of tubes plugged or repaired to date,

7. The results of condition monitoring, including the results of tube pulls and in-situ testing,

8. The effective plugging percentage for all plugging and tube repairs in each SG,

9. Repair method utilized and the number of tubes repaired by each repair method, and

10. The results of inspections performed under Specification 5.5.8.d.3 for all tubes that have flaws below the F* or EF* distance, and were not plugged. The report shall include: a) identification ofF*

and EF* tubes; and b) location and extent of degradation.

Prairie Island Unit 1 - Amendment No. +6& m 199 Units 1 and 2 5.0-39 Unit 2 - Amendment No. rss -l 187

Reporting Requirements

, 5.6 5.6 Reporting Requirements 5.6.7 Steam Generator Tube Inspection Report (continued)

b. For implementation of the alternate repair criteria discussed in Specification 5.5.8.c.2(c), notify the NRC staff prior to returning the steam generators to service should any of the following conditions arise:

1. If circumferential crack-like indications are detected at the tube support plate intersections,

2. If indications are identified that extend beyond the confines of the tube support plate, or

3. If indications are identified at the tube support plate elevations that are attributable to primary water stress corrosion cracking.

5.6.8 EM Report When a report is required by Condition C or I ofLCO 3.3.3, "Event Monitoring (EM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

Prairie Island Unit 1- Amendment No. -l-6& m 199 Units 1 and 2 5.0*40 Unit 2 - Amendment No. ~ M+ 187

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied in place of the controls'required by paragraph 10 CFR 20.1601 (a) and (b) of 10 CFR 20:

5.7.1 High Radiation Areas accessible to personnel in which radiation levels could result in an individual receiving a deep dose equivalent less than 1.0 rem in one hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates

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

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

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

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

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

2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint; or Prairie Island Unit 1 - Amendment No. 158 Units I and 2 5.0-41 Unit 2 -Amendment No. 149

High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas accessible to personnel in which radiation levels could result in an individual receiving a deep dose equivalent less than 1.0 rem in one hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates (continued)

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

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area, who is responsible for controlling personnel exposure within the area; or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

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

Prairie Island Unit 1 -Amendment No. 158 Units l and 2 5.0-42 Unit 2 - Amendment No. 149

High Radiation Area 5.7 5.7 High Radiation Area (continued) 5.7.2 High Radiation Areas accessible to personnel in which radiation levels could result in an individual receiving a deep dose equivalent in excess of 1.0 rem in one hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates, but less than 500 rad in one hour at one meter from the source

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

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

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

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

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

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

1. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint; or Prairie Island Unit I - Amendment No. 158 Units l and 2 5.0-43 Unit 2 - Amendment No. 149

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas accessible to personnel in which radiation levels could result in an individual receiving a deep dose equivalent in excess of 1.0 rem in one hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates. but less than 500 rad in one hour at one meter from the source (continued)

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

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area, who is responsible for controlling personnel exposure within the area; or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

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

Prairie Island Unit 1 - Amendment No. 158 Units 1 and 2 5.0-44 Unit 2 - Amendment No. 149

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas accessible to personnel in which radiation levels could result in an individual receiving a deep dose equivalent in excess of 1.0 rem in one hour at 30 centimeters from the radiation source or from any surface that the radiation penetrates. but less than 500 rad in one hour at one meter from the source (continued)

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

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

Prairie Island Unit I - Amendment No. 158 Units I and 2 5.0-45 Unit 2 - Amendment No. 149

APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-42 Northern States Power Company (NSPM) shall comply with the following conditions on the I schedules noted below:

Amendment Implementation Number Additional Condition Date 128 1. NSPM will provide a licensed operator in the control Prior to Unit 2 entering I room on an interim basis for the dedicated purpose of Mode 2 identifying an earthquake which results in a decreasing safeguards cooling water bay level. This operator will be in Completed - See addition to the normal NSPM administrative control room Amendment No. 140 I staffing requirements and will be provided until License Condition 2 is satisfied.

128 2. NSPM will submit dynamic finite element analyses of the July 1, 1997, and intake canal banks by July 1, 1997 for NRC review. By December 31, 1998, as December 31, 1998, NSPM will complete, as required, stated in Condition 2.

I' additional analyses or physical modifications which provide the basis for extending the time for operator post-seismic Completed - See cooling water load management and eliminating the Amendment No. 140 dedicated operator specified in License Condition 1.

128 3. Based on the results of License Condition 2, NSPM will At the next USAR update.

revise the Updated Safety Analysis Report to incorporate following completion of the changes into the plant design bases. These changes Condition 2, but no later will be included in the next scheduled revision of the than June 1, 1999.

Updated Safety Analysis Report following completion of License Condition 2 activities.

130 .4. Prairie Island will assure that heavy loads do not present. This is effective a potential for damaging irradiated fuel through use of: 1) a immediately upon single-failure-proof crane with rigging and procedures which issuance of the implement Prairie Island commitments to NUREG-0612; or amendment.

2) spent fuel pool covers with their implementing plant procedures for installation and use.

133 5. NSPM will assure that during the implementation of This is effective steam generator repairs utilizing the voltage-based repair immediately upon criteria, the totalcalculated'primary to secondary side issuance of the leakage from the faulted steam generator, under main amendment steam line break conditions (outside containment and upstream of the main steam isolation valves), will not exceed 1.42 gallons per minute (based on a reactor coolant system temperature of 578 OF).

11 Amendment No. +53, 188

unit I K) APPENDIX B ADDMONAL coNDm6Ns FACILIlY OPERATING LICENSE NO. DPR-42 Amendment Implementation Number Additional Condition Date By September 1, 1999.

145 6. Relocate cumentTechnical Specification 3.1S, Maximurn Reactor Oxygen, Chlorde, and Fluoride Concentration, I Technical Specification 5.1 flood shutdown requirements to the USAR.

141 7. Relocate currentTechnical Specification 4.6A.1.c, Diesel BySeptember1, 1999.-

Fuel Oil Testing, requirements to the Diesel Fuel Oil Testing Program.

8-2

-- .JUN 0 2 1999

APPENDIX B ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-42 Amendment Implementation Number Additional Conditions Date 158 The schedule for performing Surveillance Requirements October 31, (SRs) that are new or revised in Amendment No. 158 shall 2002 be as follows:

For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval, which begins on the date of implementation of this amendment.

For SRs that existed prior to this amendment, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.

For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.

For SRs that existed prior to this amendment, whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to the implementation of this amendment.

158 The licensee is authorized to relocate certain Technical October 31, Specification requirements previously included in 2002 Appendix A to licensee-controlled documents, as described in Table LR, "Less Restrictive Changes - Relocated Details," and Table R, "Relocated Specifications," attached to the NRC staff's safety evaluation dated July 26, 2002.

Those requirements shall be relocated to the appropriate documents no later than October 31, 2002.

I B-3 Amendment No. 161 1 t

~ash 6-1/5 -age

v t e Letter Sequence Acceptance Review
TAC:MD8513, Control Room Habitability (Approved, Closed)
Initiation Request, Request Acceptance Administration Meeting, Meeting Questions 19 November 2008 25 November 2008 23 February 2009 Answers Results Approval Other:
MONTHYEAR2009-02-10 [Table View]

ML11172A020

Text

*/'F when T < T' yr3

3.4.7 APPLICABIlITY

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