ML11252A653

License Amendment Request 244, Marked-Up Operating License and Technical Specifications Pages, Attachment 2

ML11252A653
Person / Time
Site:	Kewaunee
Issue date:	08/30/2011
From:	Dominion, Dominion Energy Kewaunee
To:	Office of Nuclear Reactor Regulation
References
11-025A, LAR 244, TAC ME7110
Download: ML11252A653 (24)

Text

Serial No. 11-025A ATTACHMENT 2 LICENSE AMENDMENT REQUEST 244:

PROPOSED REVISION TO RADIOLOGICAL CONSEQUENCES ANALYSIS AND CONTROL ROOM HABITABILITY TECHNICAL SPECIFICATIONS MARKED-UP OPERATING LICENSE AND TECHNICAL SPECIFICATIONS PAGES KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

Insert 1: Proposed Change to the Kewaunee Operating License (XX) Upon implementation of Amendment No. [ ] adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by TS SR 3.7.10.4, in accordance with TS 5.5.17.c.1, and the assessment of CRE habitability as required by Specification TS 5.5.17.c.2, shall be considered met. Following implementation:

(a) The first performance of TS 3.7.10.4, in accordance with Specification TS 5.5.17.c.1, shall be within the specified Frequency of 6 years, plus the 18-month allowance of TS SR 3.0.2, as measured from December 15, 2004, the date of the most recent successful tracer gas test, as stated in the April 1, 2005 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b) The first performance of the periodic assessment of CRE habitability, Specification TS 5.5.17.c.2, shall be within 3 years, plus the 9-month allowance of TS SR 3.0.2, as measured from December 15, 2004, the date of the most recent successful tracer gas test, as stated in the April 1, 2005 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

Definitions 1.1 Kewaunee Power Station 1.1-2 Amendment No. 207 02/02/2011 1.1 Definitions CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual signal TEST (COT) into the channel as close to the sensor as practicable to verify 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 OPERATING LIMITS The COLR is the unit specific document that provides REPORT (COLR) cycle specific parameter limits for the current reload cycle.

These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.3.

Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes I-131, I-132, I-133, I-134, and I-135 actually present.

The determination of DOSE EQUIVALENT I-131 shall be performed using ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil."

Committed Dose Equivalent (CDE) dose conversion factors from Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclides Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion".

Containment Purge and Vent Isolation Instrumentation 3.3.6 Kewaunee Power Station 3.3.6-2 Amendment No. 207 02/02/2011 ACTIONS (continued)

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

Only applicable during movement of irradiated fuel assemblies within containment.

One or more Functions with one or more automatic actuation trains inoperable.

OR Two or more radiation monitoring channels inoperable.

OR Required Action and associated Completion Time for Condition A not met.

C.1 Place and maintain containment purge and vent valves in closed position.

OR C.2 Enter applicable Conditions and Required Actions of LCO 3.9.6, "Containment Penetrations," for containment purge and vent isolation valves made inoperable by isolation instrumentation.

Immediately Immediately recently

Containment Purge and Vent Isolation Instrumentation 3.3.6 Kewaunee Power Station 3.3.6-4 Amendment No. 207 02/02/2011 Table 3.3.6-1 (page 1 of 1)

Containment Purge and Vent Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS

1. Automatic Actuation Logic and Actuation Relays 1,2,3,4, (a) 2 trains SR 3.3.6.2

2. Containment Radiation

a. Gaseous 1,2,3,4, (a) 2 SR 3.3.6.1 SR 3.3.6.3 SR 3.3.6.4

b. Particulate 1,2,3,4, (a) 1 SR 3.3.6.1 SR 3.3.6.3 SR 3.3.6.4

3. Containment Isolation - Manual Initiation Refer to LCO 3.3.2, "ESFAS Instrumentation,"

Function 3.a, for all initiation functions and requirements.

4. Containment Spray - Manual Initiation Refer to LCO 3.3.2, "ESFAS Instrumentation,"

Function 2.a, for all initiation functions and requirement.

5. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all functions and requirements.

(a)

During movement of irradiated fuel assemblies within containment.

recently

CRPAR System Actuation Instrumentation 3.3.7 Kewaunee Power Station 3.3.7-1 Amendment No. 207 02/02/2011 3.3 INSTRUMENTATION 3.3.7 Control Room Post Accident Recirculation (CRPAR) System Actuation Instrumentation LCO 3.3.7 The CRPAR System actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.7-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Automatic Actuation Logic and Actuation Relay train inoperable.

A.1 Place associated CRPAR train in emergency mode.

7 days B. Two Automatic Actuation Logic and Actuation Relay trains inoperable.

OR Control Room Vent Radiation Monitor inoperable.

B.1.1 Place one CRPAR train in emergency mode.

AND B.1.2 Enter applicable Conditions and Required Actions for one CRPAR train made inoperable by inoperable CRPAR System actuation instrumentation.

OR B.2 Place both CRPAR trains in emergency mode.

Immediately Immediately Immediately

CRPAR System Actuation Instrumentation 3.3.7 Kewaunee Power Station 3.3.7-2 Amendment No. 207 02/02/2011 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time for Condition A or B not met in MODE 1, 2, 3, or 4.

C.1 Be in MODE 3.

AND C.2 Be in MODE 5.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours D. Required Action and associated Completion Time for Condition A or B not met during movement of irradiated fuel assemblies.

D.1 Suspend movement of irradiated fuel assemblies.

Immediately E. Required Action and associated Completion Time for Condition A or B not met in MODE 5 or 6.

E.1 Initiate action to restore one CRPAR train to OPERABLE status.

Immediately SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.7-1 to determine which SRs apply for each CRPAR System Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.7.2 Perform COT in accordance with the Setpoint Control Program.

92 days recently recently

CRPAR System Actuation Instrumentation 3.3.7 Kewaunee Power Station 3.3.7-3 Amendment No. 207 02/02/2011 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.7.3

---

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

This Surveillance is only applicable to the actuation logic of the ESFAS Instrumentation.

Perform ACTUATION LOGIC TEST.

18 months SR 3.3.7.4 Perform CHANNEL CALIBRATION in accordance with the Setpoint Control Program.

18 months 3.3.7.1

CRPAR System Actuation Instrumentation 3.3.7 Kewaunee Power Station 3.3.7-4 Amendment No. 207 02/02/2011 Table 3.3.7-1 (page 1 of 1)

CRPAR System Actuation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS

1. Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4, 5, 6, (a) 2 trains SR 3.3.7.3 2 Control Room Vent Radiation Monitor 1, 2, 3, 4, 5, 6, (a) 1 SR 3.3.7.1 SR 3.3.7.2 SR 3.3.7.4

3. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.

(a)

During movement of irradiated fuel assemblies.

recently 3.3.7.1

2.

RCS Specific Activity 3.4.16 Kewaunee Power Station 3.4.16-1 Amendment No. 207 02/02/2011 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT I-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT I-131 not within limit.

---

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

LCO 3.0.4.c is applicable.

A.1 Verify DOSE EQUIVALENT I-131 20 µCi/gm.

AND A.2 Restore DOSE EQUIVALENT I-131 to within limit.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 48 hours B. DOSE EQUIVALENT XE-133 not within limit.

---

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

LCO 3.0.4.c is applicable.

B.1 Restore DOSE EQUIVALENT XE-133 to within limit.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 10

RCS Specific Activity 3.4.16 Kewaunee Power Station 3.4.16-2 Amendment No. 207 02/02/2011 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A or B not met.

OR DOSE EQUIVALENT I-131 > 20 µCi/gm.

C.1 Be in MODE 3.

AND C.2 Be in MODE 5.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant DOSE EQUIVALENT XE-133 specific activity 595 µCi/gm.

7 days SR 3.4.16.2 Verify reactor coolant DOSE EQUIVALENT I-131 specific activity 1.0 µCi/gm.

14 days AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a THERMAL POWER change of 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period 16.4 0.1 10

CRPAR System 3.7.10 Kewaunee Power Station 3.7.10-1 Amendment No. 207 02/02/2011 3.7 PLANT SYSTEMS 3.7.10 Control Room Post Accident Recirculation (CRPAR) System LCO 3.7.10 Two CRPAR trains shall be OPERABLE.

---

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

The control room boundary may be opened intermittently under administrative control.

APPLICABILITY:

MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRPAR train inoperable.

A.1 Restore CRPAR train to OPERABLE status.

7 days B. Two CRPAR trains inoperable due to inoperable control room boundary in MODE 1, 2, 3, or 4.

B.1 Restore control room boundary to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, 3, or 4.

C.1 Be in MODE 3.

AND C.2 Be in MODE 5.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours envelope (CRE)

---

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

The CRE shall be isolated during movement of recently irradiated fuel assemblies and recently for reasons other than Condition B Insert 2

CRPAR System 3.7.10 Kewaunee Power Station 3.7.10-2 Amendment No. 207 02/02/2011 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.

D.1 Place OPERABLE CRPAR train in emergency mode.

OR D.2 Suspend movement of irradiated fuel assemblies.

Immediately Immediately E. Two CRPAR trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies.

E.1 Suspend movement of irradiated fuel assemblies.

Immediately F. Two CRPAR trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

F.1 Enter LCO 3.0.3.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CRPAR train for 15 minutes.

31 days SR 3.7.10.2 Perform required CRPAR filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with VFTP SR 3.7.10.3 Verify each CRPAR train actuates on an actual or simulated actuation signal.

18 months recently recently recently recently Insert 3 Perform required CRE unfiltered air inleakage testing in accordance with CRE Habitability Program In accordance with CRE Habitability Program SR 3.7.10.4

Insert 2:

B. One or more CRPAR trains inoperable due to an inoperable CRE boundary in Modes 1, 2, 3, or 4.

B.1 Initiate action to implement mitigating actions.

AND B.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND B.3 Restore CRE boundary to OPERABLE status.

Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 90 days Insert 3:

OR Required Actions and associated Completion Times of Condition B not met during movement of recently irradiated fuel assemblies.

CRAC Alternate Cooling System 3.7.11 Kewaunee Power Station 3.7.11-1 Amendment No. 207 02/02/2011 3.7 PLANT SYSTEMS 3.7.11 Control Room Air Conditioning (CRAC) Alternate Cooling System LCO 3.7.11 Two CRAC Alternate Cooling trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRAC Alternate Cooling train inoperable.

A.1 Restore CRAC Alternate Cooling train to OPERABLE status.

30 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, 3, or 4.

B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours C. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies.

C.1 Place OPERABLE CRAC Alternate Cooling train in operation.

OR C.2 Suspend movement of irradiated fuel assemblies.

Immediately Immediately D. Two CRAC Alternate Cooling trains inoperable during movement of irradiated fuel assemblies.

D.1 Suspend movement of irradiated fuel assemblies.

Immediately recently recently recently recently recently

Secondary Specific Activity 3.7.16 Kewaunee Power Station 3.7.16-1 Amendment No. 207 02/02/2011 3.7 PLANT SYSTEMS 3.7.16 Secondary Specific Activity LCO 3.7.16 The specific activity of the secondary coolant shall be 0.10 µCi/gm DOSE EQUIVALENT I-131.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not within limit.

A.1 Be in MODE 3.

AND A.2 Be in MODE 5.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the specific activity of the secondary coolant is 0.10 µCi/gm DOSE EQUIVALENT I-131.

31 days 0.05 0.05

AC Sources - Shutdown 3.8.2 Kewaunee Power Station 3.8.2-1 Amendment No. 207 02/02/2011 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 qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown"; and

b.

One diesel generator (DG) capable of supplying one train of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10.

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 offsite circuit 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 Declare affected required feature(s) with no offsite power available inoperable.

OR A.2.1 Suspend movement of irradiated fuel assemblies.

AND Immediately Immediately recently recently

AC Sources - Shutdown 3.8.2 Kewaunee Power Station 3.8.2-2 Amendment No. 207 02/02/2011 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.2.2 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.2.3 Initiate action to restore required offsite power circuit to OPERABLE status.

Immediately Immediately B. One required DG inoperable.

B.1 Suspend movement of irradiated fuel assemblies.

AND B.2 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND B.3 Initiate action to restore required DG to OPERABLE status.

Immediately Immediately Immediately recently

DC Sources - Shutdown 3.8.5 Kewaunee Power Station 3.8.5-1 Amendment No. 207 02/02/2011 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 One DC electrical power subsystem shall be OPERABLE to support one subsystem of the DC Electrical Power Distribution System required by LCO 3.8.10, "Distribution System - Shutdown."

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 DC electrical power subsystem inoperable.

A.1 Suspend movement of irradiated fuel assemblies.

AND A.2 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.3 Initiate action to restore required DC electrical power subsystem to OPERABLE status.

Immediately Immediately Immediately recently recently

Inverters - Shutdown 3.8.8 Kewaunee Power Station 3.8.8-1 Amendment No. 207 02/02/2011 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters - Shutdown LCO 3.8.8 One inverter shall be OPERABLE to support the 120 VAC electrical distribution subsystem required by LCO 3.8.10, "Distribution Systems -

Shutdown."

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 inverter inoperable.

A.1 Suspend movement of irradiated fuel assemblies.

AND A.2 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND A.3 Initiate action to restore required inverter to OPERABLE status.

Immediately Immediately Immediately recently recently

Distribution Systems - Shutdown 3.8.10 Kewaunee Power Station 3.8.10-1 Amendment No. 207 02/02/2011 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems - Shutdown LCO 3.8.10 The necessary portion of AC, DC, and AC instrument bus 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 AC, DC, or AC instrument bus electrical power distribution subsystems inoperable.

A.1 Declare associated supported required feature(s) inoperable.

OR A.2.1 Suspend movement of irradiated fuel assemblies.

AND A.2.2 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND Immediately Immediately Immediately recently recently

Containment Penetrations 3.9.6 Kewaunee Power Station 3.9.6-1 Amendment No. 207 02/02/2011 3.9 REFUELING OPERATIONS 3.9.6 Containment Penetrations LCO 3.9.6 The containment penetrations shall be in the following status:

a.

The equipment hatch is closed and held in place by four bolts;

b.

One door in each air lock is capable of being closed; and

c.

Each penetration providing direct access from the containment atmosphere to the outside atmosphere is either:

1.

Closed by a manual or automatic isolation valve, blind flange, or equivalent; or

2.

Capable of being closed by an OPERABLE Containment Purge and Vent Isolation System.

APPLICABILITY:

During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment penetrations not in required status.

A.1 Suspend movement of irradiated fuel assemblies within containment.

Immediately capable of being recently recently

---

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

Penetration flow paths providing direct access from the containment to outside atmosphere may be opened under administrative controls.

Programs and Manuals 5.5 Kewaunee Power Station 5.5-15 Amendment No. 207 02/02/2011 5.5 Programs and Manuals 5.5.16 Setpoint Control Program (continued) 10 CFR 50.90 is required to change the listed value of the NTSP, AV, AFT, and ALT (as applicable) for each Function described in Paragraph a.

c.

The program shall establish methods to ensure that Functions described in Paragraph a. will function as required by verifying the as-left and as-found settings are consistent with the list of values established by Paragraph b. If the as-found value of the instrument channel trip setting is less conservative than the specified AV, then the SR is not met and the instrument channel shall be immediately declared inoperable.

d.

The program shall identify the Functions described in Paragraph a. that are automatic protective devices related to variables having significant safety functions as delineated by 10 CFR 50.36(c)(1)(ii)(A). The NTSP of these Functions are Limiting Safety System Settings. These Functions shall be demonstrated to be functioning as required by applying the following requirements during CHANNEL CALIBRATIONS, CHANNEL OPERATIONAL TESTS, and TRIP ACTUATING DEVICE OPERATIONAL TESTS that verify the NTSP.

1.

The as-found value of the instrument channel trip setting shall be compared with the previous as-left value or the specified NTSP.

2.

If the as-found value of the instrument channel trip setting differs from the previous as-left value or the specified NTSP by more than the pre-defined test acceptance criteria band (i.e., the specified AFT), then the instrument channel shall be evaluated before declaring the SR met and returning the instrument channel to service. This condition shall be entered in the plant corrective action program.

3.

If the as-found value of the instrument channel trip setting is less conservative than the specified AV, then the SR is not met and the instrument channel shall be immediately declared inoperable.

4.

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the NTSP at the completion of the surveillance test; otherwise, the channel is inoperable (setpoints may be more conservative than the NTSP provided that the as-found and as-left tolerances apply to the actual setpoint used to confirm channel performance).

e.

The program shall be specified in the Technical Requirements Manual.

5.5.17 (see Insert 4)

Insert 4:

5.5.17 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 Post-Accident Recirculation (CRPAR) System and CRE boundary, 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 total effective dose equivalent (TEDE) 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 condition including configuration control and preventive maintenance.

c. Requirements for:

1. Determining the unfiltered air in-leakage past the CRE boundary into the CRE 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;

2. Assessing CRE habitability at the frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d. Licensee controlled programs 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 36-month assessment of the CRE boundary in accordance with TS 5.5.17.c.2.

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 air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses 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 in the licensing basis.

f.

The provisions of SR 3.0.2 are applicable to the frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and assessing the CRE boundary as required by TS 5.5.17.c. and TS 5.5.17.d., respectively.