ML063420517

From kanterella
Jump to navigation Jump to search

Tech Spec Pages for Amendment 148 Regarding Full-Scope Implementation of the Alternative Source Term Methodology
ML063420517
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/07/2006
From:
NRC/NRR/ADRO/DORL/LPLIII-1
To:
Shared Package
ML062850049 List:
References
TAC MC8971
Download: ML063420517 (20)
v • d • e


Text

Definitions 1.1 1.1 Definitions CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and
b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific 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 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same dose I as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR)-I 1, "Limiting Values of Radionuclide Intake and Air Concentration Factors for Inhalation, Submersion and Ingestion," September 1988, and FGR-12, "External Exposure to Radionuclides in Air, Water and Soil,"

September 1993.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE
1. LEAKAGE into the drywell, such as that from pump seals or valve packing that is captured and conducted to a sump or collecting tank; or
2. LEAKAGE into the drywell 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; Monticello 1.1-2 Amendment No. 446, 148

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

APPLICABILITY: MODES 1, 2, and 3.

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

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

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

other than Condition A.

C. Two SLC subsystems C.1 Restore one SLC subsystem 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> inoperable for reasons to OPERABLE status.

other than Condition A.

D. Required Action and D.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> Monticello 3.1.7-1 Amendment No. 446, 148

CREF System Instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Filtration (CREF) System Instrumentation LCO 3.3.7.1 The CREF System instrumentation for each Function in Table 3.3.7.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.7.1-1 ACTIONS

----------- Iki t'*Vrl" Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Declare associated CREF 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery inoperable, subsystem inoperable, of loss of CREF initiation capability in AND both trip systems A.2 Place channel in trip. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> B. Required Action and B.1 Place the associated CREF 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated Completion subsystem in the Time not met. pressurization mode of operation.

OR B.2 Declare associated CREF 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> subsystem inoperable.

Monticello 3.3.7.1-1 Amendment No. 446, 148

CREF System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREF System Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains CREF System initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.7.1.3 Calibrate the trip unit. 92 days SR 3.3.7.1.4 Perform CHANNEL CALIBRATION. 92 days SR 3.3.7.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months Monticello 3.3.7.1-2 Amendment No. 446, 148

CREF System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (Page 1 of 1)

Control Room Emergency Filtration System Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE

1. Reactor Vessel Water 1, 2, 3, (a) 2 SR 3.3.7.1.1 -48 inches Level - Low Low SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.5 SR 3.3.7.1.6
2. Drywell Pressure - 1, 2, 3 2 SR 3.3.7.1.2 -<2 psig High SR 3.3.7.1.4 SR 3.3.7.1.6
3. Reactor Building 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 < 100 mRlhr Ventilation Exhaust SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.4 SR 3.3.7.1.6
4. Refueling Floor 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 -<100 mRlhr Radiation - High SR 3.3.7.1.2 SR 3.3.7.1.4 SR 3.3.7.1.6 (a) During operations with a potential for draining the reactor vessel.

(b) During movement of recently irradiated fuel assemblies in the secondary containment.

Monticello 3.3.7.1-3 Amendment No. 148

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

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

ACTIONS

- --------------------------- I. I " r" -

I Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> inoperable. OPERABLE status.

OR A.2 ---- -- NOTE- - -

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

Place channel in trip. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> B. Mechanical vacuum B.1 Restore mechanical vacuum 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> pump isolation capability pump isolation capability.

not maintained.

Monticello 3.3.7.2-1 Amendment No. 446, 148

Mechanical Vacuum Pump Isolation Instrumentation 3.3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Isolate the mechanical 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion vacuum pump.

Time not met.

OR C.2 Isolate main steam lines. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> OR C.3 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SURVEILLANCE REQUIREMENTS

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

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> provided the associated Function maintains mechanical vacuum pump isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.7.2.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.7.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.7.2.3 Perform CHANNEL CALIBRATION. The Allowable 24 months Value shall be - 6.9 R/hour.

SR 3.3.7.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST, 24 months including mechanical vacuum pump breaker and isolation valves actuation.

Monticello 3.3.7.2-2 Amendment No. 446, 148 ,

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

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

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

activity > 0.2 itCi/gm and LCO 3.0.4.c is applicable.

< 2.0 pCi/gm DOSE EQUIVALENT 1-131.

A.1 Determine DOSE Once per 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> EQUIVALENT 1-131.

AND A.2 Restore DOSE 48 hours2 days <br />0.286 weeks <br />0.0658 months <br /> EQUIVALENT 1-131 to within limits.

B. Required Action and B.1 Determine DOSE Once per 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> associated Completion EQUIVALENT 1-131.

Time of Condition A not met. AND OR B.2.1 Isolate all main steam lines. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> Reactor Coolant specific OR activity > 2.0 p.Ci/gm DOSE EQUIVALENT B.2.2.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> I

1-131.

AND B.2.2.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> Monticello 3.4.6-1 Amendment No. 446, 148

RCS Specific Activity 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 ------------------.-------- NOTE ---..............-------- -

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 1-131 7 days specific activity is _ 0.2 pCi/gm.

Monticello 3.4.6-2 Amendment No. 446, 148

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

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

APPLICABILITY: MODES 1, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation."

ACTIONS SI. r-e.*

1"

.... .... ... II ~---------------

I----------1\LJ

1. Penetration flow paths may be unisolated intermittently under administrative controls.
2. Separate Condition entry is allowed for each penetration flow path.
3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment,"

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

CONDITION REQUIRED ACTION COMPLETION TIME A. --------- NOTE -------- A.1 Isolate the affected 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> except for Only applicable to penetration flow path by main steam line penetration flow paths use of at least one closed with two PCIVs. and de-activated automatic AND valve, closed manual valve, blind flange, or check valve 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> for main One or more penetration with flow through the valve steam line flow paths with one secured.

PCIV inoperable for reasons other than AND Condition D or E. I Monticello 3.6.1.3-1 Amendment No. 446, 148

PCIVs 3.6.1.3 ACTIONS (continued)

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

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

C. ---------- NOTE--------- C.1 Isolate the affected 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> except for Only applicable to penetration flow path by excess flow check penetration flow paths use of at least one closed valves (EFCVs) and with only one PCIV. and de-activated automatic penetrations with a

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

One or more penetration AND flow paths with one PCIV inoperable. 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> for EFCVs and penetrations with a closed system AND Monticello 3.6.1.3-3 Amendment No. 446, 148

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration D.1 Isolate the affected 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> flow paths with one or penetration flow path by more 18 inch primary use of at least one closed containment purge and and de-activated automatic vent valves not within valve, closed manual valve, purge and vent valve or blind flange.

leakage limits.

AND D.2 ---------- NOTES -..........

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

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside containment E. One or more MSIVs E.1 Restore leakage rate to within 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> with leakage rate not limits.

within limits.

F. Required Action and F.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time of Condition A, B, AND C, D, or E not met in MODE 1, 2, or 3. F.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> Monticello 3.6.1.3-5 Amendment No. 446, 148

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Initiate action to suspend Immediately associated Completion operations with a potential Time of Condition A or B for draining the reactor not met for PCIV(s) vessel (OPDRVs).

required to be OPERABLE during OR MODE 4 or 5.

G.2 Initiate action to restore Immediately valve(s) to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 ------------ NOTE--------------

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

Verify each 18 inch primary containment purge and 31 days vent valve is closed.

Monticello 3.6.1.3-6 Amendment No. 446, 148

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.6 Verify the isolation time of each MSIV is 24 months

> 3 seconds and < 9.9 seconds.

SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation 24 months position on an actual or simulated isolation signal.

SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV 24 months actuates on a simulated instrument line break to restrict flow to < 2 gpm.

SR 3.6.1.3.9 Verify each 18 inch primary containment purge and 24 months vent valve is blocked to restrict the valve from opening > 40°.

SR 3.6.1.3.10 Remove and test the explosive squib from each 24 months on a shear isolation valve of the TIP System. STAGGERED TEST BASIS SR 3.6.1.3.11 Perform leakage rate testing for each 18 inch primary In accordance containment purge and vent valve with resilient seals. with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify leakage rate through each MSIV is: In accordance (a) 5 100 scfh when tested at > 42 psig (Pa); or with the Primary Containment (b) < 77 scfh when tested at > 25 psig. Leakage Rate Testing Program SR 3.6.1.3.13 Verify leakage rate through the main steam pathway is: In accordance with the Primary (a) 5 200 scfh when tested at -> 42 psig (P,); or Contaiment Containment (b) 5 154 scfh when tested at ->25 psig. Leakage Rate Testing Program Monticello 3.6.1.3-8 Amendment No. 446, 148

Control Room Ventilation System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Control Room Ventilation System LCO 3.7.5 Two control room ventilation subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room A.1 Restore control room 30 days ventilation subsystem ventilation subsystem to inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> associated Completion Time of Condition A not AND met in MODE 1, 2, or 3.

B.2 Be in MODE 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> C. Required Action and .NOTE-..........

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not ---------

met during movement of recently irradiated fuel C.1 Place OPERABLE control Immediately assemblies in the room ventilation subsystem secondary containment in operation.

or during OPDRVs.

OR Monticello 3.7.5-1 Amendment No. 446, 148

Control Room Ventilation System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.

AND Immediately C.2.2 Initiate action to suspend OPDRVs.

D. Two control room D.1 Enter LCO 3.0.3. Immediately ventilation subsystems inoperable in MODE 1, 2, or 3.

E. Two control room ................ NOTE-ventilation subsystems LCO 3.0.3 is not applicable.

inoperable during --- ............ ---------. . ..-----

movement of recently irradiated fuel E.1 Suspend movement of Immediately assemblies in the recently irradiated fuel secondary containment assemblies in the or during OPDRVs. secondary containment.

AND Immediately E.2 Initiate actions to suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each control room ventilation subsystem has 24 months the capability to remove the assumed heat load.

Monticello 3.7.5-2 Amendment No. 446, 148

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 qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems - Shutdown;" and
b. One emergency diesel generator (EDG) capable of supplying one division of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

APPLICABILITY: MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

I ACTIONS

,NOTE----

LCO 3.0.3 is not applicable.

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

circuit inoperable. Enter applicable Condition and Required Actions of LCO 3.8.8, with one required division de-energized as a result of Condition A.

A.1 Declare affected required Immediately feature(s), with no offsite power available, inoperable.

OR Monticello 3.8.2-1 Amendment No. 446, 148

AC Sources - Shutdown 3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately recently irradiated fuel I assemblies in the secondary containment.

AND A.2.3 Initiate action to suspend Immediately operations with a potential for draining the reactor vessel (OPDRVs).

AND A.2.4 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.

B. One required EDG B.1 Suspend CORE Immediately inoperable. ALTERATIONS.

AND B.2 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.

AND B.3 Initiate action to suspend Immediately OPDRVs.

AND B.4 Initiate action to restore Immediately required EDG to OPERABLE status.

Monticello 3.8.2-2 Amendment No. 446, 148

DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 Division 1 or Division 2 125 VDC electrical power subsystem shall be OPERABLE to support one division of the DC Electrical Power Distribution System required by LCO 3.8.8, "Distribution Systems -

Shutdown."

APPLICABILITY: MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

ACTIONS

k I t"*, "t" p U' r ------------------- - --------------------- ------------ -

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical A.1 Suspend CORE Immediately power subsystem ALTERATIONS.

inoperable.

AND A.2 Suspend movement of Immediately recently irradiated fuel I assemblies in the secondary containment.

AND Immediately A.3 Initiate action to suspend operations with a potential for draining the reactor vessel.

AND Immediately A.4 Initiate action to restore required DC electrical power subsystem to OPERABLE status.

Monticello 3.8.5-1 Amendment No. 446, 148

Distribution Systems - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems - Shutdown LCO 3.8.8 The necessary portions of the AC and DC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY: MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC or DC electrical supported required power distribution feature(s) inoperable.

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend handling of Immediately recently irradiated fuel assemblies in the secondary containment.

AND Immediately A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel.

AND Monticello 3.8.8-1 Amendment No. 446, 148

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Safety Function Determination Program (SFDP) (continued)

3. A required system redundant to the support system(s) for the supported systems described in Specifications 5.5.10.b.1 and 5.5.10.b.2 above is also inoperable.
c. 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.

5.5.11 Primary Containment Leakage Rate Testing Program

a. A program shall establish 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 exception:
1. The Type A testing Frequency specified in NEI 94-01, Revision 0, Paragraph 9.2.3, as "at least once per 10 years based on acceptable performance history" is modified to be "at least once per 15 years based on acceptable performance history." This change applies only to the interval following the Type A test performed in March 1993;
2. The main steam line pathway leakage contribution is excluded from the sum of the leakage rates from Type B and C tests specified in Section III.B of 10 CFR 50, Appendix J, Option B, Section 6.4.4 of ANSI/ANS 56.8-1994, and Section 10.2 of NEI 94-01, Rev. 0; and
3. The main steam line pathway leakage contribution is excluded from the overall integrated leakage rate from Type A tests specified in Section III.A of 10 CFR 50, Appendix J, Option B, Section 3.2 of ANSI/ANS 56.8-1994, and Section 8.0 and 9.0 of NEI 94-01, Rev. 0.
b. The calculated peak containment internal pressure for the design basis loss of coolant accident, P2, is 42 psig. The containment design pressure is 56 psig.
c. The maximum allowable containment leakage rate, L,, at Pa, shall be 1.2%

of containment air weight per day.

Monticello 5.5-10 Amendment No. 446 , 148

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Primary Containment Leakage Rate Testing Program (continued)

d. Leakage rate acceptance criteria are:
1. Containment leakage rate acceptance criterion is _ 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests and _<0.75 La for Type A tests.
2. Air lock testing acceptance criteria are:

a) Overall air lock leakage rate is :5 0.05 La when tested at >_Pa.

b) For each door, leakage rate is < 0.007 La when pressurized to

> 10 psig.

e. The resilient seals of each 18 inch primary containment purge and vent valve shall be replaced at least once every 9 years. The provisions of SR 3.0.2 are applicable to this requirement. If a common mode failure attributable to the resilient seals is identified based on the results of SR 3.6.1.3.11, the resilient seals of all 18 inch primary containment purge and vent valves shall be replaced.
f. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

5.5.12 Battery Monitoring and Maintenance Program This Program provides for battery restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," or of the battery manufacturer of the following:

a. Actions to restore battery cells with float voltage < 2.13 V; and
b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit.

Monticello 5.5-11 Amendment No. 446, 148

Retrieved from "https://kanterella.com/w/index.php?title=ML063420517&oldid=2580947"