ML082490835

Amendment 273 Application of Alternative Source Term Methodology

ML082490835
Person / Time
Site:	Peach Bottom
Issue date:	09/05/2008
From:	Plant Licensing Branch 1
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ML08232057	List: ML082490835
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TAC MD6807
Download: ML082490835 (16)

Text

Definitions 1.1 1.1 Definitions (continued)

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel wi th the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of wide range neutron monitors, local power range monitors, traversing incore probes, or speci a1 movabl e 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 REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. 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 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 Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites,"

or Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989.

(continued)

PBAPS UNIT 3 1.1-2 Amendment No. 273

Definitions 1.1 1.1 Definitions PHYSICS TESTS b. Authorized under the provisions of (continued) 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3514 MWt.

REACTOR PROTECTION SYSTEM The RPS RESPONSE TIME shall be that time interval (RPS) RESPONSE TIME from the opening of the sensor contact up to and including the opening of the trip actuator contacts.

RECENTLY IRRADIATED RECENTLY IRRADIATED FUEL is fuel that has occupied FUEL part of a critical reactor core within the previous 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />. When using this definition to suspend the Applicability of LCOs, secondary containment ground-level hatches H20, H21, H22, H23, H24, and H34 shall be closed during the movement of any irradiated fuel in Secondary Containment.

SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:

a. The reactor is xenon free;

b. The moderator temperature is 68°F; and

c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components 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.

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

(continued)

PBAPS UNIT 3 1.1-5 Amendment No. 273

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 REQU I RED ACTI ON COMPLETION TIME A. Concentration of boron A.l Verify the 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> in solution> 9.82% concentration and weight. temperature of boron AND in solution and pump suction piping Once per temperature are 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> within the limits of thereafter Figure 3.1.7-1.

AND A.2 Restore concentration 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> of boron in solution to ~ 9.82% weight. AND 10 days from discovery of failure to meet the LCO B. One SLC subsystem B.l Restore SLC sUbsystem 7 days inoperable for reasons to OPERABLE status.

other than AND Condition A.

10 days from discovery of failure to meet the LCO (continued)

PBAPS UN IT 3 3.1-20 Amendment No. 273

SLC System 3.1. 7 ACTIONS (continued)

CONDITION REQU I RED ACTI ON COMPLETION TIME C. Two SLC subsystems C.1 Restore one SLC 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> inoperable for reasons subsystem to OPERABLE other than status.

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 /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify level of sodium penta borate solution 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> in the SLC tank is ~ 46%.

SR 3.1.7.2 Verify temperature of sodium penta borate 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> solution is ~ 53°F.

SR 3.1.7.3 Verify temperature of pump suction piping 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> is ~ 53" F.

SR 3.1.7.4 Verify continuity of explosive charge. 31 days (continued)

PBAPS UN IT 3 3.1-21 Amendment No.273

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3l Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIREO REFERENCED OTHER CHANNELS FROM SPEC I FlED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION COND IT IONS SYSTEM ACTION C.l REQUIREMENTS VALUE

5. Reactor Water Cleanup (RWCU) System Isolation

a. RWCU Flow-High 1,2,3 SR 3.3.6.1.1 $ 125% rated SR 3.3.6.1.3 flow (23.0 SR 3.3.6.1.7 in-we)

b. SLC System I nit i at ion 1,2,3 H SR 3.3.6.1.7 NA

c. Reactor Vessel Water 1,2,3 SR 3.3.6.1.1 ~ 1.0 inches Level - Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

6. RHR Shutdown Cooling System Isolation

a. Reactor Pressure Hi gh 1, 2,3 SR 3.3.6.1.3 $ 70.0 psig SR 3.3.6.1.7

b. Reactor Vessel Water 3,4,5 2 (a 1 SR 3.3.6.1.1 ~ 1.0 inches Level - Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

7. Feedwater Recirculation Isolation

a. Reactor Pressure Hi gh 1,2,3 SR 3.3.6.1.1 $ 600 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

8. Traversing Incore Probe Isolation

a. Reactor Vessel Water 1,2,3 J SR 3.3.6.1.1 ~ 1.0 inches Level-Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

b. Drywell Pressure-High 1,2,3 J SR 3.3.6.1.1 $ 2.0 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 (a ) In MODES 4 and 5, provided RHR Shutdown Cooling System integrity is maintained. only one channel per trip system with an isolation signal available to one shutdown cooling pump suction isolation valve is required.

PBAPS UN IT 3 3.3-54 Amendment NO.2 73

Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEI LLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE

1. Reactor Vessel Water 1.2,3. SR 3.3.6.2.1 :2 1.0 inches Level--Low (Level 3 ) (a) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5

2. Drywell Pressure--High 1 .2,3 SR 3.3.6.2.1 s 2.0 psig SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5

3. Reactor Building 1 .2,3. 2 SR 3.3.6.2.1 s 16.0 mR/hr Ventilation Exhaust (a) *(b) SR 3.3.6.2.3 Radiation--High SR 3.3.6.2.5

4. Refueling Floor 1, 2,3. SR 3.3.6.2.1 s 16.0 mR/hr Ventilation Exhaust ( a ) *(b) SR 3.3.6.2.3 Radiation--High SR 3.3.6.2.5 (a) During operations with a potential for draining the reactor vessel.

(b) During movement of RECENTLY 1RRADIATED FUEL assemblies in secondary containment.

PBAPS UNIT 3 3.3-58 Amendment No. 273

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Purge/Vent flowpath E.1 Isolate the 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> open for an penetration.

accumulated time greater than 90 hours3.75 days <br />0.536 weeks <br />0.123 months <br /> OR for the calendar year while in MODE 1 or 2 E.2.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> with Reactor Pressure greater than 100 psig.

E.2.2 Be in Mode 4. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> 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, AND B, C, or D 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 /> G. Required Action and G.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A, with a potential for B, C, or D not met draining the reactor for PCIV(s) required vessel.

to be OPERABLE during MODE 4 or 5. OR G.2 Initiate action to Immediately restore valve(s) to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.6.1.3.1 Verify Containment Atmospheric Dilution 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> (CAD) System liquid nitrogen storage tank level is ~ 16 inches water column.

SR 3.6.1.3.2 Verify Safety Grade Instrument Gas (SGIG) 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> System header pressure is ~ 80 psig.

(continued)

PBAPS UNIT 3 3.6-12 Amendment No.2 73

PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.14 Verify combined MSIV leakage rate for all In accordance four main steam lines is ~ 204 scfh, and with the

~ 116 scfh for anyone steam line, when Primary tested at ~ 25 psig. Containment Leakage Rate Testing Program SR 3.6.1.3.15 Verify each 6 inch and 18 inch primary 24 months containment purge valve and each 18 inch primary containment exhaust valve is blocked to restrict opening greater than the required maximum opening angle.

SR 3.6.1.3.16 Replace the inflatable seal of each 96 months 6 inch and 18 inch primary containment purge valve and each 18 inch primary containment exhaust valve.

PBAPS UN IT 3 3.6-16 Amendment No. 273

Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

APPLICABI LITY: 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. Secondary containment A.1 Restore secondary 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> inoperable in MODE 1, containment to 2, or 3. 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 met.

C. Secondary containment C.1 - - - - - - - - NOT E- - - - - - -

inoperable during LCO 3.0.3 is not movement of RECENTLY applicable.

IRRADIATED FUEL assemblies in the secondary containment Suspend movement of Immediately or during OPDRVs. RECENTLY IRRADIATED FUEL assemblies in the secondary containment.

(continued)

PBAPS UNIT 3 3.6-34 Amendment No.2 73

Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment 31 days equipment hatches are closed and sealed.

SR 3.6.4.1.2 Verify one secondary containment access 31 days door in each access opening is closed.

SR 3.6.4.1.3 Verify secondary containment can be drawn 24 months on a down to ~ 0.25 inch of vacuum water gauge STAGGERED TEST in ~ 180 seconds using one standby gas BASIS for each treatment (SGT) subsystem. subsystem SR 3.6.4.1.4 Verify the secondary containment can be 24 months on a maintained ~ 0.25 inch of vacuum water STAGGERED TEST gauge for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using one SGT subsystem BASIS for each at a flow rate ~ 10,500 cfm. subsystem PBAPS UNIT 3 3.6-35 Amendment No. 273

SCIVs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABI LITY: 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

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

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

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.l Isolate the affected 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> penetration flow paths penetration flow path with one SCIV by use of at least inoperable. one closed and de-activated automatic valve, closed manual valve, or blind flange.

(continued)

PBAPS UNIT 3 3.6-36 Amendment No.273

SCIVs 3.6.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and 0.1 - - - - - - - - NOTE - - - - - - -

associated Completion LCO 3.0.3 is not Time of Condition A applicable.

or B not met during movement of RECENTLY IRRADIATED FUEL Suspend movement of Immediately assemblies in the RECENTLY IRRADIATED secondary containment FUEL assemblies in or during OPDRVs. the secondary containment.

0.2 Initiate action to Immediately suspend OPDRVs.

PBAPS UN IT 3 3.6-38 Amendment No. 273

SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

APPLICABI LITY: 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 SGT subsystem A .1 Restore SGT subsystem 7 days inoperable. to 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 met in MODE 1, 2, or 3.

C. Required Action and - - - - - - - - - - - - NOT E- - - - - - - - - - - -

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of RECENTLY C.1 Place OPERABLE SGT Immediately IRRADIATED FUEL subsystem in assemblies in the operation.

secondary containment or during OPDRVs.

(continued)

PBAPS L1NIT 3 3.6-40 Amendment No.273

SGT System 3.6.4.3 ACT IONS CONDITION REQU I RED ACTI ON COMPLETION TIME C. (continued) C. 2.1 Suspend movement of Immediately RECENTLY IRRADIATED FUEL assemblies in secondary containment.

C.2.2 Initiate action to Immediately suspend OPDRVs.

D. Two SGT subsystems 0.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> inoperable in MODE 1, 2, or 3.

E. Two SGT subsystems E.1 --------NOTE--------

inoperable during LCO 3.0.3 is not movement of RECENTLY applicable.

I RRADIATED FUEL assemblies in the secondary containment Suspend movement of Immediately or during OPDRVs. RECENTLY IRRADIATED FUEL assemblies in secondary containment.

E.2 Initiate action to Immediately suspend OPDRVs.

PBAPS UN IT 3 3.6-41 Amendment No. 273

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Program (SFDP) (continued)

1. A required system redundant to system(s) supported by the inoperable support system is also inoperable; or

2. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable; or

3. A required system redundant to support system(s) for the supported systems (b.1) and (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.

5.5.12 Primary Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(0) 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 to NEI 94-01, Rev. 0, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J":

a. Section 10.2: MSIV leakage is excluded from the combined tot a 1 of 0.6 La for the Type Band C tests.

b. Section 9.2.3: The first Type A test performed after the December, 1991 Type A test sha 11 be performed no 1 ater than December, 2006.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 49.1 psig.

The maximum allowable primary containment leakage rate, La' at POl shall be 0.7% of primary containment air weight per day.

Leakage Rate acceptance criteria are:

a. Primary 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 Type C tests and ~

0.75 La for Type A tests; (continued)

PBAPS UNIT 3 5.0-17 Amendment No. 273

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is s 9000 scc/min when tested at ~ Pa *

c. MSIV leakage acceptance criteria are as specified in SR 3.6.1.3.14.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

5.5.13 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 Main Control Room Emergency Ventilation (MCREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release as applicable, 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) conditio~s 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 preventative maintenance.

c. Requirements of (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Section 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 Section C.1 and C.2 of Regulatory Guide 1.197, Revision O.

(continued)

PBAPS UN IT 3 5.0-18 Amendment No. 273