ML042730364

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Technical Spec.Pages Re Implementation of Alternative Source Term
ML042730364
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 09/27/2004
From:
Office of Nuclear Reactor Regulation
To:
Brown Eva, NRR/DLPM, 415-2315
Shared Package
ML042730052 List:
References
TAC MB5733, TAC MB5734, TAC MB5735, TAC MC0156, TAC MC0157, TAC MC0158
Download: ML042730364 (23)
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Text

(4) The licensee shall review the Technical Specification (TS) changes made by License Amendment No. 234 and any subsequent TS changes, verify that the required analyses and modifications needed to support the changes are complete, and submit them for NRC review and approval prior to entering the mode for which the TS applies. This amendment is effective immediately and shall be implemented prior to entering the mode for which the TS applies.

(5) Deleted.

(6) Deleted.

(7) Deleted.

(8) Deleted.

(9) Deleted.

(10) Deleted.

(11) The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Browns Ferry Physical Security Plan", with revisions submitted through May 24, 1988; "Browns Ferry Security Personnel Training and Qualification Plan", with revisions submitted through April 16,1987; and "Browns Ferry Safeguards Contingency Plan", with revisions submitted through June 27, 1986. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

BFN-UNIT 1 4 Amendment No. 251

(12) Deleted.

(13) Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated December 8, 1988, March 6,1991, March 31, 1993, November 2, 1995 and Supplement dated November 3, 1989 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(14) The licensee shall maintain the Augmented Quality Program for the Standby Liquid Control System to provide quality control elements to ensure component reliability for the required alternative source term function defined in the Updated Final Safety Analyses Report.

(15) The licensee is required to confirm that the conclusions made in TVA's letter dated September 17, 2004, for the turbine building remain acceptable using seismic demand accelerations based on dynamic seismic analysis prior to the restart of Unit 1.

D. This amended license is effective as of the date of issuance and shall expire midnight on December 20, 2013.

FOR THE ATOMIC ENERGY COMMISSION Original Signed By S/ A. Giambusso A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Date of Issuance: DEC 20 1973 See Appendix B for additional License Conditions.

BFN-UNIT 1 5 Amendment No. 251

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. One SLC subsystem A.1 Restore SLC subsystem 7 days inoperable. to OPERABLE status.

B. Two SLC subsystems B.1 Restore one SLC 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable. subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.

AND C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> BFN-UNIT 1 3.1-23 Amendment No. 234, 251

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium pentaborate 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> solution (SPB) is 2 4000 gallons.

SR 3.1.7.2 Verify continuity of explosive charge. 31 days SR 3.1.7.3 Verify the SPB concentration is 2 8.0% by 31 days weight.

AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or boron is added to solution SR 3.1.7.4 Verify the SPB concentration is < 9.2% by weight. 31 days AND Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or boron is added to solution OR (continued)

BFN-UNIT 1 3.1 -24 Amendment No. 234, 251

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY Verify the concentration and temperature of Once within boron in solution are within the limits of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after Figure 3.1.7-1. discovery that SPB concentration is

> 9.2% by weight AND 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter SR 3.1.7.5 Verify the minimum quantity of Boron-10 in the 31 days SLC solution tank and available for injection is 2 186 pounds.

SR 3.1.7.6 Verify the SLC conditions satisfy the following 31 days equation:

AND (C )( Q )( E (13 wt. %)(86 gpm)(19.8 atom%) Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after where, water or boron is added to the solution C = sodium pentaborate solution concentration (weight percent)

Q = pump flow rate (gpm)

E = Boron-10 enrichment (atom percent Boron-1 0)

SR 3.1.7.7 Verify each pump develops a flow rate 2 39 18 months gpm at a discharge pressure 2 1275 psig.

(continued)

BFN-UNIT 1 3.1-25 Amendment No. X34, 251

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.8 Verify flow through one SLC subsystem from 18 months on a pump into reactor pressure vessel. STAGGERED TEST BASIS SR 3.1.7.9 Verify all piping between storage tank and 18 months pump suction is unblocked.

SR 3.1.7.10 Verify sodium pentaborate enrichment is within 18 months the limits established by SR 3.1.7.6 by calculating within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and verifying by AND analysis within 30 days. After addition to SLC tank SR 3.1.7.11 Verify each SLC subsystem 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, or can be aligned to the correct position.

BFN-UNIT 1 3.1-26 Amendment No. 234, 251

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 FUNCTION OTHER CHANNELS SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIREMENTS VALUE CONDITIONS TRIP SYSTEM

1. ReactorVesselWaterLevel - 1,2,3, 2 SR 3.3.6.2.1 2538 inches above Low, Level 3 (a) SR 3.3.6.2.2 vesselzero SR 3.3.6.2.3 SR 3.3.6.2.4
2. Drywell Pressure - High 1,2,3 2 SR 3.3.6.2.2 S 2.5 psig SR 3.3.6.2.3 SR 3.3.6.2.4
3. ReactorZoneExhaust 1,2,3, 1 SR 3.3.6.2.1 -. 100 mR/hr Radiation - High (a) SR 3.3.6.2.2 I SR 3.3.6.2.3 SR 3.3.6.2.4
4. Refueling Floor Exhaust 1,2,3, 1 SR 3.3.6.2.1 S 100 mR/hr Radiation - High (a) SR 3.3.6.2.2 I SR 3.3.6.2.3 SR 3.3.6.2.4 (a) During operaffons with a potential for draining the reactor vessel.

I BFN-UNIT 1 3.3-64 Amendment No. 234, 251

CREV System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)

Control Room Emergency Ventilation System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION A.1

1. Reactor Vessel Water Level - 1,2,3,(a) 2 B SR 3.3.7.1.1 Ž538inches Low, Level 3 SR 3.3.7.1.2 above vessel SR 3.3.7.1.5 zero SR 3.3.7.1.6
2. Drywell Pressure - High 1,2,3 2 B SR 3.3.7.1.2 s 2.5 psig SR 3.3.7.1.5 SR 3.3.7.1.6
3. ReactorZone Exhaust 1,2,3 1 C SR 3.3.7.1.1 l1OOmR/hr Radiation - High (a) SR 3.3.7.1.2 I SR 3.3.7.1.5 SR 3.3.7.1.6
4. Refueflng Floor Exhaust 1,2,3. 1 C SR 3.3.7.1.1 s 100 mR/hr Radiation - High (a) SR 3.3.7.1.2 I SR 3.3.7.1.5 SR 3.3.7.1.6
5. Control Room Air Supply Duct 1,2,3. 1 D SR 3.3.7.1.1 S 270 cpm Radiation - High (a) SR 3.3.7.1.2 above I SR 3.3.7.1.3 background SR 3.3.7.1.4 (a) During operations with a potential for draining the reactor vessel.

I BFN-UNIT 1 3.3-69 Amendment No. 234, 251

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.

APPLICABILITY: MODES 1, 2, and 3, During operations with a potential for draining the reactor vessel I (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable in MODE 1, 2, containment to or 3. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not AND met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)

BFN-UNIT 1 3.6-44 Amendment No. 234, 251

Secondary Containment 3.6.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Secondary containment C.1 Initiate action to suspend Immediately inoperable during OPDRVs.

OPDRVs.

BFN-UNIT 1 3.6-45 Amendment No. 234, 251

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.

APPLICABILITY: MODES 1, 2, and 3, During operations with a potential for draining the reactor vessel I (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 penetration A.1 Isolate the affected 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> flow paths with one SCIV penetration flow path by inoperable. use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND (continued)

BFN-UNIT 1 3.6-47 Amendment No. 234, 251

SCIVs 3.6.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to suspend Immediately associated Completion OPDRVs.

Time of Condition A or B not met during OPDRVs.

BFN-UNIT 1 3.6-49 Amendment No. ,24,251

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

APPLICABILITY: MODES 1, 2, and 3, During operations with a potential for draining the reactor vessel I (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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not AND met in MODE 1, 2, or 3.

B.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)

BFN-UNIT 1 3.6-51 Amendment No. 234, 251

SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Place two OPERABLE Immediately associated Completion SGT subsystems in Time of Condition A not operation.

met during OPDRVs.

OR C.2 Initiate action to suspend Immediately OPDRVs.

D. Two or three SGT D.1 Enter LCO 3.0.3. Immediately subsystems inoperable in MODE 1, 2, or 3.

(continued)

BFN-UNIT 1 3.6-52 Amendment No. 234, 251

SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two or three SGT E.1 Initiate action to suspend Immediately subsystems inoperable OPDRVs.

during OPDRVs.

BFN-UNIT 1 3.6-53 Amendment No. 234, 251

CREV System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation (CREV) System LCO 3.7.3 Two CREV subsystems shall be OPERABLE.

OT--------------- ------ ------- ---- --

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

APPLICABILITY: MODES 1, 2, and 3, During operations with a potential for draining the reactor vessel I (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREV subsystem A.1 Restore CREV subsystem 7 days inoperable. to OPERABLE status.

B. Two CREV subsystems B.1 Restore control room 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable due to boundary to OPERABLE inoperable control room status.

boundary in MODES 1, 2, and 3.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A or B AND not met in MODE 1, 2, or

3. C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)

BFN-UNIT 1 3.7-8 Amendment No.234, 246, 251

CREV System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Place OPERABLE CREV Immediately associated Completion subsystem in Time of Condition A not pressurization mode.

met during OPDRVs.

OR D.2 Initiate action to suspend Immediately OPDRVs.

E. Two CREV subsystems E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

(continued)

BFN-UNIT 1 3.7-9 Amendment No.234, 246, 251

CREV System

. 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREV subsystems F.1 Initiate action to suspend Immediately inoperable during OPDRVs.

OPDRVs.

BFN-UNIT 1 3.7-10 Amendment No.234, 246, 251

Decay Time 3.9.9 3.9 REFUELING OPERATIONS 3.9.9 Decay Time LCO 3.9.9 The reactor shall be subcritical for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

APPLICABILITY: During in-vessel fuel movement.

ACTIONS _

CONDITION REQUIRED ACTION COMPLETION TIME A. With the reactor A.1 Suspend in-vessel fuel Immediately subcritical for less than movement.

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

BFN-UNIT 1 3.9-22 Amendment No. 251

Decay Time 3.9.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.9.1 Verify the reactor has been subcritical for at Once prior to the least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. movement of irradiated fuel in the reactor vessel BFN-UNIT 1 3.9-23 Amendment No. 251

Decay Time B 3.9.9 B 3.9 REFUELING OPERATIONS B 3.9.9 Decay Time BASES BACKGROUND This postulated refueling accident involves the drop of a fuel assembly on top of the reactor core during refueling operations (Ref. 1). The drop over the reactor core is more limiting than the drop over the spent fuel pool since the kinetic energy for the drop over the reactor core area (greater than 23 feet) produces a larger number of damaged fuel pins on impact than the shorter drops that could occur over the fuel pool. The refueling accident is analyzed using Alternate Source Term methodology governed by 10 CFR 50.67 and the guidelines of Regulatory Guide 1.183 (Ref. 2).

The refueling accident analysis assumes that the accident occurs at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after plant shutdown. Specifically, a 24-hour radioactive decay time of the fission product inventory is assumed during the interval between shutdown and movement of assemblies in the reactor core.

APPLICABLE The minimum requirement of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reactor subcriticality SAFETY ANALYSES prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is an initial condition of the refueling accident analysis.

Decay time satisfies the requirements of Criterion 2 of the NRC Policy Statement (Ref. 3).

(continued)

BFN-UNIT 1 B 3.9-36 Amendment No. 251

Decay Time B 3.9.9 BASES (continued)

LCO The specified decay time limit requires the reactor to be subcritical for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Implicit in this TS is the Applicability (during movement of irradiated fuel in the reactor vessel). This ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products, thus reducing the fission product inventory and reducing the effects of a refueling accident.

APPLICABILITY The decay time restriction is applicable only during movement of irradiated fuel in the reactor vessel following reactor operation. Therefore, it effectively prohibits movement of irradiated fuel in the reactor vessel during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following reactor shutdown.

ACTIONS A.1 I With the reactor subcritical less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, all movement of irradiated fuel in the reactor vessel must be suspended. As stated above, movement of irradiated fuel in the reactor vessel is prohibited during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following reactor shutdown.

SURVEILLANCE SR 3.9.9.1 REQUIREMENTS Since movement of irradiated fuel in the reactor vessel is prohibited during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following reactor shutdown, a verification of time subcritical must be made prior to movement of irradiated fuel in the reactor vessel. This is done by confirming the time and date of subcriticality, and verifying that at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> have elapsed. The Frequency of "once prior to movement of irradiated fuel in the reactor vessel" ensures that the operation is within the design basis assumption for decay time in the refueling accident analysis.

(continued)

BFN-UNIT 1 B 3.9-37 Amendment No. 251

Decay Time B 3.9.9 BASES (continued)

REFERENCES 1. FSAR, Section 14.6.4.

2. Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", USNRC, July 2000.
3. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23,1993.

BFN-UNIT 1 B3 3.9-38 Amendment No. 251

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