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Synopsis of Revisions Included in Watts Bar Unit 2 Developmental Revision H of Technical Specifications and Technical Specification Bases. Part 1 of 2
	ML13357A050
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Site:	Watts Bar
Issue date:	12/12/2013
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
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ML13357A047	List: ML13357A048; ML13357A050; ML13357A051; ML13357A053; ML13357A054;
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Enclosure SYNOPSIS OF REVISIONS INCLUDED IN WATTS BAR NUCLEAR PLANT UNIT 2 DEVELOPMENTAL REVISION H OF THE TECHNICAL SPECIFICATIONS AND TECHNICAL SPECIFICATION BASES 1.0

SUMMARY

This letter provides the Watts Bar Nuclear Plant (WBN) Unit 2 Developmental Revision H Technical Specifications (TS) and TS Bases. This is a complete copy of the entire TS and TS Bases.

The revisions include changes previously submitted by letter for WBN Unit 2 since the submittal of Developmental Revision G. Developmental Revision H also incorporates recently approved WBN Unit 1 amendments and amendments submitted and currently under review by the Nuclear Regulatory Commission (NRC). This revision adds Appendix B, "Environmental Protection Plan." Finally there are changes included that have been developed for WBN Unit 2 but have not submitted previously.

For the WBN Unit 2 revisions previously submitted (References 1 - 3, inclusive), a justification for these changes is not provided in this document as it was included in the referenced submittal. A discussion of the applicability of the WBN Unit 1 TS changes to WBN Unit 2 is provided in this enclosure. A technical basis for the WBN Unit 2 TS and TS Bases changes not previously submitted is provided in this enclosure. For all previously submitted and current changes, a summary of the changes is provided in Attachments 1 & 2.

2.0 CHANGES 2.1 WBN Unit 2 Changes Previously Submitted

Submitted by Reference 1

" TS 4.3.1 Criticality

TS Bases B3.7.15 Spent Fuel Assembly Storage

" Submitted by Reference 2

" TS 3.4.16 Reactor Coolant System Specific Activity

TS Table 3.3.7-1 CREVS Actuation Instrumentation

TS 3.7.7 Component Cooling System (CCS)

" TS 5.9.2 Annual Radiological Environmental Operating Report

" TS Bases B.3.7.7 Component Cooling System (CCS)

" TS Bases B.3.4.16 RCS Specific Activity

Submitted by Reference 3

TS Table 3.3.3-1 Post Accident Monitoring Instrumentation

" TS Bases B3.3.3 PAM Instrumentation E-1

Enclosure 2.2 Approved WBN Unit 1 Amendments Applicable to WBN Unit 2 2.2.1 WBN Unit 1 Amendment 92 Associated with Alternate Source Term WBN Unit 1 submitted an amendment request for the selective application of the Alternate Source Term (AST) for the Fuel Handling Accident (FHA). The WBN Unit 1 analysis that supported this application assumed no filtration or hold-up of the radioactive releases. This assumption resulted in the removal of operability requirements for certain safety-related filtration systems and normal ventilation system isolation functions during Mode 6 Operation (Refueling).

WBN Unit 2 submitted (Reference 4) revised Final Safety Analysis Report (FSAR) discussions, Technical Specifications (TS), and Technical Specification Bases (TSB) changes associated with the Design Basis Accident (DBA) discussion for the FHA that are based on the selective application of the AST. The WBN Unit 2 submittal was based on the WBN Unit 1 amendment request, and provided specific details of the WBN Unit 2 changes that were made to the FSAR, TS, and TSB.

The following provides a summary of the specific WBN Unit 2 TS, TS Bases, and Technical Requirements Manual changes that were made. Specific discussion is provided in Reference 4.

1. Add new WBN Unit 2 TS 3.9.10, "Decay Time" and associated TS Bases;

2. Modify WBN Unit 2 TS 3.3.6, "Containment Vent Isolation Instrumentation," TS 3.3.8, Auxiliary Building Gas Treatment System (ABGTS) Actuation Instrumentation," and TS 3.7.12, "Auxiliary Building Gas Treatment System (ABGTS)," in addition to the associated TS Bases;

3. Eliminate TS 3.9.4, "Containment Penetrations," and TS 3.9.8, "Reactor Building Purge Air Cleanup Units;"

4. Modify WBN Unit 2 TS 5.7.2.14, "Ventilation Filter Testing Program (VFTP):"

5. Modify WBN Unit 2 TS 5.7.2.20, "Control Room Envelope Habitability Program;"

6. Modify TS Bases B.3.6.1, "Containment Penetrations, B.3.6.2, "Containment Air Locks," and B.3.6.3, "Containment Isolation Valves," delete TS Bases B.3.9.4, and remove reference to TS 3.9.4 from TS Bases B.3.9;

7. Modify TS Bases B.3.7.13 "Spent Fuel Pool Level" and B.3.9.7 "Reactor Cavity Water Level" to update references associated with AST; and

8. Remove the decay time restriction on post shutdown irradiated fuel movement from Section 3.9.1 of the Technical Requirements Manual.

2.3 WBN Unit I Amendments Under NRC Review Applicable to WBN Unit 2 2.3.1 TS 3.8.4 DC Sources Operating Reference 5 submitted a WBN Unit 1 amendment request related to the safety-related DC power system that was based on Technical Specification Task Force - 500 (TSTF-500). Because of plant specific design features at WBN, modifications to the standard TSTF template were required. The DC power system at WBN is shared by the two units and consequently, the TS for both units need to be the same.

E-0

Enclosure The proposed adoption of TSTF-500, Revision 2, provides new TS Actions for an inoperable battery charger and alternate battery charger testing criteria. A longer Completion Time (CT) for an inoperable battery charger will allow additional time for maintenance and testing.

In addition, monitoring requirements for battery cell parameters and performance requirements for battery maintenance activities are proposed to be relocated from the TSs to a licensee controlled program. This focuses TS requirements on the analysis basis safety function of the battery.

The proposed TS changes are as follows:

Revise 3.8.4, "DC Sources - Operating" to add Conditions for inoperable battery chargers and inoperable batteries, and relocate SRs on battery corrosion, connection resistance, and visual inspection, to the new Battery Monitoring and Maintenance Program. Allow use of the Modified Performance testing to satisfy SRs for Service Testing and Performance Testing.

" Revise the list of TS 3.8.4 SRs in TS 3.8.5, "DC Sources - Shutdown," that must be met to be consistent with the changes to TS 3.8.4.

Rename TS LCO 3.8.6, "Battery Cell Parameters" to "Battery Parameters."

Delete TS Table 3.8.6-1.

" Relocate TS 3.8.6 Conditions and SRs for battery cell parameters that do not meet Category A and B limits to the new Battery Monitoring and Maintenance Program. Retain Category C limits for cell float voltage and electrolyte level in new proposed TS. Relocate specific gravity limits to the new Battery Monitoring and Maintenance Program and replaced with float current monitoring to determine battery state of charge. Relocate SR for battery capacity test from TS 3.8.4 to TS 3.8.6.

" Add TS 5.7.2.21, "Battery Monitoring and Maintenance Program."

The proposed changes update the WBN Unit 2 to be consistent with TSTF-360 and TSTF-500, as the WBN Unit 2 design allows. While this amendment request does not use the NRC Model Safety Evaluation provided for TSTF-500 as the basis for this change, TVA reviewed Section 2.2 of the model application and has included all applicable information requested by the NRC in this section.

2.4 WBN Unit 2 TS or TSB Changes Not Previously Submitted to the NRC 2.4.1 Technical Specification Bases 3.6.8 HMS E-1

Enclosure Consistent with 10 CFR 50.44, Unit 2 abandoned the hydrogen recombiners in place.

Unit 2 Developmental Technical Specifications and Bases were previously revised to delete TS 3.6.7 and TS Bases 3.6.7 concerning the hydrogen recombiners. A sentence in TS Bases 3.6.8 that credits the hydrogen recombiners for maintaining the hydrogen concentration resulting from a DBA less than the hydrogen flammability limit also should have been deleted. This proposed change corrects the over-sight in TS Bases 3.6.8.

2.4.2 Technical Specification SR 3.6.13.4 Divider Barrier Integrity This section has been removed from the WBN Unit 2 TS. This section describes a test used on WBN Unit 1 to check cold bond repairs to the divider barrier. There are no cold bond repairs on WBN Unit 2. The associated TS Bases has also been removed.

2.4.3 Appendix B, Environmental Protection Plan An Environmental Protection Plan (EPP) has been added as Appendix B to the Facility Operating License. The EPP is modeled on the WBN Unit 1 and Sequoyah Nuclear Plant EPPs. Recent EPP amendments from other nuclear plants were also reviewed.

Reporting and monitoring programs were incorporated as outlined below.

Aquatic Ecological Monitoring Consistent with current standards, Aquatic Ecological Monitoring is contained in the effective National Pollution Discharge Elimination System permit for the WBN site.

Separate redundant reporting to the NRC is not required (References 6 & 7).

Terrestrial Ecological Monitoring The U.S Fish and Wildlife Service's Biological Opinion concluded that WBN plant operation would not likely jeopardize the continued existence of the species (Reference 6).

The Effects of Cooling Tower Drift and Bird Collisions with Cooling Towers monitoring programs have been completed and no further monitoring under these programs is planned or required.

WBN Unit 1 provides annual reports to the NRC on transmission line maintenance activities. This requirement is not carried over to the WBN Unit 2 EPP as it is redundant to reporting TVA makes to the states and the US Environmental Protection Agency for the transmission system including the specific transmission lines addressed by WBN Unit 1.

TVA does not conduct or propose to conduct any other monitoring activities specific to the WBN site and WBN dual-unit operation.

References

1. TVA Letter to NRC dated September 26, 2013, "Watts Bar Nuclear Plant (WBN) Unit 2 - Submittal of Revised Section 4.3.1, "Criticality" Developmental Revision G of the Unit 2 Technical Specification (TS)"

E-2

Enclosure

2. TVA Letter to NRC dated June 13, 2013, "Watts Bar Nuclear Plant (WBN)

Unit 2 - Submittal of Three Revised Specifications from Developmental Revision G of the Unit 2 Technical Specifications (TS)"

3. TVA Letter to NRC dated August 27, 2012, "Watts Bar Nuclear Plant (WBN)

Unit 2 - Update to Technical Specification (TS) Table 3.3.3-1 and Technical Specification Bases (TSBs) 3.3.3"

4. TVA letter to NRC dated December 12, 2013, "Watts Bar Nuclear Plant Unit 2

- Fuel Handling Accident Dose Analysis Final Safety Analysis Report and Specification Revision"

5. TVA letter to NRC dated August 28, 2013, "Application to Modify Watts Bar Nuclear Plant, Unit 1 Technical Specifications (TS) 3.8.4, 3.8.5, and 3.8.6 (WBN-TS-12-07)" (ADAMS Accession No. ML13248A250)

6. Final Environmental Statement Related to Operation of Watts Bar Nuclear Plant Unit No. 2, Nuclear Regulatory Commission, May 2013, Docket Nos.

50-390 and 50-391, NUREG-0498, Final Report, Supplement No. 2, Vols. 1 &

2, ADAMS Accession Nos. ML13144A092 & ML13144A093, respectively

7. Appendix B to Facility Operating License NPF-90, Watts Bar Nuclear Plant Unit 1, Environmental Protection Plan E-3

TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 2 Revisions to Developmental Technical Specification (TS) and Technical Specification Bases (TSB) Revision H ATTACHMENTS

1. TS Changes (Mark-Up) for WBN Unit 2

2. TS Bases Changes (Mark-Up) for WBN Unit 2

3. WBN Unit 2 TS and TSB Developmental Revision H (Optical Media Storage)

ATTACHMENT I Technical Specification Changes (Mark-Up) for WBN Unit 2

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 3)

Post Accident Monitoring Instrumentation APPLICABLE CONDITION MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS / REQUIRED FUNCTION CONDITIONS TRAINS ACTION D.1

1) Intermediate Range Neutron Flux (g) 1 (a), 2 (b), 3 2 E

2) Source Range Neutron Flux 2(c), 3 2 E

3) Reactor Coolant System (RCS) Hot Leg 1,2,3 1 per loop E Temperature (T-Hot)

4) RCS Cold Leg Temperature (T-Cold) 1,2,3 1 per loop

5) RCS Pressure (Wide Range) 1,2,3 3

6) Reactor Vessel Water Level (() 1,2,3 2

7) Containment Sump Water Level (Wide 1,2,3 2 Range)

8) Containment Lower Comp. 1,2,3 2 Atm. Temperature

9) Containment Pressure (Wide Range) (g) 1,2,3 2

10) Containment Pressure (Narrow Range) 1,2,3 4

11) Containment Isolation Valve Position (g) 1,2,3 2 per penetration flow path (d)(i) 2 upper

12) Containment Radiation (High Range) 1,2,3 containment 2 lower containment

13) RCS Pressurizer Level 1,2,3 3

14) Steam Generator (SG) Water Level 1,2,3 I ISG (Wide Range) (g)

(continued)

Watts Bar - Unit 2 3.3-44 (developmental) RH I

Containment Vent Isolation Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Containment Vent Isolation Instrumentation LCO 3.3.6 The Containment Vent Isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.-

Du:rin movornont of ira itofuAl asscomblios within contaInmont.

ACTIONS

NOT I--------------------------------------------------------------

Separate Condition entry is allowed for each Fi CONDITION REQUIRED ACTION COMPLETION TIME A. One radiation monitoring A.1 Restore the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months channel inoperable, channel to OPERABLE status.

(continued)

Watts Bar - Unit 2 3.3-53 (developmental) AH

Containment Vent Isolation Instrumentation 3.3.6 ACTIONS (continued)

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

Onl,, ..... InI " MODE 1, One train of automatic actuation 2, 3, G--4. logic may be bypassed and Required Action B.1 may be delayed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for One or more Functions with Surveillance testing provided the one or more manual or other train is OPERABLE.

automatic actuation trains inoperable.

B.1 Enter applicable Immediately OR Conditions and Required Actions of LCO 3.6.3, Two radiation monitoring "Containment Isolation channels inoperable. Valves," for containment OR purge and exhaust isolation valves made Required Action and inoperable by isolation associated Completion instrumentation.

Time of Condition A not met.

Watts Bar - Unit 2 3.3-54 (developmental) AH

Containment Vent Isolation Instrumentation 3.3.6 ACTION-I'S (co4Rntinud__4\

CONDITION RE-QUIREID ACTI*.N COMPLETION TIME C. 4 GNOTE Race and maintain knediate*y Only applicablo duFrin containmenFRt purgo8 an moEm... t Of irradiated ful oxhaust valves in closd assemblies within e4R OnAor-more Func'Rtions withte C.2igbl mIIe8b4 one9 or more mnal rCodtin and Requir-d-automatic actuation trains Actions of LCO 3.9.4, vpea l..v~v , ."ConCAtainment PeneratU;ionsl," for OR contanment purge and exhaust isolation valves Two radiation monitoring made iRnperable by m et,'.* *l*.$ ,*' .. l. .*.÷..* n'f- ,- ,{.*;*.

Required Action and associated Completion Time for Condition A not Watts Bar - Unit 2 3.3-55 (developmental) AH

Containment Vent Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)

Containment Vent Isolation Instrumentation REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS REQUIREMENTS VALUE

1. Manual Initiation 2 SR 3.3.6.6 NA

2. Automatic Actuation Logic 2 trains SR 3.3.6.2 NA and Actuation Relays SR 3.3.6.3 SR 3.3.6.5

3. Containment Purge 2 SR 3.3.6.1 8. 1E 02 .i,,,,

Exhaust Radiation Monitors SR 3.3.6.4 (3.43x!04 SR 3.3.6.7

< 2.8E-02 pCi/cc(b)

(1.14x10 4 cpm)

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

(a~ o.

E--% frinfo-r I mnio M...on wii I.... ---

MrrMato i en.....

(b) AMde6 1, 2, 3,ad 4 Watts Bar - Unit 2 3.3-58 (developmental) 8H I

CREVS Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)

CREVS Actuation Instrumentation REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS REQUIREMENTS VALUE

1. Manual Initiation 2 trains SR 3.3.7.3 NA

2. Control Room Radiation 2 SR 3.3.7.1 _ 1.647E-0O4Q46 Control Room Air Intakes SR 3.3.7.2 05 ýC/cc SR 3.3.7.4 (3,308 cpm)

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

Watts Bar - Unit 2 3.3-62 (developmental) AH I

ABGTS Actuation Instrumentation 3.3.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Place both trains in Immediately emergency radiation protection mode.

4 Required Action and 4 Su-eond m..ment o Immediately a..o.iated Compl.tion irradiated fuol a..omblic' TimeA for Con~dition A or B3 in the fuel handling ar.

not met during me,-emet of irradiated f-el asseomblies in the fuel h*n*dling ara.

Q.C. Required Action and 9C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A or B AND not met in MOcE 1, 2, 3,

-C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS NOTE Refer to Table 33.33.8-1 to detetrmine which 814t apply for each ABGTS9 Actuation Functon SURVEILLA.NCE F-REQUENCY S9R-84. 7 Po~orm CHANNEL CHEC 12heue 6 R 3.3. 1Pe rfor COT.MG 92 daY6 (GGRtiRued)

Watts Bar - Unit 2 3.3-63 (developmental) AH

ABGTS Actuation Instrumentation 3.3.8 SURVEILLANCE REQUIREMENTS (GORtiued_

SURVEILLANCE FREQUENCY SR 3.3.8.31 - ------------------ NOTE ---------------

Verification of setpoint is not required.

Perform TADOT. 18 months SR 3.3. Perform CHANNEL CALIBRT!ON. !8 months Watts Bar - Unit 2 3.3-64 (developmental) AH

ABGTS Actuation Instrumentation 3.3.8 Table 3.3.8-1 (page 1 of 1)

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

1. Manual Initiation 1,2,3,4 2 SR 3.3.8.31 NA (a) 2 SR 3.3-.A8 NA 2, Pool (a) 2 SR ..4&

Radition, Monitoe SR 3.3.8:2 372. Containment Refer to LCO 3.3.2, Function 3.a., for all Phase A initiating functions Isolation and requirements.

P a at *

(a) DUFin- .- ,., ment of irrliatedl fuel a*csemhi* n ftuel handllin area.

1he Watts Bar - Unit 2 3.3-65 (developmental) AH

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS average temperature (Tav,) --5000 F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 --------.----.-.- NOTE ---------

> 0.265 giCi/gm. LCO 3.0.4.c is applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT 1-131

< 24-14 pCi/gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

B. Gross specific activity of the B.1 Perform SR 3.4.16.2. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reactor coolant not within limit. AND B.2 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Tavg < 5000 F.

(continued)

Watts Bar - Unit 2 3.4-35 (developmental) AH I

RCS Specific Activity 3.4.16 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Tavg < 500 0F.

Time of Condition A not met.

OR DOSE EQUIVALENT 1-131

> 2-1-14 gCi/gm.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific activity 7 days

< 100/ tE Ci/gm.

SR 3.4.16.2 -------------------- NOTE---------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 1-131 14 days specific activity < 0.265 gCi/gm. AND Between 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of

_>15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period (continued)

Watts Bar - Unit 2 3.4-36 (developmental) AH I

Divider Barrier Integrity 3.6.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.13.1 Verify, by visual inspection, all personnel access Prior to entering doors and equipment hatches between upper and MODE 4 from lower containment compartments are closed. MODE 5 SR 3.6.13.2 Verify, by visual inspection, that the seals and Prior to final closure sealing surfaces of each personnel access door and after each opening equipment hatch have:

AND

a. No detrimental misalignments;

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

b. No cracks or defects in the sealing surfaces; and Only required for seals made of

c. No apparent deterioration of the seal material, resilient materials 10 years SR 3.6.13.3 Verify, by visual inspection, each personnel access After each opening door or equipment hatch that has been opened for personnel transit is closed.

SR 3.6.13.4 Not used.Vr,,fy, by peel test On three pein for. Prior to i*ial fuel cach roplacement coal reai location, that the length leadifig feF-jeiftS-Of Pool for at loast tavo o-f thee test specimensA is le6s mnade priortofu than Or equal to 1 ic.leadki~

AND (G4R~ued)

Watts Bar - Unit 2 3.6-32 (developmental) AH

Divider Barrier Integrity 3.6.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I

R4I6.4 D (GOetiued) 18 mRonthts for- the 46rt two r-efuelIing fabrication of4Rny-AND 18 mon9ths thorAFtor forF AfabFriAtedj splice joint, if an" Of the three test-length 4 ic 17-OR 36- monthrb thereafter 1fo a fabiricatod-three associ*ated test lengh i X)4-ic SR 3.6.13.5 Visually inspect > 95% of the divider barrier seal 18 months length, and verify:

a. Seal and seal mounting bolts are properly installed; and

b. Seal material shows no evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearance.

Watts Bar - Unit 2 3.6-33 (developmental) AH

CCS 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling System (CCS)

&If'*T=

CCS Pump 1B-B aligned to CCS Train B supports an OPERABLE CCS Train B for Unit 2 only when CCS Pump 1B-B is OPERABLE and operating as verified by SR 3.7.7.5.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCS train inoperable. A.1 -- -------- NOTE------

Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4,"

for residual heat removal loops made inoperable by CCS.

Restore CCS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Watts Bar - Unit 2 3.7-16 (developmental) AH I

CCS 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify that the alternate feeder breaker to the C-S 7 days pump is open.

SR 3.7.7.2 --------------------- NOTE---------------

Isolation of CCS flow to individual components does not render the CCS inoperable.

Verify each CCS manual, power operated, and 31 days automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.7.3 Verify each CCS automatic valve in the flow path that 18 months is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.7.4 Verify each CCS pump starts automatically on an 18 months actual or simulated actuation signal. When CCS Pump 1B-B is substituted for CCS Pump C-S to establish CCS Train B operability, SR 3.7.7.4 does not apply to CCS Pump 1B-B (See SR 3.7.7.5).

SR 3.7.7.5 When CCS Pump 1B-B is substituted for CCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Pump C-S for Unit 2 CCS Train B operability, then, Verify CCS 1B-B is aligned to CCS Train B and is operating.

Watts Bar - Unit 2 3.7-17 (developmental) AHI

ABGTS 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Auxiliary Building Gas Treatment System (ABGTS)

LCO 3.7.12 Two ABGTS trains shall be OPERABLE APPLICABILITY: MODES 1, 2, 3, and 4.-

nt.e.nnkI;nc. in tha $, .nI I..,r,.-II;~,. ara~

jmm"ý-6m-+6^

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

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not met- AND in MODE 1,2,3, on4.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Two ABGTS trains inoperable in MODE 1, 2, 3, 9F4.

G- Requird Action and G4 Place OPERABLE RRrdat-associated Completion Time cf ABGr-TS- train in operation-.

Condition A not me~t durin~g moVe-ment Of irradiated fuel OR a,.om*brhlios in the Afuel handliRg a~a.G4 Suspend moevement of lmm~ediate~y irradiated fuel asseimblieciS in the fueAl handling area D~Two AB-G-TS trains 9. Suspend moVement of Immendiately inoperable duFrig mo9VemenFt of irdae ulsmle irradiaed fuel assemnblies in the in the fuel handling area.

fuel h~andl*ng area.

Watts Bar - Unit 2 3.7-26 (developmental) AH

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 Four channels of vital DC and four Diesel Generator (DG) DC electrical power subsystems shall be OPERABLE.

-NOTE*S- -----------------------------------------

1. Vital Battery V may be substituted for any of the required vital batteries.

2. Spare Vital Chargers 6-S, 7-S, 8-S, or 9-S may be substituted for required Vital chargers.

3. Spare DG Chargers IAl, 1B1, 2A1, or 2B1 may be substituted for required DG chargers.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required vital battery A.1 Restore vital battery 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months charger inoperable, terminal voltage to greater than or equal to the minimum established float voltage.

AND A.2 Verify vital battery Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months charger float current

< 2 amps.

AND A.3 Restore vital battery 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months charger to OPERABLE status.

Watts Bar - Unit 2 3.8-21 (developmental) BH

DC Sources - Operating 3.8.4 B. One required vital battery B.1 Restore vital battery to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. OPERABLE status.

A-.C. One required vital DC AC.1 Restore vital DC ele!tiieal 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power subsystm power subsystem channel inoperable for channel to OPERABLE reasons other than status Condition A or B..

B&D. Required Action and 9D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion Time of Condition A, B, or AND C not met.

BD.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. One required DG battery E.1 Restore DG battery 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months charger inoperable, terminal voltage to greater than or equal to the minimum established float voltage.

AND E.2 Verify DG battery Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months charger float current

< 2 amps.

AND E.3 Restore DG battery 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months charger to OPERABLE status.

F. One required DG battery F.1 Restore DG battery to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. OPERABLE status.

G4-.G. One required DG DC GG.1 Restore DG DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power subsystem power subsystem to inoperable for reasons OPERABLE status other than Condition E or F.

Watts Bar - Unit 2 3.8-22 (developmental) BH

DC Sources - Operating 3.8.4 P-H. Required Action and QH.1 Declare associated DG Immediately associated Completion inoperable.

Time of Condition GE, F, or G not met Watts Bar - Unit 2 3.8-23 (developmental) BH

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify vital battery terminal voltage is 4289 V (432 V 7 days for Vital batte, , V) on float charg. greater than or equal to the minimum established float voltage.

SR 3.8.4.2 Verify DG battery terminal voltage is Ž 124 V on float 7 days Gharge greater than or equal to the minimum established float voltage.

SR 3.8.4.3 Verify for the vital batteries that the alternate feeder 7 days breakers to each required battery charger are open.

SR 3.8.4.4 Verify correct breaker alignment and indicated power 7 days availability for each DG 125 V DC distribution panel and associated battery charger SR 3&.8. Verify no visible crrFosion at teFrminals and 92-days connectors for the vital batteries.

OR Verify connection resistance for the vital batterie&s-i

< 80 E 6 ohm for inteo*'

. . connections,

,,50 E 6 ohm fori_ rco n 4120 F= 6 ohmn 1fo inter tier connRections, and

5. 0 E-6 ohm for termin'al connections.

Verify no visible croinAt termPinals; and 2de connec9tors for the IDG batterie.

OR Verify connection resistance for the DG batteie0i 9 80 I=6 ohmR for inter cell connectioS-,

9 50 E 6 ohmn for inter tier connections, and 4 50 R 6 ohm for.terminal conAAnct*es.

Watts Bar - Unit 2 3.8-24 (developmental)

DC Sources - Operating 3.8.4 RR 22 ~~Vorify batterI colIc, oel! plates, and Fracft show no- 12 ~~h ndcatonof physical damage or abnormnal visp!

detekoFatwwý Watts Bar - Unit 2 3.8-25 (developmental)

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3..A Remove *is*bleterfAiAal cofrroion and v*er1,batter,'*, 12 M-A*Rh cel! to c.9l and terminIa **o*eGtions are coated with anti ".crrosion material.

SR-..8-.Q Vorify Gconnecti9F FecsitaRco for the vital battorio i 1-2-meRth6 90 Ei 6 ohmR for int8F Gel' connections-,

50 E 6 ohm for inter rack cennections, 120 E-6 ohm for intor tier connect!ons, and

< 50 E 6 ohm for - trfmfinal connectionS.

S 2-8.440n Velrify connection resistan.e for the,DG ba**e*ie is 12 ,I..,,h&,

9 80 E= 6ohmn for inter coll connections,;

n E 6 ohm.-. for-inter NA..

50) ter,connections, and

- 50 E 6 ohm for terminal cnnectine,-s.

SR 3.8.4.445 NOTE This, 8Upreoianoe is,normally not pe~fGFmed i MODE 1,2, 3,Or 4. However, credit may be taken-for unplanned oV9nts that 6atisf,' this SR.

Verify each vital battery charger-is Gapable Gf- 18 months Fechargin~g its a6sociated batter, froem a evio capac~ity discharge test while supplying normnal lods supplies > 200 amps at greater than or equal to the minimum established float voltage for

> 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

OR Verify each vital battery charger is Gapable-ef-operating fr- .4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at current limit 220 am"p.

2)5 .a..P. can recharge the battery to the fully charged state within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

(continued)

Watts Bar - Unit 2 3.8-26 (developmental) AH

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.1-26 NOTE Credit mnay be taken for unplannoid eVent6 that satisfy th!s. SR.

Verify each diselg teDG battery charger-ie- 18 months capable Of recharging its a6ceciatod battory from a corvco r cpacity diccharge test while 6upplying normal loads, supplies > 200 amps at greater than or equal to the minimum established float voltage for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

OR Verify each DG battery charger can recharge the battery to the fully charged state within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

SR 3.8.4.437 NOTES ---------

1. The modified performance discharge test in SR 3.8.4.446 may be performed in lieu of the service test in SR 3.8.4.443-7 once per 60 months.

'2 w...

I JI~ L1 V *711 T~,~,-T~rrr~t ~.,~7Ir~7I TU~~ TrrrVr~.,~~ I 3, or 4 for required vital batt*orie. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and 18 months maintain in OPERABLE status, the required emergency loads and any connected nonsafety loads for the design duty cycle when subjected to a battery service test.

(GGRt4~ed)

Watts Bar - Unit 2 3.8-27 (developmental) AH

DC Sources - Operating 3.8.4 S1UIRVEILLANCE REQU IREMENTS (cRnnuod)

SUlRVEILIIANCE FREQUENCY 9R .. 4A4 NOCTE=

This Survewilanco i6 not porfOrmoed in MODE 1, 2, 3-,

Or 4 for roguired vital batteries. Gredit m~ay be takený for unpiannod ovents that satisfy this S-R.

Vorify batter; capacity" s! 90%, of the mnanufactrer'sF! 60 months rating When subjected to a performance di6charge test Or a mod~ified perform~anco diScharge test. AND 12 moneths when degradation Or has reached 85%**f-expected lifo with capacity e1009%Of mnanufacturer's rating ANQ 21 moenths when battery has reached 85% of the epc*,ted life with capacit m~anufacturer's-Watts Bar - Unit 2 3.8-28 (developmental) AH

DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 Vital DC and Diesel Generator (DG) DC electrical power subsystems shall be OPERABLE to support the DC electrical power distribution subsystem(s) required by LCO 3.8.10, "Distribution Systems - Shutdown" and to support the Diesel Generators (DGs) required by LCO 3.8.2, "AC Sources - Shutdown."

NOTES

1. Vital Battery V may be substituted for any of the required vital batteries.

2. Spare vital chargers 6-S, 7-S, 8-S, or 9-S may be substituted for required vital chargers.

3. Spare DG chargers 1A1, 1B1, 2A1, or 2B1 may be substituted for required DG chargers.

APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies.

ACTIONS CONDITION I REQUIRED ACTION COMPLETION TIME A. One or more required vital A. 1.1 Declare affected required Immediately DC electrical power feature(s) inoperable.

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND Watts Bar - Unit 2 3.8-26 (developmental)

DC Sources - Shutdown 3.8.5 (continued)

Watts Bar - Unit 2 3.8-27 (developmental) BH

DC Sources - Shutdown 3.8.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Initiate action to suspend Immediately operations involving positive reactivity additions.

AND A.2.4 Initiate action to restore Immediately required vital DC electrical power subsystems to OPERABLE status.

B. One or more required DG B.1 Declare associated DG Immediately DC electrical power inoperable.

subsystems inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 - ------------------ NOTE ---------------

The following SRs are not required to be performed:

SR 3.8.4.445, SR 3.8.4.426, SR 4&4.3. . ,,and SR 3.8.4.447.

For DC sources required to be OPERABLE, the In accordance with following SRs are applicable: applicable SRs SR 3.8.4.1 SR 3.8.4.6 SR444 SR 3.8.4.2 SR 3.8.4.7 SR 3.9.442 SR 3.8.4.3 SR-848 SR-&&44-SR 3.8.4.4 SR 3..&.2444 SR 3.8.4.5 SR -3.8-4.0 Watts Bar - Unit 2 3.8-28 (developmental) AH

Battery Ge4-Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery GeU-Parameters LCO 3.8.6 Battery eel-parameters for 125 V vital batteries and 125 V diesel generator (DG) batteries shall be within the limits of Table 3.8.

APPLICABILITY: When associated DC electrical power subsystems and DGs are required to be OPERABLE.

ACTIONS Separate Condition entry is allowed for each battery-Ibank.

lrTIl oREQUIRED ACTION COMPLETIONhl TIMEr" A. Ooe er mere batt*ries with A4 Ve.ify Piet-eeS 1 hoe one or mor~e batter' G9ll electrlyto levol and floa parametere not within voltage-mneet-Categor,. A or B limit&. Table 3.9.6 1 Categer,' C AND A-2 cel24 Vorify, batter,'8 h-her*

parametorc mneet Table 3.8.6 1 Category C- AND OnRe per 7 day-theFeafte AND A4 ~Roctoro battery cell 4dy paramnetere to Category A and B Ifimit6 of-Table 34,-4 (continued)

Watts Bar - Unit 2 3.8-28 (developmental) AH

Battery Getl-Parameters 3.8.6

.ACGTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and.4 Doclare assoc-i~ated- immediately associated Completion battery i prb Time of Cendition A Aet-mete.

OR orMorM batterios With-8One aVerage electrolyte temAperature of the representati'e cills - 60*F for vital battFeris and 5 0 F fGorDG batteries.

OR One Or moere bhatteries; mithh one or morFe battery oel' parameters not within Category C values.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required vital battery A.1 Perform SR 3.8.4.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with one or more battery cells float voltage AND

< 2.07 V.

A.2 Perform SR 3.8.6.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND A.3 Restore affected cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months float voltage > 2.07 V.

B. One required vital battery B.1 Perform SR 3.8.4.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with float current AND Watts Bar - Unit 2 3.8-29 (developmental) AH

Battery Qe*-Parameters 3.8.6

> 2 amps.

B.2 Restore vital battery 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months float current to

< 2 amps.

C. One required DG battery C.1 Perform SR 3.8.4.2. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with one or more battery cells float voltage AND

< 2.07 V.

C.2 Perform SR 3.8.6.2. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND C.3 Restore affected cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months float voltage > 2.07 V.

D. One required DG battery D.1 Perform SR 3.8.4.2. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with float current > I amp.

AND D.2 Restore DG battery float 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months current to < 2 amps.

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

Required Action E.2 shall be Required Actions E.1 and E.2 are completed if electrolyte level only applicable if electrolyte level was below the top of plates. was below the top of plates.

E. One required battery with E.1 Restore electrolyte 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months one or more cells with levels to above top of electrolyte level less than plates.

minimum established design limits. AND E.2 Verify no evidence of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months leakage.

AND E.3 Restore electrolyte level 31 days to greater than or equal to minimum established design limits.

Watts Bar - Unit 2 3.8-30 (developmental) AH

Battery Ge4-Parameters 3.8.6 F. One required battery with F.1 Restore battery pilot 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months pilot cell electrolyte cell temperature to temperature less than greater than or equal to minimum established minimum established design limits, design limits.

G. More than one required G.1 Restore battery 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months vital batteries with battery parameters to within parameters not within limits.

limits.

OR More than one required DG batteries with battery parameters not within limits.

H. Required Action and H.1 Declare associate Immediately associated Completion battery inoperable Time of Condition A, B, C, D, E, F, or G not met.

OR One required vital battery with one or more battery cells float voltage < 2.07 V and float current

> 2 amps.

OR One required DG battery with one or more battery cells float voltage < 2.07 V and float current

> 2 amps.

SURVEILLANCE REQUIREMENT&

S1U/RVI I ANCR rEQUlI Watts Bar - Unit 2 3.8-31 (developmental) AH

Battery GelS-Parameters 3.8.6 SR 1.9.

bae~y e~if el! a~anete6 Fset Tble3.8. 1 7day Watts Bar - Unit 2 3.8-32 (developmental) AH

Battery G*al-Parameters 3.8.6 SUVILL--ANICE REQiU IIREr MERNITS lcnnnfin*al SURVElD-I ANICE i i I* i II II Verfiy hflAtter-Acol namotornAus4 moo-t T amle id 92-days Categor~y B limitsb.

A4D 21 hours2.430556e-4 days 0.00583 hours 3.472222e-5 weeks 7.9905e-6 months aftor a battery discharge-battorios (113.5 V for vital bater,' V) or 106.5 V for DG-bateFaes AND OfiAe-w4thHi

24. hours a;ft-er a batter, ovorchargo

>150V fOr Vital-battorios (15 Viifor.

vital batter,' V)-eor 14 5 V fer-G-b;IArfedAs S£ 3.8. Veorify avorag elcctrolyte temporaturw of d2-days 0

representatiVe ce'lls is Ž 60 ro for vital batterie6 and

Ž590P for the DG- bhatte-rie4&,

Watts Bar - Unit 2 3.8-33 (developmental) AH

Battery Geu-Parameters 3.8.6 Table 3.8.6 1 (page 4 of 1)

Batte: Cell ParaeterS ReGuFiemnt P.A RAE.-T-r=- CATEGO.RY-A CATEGORY B CATEGORY C:

LIMITS FOR EACH4 LIMITS FOR E ACH AlLOW01AIABLE LIMIT DESIGNATED PILOT CONNEC-TED CELL,GR &AG-GE-LL- CONNECTE- CELL 09&eet4e Lev~el MiniR lee

- ýMum F4 MinimRumlel Above top of plates, indic*i*n maFrk, and indic rd nO*to Rloig 141. irnh above 4 V41 inch aboVe ma6iMu level maxmu leVel

_________________ idictionmark~ idication mark-W Pleat Voltage -2143V>20V

>44V SpersifGGr4ty ,29i95hnot Mere than 0.020 AND below average of all Ave~age ofa~ll connecte-d cell_

connected cells AAQ

> 1206 AveFage ofaI connecrted co~lsr

_ _ _ _ __ __ Ž1.196 (a) it is accoptable for the electrolyte level to temRpGrarily increase above the specife maiu level du~rin equalizingR charges provid-ed itis not evogewing.

(b) Corrected for electrolyte temperature and level. Level correction is not required, however, WhenR batteoy char-ging is 42 amps when OR float charge forF vfital batteries and

,<1.0 amp for DG batteris (G) A batter- ch~arging current of 42 amps when oA float charge forF vital bhatteriesF and-I A.) aI lP TU L.... GatRes~. its aGG9Ptdb;U ful 8etuLily t6PGGIIRl ylJ'.ly k ritstpIllewmg~l ai DattUI k f- f2rarn'1ruur A 1A Anr ann',n uu u ua uIrat;/ . # u. ual. A

no'fk4,oan

.W. ~~ r ,;,

reuiemets, Specific gravity Of eac~h connectr-ed Gel! shall be mneasured prier to expira;tion of the 31 day allowa;;nce-SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 ----------------------- NOTE -------- ---------

Not required to be met when vital battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each vital battery float current is < 2 amps. 7 days Watts Bar - Unit 2 3.8-34 (developmental) AH

Battery Gel-Parameters 3.8.6 SR 3.8.6.2 ------------------------------- NOTE -------------------------------

Not required to be met when DG battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.2.

Verify each DG battery float current is 2.07 V.

SR 3.8.6.4 Verify each required vital and DG battery 31 days connected cell electrolyte level is greater than or equal to minimum established design limits.

SR 3.8.6.5 Verify each required vital and DG battery pilot 31 days cell temperature is greater than or equal to minimum established design limits.

SR 3.8.6.6 Verify each required vital and DG battery 92 days connected cell float voltage is > 2.07 V.

Watts Bar - Unit 2 3.8-35 (developmental) AH

Battery Ge4-Parameters 3.8.6 SR 3.8.6.7 NOTE ----------.----....-------.----

Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is > 80% of the 60 months manufacturer's rating when subjected to a performance discharge test or a modified AND performance discharge test.

12 months when battery shows degradation, or has reached 85%

of the expected life with capacity

< 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity >_100% of manufacturer's rating Watts Bar - Unit 2 3.8-36 (developmental) AH

THIS SECTION NOT USEDContainmont Penetrations 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 THIS SECTION NOT USED G.tai.Ment Penetrtation no i1 ntainment po*nt*rlO1* SalI l eI*Ronle +loIlIWig ItaI UG;

a. The eau'uieet hatch closod and held in placo by a minumn of four beft&si

b. One door inoach air Ieock clooed-; or capable of being Gdocod provided

.AB-GTS6 ic6 OPER'ABLEM in acco~rd-ance 40ith IS 3.7.12; and G. Each 9enetration oroviding direct access from the containment I

aimospnoroe to the euisipoa aumeepnore pimer

1. csod by a m.an.ual or automatic iol.ation valve, blind flange, Or

2. capab!e of being Glesd by an OPERA.BLE Containment Vent iNOTSystem.

Penetration flew path(s) providing directaccess froem the containment

~

n~~~~mnrnnnrn In tImff ~ ~

rmpr' ~ 1 ~ ~

nI'F'ýn

- -aI n

ý.,

I aemiFnirative cnroic prOVIGep :Mu¶- i is ur' O L+/- in accorgaRnc WIt Duringq movement Of irradiated fuel a66eomblie6 within conptainment APTIN*I GONDITION REQUIRED ACTIO0N COMPLETION TIME otansr- A4 Suspend movement of p9netrati9ns not in require irradiated fuel assembie StatU&Within containment.

Watts Bar - Unit 2 3.9-5 (developmental) AH

THIS SECTION NOT USEDCcntai.m.nt Ponetrations-;

3.9.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQIJENG~

SIR-4.9.A Verify each roquirod containment penetration is in 7-dy th rquidr-rr-statuc*.

I S 292 eah required cntainAen*t vent isevatiORn vlvv Verify 48-m,, h.

actuate, to th.e sol pitiR On an actual or simulated actAtnsial Watts Bar - Unit 2 3.9-6 (developmental) AH

Reactor Building Purgwe Air Cloanup UnitTHIS SECTION NOT USED 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 Reactor Bui~ldng Purge Air Cleanup UnWt THIS SECTION NOT USED T4nD Rea4cGtr BIuilding Purge AiFr Cleanup Units shall be OPERABl A.PIP*LAII ITY: Dur.ig mo..Veme eirradiated fu*o-l- ...

o.f biec. Within the containmn*t.

AGT-ONS CONDITION REQUIRED ACTI*N COMPLETION TIME A. One- Ro-acntor Building Pugo A-.4- Icolat9 the inoporable air: IFAmediately Ai.r Cleanp UnWit inoperable. G-ea*u uip-W AND A72 Verify the OPERABLE air- Immediately cleanup uniticn B. Two~n Re-actor Building Purge 4.4 Surpend move-ment of- 4FMmediatqh Air Cleanup Units irra;diatod fuel acce~mblice SURVEILLANE REQUIREMENTS S1 D1RE IRiCe- Er-QIENGY SR .9P required filtor teting in accordance with the In accordance With Vent*latieR Filter Tecting Programn (VFTP). the VF-T-Watts Bar - Unit 2 3.9-12 (developmental) AH

Decay Time 3.9.10 3.9 REFUELING OPERATIONS 3.9.10 Decay Time LCO 3.9.10 The reactor shall be subcritical for > 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

APPLICABILITY: During movement of irradiated fuel assemblies within the containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor subcritical for A.1 Suspend all operations Immediately

< 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months . involving movement of irradiated fuel assemblies within the containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.10.1 Verify the reactor has been subcritical for > 100 Prior to movement hours by confirming the date and time of of irradiated fuel in subcriticality. the reactor vessel.

Watts Bar - Unit 2 3.9-13 (developmental) H

Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks (shown in Figure 4.3-1) are designed and shall be maintained with:

a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent (wt%);

b. kff < 0.95 if fully flooded with unborated water, which, includes an allowance for uncertainties as described in Sections 4.3.2.7 and 9.1 of the FSAR;

c. Distances between fuel assemblies are a nominal 10.375 inch center-to-center spacing in the twenty-four flux trap rack modules.

d. Fuel assemblies with initial enrichments less than a maximum of 5 wt% U-235 P9FGei#-enrichment (nominally 4.95 +/- 0.05 wt%

U-235peFree*) may be stored in the spent fuel racks in any one of four arrangements with specific limits as identified below:

1. New and 6pe uel assemblies may be stored in the racks in an all cell arrangement provided the burnup of each assembly is in the acceptable domain identified in Figure 4.3-3, depending upon the specified initial enrichment.

2. New and spent fuel assemblies may be stored in a checkerboard arrangement of 2 new and 2 spent assemblies, provided that each spent fuel assembly has accumulated a minimum burnup in the acceptable domain identified in Figure 4.3-4.

3. New fuel assemblies may be stored in 4-cell arrays with 1 of the 4 cells remaining empty of fuel (i.e. containing only water or water with up to 75 percent by volume of non-fuel bearing material.

(continued)

Watts Bar - Unit 2 4.0-2 (developmental) GH

Design Features 4.0 7.0 6.5 6.0 5.5 5.0 4.5 4.0 3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.0 Initial Enrichment wt% U-235 FIGURE 4.3-3 MINIMUM REQUIRED BURNUP FOR UNRESTRICTED STORAGE OF NEW AND SPENT FUEL OF VARIOUS INITIAL ENRICHMENTS (continued)

Watts Bar - Unit 2 4.0-8 (developmental) GHI

Design Features 4.0 I-i Initial Enrichment wt% U-235 FIGURE 4.3-4 MINIMUM REQUIRED BURNUP FOR A CHECKERBOARD ARRANGEMENT OF 2 SPENT AND 2 NEW FUEL ASSEMBLIES OF 5 wt% U-235 ENRICHMENT (MAXIMUM)

Watts Bar - Unit 2 4.0-9 (developmental)

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals (continued) 5.7.2.14 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in accordance with Regulatory Guide 1.52, Revision 2; ASME N510-1989, and the exceptions noted for each ESF system in Tables 6.5-1, 6.5-2, 6.5-3, and 6.5-4 of the FSAR.

a. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass within acceptance criterion when tested in accordance with Regulatory Guide 1.52, Revision 2, the exceptions noted for each ESF system in Tables 6.5-1, 6.5-2, 6.5-3, and 6.5-4 of the FSAR, and ASME N510-1989 at the system flowrate specified below.

ESF VENTILATION ACCEPTANCE SYSTEM CRITERIA FLOW RATE Re-actor guildIg Purge*

D,.001 14,000 cfmr+ 10%,0 Emergency Gas < 0.05% 4,000 cfm + 10%

Treatment Auxiliary Building Gas < 0.05% 9,000 cfm + 10%

Treatment Control Room Emergency < 1.00% 4,000 cfm + 10%

(continued)

Watts Bar-Unit 2 5.0-18 (developmental)

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.14 Ventilation Filter Testing Program (VFTP) (continued)

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass within acceptance criterion when tested in accordance with Regulatory Guide 1.52, Revision 2, the exceptions noted for each ESF system in Tables 6.5-1, 6.5-2, 6.5-3, and 6.5-4 of the FSAR, I and ASME N510-1989 at the system flowrate specified below.

ESF VENTILATION ACCEPTANCE SYSTEM CRITERIA FLOW RATE Rea-rotr Building PUrg 1.09% 4 114,90 A ,fm 4. 10%

Emergency Gas Treatment < 0.05% 4,000 cfm + 10%

Auxiliary Building Gas < 0.05% 9,000 cfm + 10%

Treatment Control Room Emergency < 1.00% 4,000 cfm + 10%

(continued)

Watts Bar-Unit 2 5.0-19 (developmental) SHI

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.14 Ventilation Filter Testing Program (VFTP) (continued)

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, and the exceptions noted for each ESF system in Tables 6.5-1, 6.5-2, 6.5-3, and 6.5-4 of the FSAR, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of < 300C and greater than or equal to the relative humidity specified below.

METHYL IODIDE RELATIVE ESF VENTILATION SYSTEM PENETRATION HUMIDITY Ro~acto-r Building Purge -410%9" Emergency Gas Treatment < 0.175% 70%

Auxiliary Building Gas < 0.175% 70%

Treatment Control Room Emergency < 1.0% 70%

d. Demonstrate for each of the ESF systems that the pressure drop across the entire filtration unit is less than the value specified below when tested in accordance with Regulatory Guide 1.52, Revision 2, the exceptions noted for each ESF system in Tables 6.5-1, 6.5-2, 6.5-3, and 6.5-4 of the FSAR, and ASME N510-1989 at the system flowrate specified below.

ESF VENTILATION SYSTEM PRESSURE DROP FLOW RATE ReAc-tor *ui*diRg PuFrgo 4 4.7 inc-hes water 114,000 cfm,- I %0%

Emergency Gas < 7.6 inches water 4,000 cfm + 10%

Treatment Auxiliary Building Gas < 7.6 inches water 9,000 cfm + 10%

Treatment Control Room Emergency < 3.5 inches water 4,000 cfm + 10%

(continued)

Watts Bar-Unit 2 5.0-20 (developmental) BHI

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.19 Containment Leakage Rate Testing Program (continued)

Leakage rate acceptance criteria are:

a. Containment overall 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 combined Type B and Type C tests, and _< 0.75 La for Type A tests.

b. Air lock testing acceptance criteria are:

1. Overall air lock leakage rate is < 0.05 La when tested at > Pa.

2. For each door, leakage rate is _< 0.01 La when pressurized to 6 psig.

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

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

5.7.2.20 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 Emergency Ventilation System (CREVS), 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 the applicable regulatory requirement {i.e., 5 rem Total Effective Dose Equivalent (TEDE) for a fuel handling accident or 5 rem whole body or its equivalent to any part of the body} 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.

Watts Bar-Unit 2 5.0-25 (developmental) AH

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.20 Control Room Envelope Habitability Program (continued)

c. Requirements for (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 Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREVS, operating at the flow rate defined in the Ventilation Filter Testing Program (VFTP), at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.

e. The quantitative limits on unfiltered air inleakage 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 measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

5.7.2.21 Battery Monitoring and Maintenance Program This Program provides controls for battery restoration and maintenance. The program shall be in accordance with IEEE Standard (Std) 450-2002, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," as endorsed by Regulatory Guide 1.129, Revision 2 (RG), with RG exceptions and program provisions as identified below:

a. The program allows the following RG 1.129, Revision 2 exceptions:

Watts Bar-Unit 2 5.0-26 (developmental) AH

Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals

1. Battery temperature correction may be performed before or after conducting discharge tests.

2. RG 1.129, Regulatory Position 1, Subsection 2, "References," is not applicable to this program.

3. In lieu of RG 1.129, Regulatory Position 2, Subsection 5.2, "Inspections," the following shall be used: 'Where reference is made to the pilot cell, pilot cell selection shall be based on the lowest voltage cell in the battery."

4. In Regulatory Guide 1.129, Regulatory Position 3, Subsection 5.4.1, "State of Charge Indicator," the following statements in paragraph (d) may be omitted:

"When it has been recorded that the charging current has stabilized at the charging voltage for three consecutive hourly measurements, the battery is near full charge.

These measurements shall be made after the initially high charging current decreases sharply and the battery voltage rises to approach the charger output voltage."

5. In lieu of RG 1.129, Regulatory Position 7, Subsection 7.6, "Restoration", the following may be used: "Following the test, record the float voltage of each cell of the string."

b. The program shall include the following provisions:

1. Actions to restore battery cells with float voltage < 2.13 V;

2. Actions to determine whether the float voltage of the remaining battery cells is > 2.13 V when the float voltage of a battery cell has been found to be < 2.13 V;

3. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;

4. Limits on average electrolyte temperature, battery connection resistance, and battery terminal voltage; and

5. A requirement to obtain specific gravity readings of all cells at each discharge test, consistent with manufacturer recommendations.

Watts Bar-Unit 2 5.0-27 (developmental) AH

Reporting Requirements 5.9 5.0 ADMINISTRATIVE CONTROLS 5.9 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.9.1 DELETED 5.9.2 Annual Radiological Environmental Operating Report

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

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. The roport shall identify the TLDrFe.ults that represent "co!!o"antod decsimete n relation to the NRC TLD program -an~dthe exposure poiod a..ociated with each re.ult. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

(continued)

Watts Bar - Unit 2 5.0-29 (developmental) AHI

APPENDIX B TO FACILITY OPERATING LICENSE ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)

FOR WATTS BAR NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-391 TENNESSEE VALLEY AUTHORITY Watts Bar Nuclear Plant - Unit 2 December 12, 2013 Environmental Protection Plan - Appendix B

WATTS BAR NUCLEAR PLANT UNIT 2 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)

TABLE OF CONTENTS Section Page 1.0 DEFINITIONS, ABBREVIATIONS, AND ACRONYMS ..................................... 1-1 2.0 LIMITING CONDITIONS FOR OPERATION ..................................................... 2-1 3.0 ENVIRONMENAL MONITORING ...................................................................... 2-1 4.0 SPECIAL STUDIES AND REQUIREMENTS ..................................................... 4-1 4.1 Exceptional Occurrences ................................................................................ 4-1 4.2 S pecial Studies ................................................................................................. 4-2 5.0 ADMINISTRATIVE CONTROLS ........................................................................ 5-1 5.1 R espo nsibility ................................................................................................... 5-1 5.2 Review and A udit ............................................................................................. 5-1 5.3 Changes in Station Design or Operation ....................................................... 5-2 5.4 Station Reporting Requirements .................................................................... 5-3 5.5 Changes in Environmental Protection Plan and Permits ............................. 5-6 5.6 Records Retention ........................................................................................... 5-6 Watts Bar Nuclear Plant - Unit 2 December 12, 2013 Environmental Protection Plan - Appendix B

1.0 DEFINITIONS, ABBREVIATIONS, AND ACRONYMS Annually Annually is once per calendar year at intervals of twelve (12) calendar months +/- 30 days Clean Water Act Federal Water Pollution Control Act (FWPCA) as amended.

FES Final Environmental Statement (NUREG-0498) issued December 1978 by the NRC to the TVA (Control No. 7901100061).

FES and Subsequent Supplements Consists of the FES, FES Supplement 1, and FES Supplement 2 FES Supplement 1 Final Environmental Statement (NUREG-0498 Supplement 1) issued April 1995 by the NRC to the TVA (ADAMS Accession No. ML081430592).

FES Supplement 2 Final Environmental Statement (NUREG-0498 Supplement 2, Vol. 1 &

Vol. 2) issued May 2013 by the NRC to the TVA (ADAMS Accession Nos.

ML13144A092 & ML13144A093).

FWS U.S. Fish and Wildlife Service NPDES Permit NPDES permit is the National Pollutant Discharge Elimination System Permit No. TN0020168 issued by the U.S. Environmental Protection Agency to the Tennessee Valley Authority (TVA). This permit authorizes TVA to discharge controlled waste water, from the Watts Bar Plant Unit 2 into the Tennessee River.

NRC U.S. Nuclear Regulatory Commission Plant Plant refers to the Watts Bar Nuclear Plant, either Unit 1 or Unit 2.

Site Onsite includes any area within the property owned by the TVA specifically described in the WBN FES. Offsite includes all other areas.

Station Station refers to Watts Bar Nuclear Plant Unit 1 and Unit 2.

TVA Tennessee Valley Authority Unit Unit refers to Unit 2 (i.e., WBN2) of the Watts Bar Nuclear Plant, as defined by its usage.

WBN Watts Bar Nuclear Plant Watts Bar Nuclear Plant - Unit 2 1-1 December 12. 2013 Environmental Protection Plan - Appendix B

2.0 LIMITING CONDITIONS FOR OPERATION (NIA)

None required 3.0 ENVIRONMENTAL MONITORING None required 1 In consideration of the provisions of the Clean Water Act (33 USC §1251, et seq.) and in the interest of avoiding duplication of effort, the conditions and monitoring requirements related to water quality and aquatic biota are specified in the National Pollution Discharge Elimination System (NPDES) Permit No. TN0020168 issued by the U.S. Environmental Protection Agency to the Tennessee Valley Authority (TVA). This permit authorizes TVA to discharge controlled waste water from the Watts Bar Nuclear Plant Unit 2 into the Tennessee River.

Existing Watt Bar Unit 1 monitoring and reporting programs will continue to be followed as part of WBN dual-unit operation.

The Nuclear Regulatory Commission will be relying on the NPDES permit for protection of the aquatic environment from non-radiological effluents.

Watts Bar Nuclear Plant - Unit 2 2-1 December 12, 2013 Environmental Protection Plan - Appendix B

4.0 SPECIAL STUDIES AND REQUIREMENTS 4.1 Exceptional Occurrences 4.1.1 Unusual or Important Environmental Events Requirements The licensee shall record any occurrences of "Unusual or Important Environmental Events."

"Unusual or Important Environmental Events" are those that potentially could cause or indicate environmental impact causally related with plant operation. The following are examples:

excessive bird impact events; onsite plant or animal disease outbreaks; unusual mortality of any species protected by the Endangered Species Act of 1974; fish kills near the plant site; unanticipated or emergency discharges of waste water or chemical substances.

This special requirement shall commence with the date of issuance of the operating license and continue for the life of the plant, unless changed in accordance with Subsection 5.5.1.

Action Should an "Unusual or Important Environmental Event" occur, the licensee shall make a prompt report to the NRC in accordance with the provisions of Subsections 5.4.2.a and 5.4.2.c, or Subsection 5.4.2.d.

4.1.2 Exceeding Limits of Other Relevant Permits Requirement The licensee shall notify the NRC of occurrences in which the limits specified, in relevant permits and certificates issued by other federal, state, and local governments are exceeded and which are reportable to the applicable agency.

This requirement shall commence with the date of issuance of the operating license and continue for the life of the plant, unless changed in accordance with Subsection 5.5.1.

Watts Bar Nuclear Plant - Unit 2 4-1 December 12. 2013 Environmental Protection Plan - Appendix B

Action The licensee shall make a report to the NRC in accordance with the provisions of Subsections 5.4.2.b and 5.4.2.c, or Subsection 5.4.2.d in the event if a limit specified in a relevant permit or certificate issued by another federal, state, or local agency is exceeded and is reportable to the applicable agency.

4.2 Special Studies None required at the present time.

Watts Bar Nuclear Plant - Unit 2 4-2 December 12, 2013 Environmental Protection Plan - Appendix B

5.0 ADMINISTRATIVE CONTROLS 5.1 Resoonsibility The Plant Manager has responsibility for operating the plant in compliance with this Environmental Protection Plan.

5.2 Review and Audit The licensee shall provide for review and audit of compliance with the Environmental Protection Plan. The audits shall be conducted independently of the Individual or groups responsible for performing the specific activity. A description of the organization structure utilized to achieve the independent review and audit function and results of the audit activities shall be maintained and made available for inspection.

5.2.1 Review The licensee is responsible for the review of procedures for meeting the Environmental Protection Plan.

The above mentioned review shall be conducted on the following:

A. Proposed changes to the Environmental Protection Plan and evaluated impact of the change.

B. Proposed changes to station operating procedures, which affect the environmental effects of the station.

C. Proposed changes, construction, or modifications to station or unit equipment, or systems which might have an environmental impact, in order to determine the environmental impact of the change 2 .

2 Activities are excluded from this requirement if all measurable environmental effects are confined to on-site areas previously disturbed during site preparation and plant construction.

Watts Bar Nuclear Plant - Unit 2 5-1 December 12, 2013 Environmental Protection Plan - Appendix B

D. All routine reports prior to their submittals to NRC (described in Subsection 5.4.1).

E. All nonroutine reports prior to submittal of the written report (described in Subsections 5.4.a, b, and c).

F. Investigations of all reported instances of noncompliance with the Environmental Protection Plan, associated corrective actions, and measures taken to prevent recurrence.

5.2.2 Audit The licensee shall conduct an audit on the environmental monitoring program. The audits shall be conducted independently of the individual or group responsible for performing the specific activity. Results of the audit activities shall be maintained and made available for inspection.

5.3 Changes in Station Design or Operation Changes in station design or operation may be made subject to the following conditions:

A. The licensee may (1) make changes in the station design and operation, and (2) conduct tests and experiments not described in this document without prior Commission approval, unless the proposed change, test or experiment involves a change in the objectives of the Environmental Protection Plan 3 and/or an unreviewed environmental question of significant impact.

3 This provision does not relieve the licensee of the requirements of 10 CFR 50.59.

Watts Bar Nuclear Plant - Unit 2 5-2 December 12, 2013 Environmental Protection Plan - Appendix B

B. A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the final environmental statement (FES) and subsequent supplements as modified by testimony to the Atomic Safety and Licensing Board, supplements thereto, environmental impact appraisals, or in initial or final adjudicatory decisions; or (2) a matter not previously reviewed and evaluated in the documents specified in (1) of this section which may have a significant adverse environmental impact.

C. The licensee shall maintain records of changes in facility design or operation made pursuant to this subsection. The licensee shall also maintain records of tests ad experiments carried out pursuant to paragraph "A" of this Subsection. These records shall include a written change, test, or experiment does not involve an unreviewed environmental question or substantive impact or constitute a change in the objectives of the Environmental Protection Plan. The licensee shall furnish to the Commission, annually or at such shorter intervals as may be specified in the license, a report containing description, analyses, interpretations, and evaluations of such changes, tests, and experiments.

D. Changes in the special studies, if required in Section 4.2, which affects sampling frequency, location, gear, or replication shall be reported to the NRC within 30 days after their implementation, unless otherwise reported in accordance with Subsection 5.4.2.

These reports shall describe the changes made, the reasons for making the changes, and an evaluation of the effectiveness of the revised program in assessing environmental impacts.

5.4 Station Reportingq Requirements 5.4.1 Routine Reports Annual Environmental Operation Report A WBN dual-unit report on the environmental monitoring program for the previous year shall be submitted to the NRC separate from other NRC reporting requirements within 90.days following Watts Bar Nuclear Plant - Unit 2 5-3 December 12, 2013 Environmental Protection Plan - Appendix B

each anniversary of issuance of the WBN1 operating license. The WBN1 operating license anniversary date is utilized as the basis for the WBN dual-unit anniversary date, since it was the basis for the initial and subsequent reports. The report shall include summaries, analyses, interpretations, and statistical evaluation of the results of the environmental monitoring required by special studies and requirements (Section 4) for the report period, including a comparison with preoperational studies, operating controls (as appropriate), and previous non-radiological environmental monitoring reports, and an assessment of the observed impacts of the station operation on the environment. If harmful effects or evidence of irreversible damage are suggested by the monitoring programs, the licensee shall provide a more detailed analysis of the data and a proposed course of action to alleviate the problem.

For those programs concerned with water quality or protection of aquatic biota, which are regulated under the Clean Water Act, the requirements of this section shall be satisfied by submitting to the NRC copies of the reports required by the NPDES permit (or otherwise required pursuant to the Clean Water Act), and in accordance with the frequency, content and schedules set forth by the agencies responsible for implementing the Clean Water Act.

In the event that some results are not available by the report date, the report shall be submitted noting and explaining the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The Annual Report shall also include a summary of:

1. All Environmental Protection Plan noncompliances and the corrective actions taken to remedy them.

2. Changes made to applicable state and federal permits and certifications.

3. Changes to station design which could involve a significant environmental impact or change the findings of the FES and subsequent supplements.

4. All nonroutine reports submitted per Environmental Protection Plan Section 4.1.

5. Changes in the approved Environmental Protection Plan.

Watts Bar Nuclear Plant - Unit 2 5-4 December 12, 2013 Environmental Protection Plan - Appendix B

5.4.2 Nonroutine Reports A report shall be submitted in the event that an "Unusual or Important Environmental Event," as specified in Subsection 4.1.1 occurs, or if another relevant permit is violated as specified in Subsection 4.1.2. The schedule and content for these nonroutine reports are described below.

5.4.2.a Prompt Report Those events specified as requiring prompt reporting shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone, telegraph, or facsimile transmission to the NRC followed by a written report to the NRC within 30 days.

5.4.2.b Thirty Day Report Those events not requiring a prompt report as described in Subsection 5.4.2.a shall be reported to the NRC within 30 days of their occurrence.

5.4.2.c Content of Nonroutine Reports Written 30-day reports and, to the extent possible, the preliminary telephone, telegraph, or facsimile reports shall (a) describe, analyze, and evaluate the occurrence, including the extent and magnitude of the impact, (b) describe the cause of the occurrence, (c) indicate the action taken to correct the occurrence, and (d) indicate the corrective action taken (including any significant changes made in procedures) to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.

5.4.2.d Exceptions for Matters Requlated Under the Clean Water Act For matters regulated under the Clean Water Act, the report schedules and content requirements described in Subsections 5.4.2.a, 5.4.2.b, and 5.4.2.c shall be satisfied by submitting, to the NRC copies of the reports as required by the NPDES permit (or other regulations pursuant to the Clean Water Act) and in accordance with the schedules and content requirements imposed thereby.

Watts Bar Nuclear Plant - Unit 2 5-5 December 12, 2013 Environmental Protection Plan - Appendix B

5.5 Changes in the Environmental Protection Plan and Permits 5.5.1 Changes in the Environmental Protection Plan Requests for a change to the Environmental Protection Plan shall be submitted to the NRC for review and authorization per 10 CFR 50.90. The request shall include an evaluation of the environmental impact of the proposed change and a supporting justification. Implementation of such requested changes to the Environmental Protection Plan shall not commence prior to incorporation by the NRC of the specifications in the license.

5.5.2 Changes in Permits and Certifications Changes and additions to required federal (other than NRC), state, local, and regional authority permits and certificates for the protection of the environment shall be reported to the NRC within 30 days. In the event that the licensee initiates or becomes aware of a request for changes to any of the water quality requirements, limits, or values stipulated in any certification or permit issued pursuant to the Clean Water Act, the NRC shall be notified within 30 days.

If a permit or certification, in part or in its entirety, is appealed and stayed, the NRC shall be notified within 30 days. If, as a result of the appeal process, the permit or certification requirements are changed, the change shall be dealt with as described in the previous paragraph of this section.

5.6 Records Retention Records and logs relative to the environmental aspects of station operation shall be made and retained in a manner convenient for review and inspection. These records and logs shall be made available to NRC on request.

5.6.1 The following records shall be retained for the life of the station:

(a) Record of changes to the Environmental Protection Plan including, when applicable, records of NRC approval of such changes.

Watts Bar Nuclear Plant - Unit 2 5-6 December 12, 2013 Environmental Protection Plan - Appendix B

(b) Record of modifications to plant structures, systems, and components determined to potentially affect the continued protection of the environment.

(c) Record of changes to permits and certifications required by federal (other than the NRC), state, local, and regional authorities for the protection of the environment.

(d) Routine reports submitted to the NRC.

5.6.2 Records of the following shall be retained for a minimum of six (6) years:

(a) Review and audit activities.

(b) Events, and the reports thereon, which are the subjects of non-routine reports to the NRC.

5.6.3 Records associated with requirements of federal (other than the NRC), state, local, and regional authorities' permits and certificates for the protection of the environment shall be retained for the period established by the respective permit or certificate.

Watts Bar Nuclear Plant - Unit 2 5-7 December 12, 2013 Environmental Protection Plan - Appendix B

Watts Bar Nuclear Plant 2 C) 0 Submittal of Developmental Revision H of the Unit 2 a 0 Technical Specification and Technical Specification 0 Bases 0 t'2 (D

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ATTACHMENT 2 Technical Specification Bases Changes (Mark-Up) for WBN Unit 2

PAM Instrumentation B 3.3.3 BASES LCO 5. Reactor Coolant System Pressure (Wide Range) (continued)

RCS pressure is also related to three decisions about depressurization.

They are:

to determine whether to proceed with primary system depressurization;

to verify termination of depressurization; and

to determine whether to close accumulator isolation valves during a controlled cooldown/depressurization.

A final use of RCS pressure is to determine whether to operate the pressurizer heaters.

RCS pressure is a Type A variable because the operator uses this indication to identify events and to monitor the cooldown of the RCS following a steam generator tube rupture (SGTR) or small break LOCA.

Operator actions to maintain a controlled cooldown, such as adjusting steam generator (SG) pressure or level, would use this indication.

6. Reactor Vessel Water Level Roactor Vossol Water Level, a non Type A,Category 1 variable, is provided for vo-rificatfion -andlong termn surveillance of cor colin.I is alse used 1fo accident diagnosis and to determine reactor coolant-inventory adequacy.

Reactor Vessel Water Level, a Type A, Category 1 variable is provided for:

SI re-initiation criteria,

" Pressurizer Level Control,

" Criteria for manually re-starting ECCS pumps,

" Criteria for closing CLA isolation valves,

RCS Pressure Control,

Verification and long term surveillance of core cooling,

Accident diagnosis,

Determination of reactor coolant inventory adequacy, and

Pressurizer heater control The Reactor Vessel Level Instrumentation System (RVLIS) provides a direct measurement of the liquid level above the bottom of the reactor (continued)

Watts Bar - Unit 2 B 3.3-126 (developmental) RH I

Containment Vent Isolation Instrumentation B 3.3.6 B 3.3 INSTRUMENTATION B 3.3.6 Containment Vent Isolation Instrumentation BASES BACKGROUND Containment Vent Isolation Instrumentation closes the containment isolation valves in the Containment Purge System. This action isolates the containment atmosphere from the environment to minimize releases of radioactivity in the event of an accident. The Reactor Building Purge System may be in use during reactor operation and with the reactor shutdown.

Containment vent isolation is initiated by a safety injection (SI) signal or by manual actuation. The Bases for LCO 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," discuss initiation of SI signals.

Redundant and independent gaseous radioactivity monitors measure the radioactivity levels of the containment purge exhaust, each of which will initiate its associated train of automatic Containment Vent Isolation upon detection of high gaseous radioactivity.

The Reactor Building Purge System has inner and outer containment isolation valves in its supply and exhaust ducts. This system is described in the Bases for LCO 3.6.3, "Containment Isolation Valves."

rio niant dos'nn baf~!t roou!rn~ That wrion mn'.!~nn ~rradtatod tuol !fl trio The ,RAlaR. 9e dlAmn bnrasi F8;einthant *.n9k 9VhaflaF-,,mnrat8E Anan *r the, A.H..-. HA--A.^.+k.....+.; -.

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VentilationR Isolation (CVI) in additon to their norma! inntien. In addition, a r:ignal from tho containm~ent purge radiation monitors 2 RE 90 130, and 131or1- oteGVI 6igna! wil! initiate that po~fien of the Auxiliar,' Buildfing Ipolatien !A81) Rnormall" initi-ited b" the spent fiinl meal rad'ntion monitorr

.~aoitionaiiv. a ~onrninment iso:zuion i-mace ~ sianaii irem mo oooat~o uit.e tomeratur ;en in 11e A'UXitiar'. Ruildin ar Intakes, 9r Fmanual AB!1 Wil! cause a CV! Gignal inthe refueling unit. In the case

.:h9re the containment Of beth uIt iRS open to the Auxiliar-y Buildin Spaces, a CVI inonE uit Wil! intiate A 04I in the ot~her un'it in oirde to maintain thiece spaces open to the ABSCE. Thoeterqe, theo containment Yentilation intumnato ust remnain operable when movinRg iRradiated fuel in the Auxiliary Building if the containment afir locks, penetrations, egUipMent h~atch, etc. are open to the Auxiliary Building ABSCE spaces.

(continued)

Watts Bar - Unit 2 B 3.3-150 (developmental) GH

Containment Vent Isolation Instrumentation B 3.3.6 BASES (continued)

APPLICABLE The containment isolation valves for the Reactor Building Purge System SAFETY close within six seconds following the DBA. The containment vent ANALYSES isolation radiation monitors act as backup to the Sl signal to ensure closing of the purge air system supply and exhaust valves. They-a~e-alse-the pr*i.n*y mFoan fr automatically

-.. isolating cntainm*ent in..the event of a fuel handling accident du..rg shutdown. Containment isolation in turn ensures meeting the containment leakage rate assumptions of the safety analyses, and ensures that the calculated accidental offsite radiological doses are below 10 CFR 100 (Ref. 1) limits.

The Containment Vent Isolation instrumentation satisfies Criterion 3 of the NRC Policy Statement.

IA/k i.; .... "h...t;

A;

+ A ;.. 1 ;

. - .+*.,..L

A

+_;

. .+...--

+k A

+.. +n Building With con-atainment ýair leocks or penetrations open to the Auxiliary H.

" ',*'3x~"

Building AB3SCE- rpaces, or when mo"Ving fuel in the Auxilia-y Building with the contaiRmenFt equipment hatch open, the previ6ions to intiate a

\VI from thpnt el pool radfI-I-atioRn m*nitors and to initiate an AB (131ie.

tfhe peftitn o* an AR1! ntOrmOlhy in itiated byrh*ne pnGt hIU pool rad*a*ten monritors) fr'm a-VI, i;ncludin a VI geReFated by the o-ntainmeRnt purge mRonitors, iRthe event of a fuel handliRg accident (FHMA) must be in place and func~tioning. Additionally, a Containment Isolation Phase A (SI signal) from the operating unit, high temperature in the Auxilary-Building air IntaRes, Or mnanual A141 ill GaUsc a 6*1 6ignai in tme rcTUe1ing unit. The coent-ainment equipment hatc-h c~annot bhe open when mvn

rrad-*At'd fuelI inide cntainment in accordance with Techn*ieal Specification 3.9.4.

The ABGTS is reqIuir-ed to be operable during moevement Of irradiated fuel in the A,'-xilia,,' Building during any mo4ade and durng movement of i~rradiated fuel in the Reactor Building when the Reactor Building is established as pa~t of the ABSCEF bou ndary (see TS9 3.3.13, 3.7412, &

3.9.4). When mogirdiated fuel insi*de containm~ent, at least one train cf the -nrtainment'purg system must be operating Or the c"ntaiRnment must be isolated. When moving irrgadiated fuel in the Auxiliary Building during' times wh8en the con.tainme:nt i opeRn to the Auxiliary Bud;in-g A18G spacoc, containment purge Gaa be operated, but operation of the systeFm i6 not required. H*oevF, wh"eth*e*r the cotinet purge system is operated Or*not in this configuration, all onRtainment ventilationisa*

valves, and-asoiaenstrumeAntation Im-ust reAmaRin operable.

(continued)

Watts Bar - Unit 2 B 3.3-151 (developmental) GH

Containment Vent Isolation Instrumentation B 3.3.6 BASES APPLICABLE This requiremnent is necessary to oncuro a CVI can bo accomplished fro SAFE.rTY- the peRnt fuel pIol radiatfion monitrse in the event of an FHA in the ANA~S~~ Auxiliary Building. Additionally, a ContainmenRt Isolation Phase A-(eGgfi.Rued) (8! signa!) from the oper-ating unit, high temAperature inthe Au-xiliar BuWilding air intakes, Or manual ABI will cause a CVI signal inthe refueling LCO The LCO requirements ensure that the instrumentation necessary to initiate Containment Vent Isolation, listed in Table 3.3.6-1, is OPERABLE.

1. Manual Initiation The LCO requires two channels OPERABLE. The operator can initiate Containment Vent Isolation at any time by using either of two switches in the control room or from local panel(s). Either switch actuates both trains. This action will cause actuation of all components in the same manner as any of the automatic actuation signals. These manual switches also initiate a Phase A isolation signal.

The LCO for Manual Initiation ensures the proper amount of redundancy is maintained in the manual actuation circuitry to ensure the operator has manual initiation capability.

Each channel consists of one selector switch and the interconnecting wiring to the actuation logic cabinet.

2. Automatic Actuation Logic and Actuation Relays The LCO requires two trains of Automatic Actuation Logic and Actuation Relays OPERABLE to ensure that no single random failure can prevent automatic actuation.

Automatic Actuation Logic and Actuation Relays consist of the same features and operate in the same manner as described for ESFAS Function 1.b, SI. The applicable MODES and specified conditions for the containment vent isolation portion of the SI Function is different and less restrictive than those for the SI role. If one or more of the SI Functions becomes inoperable in such a manner that only the Containment Vent Isolation Function is affected, the Conditions applicable to the SI Functions need not be entered. The less restrictive Actions specified for inoperability of the Containment Vent Isolation Functions specify sufficient compensatory measures for this case.

(continued)

Watts Bar - Unit 2 B 3.3-152 (developmental) GH

Containment Vent Isolation Instrumentation B 3.3.6 BASES LCO 3. Containment Radiation (continued)

The LCO specifies two required channels of radiation monitors to ensure that the radiation monitoring instrumentation necessary to initiate Containment Vent Isolation remains OPERABLE.

For sampling systems, channel OPERABILITY involves more than OPERABILITY of the channel electronics. OPERABILITY may also require correct valve lineups and sample pump operation, as well as detector OPERABILITY, if these supporting features are necessary for trip to occur under the conditions assumed by the safety analyses.

Only the Allowable Value is specified for the Containment Purge Exhaust Radiation Monitors in the LCO. The Allowable Value is based on expected concentrations for a small break LOCA, which is more restrictive than 10 CFR 100 limits. The Allowable Value specified is more conservative than the analytical limit assumed in the safety analysis in order to account for instrument uncertainties appropriate to the trip function. The actual nominal Trip Setpoint is normally still more conservative than that required by the Allowable Value. If the setpoint does not exceed the Allowable Value, the radiation monitor is considered OPERABLE.

4. Safety Iniection (SI)

Refer to LCO 3.3.2, Function 1, for all initiating Functions and requirements.

APPLICABILITY The Manual Initiation, Automatic Actuation Logic and Actuation Relays, Safety Injection, and Containment Radiation Functions are required OPERABLE in MODES 1, 2, 3, and 4, and during mo-ement of iradiated fuel assomblios Within containment. Under these conditions, the potential exists for an accident that could release significant fission product radioactivity into containment. Therefore, the Containment Vent Isolation Instrumentation must be OPERABLE in these MODES. See additional discussion in the Background and Applicable Safety Analysis sections.

While in MODES 5 and 6 without fuel handling in prgre.s, the Containment Vent Isolation Instrumentation need not be OPERABLE since the potential for radioactive releases is minimized and operator action is sufficient to ensure post accident offsite doses are maintained within the limits of Reference 1.

(continued)

Watts Bar - Unit 2 B 3.3-153 (developmental) AH

Containment Vent Isolation Instrumentation B 3.3.6 BASES ACTIONS B.1 (continued)

Instrumentation" and allows periodic testing to be conducted while at power without causing an actual actuation. The delay for entering the Required Actions relieves the administrative burden of entering the Required Actions for isolation valves inoperable solely due to the performance of surveillance testing on the actuation logic and is acceptable based on the OPERABILITY of the opposite train.

A Note added siI

-s Condition B3isolatioae inthEr ,2, GA-a~d-rG.2 Cendition C applies to all Containm.nt Vent IunctionS addresso-,,s the tri* n or;ietation of the SSPS and the astr andla.

,- ,,cst~n;.,,-ato *'.. hr~t

. ;-t l . . onl ~ rrI it* ,4I " ,,.. M*

rolays for these F~unctions. it also addresses the fafilure of multiploI.';. .

radiatioR nent chann~els, Or tho ~bliyt reta singleofailed c-hannel to 01PERARBLE staturi the time allowed for Roquirod Action A.1.

If a train isioealmultiple channols are inoperabble, o-r tho eqid

.Action and- assoc-Aiato-d Completion Time of Condition A are Ant mnet, operation mnay continue as lon~g as the Required Action to plac~e and mpaintain containment purge and exhaust isolation valves in their closed position is Met Or the applicable Conditions of LCO 3.9.4, "Containment Pcnotrzations," are mnet for oach valve mnade inoperable by failure of isoatinistrumentationm. The Comple-tionA Time Ifo these Requid

.Action-s is, Immediately.

A Note stt6that Cedte is6 ~l applicable movemet Of iradaed fuel a-s~semb-lies 4.within coAntainment.

SURVEILLANCE A Note has been added to the SR Table to clarify that Table 3.3.6-1 REQUIREMENTS determines which SRs apply to which Containment Vent Isolation Functions.

SR 3.3.6.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

(continued)

Watts Bar - Unit 2 B 3.3-155 (developmental) AH

ABGTS Actuation Instrumentation B 3.3.8 B 3.3 INSTRUMENTATION B 3.3.8 Auxiliary Building Gas Treatment (ABGTS) Actuation Instrumentation BASES BACKGROUND The ABGTS ensures that radioactive materials in the fuel building atmosphere following a fue! haRndling acidont or a loss of coolant accident (LOCA) are filtered and adsorbed prior to exhausting to the environment. The system is described in the Bases for LCO 3.7.12, "Auxiliary Building Gas Treatment System (ABGTS)." The system initiates filtered exhaust of air from the fuel handling area, ECCS pump rooms, and penetration rooms automatically following receipt of a fuel pool area high radiation signal or a Containment Phase A Isolation signal.

Initiation may also be performed manually as needed from the main control room.

High area radiation;, Monitorod by eithor Of tWo montrs9, I itia*ion. Each AB GTS trainis providers AB3GTS Vltby high radiation detected by a channel dedicated to that train. There are Atotal Of two channels, onoe for each train. High radiation dt*c+ted by any monitr or..A Phase A isolation signal from the Engineered Safety Features Actuation System (ESFAS) initiates auxiliary building isolation and starts the ABGTS.

These actions function to prevent exfiltration of contaminated air by initiating filtered ventilation, which imposes a negative pressure on the Auxiliary Building Secondary Containment Enclosure (ABSCE).

flo flint detion Iris rnnuiros Thit when mo~ino irmdiltod ~oi In the The ,'aA~,ta 99619 burinenass FelnnF-enant ,.,he *hnI fflnn.,nrante h-Al pth L, A ;N 0 AA1. A 00t-=

-.--- t--*-..--............

~.UUIIL IUUI UUUI iJUIzllIUIi IIIUfI~IUIt~ U F~ flU IU~ lIiU IU.~ 'XIII IIIILIJLIJ z1 ContanmontVontilat6QR Isolation (CVI) in addition to their norma function. Inaddition, a signal froM the containment purgo radiatio portion of the Auxiliar,' Building Isolation (ABI) normally initiated by the spent fue! pool rad-iation mo-nitortS. Ad-ditionally, a Containmet Islaio Phase A (lI signal) from the operating unit, high temperature in the Auxiliar; Building air intakes, Or m~anua;l ABR1 will cause a CVI signal in the FefU9eing unit. 'nthe case where the conAtainmenAt of bo0th units is open to the Auxliany Building Spaces, a CVI in one unit Will in;itiat a C:VI in wthe other u-nit in.order to mantain ths saces open to the ABSCE.

Therefore, the containm ent

-ontilatiOn instrumentation must remain i4 containment; -andOrA AannUlus air locKs, penetrations, e.imn I I hach tc.

+ +k A M. 0 HA; AQQf1C circl w %7H %P 97 "7% a 0 " 613EI6813.

(continued)

Watts Bar - Unit 2 B 3.3-166 (developmental) GH

ABGTS Actuation Instrumentation B 3.3.8 BASES (continued)

APPLICABLE The ABGTS ensures that radioactive materials in the ABSCE atmosphere SAFETY following a fuel handling a*cident or a LOCA are filtered and adsorbed ANALYSES prior to being exhausted to the environment. This action reduces the radioactive content in the auxiliary building exhaust following a LOCA or fuel handling accident so that offsite doses remain within the limits specified in 10 CFR 100 (Ref. 1).

The ABGTS Actuation Instrumentation satisfies Criterion 3 of the NRC Policy Statement.

Buildin~g With containment air locks, or penetrations pnt h uiir Building ABSCE spaces, Or When moving fuel in the Auxiliar;B ~lin With the containmen~t equipment hatch open, the proVisions to initiate CVI from the spent fuel peel radiation Monitors, and to initiate an AB! (iW.,

the Do."tion of an.AI .normall,-in!tiatod h,- tho scent f,-ol nool rmdiatin thenetitneR rnm , C'. ii. mnral. iniiated by. the spernt fuel ago! radiationn purge monitors, iR the.. eet of a fuel handling accirdeRt (FHA) must b in place and function.ing. Additionally, a Containment Isolation Phase A (.

signal) from the operating unit, high tem.perature in the Auxiliary ,uilding irinta h , Or Manual4i ABR I will cAme a-- VI igRnal in the refelWing unit.

The Ontainment equipmet hatch cannot be open When. mov-ing irradiated fuel inside coRtainmeRt in accOrdance with TechniGal Specification 3.9.4.

The ABGTS8 is required to be operable durinMgmvement Of irradiated fuel in the Auxiliar~y Building during any mode and durng9 movemento irra;diated fuel in the Reactor BuO~ding when the Reactor Bufildingi esatablished- as part of the ABSCGE boundary (see T-2 3.23.88,3712&

3.9.4). When moving irradiated fuel inside containment, at least one train of the containment purge system mnust be operating or the containment Must be- isolated. W~hen moving irradiated fuel in the Auxiliary Building duFrin times when the containment is open to the Auxiliary Building BSCE spaces, con.tainmen*"t purige can be operated, but Rof the

.peuati*

system is net required. However, whether: the containment purge system i6operated or not in ths configuration, all containmenAtvetlioisain valves and associated instr~umentation must rem:ain operable.

T-his requirement is-necess-6ary to ensu-re- a Q.11 c-an be accomplished frmM the spent fuel pGGo radiation monitors in the event of a FHA in the

,,i,,.,,' Building. AUdi..onal.l, C on,;tai6n.men.t \Iso-l Phase-- ,,ation A-(S! signal) from the operating unit, high temperaturein the Auxiliar Building air intakes, Or manRual ABIl will cau-se CVIsigal MA in the refue9ingq unit. in the caseA where the containment of both units is open to the Au*iliar-y Buildinig spaces, a C-VI.OA in e unit Will initiate a CVI OR the other uni in ord to mainptain those spaces; oven to the ABSCGE.

(continued)

Watts Bar - Unit 2 B 3.3-167 (developmental) GH

ABGTS Actuation Instrumentation B 3.3.8 BASES (continued)

LCO The LCO requirements ensure that instrumentation necessary to initiate the ABGTS is OPERABLE.

1. Manual Initiation The LCO requires two channels OPERABLE. The operator can initiate the ABGTS at any time by using either of two switches in the control room. This action will cause actuation of all components in the same manner as any of the automatic actuation signals.

The LCO for Manual Initiation ensures the proper amount of redundancy is maintained in the manual actuation circuitry to ensure the operator has manual initiation capability.

Each channel consists of one hand switch and the interconnecting wiring to the actuation logic relays.

2. Fuel Pool Aroa Radiation The LCO specifies tWo required Fuel Poo! Area Radiation Monitors to ensure; anitiate that the radiation moni~toring intrmettin ecsary to the ABGTS remains OPERARBLE. One radiation monitor is dedicated to ea.h train of ABGT*S_.

For sampling systems, channel OPE&R-A.BILITY inovsmore than OPERABI!pT of channel elecr onics. OPERASBILITY may al.o I2.

equirerrent Palse nup, sample pump operation, and filter moto operation, as well a-- detectoer OPER-A.B!LITY, if those supporting features are necessary forto ocur ltrip the unide tngditions assumed by the rafet ana !yses.

Onily the Allowpable; Value iGSPecfied for the FuelA Pool Area Radiation MonitorsG in the LCO. The Allowable Value specified is mor9e conservatie than the analytical limit assumed in the safety analysis in order to a n r instrument uncertainties appropriate to the trip funcGtion. The- actu Al nominal TrFip Setpeint is norm~ally Stil!

mer~e conSeR'.at-Ve- than that required by the Allowable 4;'-ue. If the mneasured setpeint doest.excneed the Allowable Value, the 3-2. Containment Phase A Isolation Refer to LCO 3.3.2, Function 3.a, for all initiating Functions and requirements.

(continued)

Watts Bar - Unit 2 B 3.3-168 (developmental) AH

ABGTS Actuation Instrumentation B 3.3.8 BASES (continued)

APPLICABILITY The manual ABGTS initiation must be OPERABLE in MODES 1, 2, 3, and 4 and whon moving irradiatod fuel assemblies on tho fuel handling area to ensure the ABGTS operates to remove fission products associated with leakage after a LOCA or a fuel handling accident. The Phase A ABGTS Actuation is also required in MODES 1, 2, 3, and 4 to remove fission products caused by post LOCA Emergency Core Cooling Systems leakage.

High radiatin* initiation of the AB3GTS-T must be OPERABLE in any MODE durin,,g Mv,. n.t f iFrradiated fuel assomblies in the fuel hanRdling aro-a t ensure automatic initiation of the AB;GTS w.Ahon tho petentia! for a fuel handling accaident exists.

While in MODES 5 and 6 without fuel handling ir progrge., the ABGTS instrumentation need not be OPERABLE since a fuol handling accidet*

aFinnt OGGe'F. See additional discussion in the Background and Applicable Safety Analysis sections.

ACTIONS The most common cause of channel inoperability is outright failure or drift sufficient to exceed the tolerance allowed by unit specific calibration procedures. Typically, the drift is found to be small and results in a delay of actuation rather than a total loss of function. If the Trip Setpoint is less conservative than the tolerance specified by the calibration procedure, the channel must be declared inoperable immediately and the appropriate Condition entered.

A Note has been added to the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification may be entered independently for each Function listed in Table 3.3.8-1 in the accompanying LCO. The Completion Time(s) of the inoperable channel(s)/train(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.

(continued)

Watts Bar - Unit 2 B 3.3-169 (developmental) AH

ABGTS Actuation Instrumentation B 3.3.8 BASES ACTIONS A.1 (continued)

Condition A applies to the actuation logic train function from the Phase A Isolation, the radiation monitor functions, and the manual initiation function. Condition A applies to the failure of a single actuation logic train, radiation monitor channel, or manual channel. If one channel or train is inoperable, a period of 7 days is allowed to restore it to OPERABLE status. If the train cannot be restored to OPERABLE status, one ABGTS train must be placed in operation. This accomplishes the actuation instrumentation function and places the unit in a conservative mode of operation. The 7-day Completion Time is the same as is allowed if one train of the mechanical portion of the system is inoperable. The basis for this time is the same as that provided in LCO 3.7.12.

B.1.1. B.1.2. B.2 Condition B applies to the failure of two ABGTS actuation logic signals from the Phase A Isolation, two rFadiation monitor, or two manual channels. The Required Action is to place one ABGTS train in operation immediately. This accomplishes the actuation instrumentation function that may have been lost and places the unit in a conservative mode of operation. The applicable Conditions and Required Actions of LCO 3.7.12 must also be entered for the ABGTS train made inoperable by the inoperable actuation instrumentation. This ensures appropriate limits are placed on train inoperability as discussed in the Bases for LCO 3.7.12.

Alternatively, both trains may be placed in the emergency radiation protection mode. This ensures the ABGTS Function is performed even in the presence of a single failure.

G4 Conndi;tion C-applies when the Roquirod- AcAtion. and ascae ComAplation T-i.mH fo-FrCondition A orB have not boon met and irradiated fuel assemblies are being moeved inthe fuel building. Movement of irradiated fuel assemblies in the fuel building mRust be suspende immediately to eliminate the potential for eventS that could requir BGRTS Actuatqion. Petrformance; of thoseR ;;actions shall net preclud movingo a component to) a safe aeoition.

(continued)

Watts Bar - Unit 2 B 3.3-170 (developmental) AH

ABGTS Actuation Instrumentation B 3.3.8 BASES ACTIONS PC.1 and 9C.2 (continued)

Condition D-C applies when the Required Action and associated Completion Time for Condition A or B have not been met and the plant is in MODE 1, 2, 3, or 4. The plant must be brought to a MODE in which the LCO requirements are not applicable. To achieve this status, the plant must be brought to MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and MODE 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

A Note has been added to the SR Table to clarify that Table 3.3.8-1 SURVEILLANCE REQUIREMENTS determines which SRs apply to which ABGTS Actuation Functions.

SR--3-34.

PterormRanc of the CHANNELF= CHE=CK oncoover,' 12 houi-rs Gensresthat a gro6s failure Of itrmntonhas not occnurred. A CHANINEL CHECK is orfmally a compp, a nthe parameter nonG.e channel. toa

,ndicated similar par.ameter

. on other* haels. it is based on the assumption that iRnstr-u-men-t cahannels- monJitoring the same parameter Ashould- read-approximately the same value. Significant deviations betweeR the 0"'0

.nStrument channels could be an indication Of excessive inistrument drfift i one of the channels or of someth;ng even mor*e *e*reiG. A CHANNEL CHE=CK ill detest 9gros channel failur~e; thus, it is key to Y8erinfin the

, 1, ..... 0 -v, , . .. . . ... ....1 * - - ""v " '" * *. . . . .

instrumenRtation continues to operate properly between each CHANNEL Ag~eemen n--tra reFdetefrmined by the unit staff, b~ased on a com:bin;ation Of the ch-annel ins6trument uncertainties, including indication and readability. if a channel is outside the criteria, it mnay be an indication that the sonsor or the signal processing equipment has, drifted ou tsideit The Frequency i based on operating eXPerience that demonstrates chanRne failre isare. Ih CHANNEL CHECK supplemelnt less foFmal, but mere frequent, chocks of channelsb during norma! operational ueof the d~is~lav ;assoc'iated mith the LCC) reqie hannels.

(continued)

Watts Bar - Unit 2 B 3.3-171 (developmental) AH

ABGTS Actuation Instrumentation B 3.3.8 BASES SURVEILLANCE SR,-34.342.

REQUIREMENTS (continued) A COT 06P~QF~dGG once 92 days on each required channel to enSUre the ontiro channel Will porformf tho int8nded fUncti9n. T-his test WOWS.ri,tho capability of the instrumentaftin tO proide the ABGTS actuat*On. The Froquency of 92 days i6 based On the known Feliability Of the mon itoring.qU.pm.n.t and has been shoWn to be acceptab! through operating experience. There is a plant specific program which vorifier, that the instrument chaRnnel functiRns as required by *e*ifying the a6 1,o4 and as found settng are consistent With those established by the sotpeint FnethedelegyL.

SR 3.3.8.*31 SR 3.3.8.3-1 is the performance of a TADOT. This test is a check of the manual actuation functions and is performed every 18 months. Each manual actuation function is tested up to, and including, the relay coils. In some instances, the test includes actuation of the end device (e.g., pump starts, valve cycles, etc.). The Frequency is based on operating experience and is consistent with the typical industry refueling cycle.

The SR is modified by a Note that excludes verification of setpoints during the TADOT. The Functions tested have no setpoints associated with them.

SR-34~4.

IRAION r, noomrmo every 4A months. or A AI AuI-1:XPrthL "XLMA~I at~ ~ LAKIKICA rAl PU~;... lDDATlC Kl t.-

c-mplete ,hock of the instrument loo,-*incuding the enso-r. The test verifies that the chanl r n t measured parameter Within the nocessar', range and accrcy h Frequency is based on operating eprieceAnd is; cnsistent wihtetpca nutefuoling cycleý There is g RD;ant c;RocifiR oroarm whinh verifitw; thnt the instru mept f r'hannaI ~ ,c. ~

rn,;n 1 k,. ,r Ar.th +kimn a.Ia 'mA fc- amAea 1n,

1 REFERENCES 1. Title 10, Code of Federal Regulations, Part 100.11, "Determination of Exclusion Area, Low Population Zone, and Population Center Distance."

Watts Bar - Unit 2 B 3.3-172 (developmental) FH

ML13357A050

Text

SUMMARY

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