Text

Amends 153,149 & 124 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Implementing Recommendations Contained in Generic Ltr 84-15 on Preventing Excessive Testing & Improving Diesel Generator Reliability
	ML20244D941
Person / Time
Site:	Browns Ferry
Issue date:	08/19/1988
From:	Black S; NRC OFFICE OF SPECIAL PROJECTS
To:	;
Shared Package
ML20244D945	List: ML20244D941; ML20244D959;
References
	GL-84-15, TAC-00092, TAC-00093, TAC-00094, NUDOCS 8904240215
	Download: ML20244D941 (96)
	v • d • e

' crer 4

o UNITED STATES i

8'

'A NUCLEAR REGULATORY COMMISSION

'f WASHINGTON, D. C. 20655

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TENNESSEE VALLEY AUTHORITY l

DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.153 License No. DPR-33 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated May 29, 1987, as supplemented April 13, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, ano (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the healtn and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have

'veen satisfied.

8904240215 880019 ~

PDR ADOCK 05000259 P

pon;

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-33 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.153, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is. effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

%L L

Suzanne Assistant Director for Projects TVA Projects Division Office of Special Projects 1

Attachment:

Changes to the Technical Specifications Date of Issuance: August 19, 1988 0

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o ATTACHMENT TO LICENSE AMENDMENT N0 153

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FACILITY OPERATING LICENSE NO. OPR-33 DOCKET NO. 50-259 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

Overleaf pages* are provided to maintain document completeness.

REMOVE INSERT vii vil viii viii*

3.5/4.5-1 3.5/4.5-1*

3.5/4.5-2 3.5/4.5-2 3.5/4.5-5 3.5/4.5-5 3.5/4.5-6 3.5/4.5-6 3.5/4.5-7 3,5/4.5-7*

3.5/4.5-8 3.5/4.5-8 3.5/4.5-9 3.5/4.5-9*

3.5/4.5-10 3.5/4.5-10 3.5/4.5-12 3.5/4.5-12 3.5/4.5-13 3.5/4.5-13*

3.9/4.9-1 3.9/4.9-1 3.9/4.9-2 3.9/4.9-2 3.9/4.9-3 3.9/4.9-3 3.9/4.9-4 3.9/4.9-4*

3.9/4.9-7 3.9/4.9-7*

3.9/4.9-8 3.9/4.9-8 3.9/4.9-9 3.9/4.9-9 3.9/4.9-10 3.9/4.9-10 3.9/4.9-16 3.9/4.9-16 3.9/4.9-17 3.9/4.9-17 3.9/4.9-18 3.9/4.9-18 3.9/4.9-19 3.9/4.9-19 3.9/4.9-20 3.9/4.9-20 3.9/4.9-21 3.9/4.9-21 3.9/4.9-22 3.9/4.9-22 6.0-27 6.0-27 6.0-28 6.0-28 f

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j LIST OF TABL.ES (Ccnt*d)

Table

.T_it le, Page No.

4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation.

3.2/4.2-53 4.2.F Minimum Test and Calibration Frequency for Surveillance Instrumentation.

3.2/4.2-54 4.2.c Surveillance Requirements for Control Room Isolation Instrumentation.

3.2/4.2-56 a,2.H binimum Test and Calibration Frequency for Flood Protection Instrumentation.

3.2/4.2-57 A. 2.J Seismic Monitoring Instrument Surveillance 3.2/4.2-58 Requirements.

4.2.K Radioactive Gaseous Ef fluent Instrumentation.

Surveillance.

3.2/4.2-62 3.5-1 Minimum RHRSW and EECW Pump Assignment.

1 5/4.5-11 3.5.I MAPLHGd Versus Average Planar Exposure.

3.5/s.5-21 3.7.A Primary Containment Isolation Valves.

3.7/4.7-25 3.7.B Testable Penetrations with Double 0-Ring Seals.

3.7/4.7-32 3.7.C Testable Penetrations with Testable Bellows.

3.7/4.7-33 3.7.D Air Tested Isolation Valves.

3.7/4.7-34 3.1.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water 3.7/4.7-37 Level......................

3.7.F Primary Containment Isolati'on Valves Located in Water Sealed Seismic Class 1 Lines.......

3.7/4.7-38 3.7.H Testable Electrical Penetrations.

3.7/4.7-39 4.9.A Diesel Generator Reliability.

3.9/4.9-16 4.9.A.4.C Voltage Relay Setpoints/ Diesel Generator Start.

3.9/4.9-18 3.11.A Fire Protection System Hydraulic Requirements.

3.11/4.11-10 6.0-3 6.2.A Minimum Shift Crew Requirements.

Amendment No. 153 vii BFN Unit 1

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LIST OF ILLUSTRATIONS Fiaure_

Title Paae No.

2.1.1 APRM Flow Reference Scram and APRM Rod Block Settings.

1.1/2.1-6 2.1-2 APRM Flow Bias Scram Vs. Reactor Core Flow.

1.1/2.1-7 4.1-1 Graphic Aid in the Selection of an Adequate Interval Between Tests..

3.1/4.1-13 4.2-1 System Unavailability.

3.2/4.2-64 3.4-1 Sodium Pentaborate Solution Volume Concentrated Requirements...

3.4/4.4-4 3.4-2 Sodium Pentaborate Solution Temperature Requirements.

3.4/4.4-5 3.5.K-1 NCPR Limits....................

3.5/4.5-24 3.5/4.5-25 3.5.2 Kg Factor.

C 3.6-1 Minimum Temperature F Above Change in Transient Temperature.

3.6/4.6-24 3.6-2 Change in Charpy V Transition Temperature Vs.

Neutron Exposure.

3.6/A.6-25 4.8.1.a Gaseous Release Points and Elevations.

3.8/4.8-10 4.8.1.b Land Site Boundary 3.8/4.8-11 6.2-1 Offsite Organization for Facility Management and Technical Support 6.0-33 6.2-2 Facility Organization 6.0-34 viii BFN Unit 1

d 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS-LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS' 3.5.A ~ Core Soray System (CSS) 4.5.A Core Spray System (CSS) 4.5.A.l.d (Cont'd) 105 psi differential pressure between the reactor vessel j

and the primary containment.

e.

Check Valve once/

Operating Cycle 2.

If one CSS loop is INOPERABLE, 2.

When it is determined that one the reactor may remain in core spray loop is INOPERABLE, operation for a period not to at a time when operability is exceed 7 days providing-required, the other core spray all active components in.

loop and the RHRS (LPCI mode) the other CSS loop and the shall be demonstrated to be RHR system (LPCI mode)

OPERABLE immediately.

The and the diesel generators OPERABLE core spray loop shall are OPERABLE.

be demonstrated to be OPERABLE daily thereafter.

3.

If Specification 3.5.A.1 or Specification 3.5.A.2 cannot be met, the reactor shall be shutdown in the Cold Condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

When the reactor vessel pressure is atmospheric and irradiated fuel is in the reactor vessel at least one core spray loop with one OPERABLE pump and associated diesel generator shall be OPERABLE, except with the reactor vessel head removed as specified in 3.5.A.5 or prior to reactor startup as specified in 3.5.A.1.

BFN 3.5/4.5-2 Amendment No. 153 Unit 1

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S.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS Applicability Applicability Applies tc the operational Applies to the surveillance status of the core and requirements of the core and containment cooling systems.

containment cooling systems when the corresponding limiting condi-tion for operation is in effect.

Obiective objective To assure the operability of To verify the operability.of the the core and containment cooling core and containment cooling systems under all conditions for systems under all conditions for which this cooling capability is which this cooling capability is an essential response to plant an essential response to plant abnormalities, abnormalities.

Specification Specification A.

Core' Spray System (CSS)

A.

Core Spray System (CSS) 1.

The CSS shall be OPERABLE:

1.

Core Spray System Testing.

(1) prior to reactor Item Frequency

.startup from a cold condition, or a.

Simulated once/

Automatic Operating (2) when there is irradiated Actuation Cycle fuel in the vessel test and when the reactor vessel pressure b.

Pump Opera-Once/

is greater than bility month atmospheric pressure, except as specified c.

Motor Once/

in Specification Operated month 3.5.A.2.

Valve operability d.

System flow once/3 rate:

Each months loop shall deliver at least 6250 gpm against a system head corres-ponding to a BFN 3.5/4.5-1 Unit 1

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- l 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 1

3.5.B Residuti Heat Removal System 4.5.B. Residual Heat Removal System (RHRS) (LPCI and Containment (RHRS) (LPCI and Containment Cooling)

Cooling) 3.

If one RHR pump (LPCI mode) 3.

When it is determined that is INOPERABLE, the reactor one RHR pump (LPCI mode) is may remain in operation for INOPERABLE at a time when a period not to exceed 7 days operability is required, provided the remaining RHR the remaining RHR pumps pumps (LPCI mode) and both (LPCI mode) and active

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access paths of the RHRS compcnents in both access (LPCI mode) and the CSS and paths of the RHRS (LPCI mode) the diesel generators remain and the CSS shall be OPERABLE.

demonstrated to be OPERABLE immediately and daily thereafter.

4.

If any 2 RHR purps (LPCI 4.

No additional surveillance mode) become INOPERABLE, the required.

reactor shall be placed in the Cold Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.

If one RHR pump (containment 5.

When it is determined that cooling mode) or associated one RHR pump (containment I

heat exchanger is INOPERABLE, cooling mode) or associated the reactor may remain in heat exchanger is INOPERABLE operation for a period not to at a time when operability exceed 30 days provided the is required, the remaining remaining RHR pumps RHR pu.nps (containment (containment cooling mode) cooling mode), the and associated heat associated heat exchangers exchangers and diesel and all active components generators and all access in the access paths of the l

paths of the RHRS RHRS (containment cooling (containment cooling mode) mode) shall be demonstrated are OPERABLE.

to be OPERABLE immediately and weekly thereafter L.itil the INOPERABLE RHR pump (containment cooling mode) and associated heat exchanger is returned to normal service.

BFN 3.5/4.5-5 Amendment No. 153 Unit 1 l

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},5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5 B.

Residusi Heat Removal System 4~5 B.

Residual Heat Removal' System ggg], (LPCI and Watainment (RNRS) (LPCI and Containment

' Cooling)

Cooling) 6.

If two RHR pumps.(containment 6.

When it is determined that cooling mode) or associated two RHR pumps (containment-heat exchangers are cooling mode) or associated INOPERABLE, the reactor may heat exchangers are remain in operation for a IMOPERASLE at a time when period not to exceed 7 days operability is required, the provided the remaining RNR remainin RHR pumps-pumps (containment cooling.

(containment cooling mode),

mode), the associated heat-

.the associated heat exchangers, diesel exchangers, and all active generators, and all access components in the access paths of the RNRS paths of the RHRS (containment cooling mode)

(containment cooling' are OPERABLE.

mode) shall be demonstrated to be OPERABLE inunediately and daily thereafter until at least_three RHR pumps (containment cooling mode) and associated heat exchangers are returned to normal service.

7.

If two access paths of the 7.

When it is determined that RHRS (containment cooling one or more access paths of mode) for each phase of the the RHRS (containment mode (drywell sprays, cooling mode) are INOPERABLE suppression chamber sprays, when access is required,

'and suppression pool cooling) all active components are not OPERABLE, the unit in the access paths of the may remain in operation for a RHRS (containment cooling period not to exceed 7 days mode) shall be demonstrated provided at'least one path to be OPERABLE immediately for each phase of the mode and all active components in remains OPERABLE.

the access' paths which are not backed by a second OPERABLE access path for the same phase of the mode (drywell sprays, suppression chamber sprays and suppression pool cooling) shall be demonstrated to be OPERABLE daily thereafter until the second path is returned to normal service.

BFN 3.5/4.5-6 Amendment No. 153 Unit 1

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3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.8 Residual Heat Removal System 4.5.B Residual Heat Removal System (RHRS) (LPCI and. containment (RHRS) (LPCI and Containment Cooling)

Cooling)

8. If Specifications 3.5.B.1 8.

No additional surveillance through 3.5.B.7 are not met,

required, an orderly shutdown shall be initiated and the reactor shall be shutdown and placed in the cold condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

9.

When the reactor vessel 9.

When the reactor vessel pressure is atmospheric and pressure is atmospheric, irradiated fuel is in the the RHR pumps and valves reactor vessel at least one RHR that are required to be loop with two pumps or two loops OPERABLE shall be with one pump per loop shall demonstrated to be OPERABLE be OPERABLE.

The pumps' monthly.

associated diesel generators must also be OPERABLE.

10. If the conditions of 10.

No additional surveillance Specification 3.5.A.5 are met, required.

LPCI'and containment cooling are not required.

11. When there is irradiated fuel 11.

The RHR pumps on the in the reactor and the reactor adjacent units which supply vessel pressure is greater than cross-connect capability atmospheric, 2 RHR pumps and shall be demonstrated to be associated heat exchangers and OPERABLE monthly when the valves on an adjacent unit must cross-connect capability be OPERABLE and capable of is required, supplying cross-connect capability except as specified in Specification 3.5.B.12 below.

(Note:

Because cross-connect capability is not a short-term requirement, a component is not considered INOPERABLE if cross-connect capability can be restored to service within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .)

BFN 3.5/4.5-7 Unit 1

3.5/4.5' CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.8 Residual Heat Removal System 4.5.B Residual Heat Removal System (RHRS) (LPCI and Containment (RNRS) (LPCI and containment l:

Cooling)L Cooling)

12. If one RHR pump or associated

12. When it is determined heat exchanger located that one RRR pump or on the unit cross-connection associated heat exchanger in the adjacent unit.is located on the unit INOPERABLE for any reason cross-connection in the (including; valve inoperability, adjacent unit is pipe break, etc.), the reactor INOPERABLE at a time when may remain in oneration operability is-required, for a period not to exceed the remaining RHR pump and 30 days provided the remaining associated heat exchanger 4

RHR pump and associated diesel

.on'the unit cross-connection generator are OPERABLE..

shall be demonstrated to be i

OPERABLE immediately and every 15 days thereafter until the INOPERABLE pump.and associated heat exchanger are returned to normal service.

13.

If RHR cross-connection flow or 13.

No additional surveillance heat removal capability is lost,

required, the' unit may remain in operation.

for a period not to exceed 10 days unless such capability is restored.

14.

All recirculation pump 14.

All recirculation pump discharge valves shall discharge valves shall be OPERABLE prior to be tested for operability reactor startup (or during any period of closed if permitted reactor cold shutdown elsewhere in these exceeding 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , if specifications),

operability tests have not been performed during the preceding 31 days.

BFN 3.5/4.5-8 Amendment No. 153 Unit 1 w________m____

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1 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS L

3.5.C RHR Service Water and Emergency 4.5.C RHR Service Water and Emergency Eauionent Coolina Water Systems Equipment Cooling Water System _s (RECW81 (EECWS) 1.

Prior to reactor startup from 1.

a.

Each of the RHRSW pumps a cold condition, 9 RHRSW normally assigned to pumps must be OPERABLE, with automatic service en 7 pumps (including pump D1 the EECW headers will or D2) assigned to RHRSW be tested service and 2 automatically automatically esch time starting pumps assigned to the diesel generators EECW service.

are tested.

Each of the RHRSW pumps and all associated essential control valves for.the EECW headers and RHR heat exchanger headers shall be demonstrated to be OPERABLE once every three months.

b.

Annually each RHRSW pump shall be flow-rate tested.

To be considered OPERABLE, euch pump shall pump at least 4500 spa through its normally assigned flow path.

BFN 3.5/4.5-9 Unit'l

3.5/4.5 - CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATIOh SURVEILLANCE REQUIREMENTS 3.5.C RNR Service Water and Emergency 6.5.C RHR Service Water and Emerzency touire-at Coolina Water Systems gauipment Coolina Water Systems (EECWs) (Continued)

(EECWs) (Continued)-

2.

During reactor power

2. a.

If no more than two operation, RHRSW pumps RHRSW pumps are must be OPERABLE and INOPERABLE, increased assigned to service as surveillance is not indicated in Table 3.5-1 required.

for the specified time limits.

b.

When three RHRSW pumps are INOPERABLE, the remaining pumps and associated essential control valves chall be operated daily, i

c.

When four RHRSW pumps are INOPERABLE, the remaining pumps and associated essential control valves shall be operated daily.

3.

During poker operation.

3. Routine surveillance for both RNRSW pumps D1 and these pumps is specified D2 normally or alternately in 4.5.C.1.

assigned to the RHR heat exchanger header supplying the standby coolant supply connection must be OPERABLE except as specified in 3.5.C.4 and 3.5.C.5 below.

BFN 3.5/4.5-10 Amendment No. 153 Unit 1 5

3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS.

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.D ggghnnent Area Coolers 4.5.D Eautoment Area coolers 1.

The equipment area cooler

1. Each equipment area cooler-associated with each RHR is operated in conjunction pump and the equipment with the equipment served area cooler associated by that particular cooler; with each set of core therefore, the equipment spray pumps (A and C area coolers are tested at or B and D) must be the same frequency as the OPERABLE at all times pumps which they serve.

when the pump or pumps served by that specific cooler is considered to be OPERABLE.

2.

When an equipment area cooler is not OPERABLE, the pump (s) served by that cooler must be considered INOPERABLE for Technical Specification purposes.

E.

Hiah Pressure Coolant Injection E. High Pressure Coolant System (HPCIS)

Iniection System (HPCIS) 1.

The HPCI system shall be 1.

HPCI Subsystem testing OPERABLE:

shall be performed as follows:

(1) prior to startup from a as Simulated once/

Cold Condition; or Automatic operating Actuation cycle Test (2) whenever there is b.

Pump Once/

irradiated fuel in the Opera-month reactor vessel and the bil1Ly reactor vessel pressure is greater than 122 psig, c.

Motor Oper-Once/

except as specified in ated Valve month Specification 3.5.E.2.

Operability d.

Flow Rate at once/3 normal months reactor vessel operating pressure l

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'.c 3.5/4.5 CORE AND CONTAINMENT'C00 LING SYSTEMS h

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i

3.5.C RHR Service Water and Emerzency 4.5.C RNR Service Water and Emerzenc'y

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Eauipment Coolina Water Systems Bouipment Coolina Water Systems (EECWs) (Continued):

(EECWs) (Continued) 4.

One of the D1 or D2 RHRSW.

-4. When it.is determined that.

pumps assigned to the RHR one of the RHRSW pumps heat exchanger supplying supplying standby coolant the standby coolant supply is' INOPERABLE at a time connection may be when operability is I

INOPERABLE for a. period-required, the OPERABLE not to exceed 30 days RHRSW pump on the same provided the OPERABLE pump header and the RHR heat is aligned to supply the-exchanger header and RHR heat exchanger header associated essential control and the associated diesel valves shall be demonstrated

- generator and essential to be OPERABLE immediately control valves are OPERABLE, and every 15 days thereafter.

~5.

The standby coolant supply capability may be INOPERABLE for a period not'to exceed

10. days.

6.

If Specifications 3.5.C.2 through 3.5.C.5 are not met, an orderly shutdown shall be initiated and the unit placed in the Cold Shutdown condition within-24 hours.

7.

There shall be at least 2 RHRSW pumps, associated with the selected RHR pumps, aligned for RHR heat exchanger service for each reactor vessel containing irradiated fuel.

3.5/4.5-12 BFN Unit 1 e

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3-9/4.9 ' AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 Auxiliary Electrical System 4.9 Auxiliary Electrical System-Applicability Applicability Applies to all the auxiliary Applies to the periodic electrical power system.

testing requirements of the auxiliary electrical system.

Objective objective To assure an adequate supply of Verify the operability of the electrical power for operation of auxiliary electrical system, those systems required for safety.

Specification Specification A.

Auxiliary Electrical Equipment A.

Auxiliary Electrical System 1.

The reactor shall not be 1.

Diesel Generators started up (made critical) from the cold condition unless the following are a.

Each diesel generator satisfied:

shall be manually started j

and. loaded to demonstrate

'f a.

Diesel generators A, operational readiness in B, C, and D OPERABLE.

accordance with the frequency specified in

{

b.

Requirements 3.9.A.3 Table 4.9.A on a staggered l

through 3.9.A.6 are test basis.

The test shall i

met.

continue for at least a one hour period at 75% of rated c.

At least two of the load or greater and the following offsite power operation of the diesel sources are available:

fuel oil transfer pumps shall be demonstrated.

Also, the diesel generator (1) The 500-kV system is t 'seting air compressor available to the

...all be checked for opera-

)

units 1 and 2 shut-tion and its ability to down boards through recharge air receivers, the unit 1 station-service transformer The diesel generator fast TUSS /lB with no starts (10 seconds) from credit taken for the standby conditions shall be two 500-kV Trinity performed once per 184 days lines.

If the in these surveillance unit /2 station-tests.

All other engine service transformer starts for the purpose of is the second choice, this test may be preceeded a minimum of two by an engine idle start.

500-kV lines must be available.

BFN 3.9/4.9-1 Amendment No. 153 Unit 1

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. 3.9/4.9 AUKILIARY ELECTRICAL SYSTEM i

LIMITING CONDITIONS'FOR OPERATION

- SURVEILLANCE REQUIREMF.NTS 3.9.A. Auxiliary Electrical Euuipment 4.9.A. Auxiliary Electrical Syst'em 3.9.A.1.c. (Cont'd) 4.9.A.1. (Cont'd)

Additional reporting requirements due to failures are noted in Table 4.9.A.

All diesel generator starts shall be logged.

(2) The 500-kV system is b.

Once per operating available to the units 1 cycle, a test will and 2 shutdown boards be conducted simulating a through the unit 2 loss of offsite power and station-service similar conditions that transformer TUSS 2B with would exist with the no credit taken for the presence of an actual two 500-kV Trinity lines.

safety-injection signal If the unit 1 station-to demonstrate the

-service transformer is the following:

second choice, a minimum of two 500-kV lines must (1) Deenergization of the be available.

emergency buses and load shedding from (3) The Trinity 161-kV line'i:s the emergency buses.

available to the units 1 and 2 shutdown boards (2) The diesel starts through both common from ambient station-service condition on the transformers, auto-start signal, energizes the NOTES FOR (3):

emergoney buses with permanently connected (a) If unit 3 is claiming loads, energizes the the Trinity line as an auto-connected offsite source, see emergency loads unit 3 technical through load specifications, section sequencing, and 3.9.A.1.c.2.

operates for greater than or equal to five (b) If unit 1 is in cold minutes while its shutdown, only one generator is loaded common station-service with the emergency transformer to required.

loads.

BFN 3.9/4.9-2 Amendment No. 153 Unit 1 m

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4 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxiliary Electrical Eauipment 4.9.A.

Auxiliary Electrical System 3.9.A.1.c.

(Cont'd) 4.9.A.1.b (Cont'd)

(4) The Athens 161-kV line is (3)

On diesel generator available to the units 1 breaker trip, the fonds are shed from and 2 shutdown boards through a common emergency buses station-service and the diesel output transformer when unit 1 is breaker recloses on in Cold Shutdown and unit 3 the autostart signal, is not claiming the Athens the emergency buses line as an offsite source.

are energized with permanently NOTE FOR (3) AND (4):

connected loads, the autoconnected With no cooling tower pumps' emergency loads or fans running, a cooling are energized tower transformer may be through load substituted for a common sequencing, and station-serv' ice transformer.

the diesel operates for greater than or equal to five minutes while its generator is loaded with the emergency-

loads, c.

Once a month the quantity of diesel fuel available shall be logged.

d.

Each diesel generator shall be given an annual inspection in accordance with instructions based on the manufacturer's recommendations.

e.

Once a month a sample of i

diesel fuel shall be checked for quality.

The l

quality shall be within acceptable limits specified in Table 1 of the latest revision to ASTM D975 and logged.

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BFN

3. 9/4. 9-3 Amendment No. 153 l

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3.9/4.9 AUKILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

, Auxiliary Electrical Eauirment 4.9.A.

Auxiliary Electrical System

2. The reactor shall not be 2.

DC Power System - Unit started up (made critical)

Batteries (250-V), Diesel-from the hot standby condition Generator Batteries (125-V) unless all of the following and Shutdown Board Batteries conditions are satisfied:

(250-V) a.

At least one offsite power a.

Every week the specific source is available as gravity, voltage and specified in 3.9.A.1.c.

temperature of the pilot cell and overall battery voltage shall be measured and logged.

b.

Three units 1 and 2 diesel b.

Every three months the generators shall be measurement shall be made OPERABLE.

of voltage of each cell to nearest 0.1 volt, specific gravity of each cell, and temperature of every fifth cell.

These measurements shall be logged.

c.

An additional source of c.

A battery rated power consisting of one discharge (capacity) of the following:

test shall be performed and the voltage, time, (1) A second offsite and output current power source available measurements shall as specified in be logged at 3.9.A.1.c.

intervals not to exceed 24 months.

(2) A fourth OPERABLE units 1 and 2 diesel I

generator.

d.

Requirements 3.9.A.3 through 3.9.A.6 are met.

)

BFN 3.9/4.9-4 l

Unit 1 l

l l

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3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxiliary Electrical Eauipment 4.9.A.

Auxiliary Electrical System 4.9.A.4. (Cont'd) c.

The loss of voltage and degraded voltage relays which start the diesel generatoes from the 4-kV shutdown boards shall be calibrated annually for trip and reset and the measurements logged.

These relays shall be calibrated as specified in Table 4.9.A.4.c.

d.

4-kV shutdown board voltages shall be recorded once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

5.

Logic Systems 5.

480-V RMOV Boards ID and 1F.

a.

Common accidant signal a.

Once per operating logic system is OPERABLE.

cycle the automatic transfer feature for 480-V RMOV boards 10 and IE shall be functionally tested to verify auto-transfer capability.

b.

480-V load shedding logic system is OPERADLE.

6.

There shall be a minimum I

of 103,300 gallons of diesel fuel in the standby diesel-generat or l

fuel tanks.

q 1

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l BFN 3.9/4.9-7 l

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_____!!a3A '

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3.9/4'.9 AUXILIARY ELECTRICAL EYS R LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3. 9. B. -

Operation with Inonetahlg

'4.9.B.

Operation with Inocerable Eauipment Eautoment Whenever the reactor is in' Startup mede or Run mode and not in's cold condition, the availability of electric

'I power shall be as.specified-in-3.9.A except'as specified herein.

1.

From and after the'da?.e 1.

When only one that only.one offsite offsite power source j

power source is available, is OPERABLE, all i

reactor operation is units 1 and.2 diesel permissible for 7 deys.

generators must be demonstrated to be OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

.and power availability for the associated boards shall be. verified within.

I hour and at least once per P hours thereafter.

2.

From and after the date 2.

When a required that the 4-kV bus tie offsite power source board becomes INOPERABLE, is unavailable to reactor operation is

. unit 1 because the permissible indefinitely 4-kV bus tie board provided one of the or a start bus is required offsite power INOPERABLE, all-sources is not supplied unit 1 and 2 diesel from the 161-kV system generators shall be through the bus tie board, demonstrated OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,.and power availability for the associated boards shall be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and.at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

The remaining offsite source and associated buses shall be checked to be energized daily.

l

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l BFN

3. 9/4. 9-8 Amendment No. 153 Unit 1

O 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.D.

Operation With Inoperable 4.9.B.

Operation With Inoperable Equipment Equipment 3.

When one of the units 1 3.

When one of the and 2 diesel generator is units 1 and 2 diesel INOPERABLE, continued generators is found reactor operation is to be INOPERABLE, permissible during the all of the remaining succeeding 7 days, diesel generators provided that 2 offsite shall be demonstrated power sources are to be OPERABLE within available as specified 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and power in 3.9.A.1.c and all of availability for the the CS, RHR (LPCI and associated boards containment cooling) shall be verified systems, and 'the remaining within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and three units 1 and 2 diesel at least once per generators are OPERABLE.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter..

If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be shut down and in i

the cold condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

When one units 1 and 2 4.

When one 4-kV 4-kV shutdown board is shutdown board is INOPERABLE, continued found to be reactor operation is INOPERABLE, all permissible for a period diesel generators of 5 days provided that associated with the 2 offsite power sources remaining 4-kV shutdown are available as boards shall be demon-specified in 3.9.A.1.c strated to be OPERABLE and the remaining 4-kV within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and I

shutdown boards and power availability for associated diesel the remaining 4-kV generators, CS, RHR (LPCI shutdown boards shall f

and containment cooling) be verified within systems, and all 480-V 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least emergency power boards once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

~

are OPERABLE.

If this thereafter.

requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the cold

{

condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

BFN 3.9/4.9 9 Amendment No. 153 unit 1

--______--________m.

l 3.9/4.9 AUX!LIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.B.

Operation With Inoperable 4.9.B.

Operation With Inoperable Equipment Equipment 5.

When one of the shutdown 5.

When a shutdown bus buses in INOPERABLE, is found to be reactor operation is INOPEkABLE, all permissible for a period 1 and 2 diesel of 7 days.

generators shall be proven OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

6.

When one of the 480-V 6.

When one units' 1 diesel auxiliary boards and 2 diesel becomes INOPERABLE, auxiliary board is reactor operation is found to be permissible for a period INOPERABLE, each of 5 days.

unit 1 and 2 diesel generator shall be proven OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and power availability for the remaining diesel auxiliary board shall be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

7.

From and after the date that one of the three 250-V unit batteries and/or its associated battery board is found to be INOPERABLE for any reason, continued reactor operation is permissible during the succeeding 7 days.

Except for coutine surveillance testing, NRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the situation, the precautions to be taken during this period, and the plans to return the failed ecmponent to an i

OPERABLE state.

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ATTACHMENT TO TABLE 4.9.A DIESEL GENERATOR REQUALIFICATION PROGRAM (1)

Perform seven consecutive successful demands without a failure within 30 days of diesel generator being restored to operable status and fourteen consecutive successful demands without a failure within 75 days of diesel genetator of being restored to OPERABLE status.

(2)

If a failure occurs during the first seven tests in the requalification test program, perform seven successful demands without an additional failure within 30 days of diesel generator of being restored to OPERABLE status and fourteen consecutive successful demands without a failure within 75 days of being restored to OPERABLE status.

(3)

If a failure occurs during the second seven tests (tests 8 through 14) of (1) above, perform fourteen consecutive successful demands without an additional failure within 75 days of the failure which occurred during the requalification testing.

(4) Following the second failure during the requalification test program, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

(5)

During requalification testing the diesel generator should not be tested more frequently than at 24-hour intervals.

After a diesel generator has been successfully requalified, subsequent repeated requalification tests will not be required for that diesel generator under the following conditions:

(a) The number of failures in the last 20 valid demands is less than 5.

(b) The number of failures in the last 100 valid demands is less than 11.

(c)

In the event that, following successful requalification of a diesel generator, the number of failures is still in excess of the remedial action criteria (a and/or b above) the following exception will be allowed until the diesel generator is no longer in violation of the remedial action criteria (a and/or b above).

f Requalification testing will not be required provided that after each valid demand the number of failures in the last 20 and/or 100 valid demands has not I

increased.

Once the diesel generator is no longer in violation of the remedial action criteria above the provisions of those criteria alone will prevail.

3FN 3.9/4.9 17 Amendment No. 153 Unit 1 l

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3.9-R&ggg i

p-The objective of this specification is t'o assure an adequate source of l

electrical power to operate facilities to cool the plant during shutdown j

and to operate the engineered safeguards following an accident.

There are three sources of alternating current electrical energy available, namely. the-161-kV transmission system 1 the 500-kV transmission system, and the diesel generators.

The unit station-service transformer B for unit 1 or the unit station-service transformer B'for unit 2 provide noninterruptible sources of offsite power from the 500-kV transmission system to the units 1 and 2 shutdown boards.

Auxiliary power can also be supplied from the 161-kV transmission system through the common station-se'evice transformers or through the cooling tower transformers by way of the bus tie board. The 4-kV bus tie board may remain out of service indefinitely.provided one of the required offsite power sources is not supplied from the 161-kV system through the bus tie board.

The minimum fuel oil requirement of 103,300 gallons is sufficient for seven days of full load operation of three diesels and is conservatively based on availability of a replenishment supply.

The degraded voltage sensing relays provide a start signal to the diesel-generators in the event that a deteriorated voltage condition exists on

-a 4-kV shutdown board. This-starting signal is independent of the starting signal generated by the complete loss of voltage relays and will~ continue to function and start the diesel generators on complete loss of oltage should the loss of voltage relays become inoperable.

The 15-day inoperable time limit specified when one of the three phase-to-phase degraded voltage relays is inoperable is justified ba' sed on the two-out-of-three permissive logic scheme provided with these relays.

A 4-kV shutdown board is allowed to be out of operation for a brief period to allow for maintenance and testing, provided all remaining 4-kV shutdown boards and associated diesel generators, CS, RHR, (LPCI and containment cooling) systems supplied by the remaining 4-kV shutdown boards, and all emergency 480-V power boards are operable.

There are eight 250-V de battery systems, each of which consists of a battery, battery charger, and distribution equipment.

Three of these systems provide power for unit control functiots, operative power for unit motor loads, and alternative drive power for a 115-V ac unit-preferred mg set. One 250-V de system provides power for common plant and transmission system control functions, drive power for a 115-V ac plant-preferred mg set, and emergency drive power for certain unit large motor loads.

The four remaining systems deliver control power to the 4,160-V shutdown boards.

l Amendment No. 153 BFN 3.9/4_.9-19 Unit 1 I

.1t e

3.9 RA8&T, (Cont'd) gach 250-V de shutdown board control power supply.can receive power from its own battery, battery charger, or from a spare charger.

The chargers are powered from normal plant auxiliary power or from the standby diesel-driven generator system.

Zero resistance short circuits between the control power. supply and the shutdown board are cleared by fuses located'in the respective control power supply.

sach power supply is located in the reactor building near the shutdown board it supplies.

)

gach battery is located in its own independently ventilated battery room.

1 The 250-V'de system is so arranged, and the batteries sized so that the loss of any one unit battery will not prevent the safe shutdown and cooldown of all three units in the event of the-loss of offsite power and a design basis' accident in any one unit.

Loss of control power to 4

any engineered safeguard control circuits is annunciated in the main control room of the unit affected. The loss of one 250-V shutdown board battery affects normal control power only for the 4,160-V shutdown board-

- }

wh'ich it supplies.' The station battery supplies loads that are not essential for safe shutdown and cooldown of the nuclear system.

This battery was not considered in the accident load calculations.

There are two 480-Volt ac RMOV boards that contain mg sets in their feeder lines.

These 480-Volt ac RMOV boards have an automatic transfer

.from their normal to alternate power source (480-Volt ac shutdown boards).

The mg sets act as electrical isolators to prevent a fault from propagating between electrical divisions due to an automatic transfer. The 480-Volt ac RMOV boards involved provide motive power to valves associated with the LPCI mode of the RHR system.

Having an mg set out of service reduces the assurance that full RHR (LpCI) capacity

)

will be available when required.

Since sufficient equipment is available to maintain the minimum complement required for RHR (LPCI) operation, a 7-day servicing period is justified.

Having two mg sets out of service can considerably reduce equipment availability; therefore, the affected unit shall be placed in Cold shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The offsite power source requirements are based on the capacity of the respective lines.

The Trinity line is limited to supplying two operating units because of the load limitations of CSST's A and B.

The Athens line is limited to supplying one operating unit because of the load limitations of the Athens line.

The limiting conditions are intended to prevent the 161-kV system from supplying more than two units in the event of a single failure in the offsite power system.

l l

l Am2ndment 30. 153 BFN 3.9/4:9-20 Unit 1

4.9 BASES The monthly test of the diesel generators is primarily to check for failures and deterioration in the system since last use.

The diesels will be loaded to at least 75 percent of rated power while engine and generator temperatures are stabilized (about one hour). The minimum 75-percent load will prevent soot formation in the cylinders and injection nozzles.

Operation up to an equi.11brium temperature ensuras that there is no overheating problem.

The tests also provide an eng.ne and generator operating history to be compared with subsequent engine-generator test data to identify and to correct any mechanical or electrical deficiency before it can result in a system f ailure.

The test during refueling outages is more comprehensive, including procedures that are most effectively conducted at that time.

These include automatic actuation and functional capability tests to verify that the generators can start and be ready to assume load in 10 seconds.

The annual inspection will detect any signs of wear long before failure.

Battery maintenance with regard to the floating charge, equa'lizing charge, and electrolyte level will be based on the manufacturer's instruction and sound maintenance practices.

In addition, written records will be maintained of the battery performance.

The plant batteries will deteriorate with time but precipitous failure is unlikely.

The type of surveillance called for in this specification is that which has been demonstrated through experience to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.

The equalizing charge, as recommended by the manufacturer, is vital to maintaining the ampere-hour capacity of the battery, and will be applied as recommended.

The testing of the logic systems will verify the ability of the logic systems to bring the auxiliary electrical system to running standby readiness with the presence of an accident signal from any reactor or an undervoltage signal on the 4-kV shutdown boards.

The periodic simulation of accident signals in conjunction with diesel-generator voltage available signals wil. confirm the ability of the 480-V load shedding logic system to sequentially shed and restart l

480-V loads if an accident signal were present and diesel-generator voltage was the only source of electrical power.

]

BFN 3.9/A.9-21 Amendment No. 153 Unit 1

_ _. _ _ _ _ - - _ _ -. - - - - ~

~

u l

4.9

]Lgg1 (Cont'd)

REFERENCES l

1.

Normal Auxiliary Power System (BFNP FSAR Subsection 8.4) 2.

Standby AC Power Supply and Distribution (BFNP FSAR Subsection 8.5) 3.

250-Volt DC Power Supply and Distribution (BFNP FSAR Subsection 8.6) 4.

Memorandum from Gene M. Wilhoite te H. J. Green dated December 4 1981 (LOO 811208 664) and memorandum from C. E. Winn to H. J. Green dated January 10, 1983 (G02 830112 002) 1 i

I l

l

~

BFN 3.9/4.9-21 Amendment No. 153 116 4 & 1

Report shall be submitted within 10 days after the

' event describing the magnitude,. frequency spectrum, j

and resultant effect upon plant features important to safety.

7.

Diesel Generator Reliability Improvement program Report shall be submitted within 30 days of meeting f ailure criteria in Table 4.9. A.

As a minimum, the Reliability Improvement Program report for NRC audit shall include:

A summary of all tests (valid and invalid) that a.

occurred within the time period over which the last 20/100 valid tests were performed.

b.

Analysis of failures and determination of root causes of failures.

Evaluation of each of the recommendations of c.

NUREG/CR-0660, " Enhancement of onsite Emergency Diesel Generator Reliability in Operating Reactors," with respect to their application to the plant.

d.

Identification of all actions.taken or to be taken to (1) Correct the root causes of failures defined in b above and (2) Achieve a general improvement of diesel generator reliability, A supplemental report shall be prepared for an e.

NRC audit within 30 days after each subsequent failure during a valid demand, for so long as the affected diesel generator unit continues to violate the criteria (3/20 or 6/100) for the reliability improvement program remedial action.

The supplemental report need only update the failure / demand history for the affected diesel generator unit since the last The report for that diesel generator.

supplemental report shall also present an analysis of the failure (s) with a root cause determination, if possible, and shall delineate any further procedural, hardware or operational changes to be incorporated into the site diesel generator improvement program and the schedule for implementation of those changes.

Amendment No. 153 m

bkYt1 6.0-27

8.

Secondary Containment 4.7.C.

Within 90 days Leak Rate. Testing

of completion of each test.

Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report.

This report should include data on the wind speed, wind direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate. The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate limits.

6.10 STATION OPERATING RECORDS AND RETENTION 6.10.1 Records and/or logs shall be kept in a manner convenient for review as indicated below:

a.

All normal plant operation including such items as power level, fuel exposure, and shutdowns b.

Principal maintenance activities c.

Reportable Events d.

Checks, inspections, tests, and calibrations of components i

and systems, including such diverse items as source leakage e.

Reviews of changes made to the procedures or equipment or i

reviews of tests and experiments to comply with 10 CFR 50.59 l

f.

Radioactive shipments s.

Test results in units of microcuries for leak tests performed pursuant to Specification 3.8.D BFE 6.0-28 Amendment NO. 153 Unit 1

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION o

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I WASHINGTON, D. C. 20655

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-250 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.149 License No. DPR-52 1.

The Nuclear Regulatory Comission (the Comission) has fcund that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated May 29, 1987, as supplemented April 13, 1988, complies with the standards and regt.irements of the Atomic Energy Act of 1954, as amended (the Act), and t'te Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defer.q and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

L______________

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, l 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-52 is hereby amended to read as follows:

l (2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.149, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the-Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 19, 1988 O

ese

3

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ATTACHNENT TO LICENSE AMENDMENT NO. 149 l'

' FACILITY OPERATING LICENSE NO. OPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal l

lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.,

REMOVE INSERT' vii vii viii vii1*

3.5/4.5-1 3.5/4.5-1*

3.5/4.5-2 3.5/4.5-2 3.5/4.5-5 3.5/4.5-5 3.5/4.5-6 3.5/4.5-6 3.5/4.5-7 3.5/4.5-7*

3.5/4.5-8 3.5/4.5-8 3.5/4.5-9 3.5/4.5-9*

3.5/4.5 3.5/4.5-10 3.5/4.5-12 3.5/4.5-12 3.5/4.5-13 3.5/4.5-13*

3.9/4.9-1 3.9/4.9-1 3.9/4.9-2 3.9/4.9-2 3.9/4.9-3 3.9/4.9-3 3.9/4.9-4 3.9/4.9-4*

3.9/4.9-7 3.9/4.9-7*

3.9/4.9-8 3.9/4.9-8 3.9/4.9-9 3.9/4.9-9 3.9/4.9-10 3.9/4.9-10 3.9/4.9-16 3.9/4.9-16 3.9/4.9-17 3.9/4.9-17 3.9/4.9-18 3.9/4.9-18 3.9/4.9-19 3.9/4.9-19 3.9/4.9-20 3.9/4.9-20 3.9/4.9-21 3.9/4.9-21 3.9/4.9-22 3.9/4.9-22 6.0-27 6.0-27 6.0-28 6.0-28

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LIST OF TABLES (Cont'd)

_ Table Title P*zo No.

4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation.

3.2/4.2-53 4.2.F Minimum Test and Calibration Frequency for Surveillance Instrumentation.

3.2/4.2-54 4.2.C Surveillance Requirements for Control Room Isolation Instrumentation.

3.2/4.2-56 4.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation........

3.2/4.2-57 4.2.J Seismic Monitoring Instrument Surveillance 3.2/4.2-58 Requirements.

4.2.K Radioactive Gaseous Ef fluent Instrumentation.

Surveillance.

3.2/4.2-62 3.5-1 Minimum RHRSW and EECW Pump Assignment.

3.5/4.5-11 3.5.I MAPLHGR Versus Average Planar Exposure.

3.5/4.5-21 3.7.A Primary Containment Isolation Valves.

3.7/4.7-25 3.7.B Testable Penetrations with Double 0-Ring Seals.

3.7/4.7-32 3.7.C Testable Penetrations with Testable Be11ows.

3.7/4.7-33 3.7.D Air Tested Isolation Valves.

3.7/4.7-34 3.7.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water 3.7/4.7-37 Level.

3.7.F Primary Containment Isolation Vales Located in Water Sealed Seismic class 1 Lines.

3.7/4.7-38 3.7.M Testable Electrical Penetratio.ns.

3.7/4.7-39 4.9.A Diesel Generator Reliability.

3.9/4.9-16 4.9.A.4.C Voltage Relay Setpoints/ Diesel Generator Start.

3.9/4.9-18 3.11.A Fire Protection System Hydraulic Requirements.

3.11/4.11-10 6.2.A Minimum Shift Crew Requirements.

6. 0- 3 BFN vii Amendment No. 149 Unit 2

l LIST OF ILLUSTRATIONS Figure T.lji.l.3 Pane No.

2.1.1 APRM Flow Reference Scram and APRM Rod Block Settings....................

1.1/2.1-6 2.1-2 APRM Flow Bias Scram Vs. Reactor Core Flow.

1.1/2.1-7 I

{

t 4.1-1 Graphic Aid in the Selection of an Adequate

]

Interval Between Tests.

3.1/4.1-13 4.2-1 System Unavailability.

3.2/4.2-64 3.4-1 Sodium Pentaborate Solution Volume Cone'entrated Requirements.

3. 4 /4. A-4 3.4-2 Sodium Pentaborate Solution Temperature Requirements.

3.4/4.4-5 3.5.K-1 MCPR Limits.....

3.5/4.5-22 3.5/4.5-23 3.5.2 Kg Factor.

3.6-1 Minimum Temperature *F Above Change in Transient Temperature.

3~.6/4.6-24 3.6-2 Change in Charpy V Transition Temperature Vs.

Neutron Exposure.

3.6/4.6-25 4.8.1.a Gaseous Release Points and Elevations 3.8/4.8......

4.8.1.b Land Site Boundary.

3.8/4.8-11 6.2-1

.Offsite Organization for Facility Management and Technical Support 6.0-33 6.2-2

' Facility Organization 6.0-34 i

l l

viii l

BFN Unit 2 l

3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION.

SURVEILLANCE' REQUIREMENTS 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS Aeolicability Applicability Applies to the operational.

Applies to the surveillance status of the core and requirements of the core and containment cooling systems.

containment cooling systems when the corresponding limiting condi-tion for operation is in effect.

Ob3ective objective To assure the operability of To verify the operability of the the core and containment cooling core and containment cooling systems under all conditions for systems under all conditions for which this cooling capability is which this cooling capability is an essential response to plant an essential response to plant abnormalities, abnormalities.

Specification Specification A.

Core Soray System (CSS)

A.

Core Soray System (CSS) 1.

The CSS shall be OPERABLE:

1.

Core Spray System Testing.

(1) prior to reactor Item Frequency startup from a cold condition, or a.

Simulated once/

Automatic Operating (2) when there is irradiated Actuation Cycle fuel in the vessel test and when the reactor vessel pressure b.

Pump Opera-Once/

is greater than bility month atmospheric pressure, except as specified c.

Motor once/

in Specification Operated month 3.5.A.2.

Valve Operability d.

System flow once/3 rate:

Each months l

loop shall deliver at least 6250 spm against i

a system head corres-ponding to a BFN 3.5/4.5-1 Unit 2

~

1

3.5/4.5_

CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.A Core Spray System (CSS) 4.5.A core Spray System (CSS) 4.5.A.1.d (Cont'd) 105 psi differential pressure between the reactor vessel and the primary containment.

e.

Check Valve Once/

Operating Cycle 2.

If one CSS loop is INOPERABLE, 2.

When it is determined that one the reactor may remain in core spray loop is INOPERABLE, operation for a period not to at a time when operability is exceed 7 days providing required, the other core spray all active components in loop and the RHRS (LPCI mode)

}

the other CSS loop and the shall be demonstrated to be RHR system (LPCI mode)

OPERABLE immediately.

The and the diesel generators OPERABLE core spray loop shall are OPERABLE.

be demonstrated to be OPERABLE daily thereafter.

3.

If Specification 3.5.A.1 or Specification 3.5.A.2 cannot be met, the reactor shall be shutdown in the Cold Condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

When the reactor vessel pressure is atmospheric and irradiated fuel is in the reactor vessel at least one core spray loop with one OPERABLE pump and associated diesel 5enerator shall be OPERABLE, except with the reactor vessel head removed as specified in 3.5.A.5 or prior to reactor startup as specified in 3.5.A.1.

3. 5 /4. 5-2 Amendment NO. 149 BFN Unit 2 l

lg 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT-3.5.B Residual Heat Removal System 4.5.B.

Residual Heat Removal System Rgggl (LPCI and Containment (RHRS) (LPCI and Containment Cooling)

Cooling) 3.

If one RHR pump (LPCI mode) 3.

When it is determined that

.is INOPERABLE, the reactor one RHR pump (LPCI mode) is may remain in operation for INOPERABLE at a time when a period not to exceed 7 days operability is required, provided the remaining RHR the remaining RHR pumps pumps (LPCI mode) and both (LPCI mode) and active access paths of the RHRS components in both access (LPCI mode) and the CSS and paths of the RHRS (LPCI mode) the diesel generators remain and the CSS shall be OPERABLE.

demonstrated to be OPERABLE immediately and daily thereafter.

4.

If any 2 RHR pumps (LPCI 4.

To additional surveillance mode) become INOPERABLE, the required.

reactor shall be placed in the Cold Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.

If one RHR pump (containment 5.

When it is determined that cooling mode) or associated one RHR pump (containment-heat exchanger is INOPERABLE,

_ cooling mode) or, associated the reactor may remain in heat exchanger is INOPERABLE operation for a period not to at a time when operability exceed-30 days provided the is required, the remaining remaining RHR pumps RHR pumps (containment (containment cooling mode) cooling mode), the and associated heat associated heat exchangers exchangers and diesel and all active components generators and all access in the access paths of the paths of the RNRS RHRS (containment cooling 3

(containment cooling mode) mode) shall be demonstrated

)

are OPERABLE.

to be OPERABLE immediately i

and weekly thereafter until the INOPERABLE RHR pump (containment cooling mode) and associated heat exchanger is returned to normal service.

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j BFN 3.5/4.3-:

Amendment No. 149 i

Unit 2 L

L 3.5/4.5 CORE AND CONTAINMENT COOL 7NG SYSTEMS LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5 B.

Residual Heat Removal System 4.5 B.

Residual Heat Removal System (RNRS)_ (LPCI and Containment

( RHRS)_ (LPCI and Containment Cooling)

Cooling) 6.

If.two RHR pumps (containment 6.

When it is determined that cooling mode) or associated two RRR pumps (containment heat exchangers are cooling mode) or associated INOPERABLE, the reactor may heat exchangers are remain in operation for a INOPERABLE at a time when period not to exceed 7 days operability is 6 aquired, the provided the remaining RHR remaining RHR pun s pumps (containment cooling (containment cooling mode),

mode), the associated heat the associated heat exchangers, diesel exchangers, and all generators, and all access active components in the paths of the RHRS access paths of the RHRS (containment cooling mode)

(containment cooling mode) are OPERABLE.

shall be demonstrated to be OPERABLE immediately and daily thereafter until at least three RNR pumps (containment cooling mode) and associated heat exchangers are returned to normal service.

7.

If_two access paths of the 7.

When it is determined that RHRS (containment cooling one or more access paths of mode) for each phase of the the RHRS (containment mode (drywell sprays, cooling mode) are INOPERABLE suppression chamber sprays, when access is required, and suppression pool cooling) all active components are not OPERABLE, the unit in the access paths of the may remain in operation for a RNRS (containment cooling period not to exceed 7 days mode) shall be demonstrated provided at least one path to be OPERABLE immediately for each phase of the mode and all active components in remains OPERABLE.

the access paths which are not backed by a second OPERABLE access path for the same phase of the mode (drywell sprays, suppression chamber sprays and suppression pool cooling) shall be demonstrated to be OPERABLE daily thereafter until the second path is returned to normal service.

BFN 3.5/4.5-6 Amendment NO. 149 Unit 2 I

3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5~B Residual Heat Removal Systein 4.5.B.

~ Residual Heat Removal Syste_n}

g gg),(LPCI and Containment (RHRS) (LPCI and Containment Cooling)

Cooling)

8. If Specifications 3.5.B.1 8.

No additional surveillance through 3.5.B.7 are not met, required.

an orderly shutdown shall be initiated and the reactor shall be shutdown and placed in the cold condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

9.

~ When the reactor vessel 9.

When the reactor vessel pressure is atmospheric and pressure is atmospheric, irradiated fuel is in the the.RHR pumps and valves reactor vessel-at least one RHR that are required to be loop with two pumps or two loops OPERABLE shall be with one pump per loop shall demonstrated to be OPERABLE be OPERABLE. The pumps'

monthly, associated diesel generators must also be OPERABLE.

10. If the conditions of 10.

No additional surveillance Specification 3.5.A.5 are met, required.

LPCI and containment cooling are not required.

11. When there is irradiated fuel 11.

The RHR pumps on the in the reactor and the reactor adjacent units which supply vessel pressure is greater than cross-connect capability atmospheric, 2 RHR pumps and shall be demonstrated to be associated heat exchangers and OPERABLE monthly when the valves on an adjacent unit nuast cross-connect capability be OPERABLE and capable of is required, supplying cross-connect capability except as specified in Specification 3.5.B.12 below.

(Note: Because cross-connect capability is not a short-term requirement, a component is not considered INOPERABLE if cross-connect capability can be restored to service within 5 bours.)

BFN

3. 5/4.5- /

Unit 2

j 3.5/4.5~ CORE'AND CONTAINMENT COOLING SYSTEMS l

I LIMITING CONDITIONS FOR OPERATION' SURVEILLANCE REQUIREMENTS

.' - l t

3.5.B' Residual Heat Removal System 4.5.B.

Residual Heat Removal System (RNRS) (LPCI and Containment (RHRS) (LPCI and. Containment l

Cooling)

Cooling) 12.

If three.RHR pumps or associated 12.

When it is determined heat exchangers located that three.RRR pumps or on the unit cross-connection associated. heat'exchangers in the adjacent units are located on the unit i

INOPERABLE for any reason cross-connection in the (including valve inoperability.-

adjacent units are pipe break, etc.), the reactor INOPERABLE at a time when may remain in. operation operability is required, for a period not to exceed the. remaining RHR pump and 30 days provided the remaining associated heat exchanger RHR pump and associated diesel on the unit cross-connection gensrator are OPERABLE.

shall be demonstrated to be OPERABLE immediately and every 15 days thereafter until the INOPERABLE pump and associated heat exchanger are returned to normal service.

13.

If RHR cross-connection flow or 13.

No additional. surveillance heat removal capability is lost, required.

the unit may remain in operation for a period not to exceed 10 days unless such capability is restored.

14.

All recirculation pump 14.

All recirculation pump discharge valves shall discharge valves shall be OPERABLE prior to be tested for operability reactor startup (or during any period of closed if permitted reactor Cold Shutdown elsewhere in these exceeding 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , if specifications).

operability tests have not been performed during the preceding 31 days.

(I BFN 3.5/4.5-8 Amendment No. 149 Unit 2 I

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h

3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS -3.5.C RHR Service Water and EmergencI 4.5.C RHR Service Water and Eauipment Coolina Water Systems Emermency Equipment (EECWS)

Coolir.m Water Systems (EECWS) 1.

Prior to reactor startup from 1.

a.

Each of the RHRSW pumps a cold condition, 9 RHRSW normally ar?igned to pumps must be OPERABLE, with automatic service or 7 pumps (including one of the EECW headers will pumps D1, D2, B2 or 81) be tested assigned to RHRSW service automatically each time and 2 automatically starting the diesel generators pumps assigned to EECW are tested.

Each-service.

of the RHRSW pumps and all associated essential control valves for the EECW headers and RHR heat exchanger headers shall be demonstrated to be OPERABLE once every three months.

b.

Annually each RHRSW pump shall be flow-rate tested.

To-be considered OPERABLE, each pump shall pump at least 4500 spa through itn normally assigned flow path.

BFN 3.5/4.5-9 Unit 2

V I

l 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION' SURVEILLANCE REQUIREMENTS - 3.5.C RHR Service Water and Emerzency 4.5.C. RHR Service Water and gauipment Cooling Water Systems Emergency Equipment Cooling (EECWs) (Cont'd)

Water Systems (EECWs) (Cont'd) 2.

During reactor power

2. a.

If no more than two operation, RHRSW pumps RHRSW pumps are must be OPERABLE and INOPERABLE, increased assigned to service as surveillance is not indicated in Table 3.5-1 required.

for the specified time limits.

b.

When three RHRSW pumps are INOPERABLE, the remaining pumps and associated essential control valves shall be operated weekly.

c.

When four RHRSW pumps are INOPERABLE, the remaining pumps and associated essential control valves shall be operated daily.

3.

During unit 2 power

3. Routine surveillance for-operation, any two RHRSW.

these pumps is specified pumps (D1, D2, B1, and B2) in 4.5.C.1.

normally or alternately assigned to the RHR heat exchanger header supplying the standby coolant supply connection must be OPERABLE except as specified in 3.5.C.4 and 3.5.C.5 below.

l

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BFN 3.5/4.5-10 Amendment No. 149

)

Unit 2

)

m

~

L 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.D.

Eauipment Area Coolers 4.5.D. Eauipment Area Coolers 1.

The equipment area cooler

1. Each equipment area cooler associated with each RHR

'is operated in conjunction pump and the equipment with the equipment served area cooler associated by that particular cooler; with each set of core therefore, the equipment spray pumps (A and C area coolers are tested at or B.and D) must be the same frequency as.the OPERABLE at all times pumps which they serve.

when the pump or pumps served by that specific cooler is considered to be OPERABLE.

2.

When an equipment area l

cooler is not OPERABLE, the pump (s) served by that cooler must be considered INOPERABLE.for Technical Specification purposes.

E.

Hiah Pressure Coolant Injection E. Hiah Pressure Coolant System (MPCIS)

Injection System (HPCIS) 1.

The HPCI system shall be 1.

HPCI Subsystem testing OPERABLE:

shall be performed as follows:

(1) prior to startup from a a.

Simulated once/

Cold Condition; or Automatic operating Actuation cycle Test (2) whenever there is b.

Pump once/

irradiated fuel in the opera-month reactor vessel and the bility reactor vessel pressure is greater than 122 psig, c.

Motor Oper-Once/

except as specified in ated Valve month Specification 3.5.E.2.

Operability d.

Flow Rate at Once/3 normal months reactor vessel operating pressure i

BFN 3.5/4.5-13 Unit 2 l-1

3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS

' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE. REQUIREMENTS 3.5.C RHR Service Water and Emerzency 4.5.C. RHR Service Water and Equireent Cooling Water Systems Emergency Equipment Coolina (EECWs) (Continued)

Water Systems (EECWs) (Cont'd) 4.

Three of the D1, D2, B1, B2

4. When it is determined that RHRSW pumps assigned to three of the RHRSW pumps the RHR heat exchanger supplying standby coolant supplying the standby are INOPERABLE at a time coolant supply connection when operability is may be INOPERABLE for a required, the OPERABLE period not to exceed 30 days RHRSW pump on the same provided the OPERABLE pump header and the RHR heat 1

is aligned to supply the exchanger header and RHR heat exchanger header associated essential control' and the associated diesel valves shall be demonstrated generator and essential to be OPERABLE immediately control valves are OPERABLE.

and every 15 days thereafter.

5.

The standby coolant supply-capability may be INOPERABLE for a period not to exceed 10 days.

6.

If Specifications 3.5.C.2 through 3.5.C.5 are not met, an orderly shutdown shall be initiated and the unit placed'in the Cold Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

7.

There shall be at least 2 RHRSW pumps, associated with the selected RHR pumps, aligned for RHR heat exchanger service for each reactor vessel containing irradiated fuel.

BFN 3.5/4.5-12 Amendment No. 149 Unit 2 l

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f-n 1

3. 9 / 4 '. 9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUKILIARY ELECTRICAL SYSTEM

.Acolicability Acolicability Applies to all the auxiliary Applies to the periodic electrical power system.

testing requirements of the auxiliary electrical system.

[

Obiective Obiective To assure-an. adequate supply of Verify the operability of the electrical power for operation of auxiliary electeical system.

f those systems required for safety.

Specificat12n Specification

y.

A.

Auxi-.'ary Electrical Eautoment A.

Auxiliary Electrical System 1.

16e reactor shall not be 1.

Diesel Generators l

started up (made critical) from the cold condition unless the following are a.

Each diesel generator' satisfied:

shall be manually started-and loaded to demonstrate a.

Diesel generators A, operational readiness in B, C, and D OPERABLE.

accordance with the frequency specified in b.

Requirements 3.9.A.3 Table 4.9.A on a staggered through 3.9.A.6 are

. test basis.

The test shall met.

continue for at least a one hour period at 75% of rated c.

At least two of the load or greater'and the following offsite power operation of the diesel sources are available:

fuel oil transfer pumps shall be demonstrated.

Also, the diesel generator (1) The 500-kV system is starting air compressor available to the shall be checked for units 1 and 2 shut-operation and its ability down boards through to recharge air receivers, the unit 1 station-service transformer The diesel' generator fast TUSS 1B with no starts (10 seconds) from credit taken for the standby conditions shall be two 500-kV Trinity performed once per 184 days lines.

If the in these surveillance unit 2 station-tests.

All other engine service transformer starts for the purpose of is the second source, this test may be preceeded a minimum of two by an ensino idle start.

l j

500-kV lines must be i

availabic.

BFN 3.9/4.9-1 Amendment No. 149 Unit 2

3.9/4.9 AUXILIARY ELECTRICAL SYSTEM SURVEILLANCE REQUIREMENTS LIMITING CONDITIONS FOR OPERATION 3.9.A. Auxiliary Electrical Equipment 4.9.A. Auxiliary Electrical System 4.9.A.1. (Cont'd) 3.9.A.1.c.

(Cont'd)

Additional reporting requirements due to failures are noted in i

Table 4.9.A.

All diesel generator starts shall be logged.

b.

Once per operating (2) The 500-kV system is availablo to the units 1 cycle, a test will be conducted simulating a ar.d 2 shutdown boards loss of offsite power and through the unit 2 similar conditions that station-servics transformer TUSS 2B with would exist with the no credit taken for the presence of an actual two 500-kV Trinity lines.

safety-injection signal to demonstrate the If the unit I station-service transformer.is the following:

second choice, a minimum (1) Deenergization of the of two 500-kV lines must emergency buses and be available.

load shedding from the emergency buses.

(3) The Trinity 161-kV line is available to the units 3 and 2 shutdown boards (2) The diesel starts from ambient through both common condition on the station-service auto-start signal, transformers.

energizes the emergency buses with NOTES FOR (3):

permanently connected loads, energizes the (a) If unit 3 is claiming auto-connected the Trinity line as an emergency loads offsite source, see unit 3 technical through load specifications, section sequencing, and operates for greater 3.9.A.1.c.2.

than or equal to five minutes while its (b) If unit 1 is in cold generator is loaded shutdown, only one with the emergency common station-service transformer is required, loads.

i

3. 9 / 4. 9-2 Amendment No. 149 BFN Unit 2

u-3.9/A.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxiliary Riectrical Equipment 4.9.A.

Auxiliary Electrical System 3.9.A.1.c.

(Cont'd) 4.9.A.1.b (Cont'd)

(4) The Athens 161-kV line is (3) On diesel generator available te the units 1 breaker trip, the and 2 shutdown boards loads are shed from through a common the emergency buses station-service and the diesel output transformer when unit 1 is breaker recloses on in ' Cold Shutdown and unit 3 the autostart signal, is not c1wiming the Athens the emergency buses line as an offsite source, are energized with permanently NOTE FOR (3) AND (4):

connected loads, the I

autoconnected emer-With no cooling tower pumps sency loads are or fans running, a cooling energized through tower transformer may be load sequencing, and

{

substituted for a common the diesel 1

station-service transformer.

operates for greater than or equal to five minutes while its generator is loaded with the emergency loads.

c.

Once a month the quantity of diesel fuel available shall be logged.

d.

Each diesel generator shall be given an annual inspection in accordance with instructions based I

on the manufacturer's recommendations.

{

e.

Once a month a sample of I

diesel fuel shall be j

checked for quality.

The quality shall be within act;ptable limits specified in Table 1 of the latest revision to ASTM 0975 and logged.

)

l I

1 l

BFN 3.9/4.9-3 Amendment No. 149 i

Unit 2 l

l

=

. -o 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxiliary Electrical Bouipment

'4.9.A.

Auxiliary Electrical System 1

2. The reactor shall not.be 2.

DC Power System - Unit I

started up (made critical)

Batteries (250-V), Diesel-from the. hot standby condition Generator Batteries (125-V) unless all.of the following and Shutdown Board Batteries conditions are satisfied:

-(250-V) a.

At least one offsite power a.

Every week the specific source is available as gravity, voltage and specified in 3.9.A.1.c.

temperature of the pilot cell and overall battery l

voltage shall be measured and logged.

.b.

Three units 1 and 2 diesel b.

Every three months the

-j generators shall be measurement shall be made OPERABLE.

of voltage of each cell i

to nearest 0.1 volt,.

specific' gravity of each cell, and temperature of every fifth cell.

These measurements shall be logged.

c..

An additional source of c.

A battery rated power consisting of one discharge (capacity) of the following:

test shall be performed and the voltage, ti.me,

(1) A second offsite measurements shall and output. current pcwer source available as specified in be logged at 3.9.A.1.e.

intervals not to exceed 24 months.

(2) A fourth OPERABLE units 1 and 2 diesel generator, d.

Requirements 3.9.A.3 through 3.9.A.6 are met.

1 1

BFN 3.9/4.9-4 Unit 2 l

l

=

____.._y_________________

3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.B.

Operation with Inoperable 4.9.B.

Operation with Inoperable l

Equipment Equipment Whenever the reactor is in STARTUP mode or RUN mode and not in a cold condition, the availability of electric power shall be as specified in 3.9.A except as specified herein.

1.

From and after the date 1.

When only one that only one offsite offsite power source power source is available, is OPERABLE, all reactor operation is units 1 and 2 diesel permissible for 7 days.

generators must be demonstrated to be OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and power availability for the associated boards shall be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

2.

From and after the date 2.

When a required that the 4-kV bus tie offsite power source board becomes INOPERABLE, is unavailable to reactor operation is unit 1 because the permissible indefinitely 4-kV bus tie board provided one of the or a start bus is required offsite power INOPERABLE, all sources is not supplied unit 1 and 2 diesel from the 161-kV system generators shall be throu5h the bus tie board.

demonstrated OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and power availability for the associated boards shall be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once por 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

The remainin8 offsite source and associated buses shall be checked to be energized daily.

BFN 3.9/4.9-8 Amendment No. 149 Unit 2 mg.

-_________w-___a____

3.9/4.9 AUXILIARY ELECTRICAL SYSTEM 1

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS j

L l

3.9.A.

Auxiliary Electrical Equipment 4.9.A.

Auxiliary Electrical System 4.9.A.4. (Cont'd)'

c.

The loss of voltage and degraded voltage relays which start the diesel generators from the 4-kV shutdown boards shall be calibrated annually for trip and reset and the measurements logged.

These relays shall be calibrated as specified in Tabis 4.9.A.4.c.

d.

4-kV shutdown board voltages shall be recorded once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

5.

Logic' Systems 5.

480-V RMOV Boards 2D and 2E a.

Common accident signal a.

Once per operating logic system is OPERABLE.

cycle the automatic transfer feature for 480-V RMOV boards 2D and 2E shall be functionally tested to verify auto-transfer capability.

b.

480-V load shedding logic system is OPERABLE.

6.

There shall be a minimum of 103,300 gallons of diesel fuel in the standby diesel-generator fuel tanks.

BFW 3.9/4.9-7 unit 2 l

O 3.9/4.9 AUXILIARY ELECTRICAL' SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.B.

Operation With Inocerable 4.9.B.

Operation With Inoperable Equipment Equipment 3.

When one of the units 1 3.

When one of the and 2 diesel generator is units 1 and.2 diesel INOPERABLE, continued generators is found reactor operation is to'be INOPERABLE, permissible during-the.

all of the remaining i

succeeding 7 days, diesel generators I

provided that 2 offsite shall be demonstrated power.sourass are to be OPERABLE within-l available as specified 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and' power.

)

in 3.9.A.1.c and all of availability.for the-the CS, RHR (LPCI and associated boards containment cooli.ng) shall be verified I

systems, and the remaining within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and three units 1 and 2 diesel at Isast once per generators are OPERABLE.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the cold condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

When one units 1 and 2 4.

When one 4-kV 4-kV shutdown board is shutdown board is INOPERABLE, continued found to be reactor operation is INOPERABLE, all permissible for a period diesel generators of 5 days provided that associated with the 2 offsite power sources remaining 4-kV are available as shutdown boards shall' specified in 3.9.A.1.c be demonstrated to be and the remaining 4-kV OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , shutdown boards and and power-availability associated diesel for the remaining 4-kV generators, CS, RHR (LPCI shutdown boards shall and containment cooling) be verified within 1 systems, and all 480-V hour and at least once emergency power boards per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

are OPERABLE.

If-this requirement cannot be met, an orderly shutdown shall be initiated ano the reactor shall be shut down and in the cold condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3FN 3.9/4.9-9 Amendment #;0.

Unit 2 I

3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.B.

Operation With Inoperable 4.9.B.

Operation With Inoperable Equipment Equipment l

5.

When one of the shutdown 5.

When a shutdown bus buses is INOPERABLE, is found to be reactor operation is INOPERABLE, all permissible for a period 1 and 2 diesel of 7 days.

generators shall be proven OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

6.

When one of the 480-V 6.

When one units 1 diesel auxiliary boards and 2 diesel becomes INOPERABLE, auxiliary board is reactor operation is found to be permissible for a period INOPERABLE, each of 5 days.

unit 1 and 2 diesel i

generator shall be proven l

OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and power availability for the remaining diesel auxiliary board shall be f

verified within I hour and at least once.per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

7.

From and after the date that one of the three 250-V unit batteries and/or its associated battery board is found to be INOPERABLE for any reason, continued reactor operation is permissible during the succeeding 7 days.

Except for routine surveillance testing, NRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the situation, the precautions to be taken during this period, and the plans to return the failed component to an OPERABLE state.

8FN 3.9/4.9-10 Amendment flo, 149 Unit 2

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_ l ATTACHMENT TO TABLE 4.9.A DIESEL GENERATOR REQUALIFICATION PROGRAM j

l l

l (1) Perform seven consecutive successful demands without a failure within 30 days of diesel generator being restored to operable status and fourteen l

consecutive successful demands without a failure within 75 days of diesel generator of being restored to OPERABLE status.

(2)

If a failure occurs during the first seven tests in the requalification test program, parform seven successful demands without an additional failure within 30 days of diesel generator of being restored to OPERABLE status and fourteen consecutive successful demands without a failure within 75 days of being restored to OPERABLE status.

(3)

If a failure occurs during the second seven tests (tests 8 through 14) of (1) above, perform fourteen consecutive successful demands without an additional failure within 75 days of the failure which occurred during the requalification testing.

(4) Following the second failure during the requalification test program, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

(5) During requalification testing the diesel generator should not be tested more f requently than at 24-hour intervals.

After a diesel generator has been successfully requalified, subsequent repeated requalification tests will not be required for that diesel generator under the following conditions:

(a) The number of failures in the last 20 valid demands is less than 5.

(b) The number of failures in the last 100 valid demands is less than 11.

(c)

In the event that, following successful requalification of a diesel generator, the number of failures is still in excess of the remedial action criteria (a and/or b above) the following exception will be allowed until the diesel generator is no longer in violation of the remedial action criteria (a and/or b above).

Requalification testing will not be required provided that after each valid demand the number of failures in the last 20 and/or 100 valid demands has not increased.

Once the diesel generator is no longer in violation of the remedial action criteria above the provisions of those criteria alone will prevail.

BFU 3.9/4 9-17 Amendment No. 149 Unit 2

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3.9 BASES The objective of this specification is to assure an adequate source of.

electrical power to operate facilities to cool the plant during shutdown and to operate the engineered safeguards following an accident.

There are three sources of alternating current electrical energy available, namely, the 161-kV transmission system, the 500-kV transmission system, and the diesel generators.

The unit station-service transformer B for unit 1 or the unit station-service transformer B for unit 2 provide noninterruptible sources of offsite power from the 500-kV transmission system to the units 1 and 2 shutdown boards.

Auxiliary power can also be supplied from the 161-kV transmission system through the common station-service transformers or through the cooling tower transformers by way of the bus tie board.

The 4-kV bus tie board may remain out of service indefinitely provided one of the required offsite power sources is not supplied from the 161-kV system through the bus tie board.

The minimum fuel oil requirement of 103,300 gallons is sufficient for seven days of full load operation of three diesels and is conservatively based on availability of a replenishment supply.

The degraded voltage sensing relays provide a start signal to the diesel generators in the event that a deteriorated voltage condition exists on a 4-kV shutdown bdard.

This starting signal is independent of the starting signal generated by the complete loss of voltage relays and will continue to function and start the diesel generators on complete loss of voltage should the loss of voltage relays become inoperable.

The 15-day inoperable time limit specified when one of the three' phase-to-phase degraded voltage relays is inoperable is justified based on the two-out-of-three permissive logic scheme provided with these relays.

A 4-kV shutdown board is allowed to be out of operation for a brief period to allow for maintenance and testing, provided all remaining 4-kV shutdown boards and associated diesel generators, CS, RHR, (LpCI and containment cooling) systems supplied by the remaining 4-kV shutdown j

boards, and all emergency 480-V power boards are operable.

1 There are eight 250-V de battery systems, each of which consists of a battery, battery charger, and distribution equipment.

Three of these systems provide power for unit control functions, operative power for unit motor loads, and alternative drive power for a 115-V ac unit-preferred mg set.

One 250-V de system provides power for common plant and transmission system control functions, drive power for a 115-V ac plant-preferred mg set, and emergency drive power for certain unit 1arge motor loads.

The four remaining systems deliver control power to the 4,160-V shutdown boards.

BFN 3.9/A.9-19 Amand. ment 90. lao Unit 2 1

n l

3.9 gaggi (Cont'd)-

Each 250-V de shutdown board control power supply can receive power from its own battery, battery charger, or from a spare charger.

The' chargers ~

are powered from normal plant auxiliary power or from.the standby

~

diesel-driven generator system.

Zero resistance short. circuits between the control power supply and the shutdown board are cleared by' fuses located in the respective control power' supply.

Each power supply is y

located in the reactor building near the shutdown board it supplies.

Each battery-is located in its own independently ventilated battery room.

The 250-V de system is wa arranged, and the batteries sized'so that the loss of any one unit battery will not prevent the sefe shutdown and cooldown of all three units in the event of the loss of offsite power and a design basis accident in any one unit.

Loss of control power to any engineered safeguard control circuits is annunciated in the main control room of the unit affected.

The loss of one 250-V shutdown board battery affects normal control power only for the 4,160-V shutdown board which it supplies.

The. station battery supplies loads that are not essential for safe shutdown and cooldown of the nuclear system.

This battery was not considered in the. accident load calculations.

There are two 480-V ac RMOV boards th d contain og sets in their feeder lines. These'480-V-ac RNOV boards have an automatic transfer from their normal to alternate power source (480-V ac shutdown boards).

The mg sets-act as electrical isolators to prevent a fault from propagating between electrical divisions due to an automatic transfer.

The 480-V ac RMOV boards involved provide motive power to valves associated with the LpCI. mode of the RHR system.' Having an og set out of service reduces 2

the assurance that full RNR (LpCI) capacity will be available when required.. Since sufficient equipment is available to maintain the minimum complement required for RKE (LpCI) operation, a 7-day servicing period is justified. Having two mg sets out of service can considerably reduce equipment availability; therefore, the affected unit shall be placed in Cold Shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The offsite power source requirements are based on the capacity of the respective lines. The Trinity line is limited to supplying two operating units because of the load limitations of CSST's A and B.

The Athens line is limited to supplying one operating unit because of the load limitations of the Athens line.

The limiting conditions are intended to prevent the 161-kV system from supplying more than two units in the event of a single failure in the offsite power system.

BFN 3.9/4.9-20 Amendment No. 149 Unit 2

}gL I

1 i

4.9 RAEEE The monthly tests of the' diesel generators are-primarily to' check for

. failures and deterioration in the system since last use.

The diesels l

will be loaded to at least 75 percent of rated power while engine and generator; temperatures are stabilized (about one hour).

The minimum 75-percent. load will prevent. soot formation in the cylinders and

)

injection' nozzles.

Operation up to an equilibrium temperature ensures i

that there is no overheating problem.. The tests also provide an engine and generator operating history to be compared with subsequent l

engine-generator test data to identify and to correct any mechanical or electrical deficiency before it can result in a system failure.

i The te.st during refueling outages is more comprehensive, includin,g procedures tt.at are most' effectively conducted at that time. These include autoastic actuation 2nd functional capability tests to verify that the generators can start and be ready to assume load in 10 seconds.- The annual inspection will detect any signs of wear long before failure. The diese1' generators are shared by units 1 and 2.

.Therefore..the capability for the units 1 and 2 diesel generators to accept the emergency loads will be performed during the unit 1 operating cycle using the unit 1 loads.

Battery maintenance with regard to the floating charge, squalizing charge, and. electrolyte level will-be based on the manufacturer's

instruction and sound maintenance practices.

In addition, written records will be maintained of the battery performance.

The plant batteries will deteriorate with time but precipitous failure is unlikely.

The' type of surveillance called for in this specification is that which has been demonstrated through experience to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.

1The equalizing charge, as recommended by the manufacturer, is vital to maintaining the ampere-hour capacity of the battery, and will be applied

.as recommended.

The testing of'the ldgic systems will verify the ability,of the logic systems to bring the auxiliary electrical system to running standby readiness with the presence of an accident signal from any reactor or an undervoltage signal on the 4-kV shutdown boards.

I The periodic simulation of accident signals in conjunction with diesel-generator voltage available signals will confirm the ability of the 480-V load shedding logic system to sequentially shed and restart 480-V loads if an accident signal were present and diesel-generator voltage were the only source of electrical power, i

1 l

BFN 3.9/4.9-21 Amencment No. 149

(

Unit 2

~

Q

[.

l.

REf3R_EW_qEst 1.

Motsal Auxiliary Power System (BFWP FSAR Gubsection 8.4) 2.

Standby AC Power Supply and Distribution (BFNP FSAR Subsection 8.5) 1

- 3.

250-Volt DC Power Supply and Distribution (BFMP FSAR Subsection 8.6) 4.

Memorandum from Gene M. Wilholte to H. J. Green dated' December 4, 1981 (LOO 811208 664) and memorandum from C. E. Winn to H. J. Green dat,ed January 10, 1983 (G02 830112 002) i i

P O

e BFN 3.9/4.9-22 Amendment No. 149 Unit 2 h

__m.___._._.__m._m..____._

Report shall be submitted within 10 days after the j

event describing the magnitude, frequency specttum,,

4 and resultant effect upon plant features important I

to safety.

7.

Diesel Generator Reliability Improvement program Report shall be submitted within 30 days of meeting failure criteria in Table 4.9.A.

As a minimum, the i

reliability Improvement program report for NRC audit shall include:

a.

A summary of all tests (valid and invalid) that occurred within the time period over which the

)

last 20/100 valid tests were performed.

l l

b.

Analysis of failures and determination of root causes of failures.

{

l c.

Evaluation of each of the recommendations of l

1 NUREC/CR-0660, " Enhancement of Onsite Emergency Diesel Generator Reliability in Operating Reactors," with respect to their application to the plant.

d.

Identification of all actions taken or to be taken to (1) Correct the root causes of failures defined in b above and (2) Achieve a general improvement of diesel generator reliability.

A supplemental report shall be prepared for an

)

e.

NRC audit within 30 days after each subsequent failure during a valid demand, for so long as the affected diesel generator unit continues to violate the criteria (3/20 or 6/100) for the reliability improvement program remedial f

action. -The supplemental report need only update the failure / demand history for the i

affected diesel generator unit since the last

{

report for that diesel generator.

The J

supplemental report shall also present an j

analysis of the failure (s) with a root cause l

determination, if possible, and shall delineate I

any further procedural, hardware or operational f

changes to be incorporated into the site diesel i

generator improvement program and the schedule

{

for implementation of those changes.

l 6.0-27 Amendment No. 149 BFN Unit 2 h.

L.

o

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8.

Secondary Containment 4.7.C.

Within 90 days Leak Rate Testing

of completion of each test.

9.

High-Range Primary 3.2.F Within 7 days Containment Radiation after 7 days of Monitors inoperability.

i

10. High-Range Gaseous Effluent 3.2.F Within 7 days

{

Radiation Monitors after 7 days.of inoperability.

Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report. This report should include, data on the wind speed, wind direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate.

The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate limits.

6.10 STATION OPERATING RE00RDS AND RETENTION 6.10.1 Records and/or logs shall be kept in a manner convenient for review as indicated below:

All normal plant operation including such items as power a.

level, fuel exposure, and shutdowns b.

principal maintenance activities c.

Reportable Events d.

Checks, inspections, tests, and calibrations of components and systems, including such diverse items as source leakage Reviews of changes made to'the procedures or equipment or e.

reviews of tests and experiments to comply with 10 CFR 50.59 f.

Radioactive shipments 3

Test results in units of microcuries for leak tests performed pursuant to Specification 3.8.D 3FN 6.0 28 Amendment No. 149 Unit 2

,/

$'o,,

UNITED STATES NUCLEAR REGULATORY COMMISSION E

o r,

E WASHWGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEdR PLANT, UNIT 3 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 124 License No. OPR-68 1.

The Nuclear Regulatory Commission' (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated May 29, 1987, as supplemented April 13, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be ininiical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

m

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment L

and paragraph 2.C.(2) of Facility Operating License No. DPR-68 is hereby amended to read as follows:

l (2) Technical Specifications 1

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.124, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Suzann lack, Assistant Director for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 19,.1988 i

e i

i 1

~

\\

ATTACHMENT TO LICENSE AMENDMENT NO 149 i

FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise the Appendix A Technical Specifications by removing the pages identified below anc inserting the enclosed pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.

REMOVE INSERT v11 vii viii viii*

3.5/4.5'1 3.5/4.5-1*

3.5/4.5-2 3.5/4.5-2 3.5/4.5-5 3.5/4.5-5 3.5/4.5-6 3.5/4.5-6 3.5/4.5-7 3.5/4.5-7*

3.5/4.5-8 3.5/4.5-8 3.5/4.5-9 3.5/4.5-9*

3.5/4.5-10 3.5/4.5-10 3.5/4.5-12 3.5/4.5-12 3.5/4.5-13 3.5/4.5-13*

3.9/4.9-1 3.9/4.9-1 3.9/4.9-2 3.9/4.9-2 3.9/4.9-3 3.9/4.9-3 3.9/4.9-4 3.9/4.9-4*

3.9/4.9-7 3.9/4.9-7*

3.9/4.9-8 3.9/4.9-8 3.9/4.9-9 3.9/4.9-9 3.9/4.9-10 3.9/4.9-10 3.9/4.9-15 3.9/4.9-15 3.9/4.9-16 3.9/4.9-16 3.9/4.9-17 3.9/4.9-17 3.9/4.9-18 3.9/4.9-18 3.9/4.9-19 3.9/4.9-19 3.9/4.9-20 3.9/4.9-20 3.9/4.9-21 3.9/4.9-21 6.0-27 6.0-27 6.0-28 6.0-28 l

l t

~ LIST OF TABLES (Ccnt'd)

T3)J3 I,i}J3, P*sta No.

'4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation.

3.2/4.2-52 4;2.F

, Minimum Test and Calibration Frequency for Surveillance Instrumentation..

3.2/4.2-53 L

4.2.C Surveillance Requirements for Control Room Isolation Instrumentation.

3.2/4.2-55

'4.2.H Minimus Test ar.d Calibration Frequency for Flood Protection Instrumentation.

3.2/4.2-56 4.2.J Seirdic' Monitoring Instrument Surveillance 3.2/4.2-57 Requirements.

i 4.2.K Radioactive Gaseous Effluent Instrumentation.

)

3.2/4.2-61 Surveillance.

3.5-1 Minimum RHRSW and EECW Pump Assignment.

3.5/4.5-11

3. 5. I-MAPLHGR Versus Average Planar Exposure.

3.5/4.5-21 3.7.A Primary Containment Isolation Valves..

3.7/.i.7-24 3.7.B Testable Penetrations with Double 0-Ring Seals.

3.7/4.7-31 3.7.C Testable Penetrations, with Testable Bellows.

3.7/4.7-32

3. 7.D.

Air Tested Isolation Valves.

3.7/4.7-33 3.7.E Primary Containment Isolation Valves which

' Terminate below the Suppression Pool Water Level......................

3.7/4.7-36 3.7.F Primary Containment Isolation Vales Located in Water Sealed Seismic Class 1 Lines.

3.7/4.7-37 3.7.H Testable Electrical Penetrations.

3.7/4.7-38 4.9.A Diesel Generator Reliability.

3.9/4.9-15 4 9.A.4.C Voltage Relay Setpoints/ Diesel Generator Start.

3.9/4.9-17 3.11.A Fire Protection System Hydraulic Requirements.

3.11/4.11-10 i

6.2.A Minimum Shift Crew Requirements.

6.0-3 BFN vii Amendment No. 124 Unit 3

een,

_2.

1 l

LIST OF ILLUSTRATIONS Figure Title Pate No.

l 2.1.1 APRM Flow Reference Scram and APRM Rod Block 1.1/2.1-6 i

Settings.....................

2.1-2 APRM Flow Bias Scram Vs. Reactor Core Flow.

1.1/2.1-7 4.1-1 Graphic Aid,in the Selection of an Adequate l

Interval Between Tests.

3.1/4.1-12 4.2-1 System Unavailability.

3.2/4.2-63 3.4-1 Sodium Pentaborate Solution Volume Concentrated Requirements.

3.4/4.4-4 3.4-2 Sodium Pentaborate Solution Temperature Requirements.

3.4/4.4-5 3.5.K-1 MCPR Limits.

3.5/4.5-25

.I 3.5/4.5-26 3.5.2 Kg Factor.

C 3.6-1 Minimum Temperature F Above Change in Transient Temperature.

3.6/4.6-24 I

l 3.6-2 Change in Charpy V Transition Temperature Vs.

Neutron Exposure.

3.6/4.6-25 4.8.1.a Gaseous Release Points and Elevation.

3.8/4.8-10 4.8.1.b Land Site Boundary.

3.8/4.8-11 6.2-1 Offsite Organization for Facility Mana5ement and Technical Support 6.0-33 6.2-2 Facility Organization 6.0-34 l

l J

viii l

i BFN Unit 3

y L5/4.5 ' CORE'AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS.FOR OPERATION SURVEILLANCE REQUIREMENTS.

T.5 CORK AND COWTAINNENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS

.Asolicability toolicability Applies to the operational Applies to the surveillance status of the core and requirements of the Core and Containment Cooling Systens.

Containment Cooling. Systems when the corresponding limiting condi-tion for operation is in effect.

Obiective

Ob3ective To assure the operability of To verify the operability of the the Core and Containment Cooling Core and containment Cooling Systems under all conditions for-Systems under all conditions for which this cooling dapability is which this cooling capability is an essential response to plant an essential response to plant abnormalities.

abnormalities.

IP.gg),fication Specification A.

Core Sorsy System (CSS)

A.

Core Soray System (CSS) 1.

The CSS shall be OPERABLE:

1.

Core Spray System Testing.

(1) prior to reactor Item Frequency startup from a Cold Condition, or a.

Simulated once/

Automatic Operating (2) when there is irradiated Actuation Cycle.

fuel in the vessel test and when the reactor vessel pressure b.

Pump Opera-Once/

is greater than bility month atmospheric pressure, except as specified c.

Motor once/

in Specification Operated month 3.5.A.2.

Valve operability d.

System flow Once/3 rate:

Each months loop shall deliver at least 6250 spm against a system head corres-ponding to a BFN-Unit 3

3. 5 / 4. 5-1 hh_

sc

=3.5/4.5-CORE'AND CONTAINMENT COOLING' SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS-3 5.A Core Soray System (CSS) 4.5.A core Soray System (CSS) 4.5.A.1.d (Cont'd) 105 psi differential pressure.

between the reactor vessel and the primary containment.

e.

Testable Once/

Check Valvt Operating Cycle 2.

If one CSS loop is INOPERABLE, 2.

When it is determir:ed that one the reactor may remain in core spray loop'is. INOPERABLE, operation-for a period not to' at a time when operability is exceed 7 days providing required, the other core spray all active components in loop and-the RHRS (LPCI mode) the other CSS loop;and.the shall be demonstrated to be l

RHR system (LPCI mode)

OPERABLE immediately.

The sac Lhe diesel generators OPERABLE core spray loop shall be demonstrated to be OPERABLE are OPERABLE.

daily thereafter.

3.

If Specification 3.5.A.1 or Specification 3.5.A.2 cannot be met, the reactor shall be shutdown in the Cold Condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

When the reactor vessel pressure is atmospheric and irradiated fuel is in the reactor vessel at least one core spray loop with one OPERABLE pump and associated diesel generator shall be OPERABLE, except with the reactor vessel head removed as specified in 3.5.A.S or prior'to reactor startup as specified in 3.5.A.1.

Amendment No. 124 BFN-

3. 5 /4. 5-2

-Unit 3

\\

3.5/4.5 CORE AND CiNTAINHFWT COOLING SYSTEMS

- *~

! LIMITING CONDITIONS.FOR OPERATION SURVEILLANCE REQUIREMENT - 3.5.B -

Residual Heat Removal System 4.5.B. Residual Heat Removal System 1E B82. (LPCI and Containment (RHRS) (LPCI and Containment Cooling)

Cooling) 3'. If one RHR pump (LPCI mode)

3. When it is determined that is INOPERABLN, the reactor one RRR pump (LPCI mode) is may remain in 9peration for INOPERABLE at a time when a period not to exceed 7 days operability is required, provided.the remaining RHR the' remaining RHR pumps pumps (LPCI mode) and both (LPCI mode) and active access paths of the RHRS components in both access (LPCI mode) and the CSS and paths of the RHRS.(LPCI mode) the diesel generators remain and the CSS shall be OPERABLE.

demonstrated to be OPERABLE immediately and daily thereafter.

4. If any 2 RHR pumps (LPCI

4. No additional survelliance mode) become IBOPERABLE, the required.

reactor shall be placed in the Cold. Shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5. If one RHR pump (containment 5, When it is determined that cooling mode) or associated wne RHR pump (containment heat exchanger is INOPERABLE, cooling mode) or associated the reactor may remain in heat exchanger is INOPERABLE operation for a period not to at a time when operability exceed 30 days provided the is required, the remaining remaining RHR pumps RHR pumps (containment (containment cooling mode) cooling mode), the and associated heat associated heat exchangers exchangers and diesel and all active components in generators and all access the access paths of the RHRS paths of the RHRS (containment cooling mode)

(containment cooling mode) shall be demonstrated to be are OPERABLE.

OPERABLE immediately and weekly thereafter until the INOPERABLE RHR pump (containment cooling mode) and associated heat exchanger is returned to normal service.

Amendment No. 124 BFN 3.5/A.5-5 Unit 3

~

_____.m______

c --

y, 3.5/4.5 CORE AND CONTAINMENT'C00 LING SYSTEMS e

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5 B.-

Residual Heat' Removal' System 4.5 B.

Residual Heat Removal System (RH58) (LPCI and Containment.

~(RHRS) (LPCI and Containment-Cooling)

Cocling) 6.- If two'RHR pumps (containment 6.

When it is determined that cooling mode) or associated two RHR pumps (contal.tment heat exchangers are cooling mode) or associated INOPERABLE, the reactor may heat exchangers are

. remain in operation for a INOPERABLE at a time when period not to exceed 7 days operability is required, the provided the remaining RHR remaining RHR pumps pumps (containment cooling (containment cooling mode),

mode), the associated heat' the. associated heat exchangers,; diesel' exchangers, and all active generators, and all access components in the access p

paths of the RHES paths of the RHRS (containment cooling mode)

(containment. cooling are OPERABLE.

mode) shall be demonstrated to' be OPERABLE innediately and daily thereafter until at least three RHR-pumps (containn.ent cooling mode) and associated heat exchangers are returned to normal service.

7.

If two access' paths of the 7.

When it is determined.that' RHRS (containment cooling one or more access paths of mode) for each phase of the the RHRS (containment mode (drywell sprays, cooling mode) are INOPERABLE suppression chamber sprays, when access is required, and suppression pool' cooling) all active components are not OPERABLE, the unit in the access pa,ths of the may remain in operation for a RHRS (containment cooling period not to exceed 7 days mode) shall be demonstrated provided at least one path to be OPERABLE immediately forleach phase of the mode and all active components in remains OPERABLE.

the access paths which are not backed by a second OPERABLE access path for the same phase of the mode (drywell sprays, suppression chamber sprays and suppression pool cooling) l~

shall be demonstrated to be OPERABLE daily thereafter until the second path is returned to normal service.

BFN.

3.5/4.5-6 Amendment No. 124 L' nit 3

____.___..__m-

r 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS POR OPERATION SURVEILLANCE REQUIREMENTS 3.5.5 Residual Heat R.ymoval System 4.5.3 Residual Heat Removal System (RNRS)-(LPCI and Containment (RHRS) (LPCI and Containment.

Cooling)(Cont'd)

Cooling)(Cont'd):

8. If.Speelfications 3.5.B.1

8. No additional surveillance through. 3.5.B. 7 are not taet, required.

an orderly shutdown shall be

' initiated and the reactor

-shall be shutdown and

.placed in the Cold Condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

9.-When the, reactor vessel

9. When the reactor vessel pressure is atmospheric and pressure is atmospheric, irradiated fuel is in the-the RHR pumps and valves reactor vessel at least one RHR that are required to be loop with two pumps or two loops OPERABLE shall be with osse pump per loop shall demonstrated to be OPERABLE be OPERABLE. The pumps' monthly.

o associated diesel generators tmst also be OPERABLE.

10.

If the conditions of

10. No additional surveillance Specification 3.5.A.5 are met, required.

LPCI r,nd containment cooling are not required.

11.

When there is irradiated fuel

11. The B and D RHR pumps on in the reactor and-the reactor unit 2 which supply vessel pressure'is greater than cross-connect capability atmospheric, unit 2 RHR pumps B shall be OPERABLE

.and D associated with heat ex-monthly when the i

changers and valves must be cross-connect capability OPERABLE and capable of is required.

supplying cross-connect capability except as specified q

in Specification 3.5.B.12 j

below. '(Note: Becese cross-connect capability is not j

j a short-term requirement, a component is not considered f

INOPERABLE if cross connect j

capability can be restored to j

service within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .)

BFN Unit 3 3.5/4.5-7

~

s

_Ef_______

E

'3'.5/4.5' CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SUEVMILLANCE REQUIREMENTS 3.5.B Residual Heat Removal System 4.5.B Residual Heat Removal System (RHRS) (LPCI and Containment (RHRS) (LPCI and Containment Cooling)(Cont'd)

Cooling)(Cont'd) 12.

If one RHR pump or associated

12. When'it is determined heat exchanger located that one RHR pump or on the unit cross-connection.

associated heat exchanger in unit 2 is INOPERABLE located on the unit

'for any reason (including cross-connection in the valve inoperability, adjacent unit is pipe break, etc.)=, the reactor INOPERABLE at a time when may remain in operation operability is required, for a period not to exceed the remaining RHR pump and 30 days provided the remaining associated heat exchanger RHR pump and associated diesel on the unit cross-connecticn generator are OPERABLE.

shall be demonstrated to be OPERABLE immediately and every 15 days thereafter until the INOPERABLE pump and associated heat exchanger are returned to normal service.

13.

If RHR'eross-connection flow or

13. No additional surveillance heat removal capability is lost,

required, the unit may remain in operation for a period not to exceed 10 days.unless such capability is restored.

14.

All recirculation pump 14 All recirculation pump discharge valves shall discharge valves shall i

be OPERABLE prior to be tested for operability recator startup (or during any period of closed if permitted reactor Cold shutdown elsewhere in these exceeding 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , if specifications).

operability tests have not been performed during the preceding 21 days.

J BFN 3. 5 / 4. 5-8 Amendment NO. 124 unit 3

_ - _ _ - _ _ _ = _ _ _ _ _ _ - _ - _ _ - _ _ - _ _

3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS.

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LIMITING COUDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.C RHR Service Water and EmerzencY 4.5.C RHR Service Water and Equijnlant Coolina Water Systems Emergency Equipment Cooling (EECWS)

Water Systems (EECWS)

1. Prior to reactor startup from 1.

a.

Each of the RHRSW pumps a Cold Condition, 9 RRRSW normally assigned.to

' pumps must-be OPERABLE, with automatic service on

~7 puars (including pump 31 the EECW headers will or B2) assigned to RHRSW be tested service and 2 automatically autoastically each time starting pumps assigned to the diesel generators EECW service.

are tested.

Each of the RHRSW pumps and al1 associated essential control valves for the EECW headers and RHR heat exchanger headers shall be demonstrated to.be OPERABLE once every three months.

b.

Annually each RHRSW pump shall be flow-rate tested.

To be considered OPERABLE each pump shall pump at least 4500 spm through its normally i

assigned flow path.

1 1

)

BFN Unit 3 3.5/4.5-9 m- _. _ - - _ - _- _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

.I 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.C RHR Service Water and Emergency 4.5.C RHR Service Water and Equipment Cooling Water Systems Emergency Equipment Cooling __

(EECWs) (Cont'd)

Water Systems (EECWs) (Cont'd) g

2. During. reactor power 2.

a.

If no more than two operation RHRSW pumps RHRSW pumps are must be OPERABLE and INOPERABLE, increased assigned to service as surveillance is not i

indicated in Table 3.5-1 required.

j for the specified time.

)

limits, b.

When three RHRSW pumps are INOPERABLE, the remaining pumps and associated essential control valves shall be l

coersted weekly.

c.

When four RHRSW pumps are INOPERABLE, the remaining pumps and associated essential control valves shall be operated daily.

3. During power operation, 3.

Routine surveillance for i

both RHRSW pumps ~B1 and these pumps is specified-B2 normally or alternately in 4.5.C.1.

assigned to the RHR heat exchanger header supplying the standby coolant supply connection must be OPERABLE; except as specified'in 3.5.C.4 and 3.5.C,5 below.

BFN 3.5/4.5 10 Amendment No. 124 Unit 3

1

-3.5/4.5-CORE AND CONTAINMENT COOLING SYSTEMS LIMITING CONDITIONS.FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.D Eeulement Area coolers 4.5.D

'gauipment Area Coolers '

1. The equipment area cooler 1.

Each equipment area cooler associated with each RNR-is operated in conjunction pump and the equipment with the equipment served

]

area cooler associated by that particular cooler; j

with each set of core therefore, the equipment q

spray pumps (A and C

' area coolers are testod at.

~

or B and D) must be the same frequency as the

-)

' OPERABLE at all times pumps which they serve.

when the pump or. pumps served by that specific cooler is considered to be~0PERABLE.

2. When an equipment neea cooler is not OPERABLE, the pump (s) served by that cooler must be considered INOPERABLE for Technical Specification purposes.

i E. Hiah Pressure Coolant Injection E.

Hinh Pressure Coolant System (HPCIS)

Inlegtion System (HPCIS) 1.

The MPCI' system shall be 1.

HPCI subsystem testing OPERABLE:

shall be performed as follows:

(1) prior to startup from a a.

Simulated Once/

Cold Condition; or Automatic operating Actuation cycle Test (2) whenever there is b.

Pump Once/

irradiated fuel in the Opera-month reactor vessel and the bility reactor vessel pressure is greater than 122 psig, c.

Motor Oper-Once/

except as specified in-ated Valve month Specification 3.5.E.2.

Operability d.

Flow Rate at Once/3 normal months reactor vessel operating pressure 3FN-Unit 3 3.5/4.5-13

.m.--.______m______.._m,

s 3.5/4.5 CORE AND CONTAINMENT COOLING SYSTEMS.

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l:

3.5.C' RHR Service Water and Emerzency 4.5.C RHR Service Water and l

Eauipment Coolina Water Systems Emersoney Equipment Cooling _

(EECWs) (Cont'd)

LWater Systems (E7CWs) (Cont'd)

4. One of the B1 or B2.RHRSW 4.

When it is determined that-pumps assigned to the RHR-the B1 or B2 RHRSW pump-L heat exchanger supplying is INOPERABLE at a time l1

.the standby coolant supply when operability'is connection may_be required, the OPERABLE INOPERABLE for a period RHRSW pump on the same not to exceed 30 days header and tue RHR heat-provided the OPERABLE pump exchanger header and is aligned to supply the associated essential control RRR heat exchanger header valves shall be demonstrated and the associated diesel to be OPERABLE immediately generator and essential, and every 15 days thereafter.

control valves.are OPERABLE..

i

5. The standby coolant supply.

c'apability may be INOPERABLE for a period not to exceed 10 days.

6. If Specifications 3.5 C.2 through'3.5.C.5 are not met, an orderly shutdown shall be initiated and the

. unit placed in the Cold Shutdown condition within, 24 'nours..

7. There shall be.at least 2 RHRSW pumps, associtted with the selected RHR pumps, aligned for RNR heat exchanger service for l

each reactor vessel containing irradiated fuel.

BFN 3.5/4.5-12 Amenament No.. 4 Unit 3-W_-

l

-3. 9'/ 4. 9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 Auxiliary Electrical System 4.9 Auxiliary Electrical System s

8E211eability Applicability Applies to all the' auxiliary Applies to the periodic electrical power. system.

testing requirements of th'e auxiliary electrical system.

Obiective Objective To' assure an adequate supply of Verify the operability of the electrical power for operation of auxiliary electrical system.

those systems required for safety.

4 Specification Specification A..

Auxiliary Electrical Eculpment A.

Auxiliary Electrical System 4

1.

The reactor shall not be 1.

Diesel Generators started up (made critical) l from the Cold Condition I

unless the following are a.

Each diesel generator shall satisfied:-

be manually started and loaded to demonstrate j

a.

Diesel generators 3A, operational readiness in

~

l 3B, 3C, anc 3D OPERABLE.

accordance with the frequency specified in b.

Requirements 3.9.A.3 Table 4.9.A on a staggered test basis. The test shall through 3.9. A.6 are continue for at least a i

met, 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period at 75% of

c. 'At least two of the rated load or greater and following offsite power the operation of the diesel sources are available:

fuel oil transfer pumps shall be demonstrated.

(1) The 500-kV system is Also, the diesel generator available to the starting air compressor,

unit 3 shutdown shall be checked for

~

boards through the operation and its unit 3 station-ability to recharge service transformer air receivers.

TUSS 3B with no credit taken for ti,e The diesel generator fast two 500-kV Trinity starts (10 seconds) from I

lines, standby conditions shall be performed once per 184 days I

in these surveillance tests.

All other engine starts for the purpose of this test may be preceeded by an engine idle start.

BFN 3.9/4.9-1 Amendment flo. 124 Unit 3

___m___.__

.e<

-3.9/4.9 AUXILIARY ELECTRICAL SYSTEM-LIMITING CONDITIONS ~FOR OPERATION SURVEILLANCE REQUIREMENTS 3. 9 '. A.

Ai;wiliary Electrical Eeuipment 4.9.A.

Auxiliary Electrical System 4.9.A.1. (Cont'd)

)

3.9.A.1.c.

.(Cont'd).

Additional reporting I

requirements due to

]

failures are noted in Table'4.9.A.

4 All diesel generator j

starts shall be logged.

{

(2) The Trinity 161-kV b.

Once per operating line is available to the cycle, a test will unit 3 shutdown boards be conducted simulating a i

loss of offsite power and through a common _

station-service or~

similar conditions-that cooling tower transformer.

would exist with the presence of an actual l

NOTE FOR (2):

safety-injection signal I

to demonstrate the If units 1 and 2 are following:

both in operation'and claiming-the Trinity (1) Deenergization of the.

line as an offsite emergency. buses and

' source, TUSS 38 mest load shedding from be claimed as the other the emergency. buses.

i offsste source for unit 3.

(2) The diesel starts

)

from ambiant (3) The Athens 161-kV line condition on the is available to unit 3 auto-start signal, shutdown boards through energizes the a common station-service emergency buses with or cooling tower permanently connected transformer.

loads, energizes the auto-connected NOTE FOR (3):

emergency loads through load If either unit 1 or sequencing, and unit 2 is claiming operates for greater J

the Athens'line as than or equal to five l

an offsite source, minutes while its

{

it may not be claimed generator is loaded I

as an offsite source with the emergency j

for unit 3.

Loads.

l l

BFN 3.9/4.9-2 Amendment No. 124 Unit 3

l 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Ayx11}3ry Electrical 4.9.A.

Auxiliary Electrical Equipment System 3.9.A.1.c.(3)

(Cont'd)

4. 9. A.1.b. (Cont' d) f NOTES FOR (2) AND (3):

i If both Athens and (3) on diesel generatoe l

Trinity lines are breaker trip, the l

clained as the two loads are shed from l

?

offsite sources for the emergency buses unit 3, no credit may and the diesel output be taken for the breaker closes on the Athens-Trinity line autostart signal, the j

tie breaker, emergency buses are l

Specifically, the energized with Athens line supplies permanently connected unit 3 through common loads, the auto-station-service connected emergency transformer A or loads are energized cooling tower through load transformer 1, and sequencing, and the the Trinity line diesel operates for must supply unit 3 greater than or equal through common station-to five minutes while service transformer B or its generator is loaded with the cooling tower transformer. 2.

with the emergency loaot.

c.

Once a month the quantity of diesel fuel available shall be logged.

d.

Each diesel generator shall be given an annual inspection in accordance with instructions based on the manufacturer's recommendations.

e.

Once a month a sample of diesel fuel shall be checked for quality.

The quality shall be within acceptable limits specified in Table 1 of the latest revision to ASTM D975 and logged.

3.9/L.9-3 Amendment No. 124 BFN Unit 3

s

~

3.9/4.9 AUXILIARY ELECTRICAL SYSTEM

.LIMITINGCONDITIbMSFOROPERATION-SURVEILLANCE REQUIREMENTS

3.9.A.

Auxiliary Electrical Equipment 4.9.A.

Auxiliary Electrig l System 2.

The reactor-shall not.be 2~

DC Power System - Unit started up (made critical)

Batteries (250-V),.

from the Hot Standby condition

. Diesel-Generator unless all of the following Batteries (125-V)and conditions are satisfied:

Shutdown Board Batteries.(250-V) a.

At'least one offsite power a.

Every week the source is available as specific gravity, specified in 3.9.A.1.c.

voltage, and

. temperature of the pilot cell, and

-overall battery voltage shall be measured and logged.

b.

Three units 3' diesel b.

Every three months generators shall be the measurements-OPERABLE.

shall be made of.

voltage of each call to nearest 0.1 volt, specific gravity of each cell, and temperature of every fifth cell.

These measurements

.shall be logged.

c.

An additional source of c.

A battery rated power consisting of one discharge (capacity) of the following:

test shall be performed and the (1) A second offsite voltage, time, and power source available output current as specified in measurements shall 3.9.A.1.c.

be logged at intervals not to~

(2) A fourth unit 3 exceed 24 months.

diesel generator OPERABLE.

d.

Requirements 3.9.A.3 through 3.9.A.6 are met.

BFN.

UnitL3

3. 9 / 4. 9-4 u

3.9/4.9 AUXILIARY' ELECTRICAL SYSTEM

- LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.A.

Auxiliary Electrical Eauipment 4.9.A.

Auxiliary Electrical System 4.9.A.4 (Cont'd) c..

The loss of voltage and degraded voltage relays which start the diesel generators from the 4 kV^

shutdown boards shall be calibrated annually for trip and reset and the measurements logged.

These relays khall be calibrated as specified in Table 4.9.A.4.c.

d.

4-kV shutdown board voltages shall be recorded once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

5.

Accident signal logic

5. 480-V RMOV Boards 3D and 3E system is OPERABLE.

a.

Once per operating cycle, the automatic transfer feature for 480-V RMOV boards 3D and 3E shall be functionally tested to verify auto-transfer capability.

6.

There shall be a minimum of 103,300 gallons of diesel fuel in the unit 3 standby diesel-ger.erator fuel tanks.

1 BFN Unlt 3 3.9/4. 9-7 p

__---__.._____m______

________.___m__

-3.9/4.9 AUXILIARY ELECTRICAL SYSTEM

' b

' L_I_M_I. TING CONDITIONS ' FOR OPERATION -

SURVEILLANCE REQUIREMENTS

(

g 3.9.8.

Operation with'Inocerable 4.9.B.

Operation with Inoperable' Equipmeqi Equipment i

3:

Whenever the reactor is in

~STARTUP mode or RUN mode and I

not in a Cold Condition, the availability of electric l

power shall1be-as specifLed in 3.9.A except as specified herein.

1.

From and after the date

1. When only one that only one offsite offsite power source power source is available, is OPERABLE, all unit 3 reactor operation is diesel generators must permissible under this be demonstrated to be condition fo'r seven days.

OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and power availability for the associated boards shall be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

2.

When one unit 3 diesel

2. When one unit 3 diesel generator (3A, 3B, 3C, generator is found to be or 3D) is INOPERABLE, INOPERABLE, all of the continued reactor operation remaining unit 3 diesel

'is permissible during the generators shall be succeeding 7 days, provided demonstrated to be that two offsite power OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

sources are available as and power availability for specified in 3.9.A.1.c.

the associated boards and all of the CS, RHR shall be verified within (LPCI and containment I hour and at least once cooling) systems, and the per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, remaining three unit 3 diesel gener,ators are OPERABLE.

If this require-ment cannot be met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the Cold Condition within

'24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l BFN. Unit 3

3. 9/4. 9-8 3mendment No. 124

l 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM

- l c

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9.B.

Operation With Inocerable 4.9.B.

Operation With-Inoperable Equipment Eauipment 3.

From and after the date 3.

When a required that the 4-kV bus tie offsite power source board becomes inoperable, is unavailable reactor operation is because the 4-kV permissible indefinitely bus tie board or a provided one of the start bus is required offsite power INOPERABLE, all sources is not unit 3 diesel supplied from the 161-kV generators shall be system through the bus demonstrated OPERABLE tie board, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and power availability for the associated boards shall be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

The remain-ing offsite source and associated buses shall be checked to be i

energized daily.

4.

When one unit 3 4.

When one unit 3 4-kV 4-kV shutdown board is shutdown board is found INOPERABLE, continued to be INOPERABLE, all reactor operation is diesel generators associated with the permissible for a period of 5 days provided that remaining 4-kV shutdown boards shall be demon-2 offsite power sources are available as strated to be OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and specified in 3.9.A.1.c and the remaining unit 3 power availability for 4-kV shutdown boards and the remaining 4-kV associated diesel shutdown boards shall be generators, CS, RHR (LPCI verifie,d within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and containment cooling) and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

systems, and all unit 3 480-V emergency power boards are OPERABLE.

If this requirement cannot be met, an orderly shutdown shall be initiated and s.he reactor shall be shut down and in the Cold Condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

BFN-Unit 3 3.9/4.9-9 Amendment No. 124

3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPtRATION SURVEILLANCE REQUIREMENTS 3.9.B.

Operation With Inocerable 4.9.B.

Operation With Inoperable Equipment Equipment

+

5.

From and after the date 5.

When one 480.V diesel that one of the 480-V, auxiliary board diesel auxiliary boards is found INOPERABLE, becomes INOPERABLE, each unit 3 diesel reactor operation is shall be verified permissible for a period OPERABLE within 24 of 5 days.

hours, and power availability for the l

remaining diesel auxiliary boa'ed shall be verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

6.

From and after the date that the 250-V shutdown board 3EB battery or one of the three 250-V unit batteries and/or its associated battery board is found to be INOPERABLE for any reason, continued reactor operation is permissible during the succeeding seven days.

Except for routine carveillance testing, the NRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the situation, the precautions to be taken during this period, and the plans to return the failed component to an OPERABLE state.

7.

When one division of the q

logic system is INOPERABLE,

/

continued reactor operation is permissible under this condition for seven days, provided the CSCS j

requirements listed in Specification 3.9.B.2 are satisfied.

The NRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the situation, the precautions to be taken during this period, and the plans to return the failed component to an OPERABLE state.

BFN-Unit 3 3.9/4.9-10 Amencment No. 12C

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G,5

L ATTACHMENT TO TABLE 4.9.A DIESEL GENERATOR.REQUALIFICATION PROGRAM

.(1) Per!orm seven consecutive. successful demands without a failure within 30 l

days of diesel geneestor being restored to operable status and. fourteen consecutive successful demands without a failure within 75 days of diesel generator of being restored to OPERABLE status.

(2)

If a failure occurs'during the first seven tests in the requalification-test program, perform seven successful demands without an additional failure'within 30 days of diesel generator of being restored to OPERABLE status and fourteen consecutive successful demands without a failure within 75 days of being restored to OPERABLE status.

(3)

If a failure occurs during the second seven tests (tests 8 through'14) of (1) above, perform fourteen consecutive successful demands without an additional failure within 75 days of the' failure which occurred during the requalification testing.

(4) Following the second failure during the requalification test program, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

(5)

During requalification testing.the diesel generator should not be tested more frequently than at 24-hour intervals.

After a diesel generator has been successfully requalified, subsequent repeated requalification tests will not be requir2d for that diesel generator under the following conditions:

-(a)

The number of failures in the last 20 valid demands is less than 5.

(b) The number of failures in the last 100 valid demands is less than.11.

(c)

In the event that, following successful requalification of a diesel generator, the number of failures is still in excess of the remedial.

action criteria (a and/or b above) the following exception will be allowed until the diesel generator is no longer in violation of the remedial action criteria (a and/or b above).

Requalification testing will not be required provided that after each valid demand the number of failures in the last 20 and/or 100 valid demands has not increased.- Once the diesel generator is no longer in violation of the remedial action criteria above the provisions of those criteria alone will prevail.

BFN 3.9/A.9-16 Amendment No. 124

-Unit 3

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l

3.9 BASES The objective of this specification is to assure an adequate source of electrical power to operate facilities to cool the unit during shutdown and to operate the engineered safeguards following an accident.

There are three scurces of alternating current electrical energy available, namely, the 161-kV transmission system, the 500-kV transmission system, and the diesel generators.

The unit station-service transformer B for unit 3 provides a noninterruptible source of offsite power from the 500-kV transmission system to the unit 3 shutdown boards.

Auxiliary power can also be supplied from the 161-kV transmission system through the common station-service transformers or through the cooling tower transformers by way of the bus tie board.

The 4-kV bus tie board may remain out of service indefinitely provided one of the required offsite power soneces is not supplied from the 161-kV system through the bus tie board.

l The minimum fuel oil requirement of 103,300 gallons is sufficient for seven days of full load c'eration of three diesels and is conservatively based on availability of 4 replenishment supply.

The degraded voltage sensing relays provide a start signal to the diesel generators in the event that a deteriorated voltage condition exists os.

a 4-kV shutdown board.

This starting signal is independent of the starting signal generated by the complete loss of voltage relays and will continue to function and start the diesel generators on complete loss of voltage should the loss of voltage relays become inoperable.

The 15-day inoperable time limit specified when one of the three phase-to-phase degraded voltage relays is inoperable is justified based on the two-out-of-three permissive logic scheme provided with these relays.

A 4-kV shutdown board is allowed to be out of operation for a brief period to allow for maintenance and testing, provided all remaining 4-kV shutdown boards and associated diesel generators, CS, RHR, (LPCI and containment cooling) systems supplied by the remaining 4-kV shutdown boards, and all emergency 480-V power boards are operable.

The 480-V diesel auxiliary board may be out of service for short periods for tests and maintenance.

There are five 250-V de battery systems j

associated with unit 3, each of which consists of a battery, battery charger, and distribution equipment.

Three of these systems provide power for unit control functions, operative power for unit motor loads, I

One and alternative drive power for a 115-V ac unit-preferred mg set.

250-V de system provides power for common plant and transmission system control functions, drive power for a 115-V ac plant-preferred mg set, I

The fifth f

and emergency drive power for certain unit large motor loads.

battery system delivers control power to a 4-kV shutdown board.

I 3.9/4.9 18 Amendment No. 124 BFN unit 3 i

~

\\

(~

- 3.9:

Igggg, (Cont'd)

The 250-V de-system is so arranged and the batteries sized so that the loss of any one unit battery will not prevent the safe shutdown and cooldown of all'three units in the event of the loss of offsite power E

and a design basis accident in any one unit.

I.oss.of control power to any engineered safeguard. control circuits is annunciated in the main control room of the unit affected.

The station battery supplies' loads that are not essential for safe shutdown ~and.cooldown of the nuclear' system.

This battery was not considered in the accident load calculations.

There are two 480-V ac RMOV boards ~that contain mg sets in their feeder lines. These 480-V ac RMOV boards have an automatic transfer from their normal to alternate power source (480-V ac shutdown boards).

The mg sets act as electrical' isolators to prevent a fault from propagating between electrical divisions'due to an automatic transfer.

The 480-.V ac L

RMOV boards involved provide motive power to valves associated with the LPCI mode of the RHR system. Having an mg set out of service reduces I

the assurance that full RHR (LPCI) capacity will be available when required.

Since sufficient equipment is available to maintain the l mininum complement' required for RHR (LPCI) operation, a 7-day servicing period is justified. Having two as sets out of service can considerably reduce equipment availability; therefore, the affected unit shall~be placed in Cold Shutdown within 24. hours.

I The offsite power source requirements are based on the capacity of the

~

respective lines. The Trinity line is limited to supplying two operating units because of the load limitations of CSST's A and B.

-The Athens line is limited to supplying-one operating unit because of the load limitations of the Athens line.

The limiting conditions are intended to prevent the 161-kV system from supplying more than two units in the event of a single failure in the offsite power system.

9 0

BFN 3.9/4.9-19 Amendment No. 124 Unit 3

_.-r-----

s,47 i.

4.9-B65.30 The monthly tests of the diesel generators are primarily to check for failures and deterioration in the system since last use.

The diesels will be loaded to at least 15 percent of rated power while engine and generator temperatures are stabilized (about one hour).

The miniaum percent load will prevent soot formation in the cylinders and injection nossles.

Operation up to an equilibrium temperature ensures that:there is no overheating problem. The tests also provide an engine and generator operating history to be compared with subsequent engine-generator test data to identify and to correct any mechanical or electrical deficiency before it can result in a system failure.

The test during refueling outages is more comprehensive, including procedures that are most effectively conducted at that time. These include automatic actuation and functional capability tests to verify that the generators can start and be ready to assume load in 10 seconds.

The annual inspection will detect any signs of wear long before' failure.

Battery maintenance with regard to the floating charge, equalizing charge, and electrolyte level will be based on the manufacturer's instruction and sound maintenance practices.

In addition, written records will be maintained of the battery performance.

The plant batteries will deteriorate with time but precipitous failure is unlikely.

The type of surveillance called for in this specification is that which has been demonstrated through experience to provide an indication of a cell becoming irregular or unserviceable long before it-becomes a failure.

The equalizing charge, as recommended by the manufacturer, is vital to maintaining the ampere-hour capacity of the battery, and will be applied as recommended.

The testing of the logic system will verify the ability of the logic systems to bring the auxiliary electrical system to running standby readiness with the presence of an accident signal from any reactor or an undervoltage signal on the start buses or 4-kV shutdown boards.

The' periodic simulation of accident signals in conjunction with diesel-generator voltage available signals will confirm the ability of the e'80-V load shedding logic system to sequentially shed and restart 480-V loads if an accident signal were present and diesel-generator voltage were the only source of electrical power.

t 3.9/4.9-20 Amendment No. 124 BFN Unit 3

l l-j.

4.9 BA_Sgl (Cont'd)

References 1.

Normal Auxiliary Power System (BFNP FSAR Subsection b.4) 2.

Standby AC Power Supply and Distribution -(BFNP FSAR Subsection 8.5) 3.

250-Volt CO Power Supply and Distribution (BFNP FSAR Subsection 8.6) 4.

Memorandum from G. M. Wilholte to H. J. Green dated December 4, 1981 (LOC 811208 664) and memorandum from C. E. Winn to H. J. Green dated January 10, 1983 (G02 830112 002) t 1

l 1

BFN - Unit 3 3.9/4.9-21 l Amendment NO. 124 4

}-

s-Report shall be submitted within 10 days after the event describing the magnitude, frequency spectrum, and resultant effect upon plant features important to safety.

7.

Diesel Generator Reliability Improvement program Report shall be submitted within 30 days of meeting failure criteria in Table 4.9.A.

As a minimum, the reliability Improvement Program report for NRC audit shall include:

a.

A summary of all tests (valid and invalid) that occurred within the time period over which the last 20/100 valid tests were performed.

b.

Analysis of failures and determination of root causes of failures.

c.

Evaluation of each of the recommendations of NUREG/CR-0660, " Enhancement of Onsite Emergency Diesel Generator Reliability in Operating

)'

Reactors," with respect to their application to the plant.

d.

Identification of all actions taken or to be taken to (1) Correct the root causes of i

i failures defined in b above and (2) Achieve a general improvement of diesel generator reliability, A supplemental report shall be prepared for an e.

NRC audit within 30 days after each subsequent failure during a valid demand, for so long as the affected diesel generator unit continues to violate the criteria (3/20 or 6/100) for the enliability improvement program remedial action.

The supplemental report need only update the failure / demand history for the affected diesel generator unit since the last report for that diesel generator.

The supplemental report shall also present an analysis of the failuro(s) with a root cause determination, if possible, and shall delineate j

any further procedural, hardware or operational

]

changes to be incorporated into the site diesel generator improvement program and the schedule for implementation of those changes.

I

$$Yt3 6.0- 2]

Amendment No. 124

\\

J

l 8.

Secondary Containment 4.7.C.

Within 90 days i

Leak Rate Testing

of completion of each test.

Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report.

This report should include data on the wind speed, wind direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate.

The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate limits.

6.10 STATION OPERATING RECORDS AND RETENTION 6.10.1 Records and/or logs shall be kept in a manner convenient for review as indicated below:

a.

All normal plant operation including such items as power level, fuel exposure, and shutdowns b.

Principal maintenance activities c.

Reportable Events d.

Checks, inspections, tests, and calibrations of components and systems, including such diverso items as source leakage Reviews of changes made to the procedures or equipment or e.

reviews of tests and experiments to comply with 10 CFR 50.59 f.

Radioactive shipments s.

Test results in units of microcuries for leak tests performed pursuant to Specification 3.8.D 1

l BFN 6.0-28 Amendment "o.

124 Unit 3 i

. _ _ _ _ _ _ _ _ _

v t e Letter Sequence Other
TAC:00092, (Approved, Closed) TAC:00093, (Approved, Closed) TAC:00094, (Approved, Closed)
Initiation Acceptance... Supplement Administration Questions Answers Results Approval Other: ML18033A177, ML20244D941
MONTHYEAR1988-04-13 [Table View]

ML20244D941

Text

Attachment:

Attachment:

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