ML18036B228

Amends 192,207 & 164 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Revising TSs in Accordance W/Guidance of GLs 86-10 & 88-12

ML18036B228
Person / Time
Site:	Browns Ferry
Issue date:	04/01/1993
From:	Hebdon F Office of Nuclear Reactor Regulation
To:
Shared Package
ML18036B229	List: ML18036B228 ML18036B230 ML18036B231
References
DPR-33-A-192, DPR-52-A-207, DPR-68-A-164, GL-86-010, GL-88-012 NUDOCS 9304140278
Download: ML18036B228 (79)

Text

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/f <<<<**4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESS E VALLEY AUTHORITY OCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT 1

MENOMENT TO FACILITY OPERATING LICENSE Amendment No.

192 License No.

DPR-33 The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

C.

D.

E.

The application for amendment by Tennessee Valley Authority (the licensee) dated April 13, 1992 as supplemented March 19,

1993, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) 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; The, issuance 'of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 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.

.. 9304140278 93040k PDR ADOCK 050002S9 P

PDR

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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 paragraphs 2.C.(2), 2.C.(4), 2.C.(13) and 2.E of Facility Operating License No.

DPR-33 are hereby amended to read as follows:*

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No.192, are hereby incorporated in the license.

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

(4)

Deleted (13)

Browns Ferry Nuclear Plant shall 'implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated December 8,

1988, March 6,

1991, March 31, 1993 and Supplement dated November 3, 1989 subject to the following provision:

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

D.

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

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Project Directorate II-4 Division of Reactor Projects - I/ll Office of Nuclear Reactor Regulation Attachments:

1.

Pages 2, 3, 4, 5, and 6 of License DPR-33 2.

Changes to the Technical Specifications Date of Issuance:

April 1, 1993

• Pages 2, 3, 4, 5,

and 6 are attached, for convenience, for the composite license to reflect this change.

ATTACHMENT I TO LICENSE AM NDMENT NO. 192 FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise L'icense DPR-33 as follows:

II Insert Pa e

H.

After weighing the environmental,

economic, technical and other benefits of the facility against environmental costs and considering available alternatives, the issuance of Facility Operating License No. DPR-33, as

amended, is in accordance with 10 CFR Part 50, Appendix D, of the 'Commission's regulations; and I.

The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this amended license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70, including 10 CFR Sections 30.33, 40.32, 70.23, and 70.31.

2.

The Atomic Safety and Licensing Board having dismissed the, proceeding relating to the licensing action in a "Memorandum and Order," dated November 27, 1973, Facility Operating License No. DPR-33 issued to the Tennessee Valley Authority on June 26, 1973 is hereby amended in its entirety to read as follows:

A.

This amended license applies to the Browns Ferry Nuclear Plant, Unit 1, a boiling water nuclear reactor and associated equipment (the facility), owned by the Tennessee Valley Authority.

The facility is located in Limestone County, Alabama, and is described in the "Final Safety Analysis Report" (Amendment 9) as supplemented and amended (Amendments 10 through 52), the licensee's Draft Environmental Statement and supplement thereto dated July 1971, and November 8, 1971, respectively, and the licensee's Final Environmental Statement dated September 1,

1972.

B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Tennessee Valley Authority:

Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to

possess, use, and operate the facility at the designated location in Limestone County, Alabama, in accordance with the procedures and limitations set forth in"this amended license; (2)

Pursuant to the Act and 10 CFR Parts 40 and 70, to receive,

possess, and use at any time source and special nuclear material as reactor fuel in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report as supplemented and amended; (3)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to

receive, possess, and use at any time any byproduct,

source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; BFN Unit 1 Amendment fg, 192

(4)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to

receive, possess, and use in amounts as required any byproduct,

source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5)

Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

w v

The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3293 megawatts thermal.

(2)

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 192, are hereby incorporated in the license.

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

(3)

In the operation of the facility, the licensee shall, pursuant to the Federal Water Pollution Control Act Amendments of 1972 (Public Law 92-500),

comply with all applicable thermal water quality standards of the State of Alabama and the United States.

(4)

Deleted.

(5)

The facility may be modified by plugging the bypass flow holes in the lower core support plate as described in Browns Ferry Nuclear Plant Units 1 and 2 Safety Analysis Report for Plant Modifications to Eliminate Significant In-Core Vibrations (NEDC-21091), October 1975.

The reactor shall not be operated with the plugs installed in the lower core support plate bypass Slow holes without further authorization by the NRC.

BFN Unit 1 Amendment fg,

$7, 27, 192

(6)

The facil'ity may be modified by drilling bypass flow holes in Type 2 and Type 3 fuel assemblies as described in NED0-21091, "Browns Ferry Nuclear Plant, Units 1

& 2 Safety Analysis Report for Plant 'Modifications to Eliminate Significant In-Core Vibrations;"'nd NEDE-21156, "Supplemental Information for Plant Modification,to Eliminate Significant In-Core Vibrations," dated January 1976.

(7)

The facility may be modified as described in "Browns Ferry Nuclear Plant Units 1 and 2 Emergency Core Cooling Systems Low Pressure Coolant Injection Modifications for Performance Improvement (December 1975)" submitted by application dated December 1,

1975 and supplements dated February 12,

1976, March 24, 1976, March 30,

1976, May 21,

1976, June ll, 1976, and July 21, 1976.

(8)

The licensee shall maintain in effect and fully implement all provisions of the Commission approved physical security plan including amendments made pursuant to the authority of 10 CFR 50.54(p).

The approved plan, which contains information protected under 10 CFR 73.21, is entitled "Browns Ferry Nuclear Plant Physical Security Plan," dated'ay 15, 1982 (TVA letter dated June 11, 1982) and revisions submitted by TVA letters dated August 31, 1982 and October 19, 1982.

Notwithstanding the statement in Section 9.1 of the physical security plan, the licensee shall maintain positive access control over containment in accordance with the requirements of 10 CFR 73.55(d)(8).

(9)

The facility may be modified as described in "Browns Ferry Nuclear Plant Units 1 and 2 Emergency Core Cooling Systems Low Pressure Coolant Injection Modifications For Performance Improvement (October 1977)" submitted by letter dated December 28, 1977 and supplemented by letter dated December 13, 197.8.

(10)

The licensee shall follow all provisions of the NRC approved Guard Training

& Qualification Plan, including amendments and changes made pursuant to 10 CFR 50.54(p).

The approved Guard Training

& Qualification Plan is identified as "Browns Ferry Nuclear Power Station Guard Training

& Qualification Plan,"

dated August 17,

1979, as revised by pages dated January 24,

1980, May 21, 1980, October 1, 1980, and March 9, 1981 and as may subsequently be revised in accordance with 10 CFR 50.54(p).

The Guard Training

& Qualification Plan shall be followed, in accordance with 10 CFR 73.55(b),

60 days after the date of this amendment.

BFN Unit 1 Amendment RH, 27, Ff, 72, ffg, 192

(11)

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR '50'0 and 10 CFR 50.54(p)

~

The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:

"Browns Ferry Physical Security Plan", with revisions submitted through May 24, 1988; "Browns Ferry Security Personnel Training and Qualification Plan", with revisions submitted through April 16, 1987; and "Browns Ferry Safeguards Contingency Plan", with revisions submitted through June 27, 1986.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

(12)

The licensee is authorized to temporarily store low-level radioactive waste in an existing covered pavilion that is situated outside the security fence, as presently located, but inside the site exclusion area.

The total amount of low-level waste to be stored shall not exceed 1320 curies of total activity.

This authorizati'on expires two years from the effective date of this amendment and is subject to all the conditions and restrictions in TVA's application dated January 21, 1980.

(13)

Browns Ferry'uclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated December 8,

1988, March 6, 1991, March 31, 1993 and Supplement dated November 3, 1989'ubject to the following provision:

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

D.

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

'OR'HEATOMIC ENERGY COMMISSION l~b A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Date of Issuance:

DEC 20 1973 BFN Unit 1 Amendments HS, 78,

~S7,

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THIS PAGE INTENTIONALLYLEFT BLANK BFN Unit 1 Amendment 192

ATTACHMENT 2 TO ICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. DPR-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.*

REMOVE ivvii 3.11/4.11-1 3.11/4.11-2 3.11/4.11-3 3.11/4.11-4 3.11/4.11-5 3.11/4.11-6 3.11/4.11-7 3.11/4.11-8 3.11/4.11-9 3.11/4.11-10 3.11/4.11-11 3.11/4.11-12 3.11/4.11-13 3.11/4.11-14 3.11/4.11-15 3.11/4.11-16 3.11/4.11-17 3.11/4.11-18 3.11/4.11-19 3.11/4.11-20 3.11/4.11-21 3.11/4.11-22 3.11/4.11-23 3.11/4.11-24 6.0-3 6.0-9 INSERT iii*

iv vli viii*

3.11/4.11-1 3.11/4.11-2 6.0-3 6.0-4*

6.0-9 6.0-10*

E.

Je't Pumps

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F.

Recirculation Pump Operation G.

Structural Integrity.

H.

Snubbers 3.7/4.7 Containment Systems,.

A.

Primary Containment.

B.

Standby Gas Treatment System C.

Secondary Containment.

D.

Primary Containment Isolation Valves E.

Control Room Emergency Ventilation F.

Primary Containment Purge System 3.6/4.6-11 3.6/4.6-12 3.6/4.6-13 3-6/4.6-15 3.7/4.7-1 3.7/4 '-1 3.7/4.7-13 3-7/4.7-16 3.7/4.7-17 3.7/4.7-19 3.7/4.7-21 G.

Containment Atmosphere Dilution System (CAD).

3.7/4.7-22 H.

3.8/4.'8 Radioactive Materials Containment Atmosphere Monitoring (CAM)

System H2 Analyzer 3.7/4.7-24 3.8/4.8-1 A.

Liquid Effluents 3.8/4.8-1 B.

Airborne Effluents C.

Radioactive Effluents Dose D.

Mechanical Vacuum Pump 3.8/4.8-3 3.8/4.8-6 3.8/4.8-6 E.

Miscellaneous Radioactive Materials Sources.

3.8/4.8-7 F.

Solid Radwaste 3.9/4.9 Auxiliary Electrical System 3.8/4.8-9 3.9/4.9-1 A.

B.

Auxiliary Electrical Equipment 3.9/4.9-1 Operation with Inoperable. Equipment.

3.9/4.9-8 C.

3.10/4.10 Core Alterations A.

Refueling Interlocks B.

Core Monitoring.

Operation in Cold Shutdown 3.9/4.9-15 3.10/4.10-1 3.10/4.10-1 3.10/4.10<<4 BFN Unit 1 pi'/,ryDMEt7 gg y 6 g

Sect o

@adage

]Loo C ~

Spent Fuel Pool Water.

3.10/4.10-7 D.

Reactor Building Crane 3.10/4.10-8 Spent Fuel Cask.

3.10/4.10-9 F.

Spent Fuel Cask Handling-Refueling Floor 3.10/4.10-10 3.11/4.11 Deleted.

3.11/4.11-1 5.0 Major Design Features 5.1 Site Features.

5.2 Reactor.

5.0-1 5.0-1 5.0-1 5.3 Reactor 'Vessel 5.4 Containment.

5.5 Fuel Storage

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5.0-1 5.0-1 5.0-1 5.6 Seismic Design 5.0-2 BFH Unit 1 iv Amendment 192

(0ont'd) 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.G 4.2.H Surveillance Requirements for Control Room Isolation Instrumentation.

t Minimum Test and Calibration Frequency for Flood Protection Instrumentation 3.2/4.2-56 3.2/4.2-57 4.2.J Seismic Monitoring Instrument Surveillance Requirements 3.2/4.2-58 4.2.K Radioactive Gaseous Effluent Instrumentation

~ ~

Surveillance 3.2/4.2-62

4. 2.L ATWS-Recirculation Pump Trip (RPT)

Instrumentation Surveillance

3. 5-1 3.5.I 4.9.A Minimum RHRSW and EECW Pump Assignment MAPLHGR Versus Average Planar Exposure

'Auxiliary Electrical 'Systems 6.2.A Minimum Shift Crew Requirements.

4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start 3.2/4.2-63a 3.5/4.5-11 3.5/4.5-21 3.9/4.9-16'.9/4.9-18 6.0-4 BFN Unit 1 vii Amendment 192

2.1.1 APRM Fl'ow Reference Scram and APRM Rod Block Settings

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1.1/2.1-6 2.1-2 4.1-1 APRM Flow Bias Scram Vs. Reactor Core Flow.

1.1/2.1-7 Graphical Aid in the Selection of an Adequate Interval Between Tests 3.1/4.1-13 4.2-1 3.5.K-1 3.5.2 3.6-1 4.8.l.a Sys tern Unavailability.

MCPR Limits ~

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Kf Factor.

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Minimum Temperature F Above Change in Transient Temperature.

,Gaseous Release Points and Elevations 3.2/4.2-64 3.5/4.5-24 3.5/4.5-25 3.6/4.6-24 3.8/4.8-10 4.8.-1.b Land Site Boundary 3.8/4.8-11 BFN Unit 1 viii

RE RO C

0 S

S S

IMITING CONDI IONS FOR OPERATION 0

SURVEILLANCE RE UIREME S

Deleted Deleted BFH Unit 1 3.11/4.11-1 Amendment 192

THIS PAGE INTENTIONALLYLEFT BLANK BFN Unit 1 3.11/4.11-2 Amendment 192

6.2.2 (Cont.)

d.

Two licensed reactor operators shall be in the control room during any cold startups, while shutting down the reactor, and during recovery from unit trip.

In addition, a person holding a senior operator license shall be in the control room for that unit whenever it is in an operational mode other than cold shutdown or refueling.

e.

A Health Physics Technician+ shall be present at the facility at all times. when there is fuel in the reactor.

f.

A person holding a senior operator license or a senior operator license limited to fuel handling, shall be present during alteration of the core to directly supervise the activity and during this time shall not be assigned other duties.

g.

Deleted.

• The Health Physics Technician may be absent from the facility for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided immediate action is taken to fillthe required position.

BFH Unit l 6.0-3 Amendment 192

Zemi.Lian Senior Operator Senior Operator Licensed Operators Additional Licensed Operators Assistant Unit Operators

'(AUO)

Shift Technical Advisor (STA)

Health Physics Technician 1

1 1

1 1

0' 2

2 3

3 3

3 0

1 2

2 4

4 5

5 0

1 1

1 1

1 1

1 SRO SRO RO or SRO RO or SRO None None None a.

A senior operator will be assigned responsibility for overall plant operation at all times there is fuel in any unit.

b.

Except for the sen'ior operator discussed in note "a", the shift crew composition may be one less than the minimum requirements of Table 6.2.A for aperiod of time not to exceed two hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.A.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

c.

One of the Additional Licensed Operators must be assigned to each control room with an operating unit.

d.

The number of required licensed personnel, when the operating units are controlled from a common control room, are two senior operators and four operators.

BFN Unit 1 6.0-4 AMENDMENTNO. 74 g

6.5.1.6 (Cont.)

1.

Review of reportable

events, unusual events, operating anomalies, and abnormal performance, of plant equipment.

m.

Investigate reported or suspected incidents involving safety questions or violations of the Technical Specifications.

n.

Review of unit operations to detect potential hazards to nuclear safety.

Items that may be included in this review are HRC inspection reports, QA audit, HSRB audit results, American Huclear Insurer (AHI) inspection results, and significant corrective action reports (CARs).

o.

Performance of special reviews, investigations, or analysis, and report thereon as requested by the Plant Manager or the Huclear Safety Review Board.

p.

Review of the 'Fire Protection Program, "Fire Protection Report, Volume-1", and implementing procedures, "Safe Shutdown Instructions",

and the submittal of PORC approved changes to Huclear Safety Review Board.

BFH Unit 1 6.0-9 Amendment 192

AUTHORITY 6.5.1.7 The PORC shall:

a.

Recommend to the Plant Manager in writing, approval', or disapproval of items considered under 6.5.1.6.a through i above.

l.

The recommendation shall be based on a majority vote of the PORC at a formal meeting.

2..

The recommendation shall be based on a unanimous vote of the PORC when the PORC members are acting individually.

3.

Each member or alternate member shall have one vote.

b.

Furnish for consideration a determination in writing with regard to whether or not each item, considered under 6.5.1.6.f above constitutes an unreviewed safety question.

c.

Make recommendations to the Plant Manager in writing that action reviewed under 6.5.1.6.k above did not constitute an unreviewed safety question.

d.

'Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Site Director and the Nuclear Safety Review Board of disagreements between the PORC and the Plant Manager.

However,.the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.

BFN Unit 1 6.0-10 A<~EZOA~Em Na. T49

ggS AEGIS

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%**~4 UNITED STATES NUCLEAR REGULATORY COMlVllSSION WASHINGTON, D.C. 205554001 TENNESSEE VALLEY AUTHORITY OCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT UNI MENOMENT TO AC LITY OPERATING LICENS Amendment No. 207 License No.

OPR-52 The Nuclear Regulatory Commission. (the Commission) has found that:

A.

B.

C.

D.

The application for amendment by Tennessee Valley Authority (the licensee) dated April 13,

1992, as supplemented March 19,

1993, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment

.can be conducted without endangering the health and safety of the publ,ic, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraphs 2.C.(2), 2.C.(5), 2.C.(5)(a),

2.C.(14) and 2.E of Facility Operating License No.

DPR-52 are hereby amended to read as follows:*

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and B,

as revised through Amendment No.207, are hereby incorporated in the license.

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

(5)

The facility may be modified by plugging the bypass flow holes in the lower core support plate as described in Browns Ferry Nuclear Plant Units 1 and 2 Safety Analysis Report for Plant Modifications to Eliminate Significant In-Core Vibrations (NEDC-21091),

October 1975.

The reactor shall not be operated with the plugs installed in the lower core support plate bypass flow holes without further authorization by the NRC.

(5)(a)

Deleted (14)

Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated December 8,

1988, March 6,

1991, March 31, 1993 and Supplement dated November 3, 1989 subject to the following provision:

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

D.

This amendment is effective as of the date of issuance and shall expire midnight on June 28, 2014.

• Pages 3, 4, 5 and 6 are attached, for convenience, for the composite license to reflect this change.

4

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3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Attachments:

1.

Pages 3, 4, 5, and 6 of License DPR-52 2.

Changes to the Technical Specifications Frederick J.

Hebdon, Director Project Directorate II-4 Division of Reactor Projects I/ll Office of Nuclear Reactor Regulation Date of Issuance:

April 1, 1993

ATTACHMENT I TO LICENSE AMENDMENT NO.

207 FACILITY OPERATING LICENSE NO.

DPR-52 DOCKET NO. 50-260 Revise License DPR-52 as follows:

Remove Pa e

Insert Pa e

(2)

Pursuant to the Act and 10 CFR Parts 40 and 70, to receive,

possess, and use at any time source and special nuclear material as reactor fuel in accordance with the limitations for storage and amounts required for reactor operation, as

,described. in the Final Safety Analysis Report as supplemented and amended; (3)

Puisuant to the Act and 10 CFR Parts 30, 40, and 70, to

receive, possess, and use at any time any byproduct,

source, and special nuclear material as sealed neutron sources for reactor startup,, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to

receive, possess, and use in amounts as required any byproduct,

source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5)

Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) v The licensee is authorised to operate the facility at steady state reactor core power levels not in excess of 3293 megawatts thermal.

(2)

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The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 207, are hereby incorporated in the license.

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

BFN Unit 2 Amendment f, f8, 207

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(3)

(4)

(5)

(5)(a)

In the operation of the facility, the licensee shall, pursuant to the Federal Water Pollution Control Act Amendments of 1972 (Public Law 92-500),

comply with all applicable thermal water quality standards of the State of Alabama and the United States.

The licensee is hereby granted an exemption from the requirements of General Design Criterion 4 with respect to high energy pipes outside conta'inment in accordance with the condition set forth in the Technical Specifications, Section 3 ' '.2 which requires completion of those items listed in "Concluding Report on the Effects of Postulated Pipe Failure Outside of Containment for the Browns Ferry Nuclear Plant Units 2 and 3" and related to Unit 2 prior to startup of Unit 2 followi'ng the first refueling outage.

The facility may be modified 'by plugging the bypass flow holes in the lower core support plate as described in Browns Ferry Nuclear Plant Units 1 and 2 Safety Analysis Report for Plant Modifications to Eliminate Significant In-Core Vibrations (NEDC-21091), October 1975..

The reactor shall not be operated with the plugs. installed in the lower core support plate bypass flow holes without further authorization by the NRC.

Deleted (6)

The facility may be modified by drilling bypass flow holes in Type 2 and Type 3 'fuel assemblies as described in NED0-21091, "Browns Ferry Nuclear Plant, Units 1

& 2 Safety Analysis Report for Plant Modifi'cations to Eliminate Significant In-Core Vibrations; and NEDE-'21156, "Supplemental Information for Plant Modification to, Eliminate Significant In-Core Vibrations,"

dated January 1976

'7)

'The facility may be modified as described in "Browns Ferry Nuclear Plant Units 1 and 2 Emergency Core Cooling Systems Low Pressure Coolant Injection Modifications for Performance Improvement (December 1975)" submitted by application dated December 1,

1975 and supplements dated February 12,

1976, March 24, 1976, March 30, 1976, May 21,. 1976, June 11,

1976, and July 21, 1976

'PN Unit 2 Amendment f, N, f7, 2C, f92, 207'

ll

(8)

The licensee shall maintain in effect and fully implement all provi'sions of the Commission approved physical security plan including amendments made=pursuant to the authority of 10 CFR 50.54(p).

The approved plan, which contains information protected under 10 CFR 73.21, is entitled "Browns Ferry Nuclear Plant Physical Security Plan," dated May 15, 1982 (TVA letter dated June ll, 1982) and revisions submitted by TVA letters dated 'August 31, 1982 and October 19, 1982.

Notwithstanding the statement in Section '9.1 of the physical security plan, the licensee shall maintain positive access control over containment in accordance with the requirements of 10 CFR 73.55(d)(8).

(9)

The facility may be modified as described in "Browns Ferry Nuclear Plant Units 1 and 2 Emergency Core Cooling Systems Low Pressure Coolant Injection. Modifications For Performance Improvement (October 1977)" submitted by letter dated December 28, 1977 and supplemented by letter dated December 13, 1978.

(10)

The licensee shall follow all provisions of the NRC approved Guard Training

& Qualification Plan, including amendments and changes made pursuant to 10 CFR 50.54(p).

The approved Guard Training

& Qualification Plan is identified as "Browns Ferry Nuclear Power Station Guard Training

& Qualification Plan,"'ated August 17, 1979, as revised by pages dated January 24,

1980, May 21, 1980, October 1, 1980, and March 9, 1981 and as may subsequently be revised in accordance with 10 CFR 50.54(p).

The Guard Training

& Qualification Plan shall be followed, in accordance with 10 CFR 73.55(b),

60 days after the date of this amendment.

(ll)

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:

"Browns Ferry Physical Security Plan", with revisions submitted through May 24, 1988; "Browns Ferry Security Personnel Training and Qualification Plan", with revisions submitted through April 16, 1987; and "Browns Ferry Safequards Contingency Plan", with revisions submitted through June 27, 1986.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

BFN Unit 2 Amendment 45, 89,.N9, f98, 207

(12)

The licensee is authorized to temporarily store low-level radioactive waste in an existing covered pavilion that is situated outside the security fence, as presently located, but inside the site exclusion area.

The total amount of low-level waste to,be stored shall not exceed 1320 curies of total activity.

This authorization expires two years from the effective date of this amendment and is subject to all the conditions and restrictions in TVA's application dated January 21, 1980

'13)

Commission Order dated March 25, 1983 is modified as follows:

in Attachment 1, for item II.F.1 ~ 1 and II'.1 ~ 2 change "12'/31/84" to "Prior to startup in Cycle 6 '

(14)

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

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

This amended license is effective as of the date of issuance and shall expire midnight on June 28, 2014

'OR THE ATOMIC ENERGY COMMISSION s/

A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing

Attachment:

Appendices A

6 B Technical Specifications Date of Issuance:

JUN 28, 1974 BFM Unit 2 Amendments SS, 74, fN, fN, 207

ATTACHMENT 2 TO LICENSE AMENDMENT O.

FACILITY OPERATING LICENSE NO.

DPR-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 lines indicating the area of change.

Overleaf pages.*

REMOVE lv Vl 1 1.0-12a 3.11/4.11-1 3.11/4.11-2 3.11/4.11-3

'3.11/4.11-4 3.11/4.11-5 3.11/4.11-6 3.11/4.11-7 3.11/4.11-8 3.11/4.11-9 3.11/4.11-10 3.11/4.11-11 3.11/4.11-12 3.11/4.11-13 3.11/4.11-14 3.11/4.11-15 3.11/4.11-16 3.11/4.11-17 3.11/4.11-18 3.1'1/4.11-19 3.11/4.11-20 3.11/4.11-21 3.11/4.11-22 6.0-3 6.0-8 6.0-9 6.0-14 6.0-20 INSERT 1 1 1*

lv Vl 1 Vl 1 1*

1.0-12a 1.0-12b*

3.11/4.11-1 3.11/4.11-2 6.0-3 6.0-4*

6.0-7*

6.0-8 6.0-9 6.0-10*

6.0-13*

6.0-14 6.0-19*

6.0-20

Section

~Pa e No 3.7/4.7 E

Jet Pumps.

F.

Recirculation Pump Operation G.

Structural Integrity.

H.

Snubbers Containment Systems A.

Primary Containment.

B.

'Standby Gas Treatment System C.

Secondary Containment.

3.6/4.6-11 3.6/4.6-12 3.6/4.6-13 3.6/4.6-15 3.7/4.7-1 3.7/4.7-1 3.7/4.7-13 3.7/4.7-16 D.

Primary Containment Isolation Valves 3.7/4.7-17 E.

Control'oom Emergency Ventilation

'3.7/4.7-19 F.

Primary Containment Purge System 3.7/4.7-21 G.

Containment Atmosphere Dilution System (CAD) 3.7/4.7-22 3.8/4.8 H.

Containment Atmosphere Monitoring (CAM)

System H2 Analyzer Radioactive Materials A.

Liquid Effluents B.

Airborne Effluents

.3.7/4.7-24 3.8/4.8-1 3.8/4.8-1 3.8/4.8-3 C.

Radioactive Effluents Dose 3.8/4.8-6 D.

Mechanical Vacuum Pump 3.8/4.8-6 E.

Miscellaneous Radioactive Materials Sources.

3.8/4.8-7 F.

Solid Radwaste 3.8/4.8-9 3.9/4.9 Auxiliary Electrical System 3.9/4.9-1 A.

Auxiliary Electrical Equipment 3.9/4.9-1 B.

Operation with Inoperable Equipment.

3.9/4.9-8 C.

Operation in Cold Shutdown 3.9/4.9-15 D.

Unit 3 Diesel Generators Required for Unit 2 Operation 3.9/4.9-15a BFN Unit 2 AMENDMFNTNo; I 8 6

~

~

~Sectio

~aero 3.10/4.10 Core Alterations,.

3.10/4.10-1 A.

Refueling Interlocks 3.10/4.10-1 B.

Core Monitoring 3.lo/a.lo-a C.

Spent Fuel Pool Water 3.10/4.10-7 D.

Reactor Building Crane 3.10/4.10-8 E.

Spent Fuel Cask 3.10/4.10-9 F.

Spent Fuel Cask Handling-Refueling Floor 3.10/4.10-10 3.11/4.11 Deleted.

3.11/4.11-1 5.0 Major Design Features 5.0-1 5.1 Site Features 5.0-1 5 ~ 2 Reac'tor

~

~

~

~

~

~

~

~

~

~

~

~

~

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~

5.0-1 5.3 Reactor Vessel 5.0-1 5.4 Containment 5.5 Fuel Storage.

5.0-1 5.0-1 5.6 Seismic Design 5.0-2 BFH Unit 2 iv Amendment 207

LIST OF TABLES (Cont'd)

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

~Pa e Ho 3.2/4.2-53 4.2.F Minimum Test and Calibration Frequency for Surveillance Instrumentation.

3.2/4.2-54 4.2.G 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 Requirements.

3.2'/4.2-58 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance.

3.2/4.2-62 4.2.L ATWS-Recirculation Pump Trip (RPT)

Instrumentation Surveillance 3.2/4.2-63a 3.5-1 Minimum RHRSW and EECW Pump Assignment.

3.5/4.5-11 3.5.I 4.9.A MAPLHGR Versus Average Planar Exposure.

3.5/4.5-21 Diesel Generator Reliability.

3.9/4.9-16 6.2.A Minimum Shift Crev Requirements 4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start.

3.9/4.9-18 6.0-6 BFN Unit 2 vii Amendment 207

IST OF ILLUST TIONS

~ri are 2.1.1 2.1-2 Title APRM Flow Reference

'Scram and APRM Rod Block Settings

~

~

~

~

~

~

~

~

~

~

~

~

~ '

~

~

~

~

~

~

APRM Flow Bias Scram Vs. Reactor Core Flow.

~Pa e

Na 1.1/2.1-6 1.1/2.1-7 4.1-1 4.2-1 3.5.K-1 3.5.M-1 3.5.2 3.6-1 4.8.l.a 4.8.1.b Graphical Aid in the Selection of an Adequate Interval Between Tests System Unavailability.

MCPR Limits.

BFN Power/Flow Stability Regions Kf Factor.

Minimum Temperature

'F Above Change in Transient Temperature.

Gaseous Release Points and Elevations Land Site Boundary 3.1/4.1-13 3.2/4.2-64 3.5/4.5-22 3.5/4.5-22a 3.5/4.5-23 4

3.6/4.6-24 3.8/4.8-10 3.8/4.8-11 BFN Unit 2 viii AMEgDMEtbtTgP P O~

BFN has developed an Appendix R Safe Shutdown Program.

This Program is to ensure that the equipment required by the Appendix R Safe Shutdown Analysis is maintained and demonstrated functional as follows:

1.

The functional requirements of the Safe Shutdown systems and equipment,.

as well as -appropriate compensatory measures should these systems/components be unable to perform their intended function are outlined in Section III of the Program.

2.

Testing and monitoring of the Appendix R Safe Shutdown systems and equipment are defined in Section V of the Program.

3.

Deleted BFN Unit 2 1.0-12a Amendment 207

THIS PAGE IHTEHTIOHALLYLEFT BLAHK BFN Unit 2 1.0-12b

ll 4 ll FIRE PROTECTION SYSTEMS IMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREME S

Deleted BFH Unit, 2 3.11/4.11-1 Amendment 207

THES PAGE INTENTIONALLYLEFT BLANK

'BFN Unit 2 3 >>~4 >>-2 Amendment 207

6.2.2 (Cont.)

d.

Two licensed reactor operators shall be in the control room during any cold startups, while shutting down 'the reactor, and during recovery from -unit trip.

In addition, a person holding a senior operator 1'icense shall be in the control room for that unit whenever it is in an operational mode other than cold shutdown or refueling.

e.

A Health Physics Technician+ shall be present at the facility at all times when there is fuel in the reactor.

f.

A person holding a senior operator license or a senior operator license limited to fuel handling, shall be present during alteration of the core to directly supervise the activity and during this time shall not be assigned other duties.

g.

Deleted.

• The Health Physics Technician may be absent from the facility for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided immediate action is taken to fillthe required position.

BFH Unit 2 6.0-3 Amendment 207

inimum Shift Crew Re uireme ts Position Senior Operator Senior Operator

'Licensed Operators Additional Licensed Operatorsc Assistant Unit Operators (AUO)

Shift Technical Advisor (STA)

Health Physics Technician Units in 0 eration g

1 2d 1

1 1

1 0

1 2

2 3

3 3

3 0

1 2

2 4

4 S

5 0

1 1

1 1

1 1

1 e of License SRO SRO'O or SRO RO or SRO None None None Note for Table 2 A a.

A senior operator will be assigned responsibility for overall plant operation at all times there is fuel in any unit.

b.

Except for the senior operator discussed in note "a", the shift crew composition may be one less than the minimum requirements of Table 6.2.A for a period of time not to exceed two hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.A.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

c.

One of the Additional Licensed Operators.must be assigned to each control room with an operating unit.

d.

The number of required licensed personnel, when the operating units are controlled from a common control room, are two senior operators and four-operators.

BFN Unit 2 6.0-4 AMENDMElpgg. ~ g g

6.5.1.4 For expedited meetings, when it is not practical to convene as a

group, the chairman or alternate chairman may conduct committee business by polling the members individually (by telephone or in person) or via a serialized review.

QUORUM 6.5.1.5 The quorum necessary for the PORC to act in a formal meeting shall consist of the chairman or alternate chairman and at least five members or their alternates.

Members shall be considered present if they are in telephone communication with the committee.

RESPOHSIBILITIES 6.5.1.6 The PORC shall be responsible for the activities listed below.

The PORC may delegate the performance of reviews, but will maintain cognizance over and responsibility for them, e.g.,

subcommittees.

a.

Review of administrative procedures for the control of the technical and cross-disciplinary review of (1) all procedures required by Specification 6.8.1.1, and changes

thereto, (2) any other procedures and changes thereto determined by the Plant Manager to affect nuclear safety.

b.

Review of the administrative procedures required by Appendix A of Regulatory Guide 1.33, Revision 2, February 1978 and changes thereto.

c.

Review of emergency operating procedures and changes thereto.

d.

Review implementing, procedures of the Radiological Emergency Plan and the Industrial Security Program.

BFH Unit 2 6.0-7 AMENDMEMTNO. y 4 g

6.5.1.6 (Cont.)

e.

Review of all proposed changes to the Technical Specifications.

f.

Revi'ew of safety evaluation for proposed tests or experiments to be completed under the provisions of 10 CFR 50.59 g.

Review proposed changes to the Radiological Effluent Manual.

h.

Review adequacy of the Process Control Program and Offsite Dose Calculation Manual at least once every 24 months.

i.

Review changes to the radwaste treatment systems.

Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendation, and disposition of the corrective action to prevent recurrence to the Senior Vice President, Nuclear Power, and to the Nuclear Safety Review Board.

k.

Review of all'afety evaluations for modifications to structures, systems or components that affect nuclear safety to verify that such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59, or requires a

change to these Technical Specifications.

BFN Unit 2 6 0-8 Amendment 207

6'.1.6 (Cont) l.

Review of reportable

events, unusual events, operating anomalies, and abnormal performance of plant equipment.

m.

Investigate reported or suspected incidents involving safety questions or violations of the Technical Specifications.

n.

Review of unit operations to detect potential hazards to nuclear safety.

Items that may be included in this review are NRC inspection reports, QA audit, NSRB audit results, American Nuclear Insurer (ANI) inspection results, and significant corrective action reports (CARs).

o.

Performance of special reviews, investigations, or analysis, and report thereon as requested by the Plant Manager or the Nuclear Safety Revi'ew Board.

p.

Review.of the Fire Protection Program, "Fire Protection Report, Volume-1", and implementing procedures, "Safe Shutdown Instructions",

and the submittal of PORC approved changes to Nuclear Safety Review Board.

BFN Unit 2

< ~ o-9 Amendment 207

AUTHORITY 6.5.1.7 The PORC shall:

a.

Recommend to the Plant Manager in writing, approval, or disapproval of items considered under 6.5.1.6.a through i above.

l.

The, recommendation shall be based on a majority vote of the PORC at a formal meeting.

2.

The recommendation shall be based on a unanimous vote of the PORC when the PORC members are acting individually.

3.

Each member or alternate member shall have one vote.

b.

Furnish for consideration a determination in writing with regard to whether or not each item considered under 6.5.1.6.f above constitutes an unreviewed safety question.

c.

Make recommendations to the Plant Manager in writing that action reviewed under 6.5.1.6.k above did not constitute an unreviewed safety question.

d.

Provide written no'tification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Site Director and the Nuclear Safety Review Board of disagreements between the PORC and the Plant Manager.

However, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.

BFN Unit 2 6.0-10 AMENDMPQgP ~gg

REVIEW 0

6.5.2.7 The HSRB shall review:

a.

The safety evaluations for:

(1) changes to procedures, equipment or systems, and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b.

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

c.

Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d.

Proposed changes to Technical Specifications or this Operating License.

e.

Violations of Codes, regulations,

orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f.

Significant operating abnormalities or deviations from normal and expected performance of plant equipment that

~affect nuclear safety.

g.

All Reportable Events h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,

systems, or components that could affect nuclear safety; and i.

Reports and meeting minutes of the PORC.

BFN Unit 2 6.0-13 AMENDMEMTNQ. y g g

AUDITS 6.5.2.8 Audits of unit activities shall be performed under.the cognizance of the HSRB.

These audits shall encompass:

a.

The conformance of plant operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b.

.The performance, training and qualifications of the entire plant staff at least once per 12 months.

c.

The results of actions taken to correct deficiencies occurring in site equipment, structures, systems or method of operation that affect. nuclear safety at least once per 6

months.

d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix

,B, 10 CFR Part 50, at least once per 24 months.

e.

The Site Radiological Emergency Plan and implementing procedures at least once every 12 months.

f.

The Plant Physical Security Plan and implementing procedures at least once every 12 months.

g.

Any other area of site operation considered appropriate by the HSRB or the Senior Vice President, Huclear Power.

h.

The fire protection programmatic controls including the implementing procedures at least once per 24 months.

BFH Unit 2 6.0-14 Amendment 207

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Senior Vice President, Nuclear Power and the NSRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PORC.

This report shall describe (1) applicable circumstances preceding the violation, (2).effects of the violation upon facility

.components,

systems, or. structures, and (3) corrective action taken to prevent recurrence.

c.

The Safety Limit Violation Report shall be submitted to the Commission, the NSRB, and the Senior Vice President, Nuclear Power within 14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

BFN Unit 2 6.0-19 AMENDMENTg0. ~ g g

6.8 PROCEDURES INSTRUCTIONS PROGRAMS 6.8.1 PROCEDURES 6.8.1.1 Mritten procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Limitations on the amount of overtime worked by individuals performing safety-related functions in accordance with NRC Policy statement on working hours (Generic Letter No. 82-12).

c.,

Surveillance and test activities of safety-related equipment.

d.

Security plan implementation.

e.

Emergency plan implementation.

f.

Fire Protection Program implementation.

g.

Radiological Effluent Manual implementing procedures.

h.

Process Control Program (PCP).

i.

Offsite Dose Calculati'on Manual.

j.

Administrative procedures which control technical and cross-disciplinary review.

BFH Unit 2 6.0-20 Amendment 207

~

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~

0 Cy P

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I 0

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VAI.LEY AUTHORIT DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 164 License No. DPR-68 The Nuclear Regulatory Commission (the Commission) has found that:

A.

B.

C.

D.

E.

The application for amendment by Tennessee Valley Authority (the licensee) dated April 13,

1992, as supplemented March 19,

1993, 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; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) 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; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 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.

ii

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraphs 2.C.(2) and 2.C.(7) of Facil.ity Operating License No.

DPR-68 are hereby amended to read as follows:*

(2)

Technical S ecifi'cations The Technical Specifications contained in Appendices A and B,

as revised through Amendment No.164, are hereby incorporated in the l.icense.

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

(7)

Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated.December 8,

1988, March 6,

1991, March 31, 1993 and Supplement dated November 3, 1989 subject to the following provision:

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

3.

The license is also amended by a few format and numbering changes as follows:

page 5

2.D.

becomes 2.C.(8) page 5 2.D.(3) becomes 2.C.(9) page 5 2.E.

becomes 2.0.

Page,6

,2.F.

becomes 2.E.

• Pages 3, 4, 5, and 6 are attached, for convenience, for the composite license to reflect this change.

4l Qi 4.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Attachments:

1.

Pages 3, 4, 5, and 6 of License DPR-68 2.

Changes to the Technical Specifications Date of Issuance:

April i Frederick J.

Hebdon, Director Project Directorate II-4 Division of Reactor Projects I/ll Office of Nuclear Reactor Regulation

4i Qi

ATTACHMENT I TO LICENSE 'AMENDMENT NO.

164 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise License DPR-68 as follows:

Remove Pa e

3 4

4a 5

Insert Pa e

5 6

(3)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)

Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of,the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and. 50.59 of -Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) v The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3293 megawatts thermal.

(2)

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 164, are hereby incorporated in the license.

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

(3)

In the operation of the facility, the licensee shall, pursuant to the Federal Water Pollution Control Act Amendments of 1972 (Public Law 92-500),

comply with all applicable thermal water quality standards of the State of Alabama and the United States.

BFN Unit 3 Amendment 164

(4) The licensee shall maintain in effect and fully implement all provisions of the Commission approved physical security plan including amendments made pursuant to the authority of 10 CFR 50 '4(p) ~

The approved plan, which contains information protected under 10 CFR 73'1, is entitled "Browns Ferry Nuclear Plant Physical Security Plan," dated May 15, 1982 (TVA letter dated June 11, 1982) and revisions submitted by TVA letters dated August 31, 1982 and October 19, 1982.

Notwithstanding the statement in Section F 1 of the physical security

plan, the licensee shall maintain positive access control over containment in accordance with the requirements of 10 CFR 73 '5(d)(8) ~

(5) The licensee shall follow all provisions of the NRC approved Guard Training 6 Qualification Plan, including amendments and changes made pursuant to 10 CFR 50 '4(p) ~

The approved Guard Training 6

Qualification Plan is identified as "Browns Ferry Nuclear Power Station Guard Training 6 Qualification Plan," dated August 17,

1979, as revised by pages dated January 24,

1980, May 21,

1980, October 1,

1980, and March 9, 1981 and as may subsequently be revised in accordance with 10 CFR 50.54(p)

~

The Guard Training

& Qualification Plan shall be followed, in accordance with 10 CFR 73 '5(b),

60 days after the date of this amendment.'6)

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73'5 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50 '4(p) ~

The plans, which contain Safeguards Information protected under 10 CFR 73'1, are entitled:

"Browns Ferry Physical Security Plan", with revisions submitted through May 24, 1988; "Browns Ferry Security Personnel Training and Qualification Plan", with revisions submitted through April 16, 1987; and "Browns Ferry Safequards Contingency Plan", with revisions submitted through June 27, 1986

'Changes made in accordance with 10 CFR 73'5 shall be implemented in accordance with the schedule set forth therein.

(7)

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

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

BFN Unit 3 Amendment H, N, QS,

~64

0 0

(8)

The licensee shall maintain in effect and fully implement all provisions of the Commission's Staff-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p)

~

The approved security plan consists of a proprietary document titled, "Browns Ferry Nuclear Plant Physical Security Plan," which was submitted with the licensee's letter dated April 23, 1974, as supplemented by information submitted with letters dated June 27,

1974, and August 27, 1974.

(9)

The licensee is authorized to temporarily store low-level radioactive waste in an existing covered pavilion that is situated outside the security fence, as presently located, but inside the site excl'usion area.

The total amount of low-level waste to be stored shall not exceed 1320 curies of total activity.

This authorization expires two years from the effective date of this amendment and is subject to all the conditions and restrictions in TVA's application dated January 21, 1980.

D.

This license is subject to the following additional conditions:

(1)

The licensee is required to assure that:

(a)

The plant unique analysis for torus support structures and attached piping for the facility meets the approved Mark I Owners Group short-term acceptance criteria when subjected to dynamic loads associated with a postulated loss-of-coolant accident.

Should the licensee determine that the results of the plant unique analysis are not in conformance with the approved Hark I Owners 'Group short-term acceptance

criteria, a specific action plan will be developed by the licensee for the facility and presented to the Commission.

This action plan will include as a minimum the following information:

(1)

The value of the load factor for which the criteria are satisfied.

(2)

A description of proposed plant modifications or, other acti, on which will result in reduced loads or increased capacities that would satisfy the criteria.

(3) If a plant hardware modification is made, the acceptance criteria will be described on a plant unique basis.

(b)

Upon completion of the Mark I Owners Group long-term program related to dynamic loads associated with a postulated loss-of-coolant accident, areas of design found not meeting the original design safety margins approved for the construction permit will be modified on a timely schedule to restore the original design safety margins.

BFN Unit 3 Amendment f, 22, N,

~64

(2)

The licensee is required, upon completion of the Mark I Owners Group containment long-term program related to relief valve operation, to make such modifications on a timely basis as may be necessary to restore the original design safety margins approved for the construction permit and used for the design of the torus structures when subjected to relief valve operation.

(3)

The facility may be modified as described in "Browns Ferry Nuclear Plant Unit 3 Emergency Core Cooling Systems Low Pressure Coolant Injection Modifications for Performance Improvement (October 1977)" and as described in TVA's letter of December 28, 1977'ransmitting the aforementioned report and in TVA's supplemental letter of December 13, 1978.

(4)

Commission Order dated March 25, 1983 is modified as follows:

In Attachment 1, for item II.F.l.l and II.F.1.2 change "12/31/84" to "Prior to Unit 2 startup in Cycle 6."

E.

This amended license is effective as of the date of issuance and shall expire midnight on July 2, 2016.

FOR THE NUCLEAR REGULATORY COMMISSION BL3~~eXsums fur Roger S. Boyd, Director Division of Project Management Office of Nuclear Reactor Regulation

Attachment:

Appendices A

6 B-Technical Specifications Date of Issuance:

JUL 2 1976 BFN Unit 3 Amendment f, N, P8, HS, fN, 164

ATTACHMENT 2 TO LICENSE AMENDMENT NO.

FACILITY OPERATING LIC NSE NO.

DPR-68 OCKET NO. 50-296 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.*

REMOVE 1V V11 3.11/4.11-1 3.11/4.11-2 3.11/4.11-3 3.11/4.11-4 3.11/4.11-5 3.11/4.11-6 3.11/4.11-7 3'.ll/4.11-8 3.11/4.11-9 3.11/4.11-10 3.11/4.11-11 3.11/4.11-12 3.11/4.11-13 3.11'/4.11-14 3.11/4.11-15 3.11/4.11-16 3.11/4.11-17 3.11/4.11-18 3.11/4.11-19 3.11/4.11-20 3.11/4.11-21 3.11/4.11-22 3.11/4.11-23 3.11/4.11-24 6.0-3 6.0-9 INSERT iii*

1V V11 V11 1*

3.11/4.11-1 3.11-4.11-2 6.0-3 6.0-4*

6'. 0-9 6.0-10*

Section

~aero F.

Recirculation Pump Operation G.

Structural Integrity.

H.

Snubbers 3.7/4.7 Containment Systems A.

Primary Containment.

3.6/4.6-12 3.6/4 '-13 3 '/4.6-15 3.7/4.7-1 3.7/4.7-1 B.

Standby Gas Treatment System 3.7/4.7-13 C.

Secondary Containment.

3.7/4.7-16 D.

Primary Containment Isolation Valves 3.7/4.7-17 E.

Control Room Emergency Ventilation 3.7/4.7-19 F.

Primary Containment Purge System 3.7/4.7-21 G.

Containment Atmosphere Dilution System (CAD) 3.7/4.7-22 H.

Containment Atmosphere Monitoring (CAM)

System H2 Analyzer 3.8/4.8 Radioactive Materials A.

Liquid Effluents

.B.

Airborne Effluents 3.7/4.7-23a 3.8/4.8-1 3.8/4.8-1 3.8/4.8-2 C.

Radioactive Effluents Dose 3.8/4.8-6 D.

Mechanical Vacuum Pump 3.8/4.8-6 E.

Miscellaneous Radioactive Materials Sources 3.8/4.8-7 F;.

Solid Radwaste 3.8/4.8-9 3.9/4.9 Auxiliary Electrical System 3.9/4.9-1 A.

Auxiliary Electrical Equipment 3.9/4.9-1 B.

Operation with Inoperable 'Equipment.

3.9/4.9-8 C.

Operation in Cold Shutdown 3.9/4.9-14 3.10/4.10 Core Alterations A.

Refueling Interlocks B.

Core Monitoring C.

Spent Fuel Pool Mater 3.10/4.10-1 3.10/4.10-1 3.10/4.10-4 3.10/4.10-7 BFH Unit 3 AMENOMENTNO. y 5 6

~Sect% o Pae o

D.

Reactor Building Crane 3'.10/4.10-8 E.

Spent Fuel Cask 3.10/4.10-9 F.

Spent Fuel Cask Handling-Refueling Floor.

3.10/4.10-9 3.11/4.11 Deleted.

3.11/4.11-1 5.0 Major Design Features 5.0-1 5.1 Site Features 5.0-1 5.2 Reactor

~

~

~

~

~

~

~

~

~

~

~

~

~

5.0-1 5.3 Reactor Vessel 5.0-1 5.4 Containment 5.0-1 5.5 Fuel Storage

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~

~

~

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~

.5.6 Seismic Design 5.0-1 5.0-2 BFH Unit 3 iv Amendment 164

Table 4'.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation.

a e No.

3.2/4.2-52 4.2.F Minimum Test and Calibration Frequency for.

Surveillance Instrumentation 3.2/4.2-53 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation.

3.2/4.2-55 4.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation 3.2/4.2-56 4.2.J Seismic Monitoring Instrument Surveillance Requirements 3.2/4.2-57 4.2.K Radioactive Gaseous Effluent Monitoring Instrumentation 3.2/4.2-61 4.2.L ATWS-Recirculation Pump Trip (RPT)

Instrumentation Surveillance.

3.2/4.2-62a 3.5-1 3.5.I 4.9.A Minimum RHRSW and EECW Pump Assignment.

3.5/4.5-11 MAPLHGR Versus Average Planar Exposure.

3.5/4.5-21 Auxiliary Electrical System 3.9/4.9-15 4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start.

3.9/4.9-17 6.2.A Minimum Shift Crev Requirements 6.0-4 BFN Unit 3 vii Amendment 164

IS OF IILUSTRATIONS

~iure 2.1.1 aeNo 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.

l.l/2.1-7 4.1-1 Graphical Aid in the Selection of an Adequate Interval Between 'Tests 3.1/4.1-12 4'. 2-1 3.5.K-1 System Unavailabi.lity.

3.2/4.2-63 MCPR Limits..

3.5/4.5-25 3.5.2 3.6-1 4.8.1.a Kf Factor.

Minimum Temperature F Above.Change in Transient Temperature.

Gaseous Release Points and Elevation 3.5/4.5-26 3.6/4.6-24 3.8/4.8-10 4.8'.l.b Land Site Boundary 3.8/4.8-11 BFN Unit 3 viii AMENPggggg ~ ~<

1 4 1 FIRE PROTECTIOH SYSTEMS IMITIHG COHDITIO S FOR OPERATIOH Deleted SURVEILLAHCE RE UIREMEHTS Deleted BFH Unit 3

3. 11/4 ~ 11-1 Amendment 164

THIS PAGE INTENTIONALLYLEFT BLANK BFN Unit 3 3.11/4.11-2 Amendment

) 64.

0

6.2.2 (Cont.)

d.

Two licensed reactor operators shall be in the control room during any cold startups, while shutting down the reactor, and during recovery from unit trip.

In addition, a person holding a senior operator license shall be in the control room for that unit whenever it is in an operational mode other than cold shutdown or refueling.

e.

A Health Physics Technician~ shall be present at the facility at all times when there is fuel in. the reactor.

f.

A person holding a senior operator license or a senior operator license limited to fuel handling, shall be present during alteration of the core to directly supervise the activity and during this time shall not be assigned other duties.

g.

Deleted.

• The Health Physics Technician may be absent from the facility for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided immediate action is taken to fillthe required position.

BFN Unit 3 6.0-3 Amendment 164

inimum Shift Crew Re uirements Position Senior Operator Senior Operator Licensed Operators Additional Licensed Operatorsc Assistant Unit Operators (AUO)

Shift Technical Advisor.(STA)

Health Physics Technician Units in 0 eration 1

1 1

1 0

1 2

2 3

3 3

3 0

1

.2 2

a 4

s 5

0 1

1 1

1 1

1 1

e of License SRO SRO RO or SRO RO or SRO None None None Note for Table 2 A a.

A senior operator will be assigned responsibility for overall plant operation at all times there is fuel in any unit.

b.

Except for the senior operator discussed in note "a", the shift crew composition may be one less than the minimum requirements of Table 6.2.A for a period of time not to exceed two hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.A.

'This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

c.

One of the Additional Licensed Operators must be assigned to each control room with an operating unit.

d.

The number of.required licensed personnel, when the operating units are

,controlled from a common control room, are two senior operators and four operators.

BFN Unit 3 6.0-a AMENDMENTgg. y p p

6.5.1.6 (Cont.)

l.

Review of reportable

events, unusual events, operating anomalies, and abnormal performance of plant equipment.

m.

Investigate reported or suspected incidents involving safety questions or violations of the Technical Specifications.

n.

Review of unit operations to detect potential hazards to nuclear safety.

Items that may be included in this review are NRC inspection reports, QA audit, HSRB audit results, American Nuclear Insurer (AHI) inspection results, and significant corrective action reports (CARs).

o.-

Performance of special reviews, investigations, or analysis, and report thereon as requested by the Plant Manager or the Huclear Safety Review Board.

p.

Review of the Fire Protection Program, "Fire Protection Report, Volume-1", and implementing procedures, "Safe Shutdown Instructions",

and the submittal of PORC approved changes to the Nuclear Safety Review Board.

BFN Unit 3 6.0-9 Amendment 164

AUTHORITY 6.5.1.7 The PORC shall:

a.

Recommend to the Plant Manager in writing, approval, or disapproval of items considered under 6.5.1.6.a through.

i above.

l.

The.recommendation shall be based on a majority vote of the PORC at a formal meeting.

2.

The recommendation shall be based on a unanimous vote of the PORC when the PORC members are acting individually.

3.

Each member or alternate member shall have one vote.

b.

Furnish for consideration a determination in writing with regard to whether or not each item considered under 6.5.1.6.f above constitutes an unreviewed safety question.

c.

Make recommendations to the Plant Manager in writing that action reviewed under 6.5.1.6.k above did not constitute an unreviewed safety question.

d.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Site Director and the Nuclear Safety Review Board of disagreements between the PORC and the Plant Manager.

However, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.

BFN Unit 3 6.0-10 AMENOMEe g0. > > 0

4I