Text

License Amendments 195, 210, & 167, Revising the Technical Specifications to Reflect a Design Change of Refuel Zone and Reactor Building Ventilation Radiation Monitoring System That Replaces Existing Analog Components
	ML020030170
Person / Time
Site:	Browns Ferry
Issue date:	04/13/1993
From:	Hebdon F; Office of Nuclear Reactor Regulation
To:	Medford M; Tennessee Valley Authority
References
	-RFPFR, TAC M84161, TAC M84162, TAC M84163 NUDOCS 9304220004
	Download: ML020030170 (96)
	v • d • e

0, tjF9 R EG&0q UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 April 13, 1993 Docket Nos. 50-259, 50-260 and 50-296 Tennessee Valley Authority ATTN:

Dr. Mark 0. Medford, Vice President Nuclear Assurance, Licensing & Fuels 3B Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801

Dear Dr. Medford:

SUBJECT:

ISSUANCE OF AMENDMENTS (TAC NOS.

M84161, M84162 AND M84163)

(TS-316)

The Commission has issued the enclosed Amendment Nos.195, 210

, and 167 to Facility Operating Licenses Nos.

DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant (BFN),

Units 1, 2, and 3, respectively, in response to an application dated July 23, 1992, as supplemented by letter dated April 6, 1993, from the Tennessee Valley Authority (TVA).

By letter dated March 16, 1993, TVA also provided the staff with additional information to support its license amendments.

These amendments revise the BFN Technical Specifications (TS) to reflect a design change of the Refuel Zone and Reactor Building Ventilation Radiation Monitoring (RBVRM) system that replaces existing analog components with digital equipment manufactured by General Electric (GE).

This digital equipment is part of the GE Nuclear Measurement Analysis ana Control (NUMAC) product line.

The NUMAC RBVRM design change will be implemented by the end of the current BFN, Unit 2, Cycle 6 Refueling Outage.

A copy of the staff's Safety Evaluation (SE) is also enclosed.

However, TVA should note that the staff's conclusions regarding the capability of the NUMAC RBVRM system to tolerate electromagnetic and radio frequency interferences are contingent upon the successful accomplishment of several TVA commitments, as described in Section 4.4 of the SE.

TVA is requested to inform the staff of the results from its plant survey, and GE's testing, as soon as practicable.

These results are to be formally submitted within 60 days after the 93042204 930413 PWR WDOCK 05000259 P

PDR

/

Wý -/

April 13, 1993 Dr. Mark 0. Medford respective plant survey or GE testing is completed, but no later than December 31, 1993.

This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.

Also enclosed is the Notice of Issuance which has been forwarded to the Office of the Federal Register for publication.

Sincerely, Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No.195to License No. DPR-33

2.

Amendment No.210to License No.

DPR-52

3.

Amendment No.167to License No. DPR-68

4.

Safety Evaluation

5.

Notice cc w/enclosures:

See next page

-2

April 13, 1993 Dr. Mark 0. Medford respective plant survey or GE testing is completed, but no later than December 31, 1993.

This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.

Also enclosed is the Notice of Issuance which has been forwarded to the Office of the Federal Register for publication.

Sincerely, Original signed by Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosures:

1. Amendment No.195to License No.

DPR-33

2.

Amendment No.210to License No. DPR-52

3.

Amendment No.167to License No.

DPR-68

4.

Safety Evaluation

5.

Notice cc w/enclosures:

See next page

-2

Tennessee Valley Authority ATTN:

Dr. Mark 0. Medford cc:

Mr. John B. Waters, Chairman Tennessee Valley Authority ET 12A 400 West Summit Hill Drive Knoxville, Tennessee 37902 Mr. J. R. Bynum, Vice President Nuclear Operations 3B Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 Site Licensing Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, Alabama 35602 Mr. 0. J. Zeringue, Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, Alabama 35602 Mr. M. J. Burzynski, Manager Nuclear Licensing and Regulatory Affairs 5B Lookout Place Chattanooga, Tennessee 37402-2801 TVA Representative Tennessee Valley Authority 11921 Rockville Pike Suite 402 Rockville, Maryland 20852 General Counsel Tennessee Valley Authority ET 11H 400 West Summit Hill Drive Knoxville, Tennessee 37902 Chairman, Limestone County Commission P.O. Box 188 Athens, Alabama 35611 Browns Ferry Nuclear Plant State Health Officer Alabama Dept. of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701 Regional Administrator U.S.N.R.C. Region II 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. Charles Patterson Senior Resident Inspector Browns Ferry Nuclear Plant U.S.N.R.C.

Route 12, Box 637 Athens, Alabama 35611 Site Quality Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P. 0. Box 2000 Decatur, Alabama 35602

AMENDMENT NO.

DATED:

April 195FOR BROWNS 210FOR BROWNS 167FOR BROWNS 13, 1993 FERRY UNIT 1 -

DOCKET NO. 50-259 FERRY UNIT 2 -

DOCKET NO.

50-260 FERRY UNIT 3 -

DOCKET NO.

50-296 DISTRIBUTION:

Docket File NRC PDR & Local PDR BFN Reading File S. Varga 14-E-4 G. Lainas 14-H-3 F. Hebdon M. Sanders T. Ross J. Williams P. Frederickson RII OGC 15-B-13 D. Hagan MNBB-3302 E. Jordan MNBB-3302 G. Hill P1-130 (2 per docket)

Wanda Jones MNBB-7103 C. Grimes 11-E-21 E. Lee ACRS (10)

OPA 2-G-5 OC/LFDCB MNBB-9112 cc:

Plant Service List 210102

R 4

0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

195 License No. DPR-33 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated July 23, 1992, as supplemented March 16 and April 6, 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; 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 (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; D.

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 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.

9304220005 930413 PDR ADOCK 05000259 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 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.195, 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 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebd~n, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 13, 1993

ATTACHMENT TO LICENSE AMENDMENT NO.

195 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* and spillover** pages are provided to maintain document completeness.

REMOVE INSERT 1.0-9 1.0-10 3.2/4.2-7 3.2/4.2-8 3.2/4.2-9 3.2/4.2-10 3.2/4.2-12 3.2/4.2-13 3.2/4.2-40 3.2/4.2-41 3.2/4.2-59 3.2/4.2-60 3.2/4.2-61 3.2/4.2-61a 3.2/4.2-67 3.2/4.2-68 3.2/4.2-69 3.2/4.2-70 3.2/4.2-73 3.2/4.2-73a 1.0-9 1.0-10*

3.2/4.2-7*

3.2/4.2-8 3.2/4.2-9 3.2/4.2-10*

3.2/4.2-12*

3.2/4.2-13 3.2/4.2-13a 3.2/4.2-13b 3.2/4.2-40*

3.2/4.2-41

3. 2/4.2-59*

3.2/4.2-60 3.2/4.2-61 3.2/4.2-61a*

3.2/4.2-67*

3.2/4.2-68 3.2/4.2-69 3.2/4.2-70*

3.2/4.2-73 3.2/4.2-73a*

1.0 DEFINITIONS (Cont'd)

10. Logic -

A logic is an arrangement of relays, contacts, and other components that produces a decision output.

(a)

Initiating -

A logic that receives signals from channels and produces decision outputs to the actuation logic.

(b)

Actuation -

A logic that receives signals (either from initiation logic or channels) and produces decision outputs to accomplish a protective action.

11.

Channel Calibration -

Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors.

The channel calibration shall encompass the entire channel including alarm and/or trip functions and shall include the channel functional test.

The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

Non-calibratable components shall be excluded from this requirement, but will be included in channel functional test and source check.

12. Channel Functional Test - Shall be:

a.

Analog/Digital Channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b.

Bistable Channels -

the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

13. Source Check - Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources.

BFN 1.0-9 Amendment 195 Unit 1

1.0 DEFINITIONS"-,,Jont'd)

W.

Functional Tests -

A functional test is the manual operation or initiation of a system, subsystem, or components to verify that it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps the required volume of water).

X.

Shutdown -

The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.

Y.

Engineered Safeguard - An engineered safeguard is a safety system the actions of which are essential to a safety action required in response to accidents.

Z.

Reportable Event -

A reportable event shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

AA.

Solidification - Shall be the conversion of radioactive wastes into a form that meets shipping and burial ground requirements.

BB.

Offsite Dose Calculation Manual (ODCM)

Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and offsite doses due to radioactive gaseous and liquid effluents.

The ODCM will also provide the plant with guidance for establishing alarm/trip setpoints to ensure technical specifications sections 3.8.A.1 and 3.8.B.1 are not exceeded.

CC.

Purge or purging -

The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the containment.

DD.

Process Control Progrwu - Shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.

EE.

Radiological Effluent Manual (REM)

Shall be a manual containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposure to individuals from station operation.

It shall also specify operating guidelines for radioactive waste treatment systems and report content.

FF.

Venting -

The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required.

Vent, used in system names, does not imply a venting process.

BFN 1.0-10 Unit 1

TABLE 3.2.A PRIMARY CONTAINMENT AND REACTOR BUILDING Minimum No.

Instrument Channels Operable Per Trip Sys(l)(11) 2 Function Instrument Channel Reactor Low Water Level(6)

Instrument Channel Reactor High Pressure (PS-68-93 and 94)

Instrument Channel Reactor Low Water Level (LIS-3-56A-D, SW #1)

Instrument Channel High Drywell Pressure (6)

(PS-64-56A-D)

Trip Level Setting

> 538" above vessel zero 100 +/- 15 psig

2. 378" above vessel zero j 2.5 psig ISOLATION INSTRUMENTATION Action (1)

A or (B and E)

D A

A or (B and E)

Remarks

1. Below trip setting does the following:

a.

Initiates Reactor Building Isolation

b.

Initiates Primary Containment Isolation (Groups 2,

3, and 6)

c.

Initiates SGTS

1. Above trip setting isolates the shutdown cooling suction valves of the RHR system.

1. Below trip setting initiates Main Steam Line Isolation

1. Above trip setting does the following:

a.

Initiates Reactor Building Isolation

b.

Initiates Primary Containment Isolation

c.

Initiates SGTS Fl-Z rt I.-

1 2

r-s r-w I

L*

o FO o

FO I

TABLE 3.2.A (Continued)

PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION Minimum No.

Instrument Channels Operable Per Trip Sys(l)(11)

Function Trio Level Settina Instrument Channel High Radiation Main Steam Line Tunnel (6)

Instrument Channel Low Pressure Main Steam Line Instrument Channel High Flow Main Steam Line Instrument Channel Main Steam Line Tunnel High Temperature Instrument Channel Reactor Water Cleanup System Floor Drain High Temperature Instrument Channel Reactor Water Cleanup System Space High Temperature Instrument Channel Reactor Building Ventilation High Radiation - Reactor Zone 3 times normal rated full power background (13)

> 825 psig (4)

< 140% of rated steam flow

< 2000 F 160 -

1800F 160 - 180°F S100 mr/hr or downscale B

B B

B C

C G

2 2

2(3) 2(12) 2(14)

-t Action (1)

1. Above trip setting initiates Main Steam Line Isolation

1. Below trip setting initiates Main Steam Line Isolation

1.

Above trip setting initiates Main Steam Line Isolation

1. Above trip setting initiates Main Steam Line Isolation.

1. Above trip setting initiates Isolation of Reactor Water Cleanup Line from Reactor and Reactor Water Return Line.

1. Same as above

1. 1 upscale channel or 2 downscale channels will

a.

Initiate SGTS

b.

Isolate reactor zone and refueling floor.

c.

Close atmosphere control system.

Remarks

(

2

0.

=4 (D

kO

=3 C+

1(15)

I

TABLE 3.2.A (Continued)

PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION Minimum No.

Instrument Channels Operable per Trip Sys(1)(l1) 1(15) 2(7) (8) 2(7) (8) 2(7) (8) 2(10) rt Function Instrument Channel Reactor Building Ventilation High Radiation - Refueling Zone Instrument Channel SGTS Flow -

Train A R. H. Heaters Instrument Channel SGTS Flow - Train B R. H. Heaters Instrument Channel SGTS Flow - Train C R. H. Heaters Reactor Building Isolation Timer (refueling floor)

Reactor Building Isolation Timer (reactor zone)

Group 1 (Initiating) Logic Action (1)

F Trio Level Setting

< 100 mr/hr or downscale

>2000 cfm and < 4000 cfm i2000 cfm and < 4000 cfm

>2000 cfm and < 4000 cfm 0 ' t

_ 2 secs.

0 < t < 2 secs.

N/A Remarks

1. 1 upscale channel or 2 downscale channels will

a.

Initiate SGTS

b.

Isolate refueling floor

c.

Close atmosphere control system.

Below 2000 cfm airflow R.H.

heaters shall be shut off.

Below 2000 cfm airflow R.H.

heaters shall be shut off.

Below 2000 cfm airflow R.H.

heaters shall be shut off.

1. Below trip setting prevents spurious trips and system perturbations from initiating isolation.

1. Below trip setting spurious trips and perturbations from isolation.

prevents system initiating H and (A or F)

H and (A or F)

H or F G or A or H A

1. Group 1:

The valves in Group 1 are actuated by any of the following conditions:

a.

Reactor Vessel Low Low Water Level

b.

Main Steamline High Radiation

c.

Main Steamline High Flow

d.

Main Steamline Space High Temperature

e.

Main Steamline Low Pressure (D

3 (D

c-i C+

Un I

1

TABLE 3.2.A (Continued)

PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION Minimum No.

Instrument Channels Operable per Trip Sys(1)(ll)

Function Trin lpvpl Stftinn Group 1 (Actuation) Logic 2

W.

C) 2 Group 2 (Initiating) Logic Group 2 (RHR Isolation Actuation) Logic Group 8 (TIP-Actuation)

Logic Group 2 (Drywell Sump Drains-Actuation) Logic Group 2 (Reactor Building

& Refueling Floor, and Drywell Vent and Purge Actuation) Logic Group 3 (Initiating) Logic N/A N/A N/A N/A N/A N/A N/A Action (1)

B A or (B and E)

Remarks

1. Group 1:

The valves in Group I are actuated by any of the following conditions:

a.

Reactor Vessel Low Low Water Level

b.

Main Steamline High Radiation

c.

Main Steamline High Flow

d.

Main Steamline Space High Temperature

e.

Main Steamline Low Pressure

1. Group 2:

The valves in Group 2 are actuated by any of the following conditions:

a. Reactor Vessel Low Water Level

b.

High Drywell Pressure D

K F and G C

1. Part of Group 6 Logic

1. Group 3:

The valves in Group 3 are actuated by any of the following conditions:

a.

Reactor Vessel Low Water Level

b.

Reactor Water Cleanup System High Temperature

c.

Reactor Water Cleanup System High Drain Temperature I,

mr mr 1

'NOTES FOR TABLE 3.2.A

1.

Whenever the respective functions are required to be OPERABLE there shall be two OPERABLE or tripped trip systems for each function.

If the first column cannot be met for one of the trip systems, that trip system or logic for that function shall be tripped (or the appropriate action listed below shall be taken).

If the column cannot be met for all trip systems, the appropriate action listed below shall be taken.

A.

Initiate an orderly shutdown and have the reactor in Cold Shutdown in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B.

Initiate an orderly load reduction and have Main Steam Lines isolated within eight hours.

C.

Isolate Reactor Water Cleanup System.

D.

Administratively control the affected system isolation valves in the closed position within one hour and then declare the affected system inoperable.

E.

Initiate primary containment isolation within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

F.

The handling of spent fuel will be prohibited and all operations over spent fuels and open reactor wells shall be prohibited.

G.

Isolate the reactor building and start the standby gas treatment system.

H.

Immediately perform a logic system functional test on the logic in the other trip systems and daily thereafter not to exceed 7 days.

I.

Deleted J.

Withdraw TIP.

K.

Manually isolate the affected lines.

Refer to Section 4.2.E for the requirements of an inoperable system.

L.

If one SGTS train is inoperable take actions H or A and F.

If two SGTS trains are inoperable take actions A and F.

2.

Deleted

3.

There are four sensors per steam line of which at least one sensor per trip system must be OPERABLE.

BFN 3.2/4.2-12 AMENDMENT NO. 185 Unit 1

]NOTES FOR TABLE 3.2.A (Cont'd)

4.

Only required in RUN MODE (interlocked with Mode Switch).

5.

Deleted

6.

Channel shared by RPS and Primary Containment & Reactor Vessel Isolation Control System.

A channel failure may be a channel failure in each system.

7.

A train is considered a trip system.

8.

Two out of three SGTS trains required.

A failure of more than one will require actions A and F.

9.

Deleted

10. Deleted

11.

A channel may be placed in an inoperable status for up to four hours for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.

For the Reactor Building Ventilation system, one channel may be inoperable for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional testing or for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for calibration and maintenance, as long as the downscale trip of the inoperable channel is placed in the tripped condition.

12.

A channel contains four sensors, all of which must be OPERABLE for the channel to be OPERABLE.

Power operations permitted for up to 30 days with 15 of the 16 temperature switches OPERABLE.

In the event that normal ventilation is unavailable in the main steam line tunnel, the high temperature channels may be bypassed for a period of not to exceed four hours.

During periods when normal ventilation is not available, such as during the performance of secondary containment leak rate tests, the control room indicators of the affected space temperatures shall be monitored for indications of small steam leaks.

In the event of rapid increases in temperature (indicative of steam line break), the operator shall promptly close the main steam line isolation valves.

13.

The nominal setpoints for alarm and reactor trip (1.5 and 3.0 times background, respectively) are established based on the normal background at full power.

The allowable setpoints for alarm and reactor trip are 1.2-1.8 and 2.4-3.6 times background, respectively.

BFN 3.2/4.2-13 Amendment 195 Unit 1

NOTES FOR TABLE 3.2.A (Cont'd)

14.

Requires two independent channels from each physical location; there are two locations.

15.

There is a RBVRM trip function for the refueling zone and a RBVRM trip function for the reactor zone.

Each trip function is composed of two divisional trip systems.

Each trip system has one channel for each zone.

Each channel contains two sensors, both of which must be OPERABLE for the channel to be OPERABLE.

A channel downscale/inoperable trip occurs when either of the sensors are indicating less than the low radiation setpoint or are inoperable.

A channel upscale trip occurs when both of the sensors are indicating higher than the high radiation setpoint.

Only one channel upscale trip is required for trip function initiation.

Two channel downscale trips in a zone are required for trip function initiation.

3.2/4.2-13a BFN Unit 1 Amendment 195

THIS PAGE INTENTIONALLY LEFT BLANK BFN 3.2/4.2-13b Unit 1

Z1 I-REACTOR BUILDING ISOLATION INSTRUMENTATION Calibration Frequency Instrument Check (5) once/day TABLE 4.2.A SURVEILLANCE REQUIREMENTS FOR PRIMARY CONTAINMENT AND Function Functional Test Instrument Channel -

(1)

Reactor Low Water Level (LIS-3-203A-D, SW 2-3)

Instrument Channel -

(1)

Reactor High Pressure Instrument Channel -

(1)

Reactor Low Water Level (LIS-3-56A-D, SW #1)

Instrument Channel -

(1)

High Drywell Pressure (PS-64-56A-D)

Instrument Channel -

once/3 months (29)

High Radiation Main Steam Line Tunnel Instrument Channel -

once/3 months (27)

(29)

Low Pressure Main Steam Line (PT-I-72,

-76,

-82,

-86)

Instrument Channel -

once/3 months (27)

(29)

High Flow Main Steam Line (dPT-1-13A-D,

-25A-D,

-36A-D,

-50A-D)

None once/day (5)

(5) once/operating cycle (28) once/operating cycle (28)

N/A once/day None once/day once/3 months once/3 month 41 I

C m

m

-4 M,

z Reactor Building Isolation Timer (reactor zone)

(4)

(Cont'd)

AND REACTOR BUILDING ISOLATION INSTRUMENTATION Calibration Frequency Instrument Check once/operating cycle None C-1 TABLE 4.2.A SURVEILLANCE REQUIREMENTS FOR PRIMARY CONTAINMENT Function Functional Test Instrument Channel -

once/3 months (27)

Main Steam Line Tunnel High Temperature Instrument Channel -

(1) (30)

Reactor Building Ventilation High Radiation - Reactor Zone Instrument Channel -

(1)

(30)

Reactor Building Ventilation High Radiation - Refueling Zone Instrument Channel -

(4)

SGTS Train A Heaters Instrument Channel -

(4)

SGTS Train B Heaters Instrument Channel -

(4)

SGTS Train C Heaters Reactor Building Isolation (4)

Timer (refueling floor)

(9)

(9) once/operating cycle once/operating cycle N/A N/A N/A N/A N/A once/18 months once/18 Months once/day (8) once/day (8) t'3 C1 I

I

NOTES FOR TABLES 4.2.A THROUGH 4.2.L except 4.2. D AND 4.2.K

1. Functional tests shall be performed once per month.

2.

Functional tests shall be performed before each startup with a required frequency not to exceed once per week.

3.

This instrumentation is excepted from the functional test definition.

The functional test will consist of injecting a simulated electrical signal into the measurement channel.

4.

Tested iuring logic system functional tests.

5.

Refer to Table 4.1.B.

6.

The logic system functional tests shall include a calibration once per operating cycle of time delay relays and timers necessary for proper functioning of the trip systems.

7.

The functional test will consist of verifying continuity across the inhibit with a volt-ohmmeter.

8.

Instrument checks shall be performed in accordance with the definition of instrument check (see Section 1.0, Definitions).

An instrument check is not applicable to a particular setpoint, such as Upscale, but is a

qualitative check that the instrument is behaving and/or indicating in an acceptable manner for the particular plant condition.

Instrument check is included in this table for convenience and to indicate that an instrument check will be performed on the instrument.

Instrument checks are not required when these instruments are not required to be OPERABLE or are tripped.

9.

Calibration frequency shall be once/year.

10. Deleted

11.

Portion of the logic is functionally tested during outage only.

12.

The detector will be inserted during each operating cycle and the proper amount of travel into the core verified.

13.

Functional test will consist of applying simulated inputs (see note 3).

Local alarm lights representing upscale and downscale trips will be verified, but no rod block will be produced at this time.

The inoperative trip will be initiated to produce a rod block (SRM and IRM inoperative also bypassed with the mode switch in RUN).

The functions that cannot be verified to produce a rod block directly will be verified during the operating cycle.

BFN 3.2/4.2-59 AMENDMENT NO. 1 6 1 Unit I

'NOTES FOR TABLES 4.2.A THROUGH 4.2.L except 4.2.D AND 4.2.K (Cont'd)

14.

(Deleted)

15.

The flow bias comparator will be tested by putting one flow unit in "Test" (producing 1/2 scram) and adjusting the test input to obtain comparator rod block.

The flow bias upscale will be verified by observing a local upscale trip light during operation and verified that it will produce a rod block during the operating cycle.

16.

Performed during operating cycle.

Portions of the logic is checked more frequently during functional tests of the functions that produce a rod block.

17.

This calibration consists of removing the function from service and performing an electronic calibration of the channel.

18.

Functional test is limited to the condition where secondary containment integrity is not required as specified in Sections 3.7.C.2 and 3.7.C.3.

19.

Functional test is limited to the time where the SGTS is required to meet the requirements of Section 4.7.C.l.a.

20.

Calibration of the comparator requires the inputs from both recirculation loops to be interrupted, thereby removing the flow bias signal to the APRM and RBM and scramming the reactor.

This calibration can only be performed during an outage.

21.

Logic test is limited to the time where actual operation of the equipment is permissible.

22.

(Deleted)

23.

(Deleted)

24.

This instrument check consists of comparing the thermocouple readings for all valves for consistence and for nominal expected values (not required during refueling outages).

25.

During each refueling outage, all acoustic monitoring channels shall be calibrated.

This calibration includes verification of accelerometer response due to mechanical excitation in the vicinity of the sensor.

BFN 3.2/4.2-60 Unit 1 Amendment 195

-I

NOTES FOR TABLES 4.2.A THROUGH 4.2.L except 4.2.1D AND 4.2.K (Cont'd)

26.

This instrument check consists of comparing the background signal levels for all valves for consistency and for nominal expected values (not required during refueling outages).

27.

Functional test consists of the injection of a simulated signal into the electronic trip circuitry in place of the sensor signal to verify OPERABILITY of the trip and alarm functions.

28.

Calibration consists of the adjustment of the primary sensor and associated components so that they correspond within acceptable range and accuracy to known values of the parameter which the channel monitors, including adjustment of the electronic trip circuitry, so that its output relay changes state at or more conservatively than the analog equivalent of the trip level setting.

29.

The functional test frequency decreased to once/3 months to reduce challenges to relief valves per NUREG-0737, Item II.K.3.16.

30.

Functional testing for the Reactor Building Ventilation Radiation Monitoring System (RBVRMS) shall consist of verifying the High Voltage Power Supply (HVPS) voltage at the Sensor and Convertors (detectors) is within its design limits.

A channel functional test as defined in Section 1.0, "Definitions" shall be performed once per 18 months as part of the RBVRM channel calibration.

BFN 3.2/4.2-61 Amendment 195 Unit 1 I

THIS PAGE INTENTIONALLY LEFT BLANK 3.2/4.2-61a BFN Unit I AMENDMENT NO. 1 6 4

3.2 BASES (Cont'd) steam line isolation valve closure, fission product release is limited so that 10 CFR 100 guidelines are not exceeded for this accident.

Reference Section 14.6.2 FSAR.

An alarm with a nominal setpoint of 1.5 x normal full-power background is provided also.

Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drops below 825 psig.

The HPCI high flow and temperature instrumentation are provided to detect a break in the HPCI steam piping.

Tripping of this instrumentation results in actuation of HPCI isolation valves.

Tripping logic for the high flow is a l-out-of-2 logic, and all sensors are required to be operable.

High temperature in the vicinity of the HPCI equipment is sensed by four sets of four bimetallic temperature switches.

The 16 temperature switches are arranged in two trip systems with eight temperature switches in each trip system.

The HPCI trip settings of 90 psi for high flow and 200*F for high temperature are such that core uncovery is prevented and fission product release is within limits.

The ROIC high flow and temperature instrumentation are arranged the same as that for the HPCI.

The trip setting of 450" H2 0 for high flow and 200*F for temperature are based on the same criteria as the HPCI.

High temperature at the Reactor Cleanup System floor drain could indicate a break in the cleanup system.

When high temperature occurs, the cleanup system is isolated.

The instrumentation which initiates CSCS action is arranged in a dual bus system.

As for other vital instrumentation arranged in this fashion, the specification preserves the effectiveness of the system even during periods when maintenance or testing is being performed.

An exception to this is when logic functional testing is being performed.

The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR does not decrease to 1.07.

The trip logic for this function is 1-out-of-n:

e.g., any trip on one of six APRMs, eight IRMs, or four SRMs will result in a rod block.

The minimum instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met.

The minimum instrument channel requirements for the RBM may be reduced by one for maintenance, testing, or calibration.

This does not significantly increase the risk of an inadvertent control rod withdrawal, as the other channel is available, and the RBM is a backup system to the written sequence for withdrawal of control rods.

BFN 3.2/4.2-67 Unit I

3.2 BASES (Cont'd)

The APRM rod block function is flow biased and prevents a significant reduction in MCPR, especially during operation at reduced flow.

The APRM provides gross core protection; i.e., limits the gross core power increase from withdrawal of control rods in the normal withdrawal sequence.

The trips are set so that MCPR is maintained greater than 1.07.

The RBM rod block function provides local protection of the core; i.e.,

the prevention of critical power in a local region of the core, for a single rod withdrawal error from a limiting control rod pattern.

If the IRM channels are in the worst condition of allowed bypass, the sealing arrangement is such that for unbypassed IRM channels, a rod block signal is generated before the detected neutrons flux has increased by more than a factor of 10.

A downscale indication is an indication the instrument has failed or the instrument is not sensitive enough.

In either case the instrument will not respond to changes in control rod motion and thus, control rod motion is prevented.

The refueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the refueling position.

For effective emergency core cooling for small pipe breaks, the HPCI system must function since reactor pressure does not decrease rapid enough to allow either core spray or LPCI to operate in time.

The automatic pressure relief function is provided as a backup to the HPCI in the event the HPCI does not operate.

The arrangement of the tripping contacts is such as to provide this function when necessary and minimize spurious operation.

The trip settings given in the specification are adequate to assure the above criteria are met.

The specification preserves the effectiveness of the system during periods of maintenance, testing, or calibration, and also minimizes the risk of inadvertent operation; i.e., only one instrument channel out of service.

Two post treatment off-gas radiation monitors are provided and, when their trip point is reached, cause an isolation of the off-gas line.

Isolation is initiated when both instruments reach their high trip point or one has an upscale trip and the other a downscale trip or both have a downscale trip.

Both instruments are required for trip but the instruments are set so that the instantaneous stack release rate limit given in Specification 3.8 is not exceeded.

Two radiation monitors are provided for each unit which initiate Primary Containment Isolation (Group 6 isolation valves) Reactor Building Isolation and operation of the Standby Gas Treatment System.

These instrument channels monitor the radiation in the reactor zone ventilation exhaust ducts and in the refueling zone.

BFN 3.2/4.2-68 Amendment 195 Unit 1

3.2 BASES (Cont'd)

Trip setting of 100 mr/hr for the monitors in the refueling zone are based upon initiating normal ventilation isolation and SGTS operation so that none of the activity released during the refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is processed by the SGTS.

The allowed inoperable time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional testing or 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for calibration and maintenance (with the downscale trip of the inoperable channel in the tripped condition) of the Reactor Building Ventilation system is based upon a Probabilistic Risk Assessment (PRA).

The assessment considered the failures, relay failures and the probability of an accident occurring for which the RBVRMs are required to operate.

Flow integrators and sump fill rate and pump out rate timers are used to determine leakage in the drywell.

A system whereby the time interval to fill a known volume will be utilized to provide a backup.

An air sampling system is also provided to detect leakage inside the primary containment (See Table 3.2.E).

For each parameter monitored, as listed in Table 3.2.F, there are two channels of instrumentation except as noted.

By comparing readings between the two channels, a near continuous surveillance of instrument performance is available.

Any deviation in readings will initiate an early recalibration, thereby maintaining the quality of the instrument readings.

Instrumentation is provided for isolating the control room and initiating a pressurizing system that processes outside air before supplying it to the control room.

An accident signal that isolates primary containment will also automatically isolate the control room and initiate the emergency pressurization system.

In addition, there are radiation monitors in the normal ventilation system that will isolate the control room and initiate the emergency pressurization system.

Activity required to cause automatic actuation is about one mRem/hr.

Because of the constant surveillance and control exercised by TVA over the Tennessee Valley, flood levels of large magnitudes can be predicted in advance of their actual occurrence.

In all cases, full advantage will be taken of advance warning to take appropriate action whenever reservoir levels above normal pool are predicted.

Therefore, during flood conditions, the plant will be permitted to operate until water begins to run across the top of the pumping station at elevation 565.

Seismically qualified, redundant level switches each powered from a separate division of power are provided at the pumping station to give main control room indication of this condition.

At that time an orderly shutdown of the plant will be initiated, although surges even to a depth of several feet over the pumping station deck will not cause the loss of the main condenser circulating water pumps.

BFN 3.2/4.2-69 Amendment 195 Unit 1

3.2 BASES (Cont'd)

The operability of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation dose to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.

The operability of the seismic instrumentation ensures that sufficient capability is available to promptly determine the seismic response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for Browns Ferry Nuclear Plant and to determine whether the plant can continue to be operated safely.

The instrumentation provided is consistent with specific portions of the recommendations of Regulatory Guide 1.12 "Instrumentation for Earthquakes."

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm/trip setpoints for these instruments will be calculated in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

This instrumentation also includes provisions for monitoring the concentration of potentially explosive gas mixtures in the offgas holdup system.

The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alarm/trip setpoints for these instruments shall be calculated in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20 Appendix B, Table II, Column 2.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

ATWS/RPT, Anticipated Transients without Scram/Recirculation Pump Trip system provides a means of limiting the consequences of the unlikely occurrence of a failure to scram during an ATWS event.

The response of the plant to this postulated event (ATWS/RPT) follows the BWR Owners Group Report by General Electric NEDE-31096-P-A and the accompanying NRC Staff Safety Evaluation Report.

ATWS/RPT utilizes the engineered safety feature (ESF) master/slave analog trip units (ATU) which consists of four level and four pressure channels total.

The initiating logic consists of two independent trip systems each consisting of two reactor dome high pressure channels and two reactor vessel low level channels.

A coincident trip of either two low levels or two high pressures in the same trip system causes initiation of ATWS/RPT.

This signal from either trip system opens one of two EOC BFN 3.2/4.2-70 AMENDMENT NO. 160 Unit 1

"4.2 BASES (Cont'd-Y The conclusions to be drawn are these:

1.

A 1-out-of-n system may be treated the same as a single channel in terms of choosing a test interval; and

2.

more than one channel should not be bypassed for testing at any one time.

The radiation monitors in the reactor and refueling zones which initiate building isolation and standby gas treatment operation are arranged such that two sensors high (above the high level setpoint) in a single channel or one sensor downscale (below low level setpoint) or inoperable in two channels in the same zone will initiate a trip function.

The functional testing frequencies for both the channel functional test and the high voltage power supply functional test are based on a Probabilistic Risk Assessment and system drift characteristics of the Reactor Building Ventilation Radiation Monitors.

The calibration frequency is based upon the drift characteristics of the radiation monitors.

The off-gas post treatment monitors are connected in a 2-out-of-2 logic arrangement.

Based on experience with instruments of similar design, a testing interval of once every three months has been found adequate.

The automatic pressure relief instrumentation can be considered to be a l-out-of-2 logic system and the discussion above applies also.

The criteria for ensuring the reliability and accuracy of the radioactive gaseous effluent instrumentation is listed in Table 4.2.K.

The criteria for ensuring the reliability and accuracy of the radioactive liquid effluent instrumentation is listed in Table 4.2.D.

The RCIC and HPCI system logic tests required by Table 4.2.B contain provisions to demonstrate that these systems will automatically restart on a RPV low water level signal received subsequent to a RPV high water level trip.

BFN 3.2/4.2-73 Amendment 195 Unit I

THIS PAGE INTENTIONALLY LEFT BLANK BFN 3.2/4.2-73a Unit 1 By letter 07/31/92

"UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

210 License No.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated July 23, 1992, as supplemented March 16 and April 6, 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; 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 (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; D.

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 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.

- 2

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-52 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 210, 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 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Frederick J.

, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 13, 1993

ATTACHMENT TO LICENSE AMENDMENT NO. 210 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* and spillover** pages are provided to maintain document completeness.

REMOVE INSERT 1.0-9 1.0-10 3.2/4.2-7 3.2/4.2-8 3.2/4.2-9 3.2/4.2-10 3.2/4.2-12 3.2/4.2-13 3.2/4.2-40 3.2/4.2-41 3.2/4.2-59 3.2/4.2-60 3.2/4.2-61 3.2/4.2-61a 3.2/4.2-69 3.2/4.2-70 3.2/4.2-71 3.2/4.2-72 3.2/4.2-73 3.2/4.2-73a 1.0-9 1.0-10*

3.2/4.2-7*

3.2/4.2-8 3.2/4.2-9 3.2/4.2-10*

3.2/4.2-12*

3.2/4.2-13 3.2/4.2-13a 3.2/4.2-13b 3.2/4.2-40*

3.2/4.2-41 3.2/4.2-59*

3.2/4.2-60 3.2/4.2-61 3.2/4.2-61at 3.2/4.2-69 3.2/4.2-70**

3.2/4.2-71**

3.2/4.2-72**

3.2/4.2-73**

3.2/4.2-73a

1.0 DEFINITION.

Cont'd)

10. Logic -

A logic is an arrangement of relays, contacts, and other components that produces a decision output.

(a)

Initiating A logic that receives signals from channels and produces decision outputs to the actuation logic.

(b)

Actuation -

A logic that receives signals (either from initiation logic or channels) and produces decision outputs to accomplish a protective action.

11.

Channel Calibration -

Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors.

The channel calibration shall encompass the entire channel including alarm and/or trip functions and shall include the channel functional test.

The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

Non-calibratable components shall be excluded from this requirement, but will be included in channel functional test and source check.

12. Channel Functional Test - Shall be:

a.

Analog/Digital Channels -

the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b.

Bistable Channels -

the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

13. Source Check -

Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources.

BFN 1.0-9 Amendment 210 Unit 2

1.0 DEFINITIONS (Cont'd)

W.

Functional Tests -

A functional test is the manual operation or initiation of a system, subsystem, or component to verify that it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps the required volume of water).

X.

Shutdown -

The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.

Y.

Engineered Safeguard - An engineered safeguard is a safety system the actions of which are essential to a safety action required in response to accidents.

Z.

Reportable Event -

A reportable event shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

AA.

Solidification - Shall be the conversion of radioactive wastes into a form that meets shipping and burial ground requirements.

BB. Offsite Dose Calculation Manual (ODCM_

Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and offsite doses due to radioactive gaseous and liquid effluents.

The ODCM will also provide the plant with guidance for establishing alarm/trip setpoints to ensure technical specifications sections 3.8.A.1 and 3.8.B.1 are not exceeded.

CC. Purge or purgig -

The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the containment.

DD.

Proess CQntrolPro

-am - Shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.

EE. Radiological Effluent Manual (REM)

- Shall be a manual containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposure to individuals from station operation.

It shall also specify operating guidelines for radioactive waste treatment systems and report content.

FF. Venting -

The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required.

Vent, used in system names, does not imply a venting process.

BFN 1.0-10 AMENDMI' NO. I f 5 Unit 2

TABLE 3.2.A PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION Minimum No.

Instrument Channels Operable Per Trip Svs(l)(11) 2 2

2 Function Instrument Channel Reactor Low Water Level(6)

(LIS-3-203 A-D)

Instrument Channel Reactor High Pressure (PS-68-93 and -94)

Instrument Channel Reactor Low Water Level (LIS-3-56A-D)

Instrument Channel High Drywell Pressure (6)

(PIS-64-56A-D)

Trip Level Setting

> 538" above vessel zero 100 +/- 15 psig

> 398" above vessel zero e< 2.5 psig Action (1)

A or (B and E)

D A

A or (B and E)

Remarks

1. Below trip setting does the following:

a.

Initiates Reactor Building Isolation

b.

Initiates Primary Containment Isolation

c.

Initiates SGTS

1.

Above trip setting isolates the shutdown cooling suction valves of the RHR system.

1. Below trip setting initiates Main Steam Line Isolation

1. Above trip setting does the following:

a.

Initiates Reactor Building Isolation

b.

Initiates Primary Containment Isolation

c.

Initiates SGTS rt U.)

I'.

I

(

-I rn wm 00 I

TABLE 3.2.A (Continued)

PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION Minimum No.

Instrument Channels Operable Per Trip Svs(l)(11) 2 2

2(3) 2(12) 1(14) rt Trip Level Setting Action (1) 3 times normal rated full power background (13) i 825 psig (4)

( 140% of rated steam flow

( 200OF S100 mr/hr or downscale B

B B

B G

Remarks

1. Above trip setting initiates Main Steam Line Isolation

1. Below trip setting initiates Main Steam Line Isolation

1. Above trip setting initiates Main Steam Line Isolation

1. Above trip setting initiates Main Steam Line Isolation.

1. 1 upscale channel or 2 downscale channels will

a.

Initiate SGTS

b.

Isolate reactor zone and refueling floor.

c.

Close atmosphere control system.

Function Instrument Channel High Radiation Main Steam Line Tunnel (6)

Instrument Channel Low Pressure Main Steam Line (PIS-1-72, 76, 82, 86)

Instrument Channel High Flow Main Steam Line (PdIS-l-13A-D, 25A-D, 36A-D, 50A-D)

Instrument Channel Main Steam Line Tunnel High Temperature Instrument Channel Reactor Building Ventilation High Radiation - Reactor Zone I

(0 (0

(D

=3 C-+

C)o I

TABLE 3.2.A (Continued)

PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION Minimum No.

Instrument Channels Operable per Trip Sys(1)(11) 1(14) 2(7) (8) 2(7) (8) 2(7) (8) 1 2(10)

Function Instrument Channel Reactor Building Ventilation High Radiation - Refueling Zone Instrument Channel SGTS Flow -

Train A R. H. Heaters Instrument Channel SGTS Flow -

Train B R. H. Heaters Instrument Channel SGTS Flow -

Train C R. H. Heaters Reactor Building Isolation Timer (refueling floor)

Reactor Building Isolation Timer (reactor zone)

Group 1 (Initiating) Logic Trio Level Settino

< 100 mr/hr or downscale

>2000 cfm and < 4000 cfm i2000 cfm and < 4000 cfm

>2000 cfm and < 4000 cfm 0 < t

_ 2 secs.

0 < t < 2 secs.

N/A Action (1)

F H and (A or F)

H and (A or F)

H or F G or A or H A

Remarks

1.

1 upscale channel or 2 downscale channels will

a.

Initiate SGTS

b.

Isolate refueling floor

c.

Close atmosphere control system.

Below 2000 cfm airflow R.H.

heaters shall be shut off.

Below 2000 cfm airflow R.H.

heaters shall be shut off.

Below 2000 cfm airflow R.H.

heaters shall be shut off.

1. Below trip setting prevents spurious trips and system perturbations from initiating isolation.

1.

Below trip setting prevents spurious trips and system perturbations from initiating isolation.

1. Group 1:

The valves in Group 1 are actuated by any of the following conditions:

a.

Reactor Vessel Low Low Water Level

b.

Main Steamline High Radiation

c.

Main Steamline High Flow

d.

Main Steamline Space High Temperature

e.

Main Steamline Low Pressure rt

/'

LD

=3 (D

C-+

Ck C

I

TABLE 3.2.A (Continued)

PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION Minimum No.

Instrument Channels Operable per Trip Sys(l)(ll)

Fn tin tinn Group 1 (Actuation) Logic Group 2 (Initiating) Logic Group 2 (RHR Isolation Actuation) Logic Group 8 (TIP-Actuation)

Logic Group 2 (Drywell Sump Drains-Actuation) Logic Group 2 (Reactor Building

& Refueling Floor, and Drywell Vent and Purge Actuation) Logic Group 3 (Initiating) Logic Trip Level Setting N/A N/A N/A N/A N/A N/A N/A Action (1)

B A or (B and E)

Rpmarks

1. Group 1:

The valves in Group 1 are actuated by any of the following conditions:

a.

Reactor Vessel Low Low Water Level

b.

Main Steamline High Radiation

c.

Main Steamline High Flow

d. Main Steamline Space High Temperature

e.

Main Steamline Low Pressure

1. Group 2:

The valves in Group 2 are actuated by any of the following conditions:

a.

Reactor Vessel Low Water Level

b. High Drywell Pressure D

3 K

F and G C

1. Part of Group 6 Logic

1. Group 3:

The valves in Group 3 are actuated by any of the following conditions:

a.

Reactor Vessel Low Water Level

b.

Reactor Water Cleanup (RWCU)

System High Temperature in the main steam valve vault

c.

RWCU System High Temperature in the RWCU pump room 2A

d.

RWCU System High Temperature in the RWCU pump room 2B

e.

RWCU System High Temperature in the RWCU heat exchanger room

f.

RWCU System High Temperature in the space near the pipe trench containing RWCU piping rt 11) 2 1

C) 2 C

P 0

A

NOTES FOR TABLE 3.2.A

1.

Whenever the respective functions are required to be OPERABLE there shall be two OPERABLE or tripped trip systems for each function.

If the first column cannot be met for one of the trip systems, that trip system or logic for that function shall be tripped (or the appropriate action listed below shall be taken).

If the column cannot be met for all trip systems, the appropriate action listed below shall be taken.

A.

Initiate an orderly shutdown and have the reactor in Cold Shutdown in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B.

Initiate an orderly load reduction and have Main Steam Lines isolated within eight hours.

C.

Isolate Reactor Water Cleanup System.

D.

Administratively control the affected system isolation valves in the closed position within one hour and then declare the affected system inoperable.

E.

Initiate primary containment isolation within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

F.

The handling of spent fuel will be prohibited and all operations over spent fuels and open reactor wells shall be prohibited.

G.

Isolate the reactor building and start the standby gas treatment system.

H.

Immediately perform a logic system functional test on the logic in the other trip systems and daily thereafter not to exceed 7 days.

I.

Deleted J.

Withdraw TIP.

K.

Manually isolate the affected lines.

Refer to Section 4.2.E for the requirements of an inoperable system.

L.

If one SGTS train is inoperable take actions H or A and F.

If two SGTS trains are inoperable take actions A and F.

2.

Deleted

3.

There are four sensors per steam line of which at least one sensor per trip system must be OPERABLE.

BFN 3.2/4.2-12 AMENDMEIT NO. 19 8 Unit 2

NOTES FOR TABLE 3.2.A (Cont'd)

4.

Only required in RUN MODE (interlocked with Mode Switch).

5.

Deleted

6.

Channel shared by RPS and Primary Containment & Reactor Vessel Isolation Control System.

A channel failure may be a channel failure in each system.

7.

A train is considered a trip system.

8.

Two out of three SGTS trains required.

A failure of more than one will require actions A and F.

9.

Deleted

10. Deleted

11.

A channel may be placed in an inoperable status for up to four hours for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.

For the Reactor Building Ventilation system, one channel may be inoperable for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional testing or for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for calibration and maintenance, as long as the downscale trip of the inoperable channel is placed in the tripped condition.

12.

A channel contains four sensors, all of which must be OPERABLE for the channel to be OPERABLE.

Power operations permitted for up to 30 days with 15 of the 16 temperature switches OPERABLE.

In the event that normal ventilation is unavailable in the main steam line tunnel, the high temperature channels may be bypassed for a period of not to exceed four hours.

During periods when normal ventilation is not available, such as during the performance of secondary containment leak rate tests, the control room indicators of the affected space temperatures shall be monitored for indications of small steam leaks.

In the event of rapid increases in temperature (indicative of steam line break), the operator shall promptly close the main steam line isolation valves.

13.

The nominal setpoints for alarm and reactor trip (1.5 and 3.0 times background, respectively) are established based on the normal background at full power.

The allowable setpoints for alarm and reactor trip are 1.2-1.8 and 2.4-3.6 times background, respectively.

BFN 3.2/4.2-13 Amendment 210 Unit 2

NOTES FOR TABLE 3.2.A (Cont'd)

14.

There is a RBVRM trip function for the refueling zone and a RBVRM trip function for the reactor zone.

Each trip function is composed of two divisional trip systems.

Each trip system has one channel for each zone.

Each channel contains two sensors, both of which must be OPERABLE for the channel to be OPERABLE.

A channel downscale/inoperable trip occurs when either of the sensors are indicating less than the low radiation setpoint or are inoperable.

A channel upscale trip occurs when both of the sensors are indicating higher than the high radiation setpoint.

Only one channel upscale trip is required for trip function initiation.

Two channel downscale trips in a zone are required for trip function initiation.

BFN 3.2/4.2-13a Amendment 210 Unit 2

THIS PAGE INTENTIONALLY LEFT BLANK 3.2/4.2-13b BFN Unit 2 Amendment 210 I

TABLE 4.2.A SURVEILLANCE REQUIREMENTS FOR PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION r',

Instrument Channel Reactor Low Water Level (LIS-3-203A-D)

Instrument Channel Reactor High Pressure (PS-68-93 & 94)

Instrument Channel Reactor Low Water Level (LIS-3-56A-D)

Instrument Channel High Drywell Pressure (PIS-64-56A-D)

Instrument Channel High Radiation Main Steam Line Tunnel Instrument Channel Low Pressure Main Steam Line (PIS-1-72, 76, 82, 86)

Instrument Channel High Flow Main Steam Line (PdIS-1-13A-D, 25A-D, 36A-D, 50A-D)

Functional Test (1) (27)

(31)

(1) (27)

(1) (27) 29' (29)

(27)

(29)

(27)

Calibration Frequency Once/18 Months Once/18 months Once/18 months Once/18 Months (5)

Once/18 Months (28)

INSTRUMENTATION Instrument Check (28)

Once/day None (28)

Once/day (28)

N/A Once/day None Once/day H.

r't Function C) 0 C,,

p 00 0i'

I-.Z rNt Reactor Building Isolation Timer (reactor zone)

TABLE 4.2.A (Cont'd)

FOR PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION Functional Test Calibration Frequency Instrument Check once/3 months (27) once/operating cycle None SURVEILLANCE REQUIREMENTS Function Instrument Channel Main Steam Line Tunnel High Temperature Instrument Channel Reactor Building Ventilation High Radiation - Reactor Zone Instrument Channel Reactor Building Ventilation High Radiation - Refueling Zone Instrument Channel SGTS Train A Heaters Instrument Channel SGTS Train B Heaters Instrument Channel SGTS Train C Heaters Reactor Building Isolation Timer (refueling floor) once/18 months once/18 Months (4)

.(4)

(4)

(9)

(9) once/operating cycle once/operating cycle once/day (8) once/day (8)

N/A N/A N/A N/A N/A I

(1) (32)

(D (D

c-I N)

C)

I

NOTES FOR TABLES 4.2.A THROUGH 4.2.L except 4.2.D AND 4.2.K

1.

Functional tests shall be performed once per month.

2.

Functional tests shall be performed before each startup with a required frequency not to exceed once per week.

3.

This instrumentation is excepted from the functional test definition.

The functional test will consist of injecting a simulated electrical signal into the measurement channel.

4.

Tested during logic system functional tests.

5.

Refer to Table 4.1.B.

6.

The logic system functional tests shall include a calibration once per operating cycle of time delay relays and timers necessary for proper functioning of the trip systems.

7.

The functional test will consist of verifying continuity across the inhibit with a volt-ohmmeter.

8.

Instrument checks shall be performed in accordance with the definition of instrument check (see Section 1.0, Definitions).

An instrument check is not applicable to a particular setpoint, such as Upscale, but is a qualitative check that the instrument is behaving and/or indicating in an acceptable manner for the particular plant condition.

Instrument check is included in this table for convenience and to indicate that an instrument check will be performed on the instrument.

Instrument checks are not required when these instruments are not required to be OPERABLE or are tripped.

9.

Calibration frequency shall be once/year.

10.

Deleted

11.

Portion of the logic is functionally tested during outage only.

12.

The detector will be inserted during each operating cycle and the proper amount of travel into the core verified.

13.

Functional test will consist of applying simulated inputs (see note 3).

Local alarm lights representing upscale and downscale trips will be verified, but no rod block will be produced at this time.

The inoperative trip will be initiated to produce a rod block (SRM and IRM inoperative also bypassed with the mode switch in RUN).

The functions that cannot be verified to produce a rod block directly will be verified during the operating cycle.

BFN 3.2/4.2-59 AMENDMENT IM.

Unit 2

NOTES FOR TABLES 2.A THROUGH 4.2.L except 4.2.D

.D 4.2.K (Cont'd)

14.

(Deleted)

15.

The flow bias comparator will be tested by putting one flow unit in "Test" (producing 1/2 scram) and adjusting the test input to obtain comparator rod block.

The flow bias upscale will be verified by observing a local upscale trip light during operation and verified that it will produce a rod block during the operating cycle.

16.

Performed during operating cycle.

Portions of the logic is checked more frequently during functional tests of the functions that produce a rod block.

17.

This calibration consists of removing the function from service and performing an electronic calibration of the channel.

18.

Functional test is limited to the condition where secondary containment integrity is not required as specified in Sections 3.7.C.2 and 3.7.C.3.

19.

Functional test is limited to the time where the SGTS is required to meet the requirements of Section 4.7.C.l.a.

20.

Calibration of the comparator requires the inputs from both recirculation loops to be interrupted, thereby removing the flow bias signal to the APRM and RBM and scramming the reactor.

This calibration can only be performed during an outage.

21.

Logic test is limited to the time where actual operation of the equipment is permissible.

22.

(Deleted)

23.

(Deleted)

24.

This instrument check consists of comparing the thermocouple readings for all valves for consistence and for nominal expected values (not required during refueling outages).

25.

During each refueling outage, all acoustic monitoring channels shall be calibrated.

This calibration includes verification of accelerometer response due to mechanical excitation in the vicinity of the sensor.

BFN 3.2/4.2-60 Amendment 210 Unit 2

NOTES FOR TABLES 4.2.A THROUGH 4.2.L except 4.2.D AND 4.2.K (Cont'd)

26.

This instrument check consists of comparing the background signal levels for all valves for consistency and for nominal expected values (not required during refueling outages).

27.

Functional test consists of the injection of a simulated signal into the electronic trip circuitry in place of the sensor signal to verify OPERABILITY of the trip and alarm functions.

28.

Calibration consists of the adjustment of the primary sensor and associated components so that they correspond within acceptable range and accuracy to known values of the parameter which the channel monitors, including adjustment of the electronic trip circuitry, so that its output relay changes state at or more conservatively than the analog equivalent of the trip level setting.

29.

The functional test frequency decreased to once/3 months to reduce challenges to relief valves per NUREG-0737, Item II.K.3.16.

30.

Calibration shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr and a one-point source check of the detector below 10 R/hr with an installed or portable gamma source.

31.

Functional Tests shall be performed once/3months.

32.

Functional testing for the Reactor Building Ventilation Radiation Monitoring System (RBVRMS) shall consist of verifying the High Voltage Power Supply (HVPS) voltage at the Sensor and Convertors (detectors) is within its design limits.

A channel functional test as defined in Section 1.0, "Definitions" shall be performed once per 18 months as part of the RBVRM channel calibration.

BFN 3.2/4.2-61 Unit 2 Amendment 210 I

THIS PAGE INTENTIONALLY LEFT BLANK BFN 3.2/4.2-61a AMFNDMM RD. Irs. a Unit 2

3.2 BASES (Cont'uc.

adequate to assure the above criteria are met.