ML18038B085

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Amends 214,230 & 187 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Adding High Range Primary Containment RM & Recorders to TS
ML18038B085
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 12/21/1994
From: Hebdon F
Office of Nuclear Reactor Regulation
To:
Shared Package
ML18038B086 List:
References
DPR-33-A-214, DPR-52-A-230, DPR-68-A-187 NUDOCS 9412280066
Download: ML18038B085 (55)
v • d • e


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C." 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT 1

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

214 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 October 7,

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

94f2280066 94122k PDR ADOCK 05000259 P

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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 Faci.lity Operating License No.

DPR-33 is hereby amended to read as follows:

.3.

(2)

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

as revised through. Amendment No., 214, are hereby incorporated in the license.

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

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.

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

Attachment:

Changes to. the Techni'cal Specifications Date of Issuance:

December 21, 1994

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ATTACHMENT TO LICENSE 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 are provided to maintain document completeness.

REMOVE 3.2/4.'2-31 3.2/4.2-32 3.2/4.2-33 3.2/4.2-54 3.2/4.2-. 55 3.2/4.2-61 6.0-29 6.0-30.

INS RT 3.2/4.2-31*

3.2/4.2-32 3.2/4.2-33'.2/4.2-33a*

3.2/4.2-54*

3.2/4.2-55 3.2/4.2-61 3.2/4.2-6la*

6.0-29 6.0-30'

II

TABLE 3.2.F Survei 1 1 ance Instrumentation Hinimum 4 of Operabl e Ins trument h nn 1

~in r j~mn~4 LI-3-46 A LI-3-46 8 PI-3-54 PI-3-61 TI-64-52 TR-64-52 TR-64-52 Reactor Water Level Reactor Pressure Orywell Temperature Suppression Chamber Air Temperature Type Indication ndRn Indicator 155" to

+60"

~N (1) (2) (3)

Recorder, Indicator 0-400'F Recorder 0-400'F (1) (2) (3)

(1) (2) (3)

Indicator 0-1500 psig (1) (2) (3)

N/A N/A PS-64-67 TR-64-52 and PS-64-58 8 and IS-64-.67 LI-84-2A LI-84-13A Control Rod Pos ition Neutron Honitoring Drywell Pressure Orywell Temperature and Pressure and Timer CAD Tank "A" Level CAO Tank "8" Level 6V Indicating

)

Lights

)

SRH, IRH, LPRH

)

0 to lOOX power

)

Alarm at 35 psig

)

)

Alarm if temp.

)

> 281'F and

)

pressure

>2.5 psig )

after 30 minute

)

delay

)

Indicator 0 to 100K Indicator 0 to 10M (1) (2) (3) (4)

(1) (2) (3) (4)

(1)

(1)

tl J

TABLE 3.2.F (Cont'd)

Surveillance Instrumentation Hinimum 0 of Operable Instrument hannel I

2 1/Val ve I P0

~nrum n

H2H - 76 94 H2H - 76 104 PdI-64-137 PdI-64-138 LI-64-159A XR-64-159 P I-64-39A XR-64-159 PI-64-160A XR-64-159 TI-64-1 61 TR-64-161 TI-64-162 TR-64-162 RR-90-272 RR-90-273 RH-90-272A RH-90-273A RH-90-.306 RR-90-360 In rum n Drywell and Torus Hydrogen Concentration Drywell to Suppression Chamber Differential Pressure Relief Valve Tailpipe Thermocouple Temperature or Acoustic Honitor on Relief Valve Tailpipe Suppression Chamber Water Level-Wide Range Drywel1 Pressure Low Range Drywell Pressure Wide Range Suppression Pool Bulk Temperature High Range Primary Containment Radiation Honi tors and Recorders Wide Range Gaseous Effluent Radiation Honitor and Recorder Type Indication ndRn 0.1 - 20K Indicator 0 to 2 psid Indicator, Recorder 0-240" Indicator, Recorder)

-5 to +5 psig

)

Indicator, Recorder) 0-300 psig

)

Indicator, Recorder)

)

300 2300 F

)

)

Honi tor, Recorder 1 10 R/Hr 7

Honi tor, Recorder (Noble Gas 10

- 10+

pCi/cc)

(1) (2) (3)

(5)

(1) (2) (3)

( 1) (2) (3)

(1) (2) (3) (4) (6)

(7) (8)

(7) (8) (9)

I

NOTES FOR TABLE 2 F (1)

From and after the date, that one of these parameters is reduced to one indication, continued operation is permissible during the succeeding 30 days unless such instrumentation is sooner made operable.

(2)

From and after the date that one of these parameters is not indicated in the control room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.

(3) If the requirements of notes (1) and (2) cannot be met, and if one of the indications cannot be restored in (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a COLD SHUTDOWN CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(4)

These surveillance instruments are considered to be redundant to each other.

(5)

From and after the date that both the acoustic monitor and the temperature indication on any one valve fails to indicate in the control room, continued operation is permissible during the succeeding 30 days, unless one of the two monitoring channels is sooner made available. If both the primary and secondary indication on any SRV tailpipe is inoperable, the torus temperature will be monitored at least once per shift to observe any unexplained temperature increase which might be indicative of an open SRV.

(6)

A channel consists of eight sensors, one from each alternating torus bay.

Seven sensors must be operable for the channel 'to be operable.

(7)

When one of these instruments is inoperable. for more than seven days, in lieu of any other report required by Specification 6.9.1.4, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next seven days outlining the action

taken, the cause of inoperability, and the plans and schedule for restoring the system to OPERABLE status.

(8)

With the plant in REACTOR POWER OPERATION, STARTUP CONDITION, HOT STANDBY CONDITION OR HOT SHUTDOWN CONDITION and with the number of OPERABLE channels less than the required OPERABLE channels, either restore the inoperable channel(s) to OPERABLE Status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or initiate the preplanned alternate method of monitoring, the appropriate parameter.

(9)

Noble Gas only.

BFN Unit 1 3.2/4.2-33 A1KNDi~KNT NO.

214

I V

THIS PAGE'NTENTIONALLY'LEFT BLANK BFN Unit 1

3.2/4.2-33a

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TABLE 4.2.F HINIHUH TEST AND CALIBRATION FRE()UENCY FOR SURVEILLANCE INSTRUHENTATION In rmn hnnl

1) Reactor Mater Level
2) Reactor Pressure
3) Drywell Pressure
4) Drywell Temperature
5) Suppression Chamber Air Temperature
8) Control Rod Position
9) Neutron Honi toring
10) Drywell Pressure (PS-64-67) ll) Drywell Pressure (PS-64-5BB)
12) Drywell Temperature (TR-64-52)
13) Timer (IS-64-67) 14)

CAD Tank Level

15) Containment Atmosphere Honitors libr in r 'n Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months N/A (2)

Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months n

mn h

Each Shift Each Shift Each Shift Each Shift Each Shift Each Shift Each Shift N/A N/A N/A N/A Once/day Once/day

TABLE 4.2.F (Continued)

HINIHUH TEST AND CALIBRATION FRE()UENCY FOR SURVEILLANCE INSTRUHENTATION In rum n h nn 1

C libra ion Fr u n In rmn h

k

16) Drywell to Suppression Chamber Differential Pressure
17) Relief Valve Tailpipe Thermocouple Temperature
18) Acoustic Honitor on Relief Valve Tailpipe
19) Suppression Chamber Water Level-Wide Range (LI-64-159A) (XR-64-159)
20) Drywell Pressure Low Range (PI-64-39A) (XR-64-159)
21) Drywell Pressure Wide Range (PI-64-160A) (XR-64-159)
22) Suppression Pool Bulk Temperature (TI-64-161) (TR-64-161)

(TI-64-162) (TR-64-162)

23) High Range Primary Containment Radiation Honitors and Recorders (RR-90-272, RR-90-273, RH-90-272A and RH-90-273A)
24) Wide Range Gaseous Effluent Radiation Honitor and Recorder (RH-90-306 and RR-90-360)

Once/6 months N/A Once/cycle (25)

Once/cycle Once/cycle Once/cycle Once/cycle Once/18 months (32)

Once/18 months Each Shift Once/month (24)

Once/month (26)

Once/month Once/shift Once/shift Once shift Once/month Once/shift

~

0 NOTES FOR T BLES 4 A THROUGH 4 2 L exce t 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.

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.

31.

Functional tests, shall be performed once/3 months.

32.

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.

BFN Unit 1 3.2/4.2-61 AilKGMZiCHO. 214

THIS PAGE INTENTIONALLYLEFT BLANK BFN Unit 1

3.2/4.2-61a

8.

Secondary Containment Leak Rate Testing+

a.7.C.

Within 90 days of,completion of each test.

9.

High Range Primary Containment Radi'ation Monitors and Recorders 3.2.F Within 7 days after 7 days of inoperability.

10.

Wide Range Gaseous Effluent Radiation Monitor and Recorder 3.2.F Within 7 days after 7 days of inoperability.

This report should include data on the wind speed, wind direction, outside and inside temperatures, during the test, concurrent reactor building pressure, and emergency ventilation flow rate.

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

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

a.

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

Principal maintenance activities c.

Reportable Events d.

Checks, inspections,
tests, and calibrations of components and,systems, including such diverse items as source leakage e.

Reviews of changes made to the procedures or equipment or reviews of tests and experiments to comply with 10 CFR 50.59 f.

Radioactive shipments g'.

Test results in units of microcuries for leak tests performed pursuant to Specification 3.8.D BFN Unit 1 6.0-29 umvzzzi: no.

zoo

h.

Record of annual physical inventory verifying accountability of sources on record i.

Records of gaseous and liquid radioactive waste released to the environs, and the resulting calculated dose to individual,'MEMBERS OF THE PUBLIC Offsite environmental monitoring surveys

'k.

Fuel inventories and transfers 1.

Plant radiation and contamination surveys m.

Radiation exposures for all plant personnel for whom monitoring was required, n.

Updated, corrected, and as-built drawings of the plant o.

Reactor coolant.system inservice inspection p.

Minutes of meetings of the HSRB q.

Design fatigue.usage evaluation Monitoring and recording requirements below will be met for various portions of the reactor coolant, pressure boundary (RCPB) for which detail'ed fatigue usage evaluation per the ASME Boiler and'ressure Vessel Code Section III was

'erformed for the conditions defined in the design specification.

In this plant, the applicable codes require

,fatigue usage evaluation for the reactor pressure vessel only.

The locations to be monitored shall be:

1.

The feedwater nozzles 2.

The shell at or near the waterline BFN Unit 1 3.

The flange studs 6.0-30 AMENOMEHTling. 2 0 y

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260

,BROWNS FERRY NUCLEAR PLANT UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

230 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 October 7,

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.

0 0

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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-52 is hereby amended to read as fol.lows:

3.

(2)

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

as revised through Amendment No. 230, are hereby incorporated in the license.

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

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.

Heb on, Director Project Directorate II-4 Divi'sion of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 21, 1994

ATTACHMENT TO LICENSE AMENDMENT NO.

230 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 are provided to maintain document completeness.

REMOVE 3.2/4.2-31 3.2/4.2-32 3.2/4.2-54 3.2/4.2-55 6.0-29 6.'0-30 INSERT 3.2/4.2-31*

3.2/4.2-32 3.2/4.2-54*

3.2/4.2-55 6.0-29

'6.0-30*.

TABLE 3.2.F Surveillance Instrumentation Hinimum 4 of Operable Instrument harm 1

~)n rum n LI-3-58A LI-3-588 PI-3-74A PI-3-748 Reactor Water Level Reactor Pressure Type Indication ndRn Indicator -155" to

+60u Indicator 0-1200 psig

~N (1) (2) (3)

( 1) (2) (3)

XR-64-50 PI-64-678 Drywell Pressure Recorder -15 to +65 psig (1) (2) (3)

Indicator -15 to +65 psig m

C7 t4 M

XR-64-50 TI-64-52A8 XR-64-52 N/A N/A PS-64-678 TS-64-52A S

PIS-64-58A 8

IS-64-67A LI-84-2A LI-84-13A Drywell Temperature Suppression Chamber Air Temperature Control Rod Position Neutron Honi toring Drywell Pressure Drywell Temperature and Pressure and Timer CAD Tank "A" Level CAD Tank uB" Level

Recorder, Indicator 0-400'F Recorder 0-400'F 6V Indicating

)

Lights

)

SRH, IRH, LPRH

)

0 to 100K power

)

Alarm at 35 psig

)

)

Alarm if temp.

)

> 281'F and

)

pressure

>2.5 psig )

after 30 minute

)

delay

)

Indicator 0 to 1001 Indicator 0 to 100K (1) (2) (3)

(1) (2) (3)

(1) (2) (3) (4)

(1) (2) (3) (4)

Minimum ¹ of Operable Instrument harm 1

1/Val ve n

rum n H2H 94 H2H 76 104 PdI-64-137 PdI-64-138 RR-90-272 RR-90-273 RH-90-272C RH-90-273C LI-64-159A XR-64-159 PI-64-160A XR-64-159 TI-64-1 61 TR-64-161 TI-64-162 TR-64-162 RH-90-306 RR-90-360 TABLE 3.2.F (cont'd)

Surveillance Instrumentation In rum n Drywell and Torus Hydrogen Concentration Drywell to Suppression Chamber Differential Pressure Relief Valve Tailpipe Thermocouple Temperature or Acoustic Honitor on Relief Valve Tailpipe High Range Primary Containment Radiation Honitors and Recorders Suppression Chamber Water Level-Wide Range Drywell Pressure Wide Range Suppression Pool Bulk Temperature Wide Range Gaseous Effluent Radiation Honitor and Recorder Type Indication ndRn 0.1 - 20K Indicator 0 to 2 psid Honi)or, Recorder 1-10 R/HI Indicator, Recorder 0-240" Indicator, Recorder) 0-300 psig

)

Indicator, Recorder)

)

300 - 2300 F

)

)

Honitor and Recorder (Hoble Gas 10

- 10 pCi/cc)

(1) (2) (3)

(5)

(7)(8)

(1) (2) (3)

(1) (2) (3)

(1) (2) (3) (4) (6)

(7)(8)(9)

TABLE 4.2.F HINIHUH TEST ANO CALIBRATION FREQUENCV FOR SURVEILLANCE INSTRUHENTATION In trumen Channel

1) Reactor Water Level (LI-3-58A&B)
2) Reactor Pressure (PI-3-74ACB)
3) Drywall Pressure (PI-64-678) and XR-64-50
4) Orywell Temperature (TI-64-52AB) and XR-64-50
5) Suppression Chamber Air Temperature (XR-64-52)
8) Control Rod Position
9) Neutron Honitoring
10) Drywell Pressure (PS-64-67B) ll) Orywell Pressure (PIS-64-58A)
12) Orywell Temperature (TS-64-52A)
13) Timer (IS-64-67A) 14)

CAD Tank Level

15) Containment Atmosphere Honitors alibration Fre u nc Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months N/A (2)

Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months In rum n h

k Each Shift Each Shift Each Shift Each Shift Each Shift Each Shift Each Shift N/A N/A N/A N/A Once/day Once/day

r r

P

TABLE 4.2.F (Continued)

HINIHUH TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUHENTATION In trum n bann 1

libra i n Fre uen In rum n h

k lA IVl Vl

16) Drywell to Suppression Chamber Differential Pressure
17) Relief Valve Tailpipe Thermocouple Temperature
18) Acoustic Honi tor on Relief Valve Tailpipe
19) High Range Primary Containment Radiation Honitors and Recorders (RR-90-272, RR-90-273, RH-90-272C, and RH-90-273C)
20) Suppression Chamber Water Level-Wide Range (LI-64-159A) (XR-64-159)
21) Drywell Pressure - Wide Range (PI-.64-160A) (XR-64-159)
22) Suppression Pool Bulk Temperature (TI-64-161) (TR-64-161)

(TI-64-162) (TR-64-162)

23) Wide Range Gaseous Effluent Radiation Honitor and Recorder (RH-90-306 and RR-90-360)

Once/6 months N/A'nce/cycle (25)

Once/18 Honths (30)

Once/18 Honths Once/18 Honths Once/18 Honths Once/18 Honths Each Shift Once/month (24)

Once/month (26)

Once/month Once/shift Once/shi ft Once/shift Once/shift 5

8 l~

~

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O lQ C)

4l r

8.

Secondary Containment Leak Rate Testing*

4.7.C.

Within 90 days

.of completion, of each test.

9.

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

10. Wide-Range Gaseous Effluent 3.2.F'adiation Monitor and recorder Within 7 days after 7 days of inoperability.

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

This report should include data on the wind speed, wind direction, outside.and inside 'temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate.

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

6.10, STATION OPERATING RECORDS AND RETENTIO 6'.10.1 Records and/or logs shall be kept in a manner convenient for review as indicated bel'ow:

a.

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

Principal maintenance activities c.

Reportable Events d.

Checks, inspections,
tests, and calibrations of components and systems, including such diverse items as source leakage e.

Reviews of changes made 'to the procedures or equipment or reviews of tests and experiments to comply with 10 CFR 50.59 f.

Radioactive shipments g.

Test results 'in units of microcuries for leak tests performed pursuant to Specification 3.8.D BFN Unit 2 6.0-29

'QKivOi~i NO. 230

~

~

h.

Record of annual'hysical inventory verifying accountability of sources on record i.

Records of gaseous and liquid radioactive waste released to the environs, and the resulting, calculated dose to individual MEMBERS OF THE PUBLIC j.

Offsite environmental monitoring'urveys k.

Fuel inventories and transfers 1.

Plant radiati'on and contamination surveys m.

Radiation exposures for all plant personnel for whom monitoring was required n.

Updated, corrected, and as-built drawings of the plant o.

Reactor coolant system inservice inspection p.

Minutes of meetings of the HSRB q.

Design fatigue usage evaluation Monitoring and recording requirements below will be met for various portions of the reactor coolant pressure boundary (RCPB) for which detailed fatigue usage evaluation per the ASME Boiler and Pressure Vessel Code Section III was performed for the conditions defined in the design specification.

In.this plant, the applicable codes require fatigue usage evaluation for the reactor pressure vessel only.

The locations to be monitored shall be:

1.

The feedwater nozzles 2.

The shell at or near the waterline

,BFN Unit 2 3.

The flange studs 6.0-30 AMENOVENT NO. 2 2 0'

II

pe RECC 0

Cl D Q

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+**++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 TENNESSE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

187 License No.

DPR-68 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated October 7,

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 (i'i) 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.

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-68 is hereby amended to read as follows:

(2)

Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 187, are hereby incorporated in the license.

The licensee shall operate the faci.lity in accordance with the Technical Specifications.

3.

This l,icense 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

./

Freder ick J. Hebdo, Director Project Directorate II-4 Divi s i on of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

December 21',

1994 "i

4

4l II

ATTACHMENT TO LICENSE AMENDMENT NO.

187 FACILITY OPERATING LICENSE NO.

DPR-68 DOCKET 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 are provided to maintain.

document completeness.,

REMOVE 3.2/4.2-30 3.2/4.2-31 3.2'/4.2-32 3.2/4.2-53 3.2/4.2-54 3.2/4'.2-60 6.0-29 6.0-30 INSERT 3.2/4.2-30*

3.2/4.'2-31 3.2/4.2-32 3.2/4.2-32a*

3.2/4/2-53*

3.2/4.2-54

,3.2/4.2-60 3.2/4.2-60a*

6.0-29 6.0-30*

Cl P

TABLE 3.2.F Surveillance Instrumentation Minimum 0 of Operable Instrument h nn 1

n rum n LI-3-46 A LI-3-46 8 PI-3-54 PI-3-61 In rmn Reactor Water Level Reactor Pressure Type Indication ndRn Indicator 155" to

+60" Indicator 0-1500 psig (1) (2) (3)

(1) (2) (3)

XR-64-50 PI-64-67 TI-64-52 XR-64-50 XR-64-52 Drywel1 Pressure Orywell Temperature Suppressi on Chamber Air Temperature

Recorder, Indicator 0-400'F Recorder 0-400'F (1) (2) (3)

(1) (2) (3)

Recorder -15 to +65 psig (1) (2) (3)

Indicator -15 to +65 psig N/A N/A PS-64-67 XR-64-50 and PS-64-58 8 and IS-64-67 LI-84-2A LI-84-13A Control Rod Position Neutron Moni toring Drywell Pressure Orywell Temperature and Pressure and Timer CAO Tank "A" Level CAD Tank "8" Level 6V Indicating

)

Lights

)

SRM, IRM, LPRM

)

0 to 100K power

)

Alarm at 35 psig

)

)

Alarm if temp.

)

> 281'F and

)

pressure

>2.5 psig )

after 30 minute

)

delay

)

Indicator 0 to lOOX Indicator 0 to 100K (1) (2) (3) (4)

(1) (2) (3) (4)

(1)

('i)

lA IlA I

~~o CD Hinimum 0 of Operable Instrument h nn 1

1/Val ve

~ln rum n H2H 76 - 94 H2H 76 104 PdI-64-137 PdI-64-138 LI-64-159A XR-64-159 PI-64-160A XR-64-159 TI-64-161 TR-64-161 TI-64-1 62 TR-64-162 RR-90-272 RR-90-273 RH-90.-272A RH-90-273A RH-90-306 RR-90-360 TABLE 3.2.F (cont'd)

Surveillance Instrumentation In rum n Drywell and Torus Hydrogen Concentration Drywell to Suppr'ession Chamber Differential Pressure Relief Valve Tailpipe Thermocouple Temperature or Acoustic Monitor on Relief Valve Tailpipe Suppression Chamber Water Level-Wide Range Drywel1 Pressure Wide Range Suppression Pool Bulk Temperature High Range Primary Containment Radiation Honitors and Recorders Wide Range Gaseous Effluent Radiation Honitor and Recorder Type Indication ndRn 0.1 - 201 Indicator 0 to 2 psid Indicator, Recorder 0-240" Indicator, Recorder) 0-300 psig

)

Indicator, Recorder)

)

300 - 2300 F

)

)

Honitor, Recorder 1 - 10 R/Hr 7

Honitor, Recorder (Noble Gas 10

-10 5 pCi/

)

(1) (2) (3)

(5)

(1) (2) (3)

(1) (2) (3)

(1) (2) (3) (4) (6)

(7) (B)

(7)(B)(9)

NOTES FOR TABLE 2.F (1)

From and after the date that one of these parameters is reduced to one indication, continued operation is permissible during the succeeding 30 days unless such instrumentation is sooner made operable.

(2)

From and after the date that one of these parameters is not indicated in the control room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.

(3) If the requirements of notes (1) and (2) cannot be met, and if.one of the indications cannot be restored in (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a COLD SHUTDOWN CONDITION with'in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(4)

These surveillance instruments are considered to be redundant to each other.

(5)

From and after the date that both the acoustic monitor and the temperature indication on any one valve fails to indicate in the control room, continued operation is permissible during the succeeding 30 days, unless one of the two monitoring channels is sooner made available. If both the primary and secondary indication on any SRV tailpipe is inoperable, the torus temperature will be monitored at least once per shift to observe any unexplained temperature increase which might be indicative of an open SRV.

(6)

A channel consists of eight sensors, one from each alternating torus bay.

Seven sensors must be operable for the channel to be operable.

(7)

When one of these instruments is inoperable for more than seven days, in lieu of any other report required. by Specification 6.9.1.4, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next.seven days outlining the action

taken, the cause of inoperability, and the plans and schedule for restoring the system to OPERABLE status.

(8)

With the plant in REACTOR POWER OPERATION, STARTUP CONDITION, HOT STANDBY CONDITION OR HOT SHUTDOWN CONDITION and with the number of OPERABLE channels less than the required OPERABLE channels, either restore the inoperable channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or initiate the preplanned alternate method of monitoring the-appropriate parameter.

(9)

Noble Gas only.

BFN Unit 3 3.2/4.2-32 Zru-erma no.

Ze7

t 1,

THIS PAGE INTENTIONALLYLEFT BLANK BFN Unit 3 3.2/4.2-32a

4l I

r

TABLE 4.2.F HINIHUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUHENTATION In rumn hnn 1

1) Reactor Water Level
2) Reactor Pressure
3) Drywell Pressure
4) Drywell Temperature
5) Suppression Chamber Air Temperature
8) Control Rod Position
9) Neutron Honitorin9
10) Drywell Pressure (PS-64-67)
11) Drywell Pressure (PS-64-58B)
12) Drywell Temperature (TR-64-52)
13) Timer (IS-64-67) 14)

CAO Tank Level

15) Containment Atmosphere Honitors alibr i n Fr n

Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months N/A (2)

Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months Once/6 months n

n h

Each Shift Each Shift Each Shift Each Shift Each Shift

'ach Shift Each Shift N/A N/A N/A N/A Once/day Once/day

TABLE 4.2.F (Cont'd)

HINIHUH TEST AND CALIBRATION FRE(}UENCY FOR SURVEILLANCE INSTRUHENTATION In rinn hnn1 C libra i n Fr n

n r

n

16) Drywell to Suppression Chamber Differential Pressure
17) Relief Valve Tailpipe Thermocouple Temperature
18) Acoustic Honitor on

'Relief Valve Tailpipe

19) Suppression Chamber Water Level-Wide Range (LI-64-159A) (XR-64-159)
20) Drywell Pressure Wide Range (PI-64-160A) (XR-64-159)
21) Suppression Pool Bulk Temperature (TI-64-161) (TR-64-161)

(TI-64-162) (TR-64-'162)

22) High Range Primary Containment Radiation Honitors and Recorders (RR-90-272, RR-90-273, RH-90-272A, RH-90-273A)
23) Wide Range Gaseous Effluent Radiation Honitor and Recorder (RH-90-306 and RR-90-360)

Once/6 months N/A Once/cycle (25)

Once/cycle Once/cycle Once/cycle Once/18 months (32)

Once/18 months Each Shift Once/month (24)

Once/month (26)

Once/month Once/shift Once shift Once/month Once/shift

Ib e

OTES FOR ABLES 4 2

A THROUGH '4 2 L'xce t 4 2 D AND 4 (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 frequency decreased to once/3 months to reduce the challenges to relief valves per NUREG-0737, Item II.K.3.16.

28.

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

29.

Calibration consists of the adjustment of the primary sensor and associated'omponents 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 its output relay changes state at or more conservatively than the analog equivalent of the trip level setting.

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 limi'ts.

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.

, 31.

Functional tests shall be performed once/3 months.

32.

Calibration shall consist of an electronic calibration of the channel, not including the detector, for range decad'es

.above 10 R/hr and a one-point source check of the detector below-10 R/hr with an installed or portable gamma source.

BFN Unit 3 3.2/4.2-60 hl~a<DiCx.~ ho.

187

II

<t 4

THIS PAGE INTENTIONALLYLEFT BLANK BFN Unit. 3 3.2/4.2-60a

I V'a 8.

Secondary Containment Leak Rate Testing*

4.7.C.

Within 90 days of completion of each test.

9.

High Range Primary Containment Radiation Monitors and Recorders 3'.2.F Within 7 days after 7 days of inoperability.

10.

Wide Range Gaseous Effluent Radiation Monitor and Recorder 3.2.F Within 7 days after 7 days of inoperability.

This report should include data on the wind speed,,

wind, direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate.

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

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

a.

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

Principal maintenance activities c.

Reportable'vents d.

Checks,. inspections,

tests, and calibrations of components and systems, including such diverse i'tems as source leakage e.

Reviews of changes made to the procedures or equipment or reviews of tests and experiments to comply with 10 CFR 50.59 f.

Radioactive shipments g.

Test results in units of microcuries for leak tests performed pursuant to Specification 3.8.D BFN Unit 3 6.0-29'?K".D'mL": i'0.

1f~7

h.

Record of annual physical inventory veri'fying accountability of sources on record i.

Records of gaseous and liquid radioactive waste released to

.the environs, and the resulting calculated dose to individual MEMBERS OF THE PUBLIC j.

Offsite environmental monitoring surveys k.

Fuel inventories and transfers 1.

Plant radiation and contamination surveys m.

Radiation. expo'sures for all plant personnel for whom monitoring.-was required.

n.

Updated, corrected, and as-built drawings of the plant o.

.Reactor coolant system inservice inspection p.

Minutes of meetings. of the NSRB q.

Design. fatigue usage evaluation Monitoring and recording requirements below will be.met for various portions of the reactor coolant pressure boundary.

(RCPB) for which detailed fatigue usage evaluation per the ASME Boiler and Pressure Vessel Code Section III was performed for the conditions defined in the design specification.

In this plant, the applicable codes require fatigue usage evaluation for the reactor pressure vessel only.

The 1'ocations to be monitored shall be:

1.

The feedwater nozzles 2.

The shell at or.near the waterline BFN Unit 3 3.

The flange studs 6.0-30 AMENDMENTNO. I74

0 (e

t<

E

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