ML20154B751

Amends 148,144 & 119 to Licenses DPR-33,DPR-52 & DPR-68, Respectively,Modifying Tech Spec Tables 3.2.B & 4.2.K to Correct Identified Inconsistencies

ML20154B751
Person / Time
Site:	Browns Ferry
Issue date:	05/04/1988
From:	Hermann R NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20154B754	List: ML20154B751
References
NUDOCS 8805170300
Download: ML20154B751 (16)

Text

6 UNITED STATES

/

NUCLEAR REGULATORY COMMISSION e,

j j

W ASHINGTON, D. C. 20555 t

TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 148 License No. OPR-33 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee)datedJanuary 14, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (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 Comission's regulations; 0.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

[

(

I 8805170300 000425 DR ADOCK 050 9

l

m 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. 148, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION l

/

f Rob lert A. Hermann, Acting Assi'. :at Dire N

for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: May 4, 1988 l

l I

'o ATTACHMENT T0_ LICENSE AMENDMENT NO. 148 FACILITY OPERAYING 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 INSERT 3.2/4.2-14 3.2/4.2-14 3.2/4.2-15 3.2/4.2-15*

3.2/4.2-62 3.2/4.2-62 l

l l

l l

o TABLE 3.2.8 E *n INSlRUMLNIA110N THAI IN111 AILS OR CONBROLS IHE C0kE AND CONIAINMLN1 COOLING SYSILMS

-- :=

Minimum No.

Operable per Trip Sys(l)

Function Trip level Setting Action Rer; arks 2

Instrument Channel -

> 470" above vessel zero.

A 1.

Below trip setting initiated HPCI.

Reactor Low Water Level 2

Instrument Channel -

> 470" above vessel zero.

A 1.

Multiplier relays initiate RCIC.

Reactor low Water Level 2

Instrument Channel -

> 378* above vessel zero.

A 1.

Below trip setting initiates Reactor low Water Level CSS.

(LIS-3-58A-D. SW #1)

Multinlier relays initiate LPCI.

2.

Multipiier relay from CSS initiates accident signal (15).

2(16)

Instrument Channel -

> 378" above vessel zero.

A 1.

Below trip settings, in

[

I#

Reactor Low Water Level conjunction with drywell

((

(LIS-3-58A-0, SW 82) high pressure, low water level pennissive,120 sec.

delay timer and CSS or c-

$f CHR pump running, initiates ADS.

s~

1(16)

Instrument Channel -

> 544" above vessel zero.

A 1.

Below trip setting pennissive Reactor Low Water Level

~

for initiating signals on ADS.

Permissive (LIS-3-184 &

185, SW #1) 1 Instrument Channel -

> 312 5/16" above vessel zero. A 1.

Below* trip setting prevents Reactor Low Water Level I2/3 core height) inadvertent operation of (LilS-3-52 and 62 SW #1) containment spray during accident condition.

BIN-Unit I 2p

$a3 2

?

70 m

~i CI CD 3 "n

-~ =

1ABLE 3.2.8 (Continued) l Minimum No.

Operable Per i

1 rip sys(l)

Function -

Trip level Setting Action Remarks 2

Instrument Channel -

15 p12.5 psig A

1.

Below trip setting, prevents inadvertent operation of Drywell High Pressure containment spray during (PS-64-58 E-H) accident conditions.

2 Instrument channel -

$ 2.5 psig A

1.

Above trip setting in con-junction with low reactor Drywell High Pressure pressure initiates CSS.

(PS-64-58 A-D, SW #2)

Multiplier relays initiate HPCI.

2.

Multiplier relay f oma CSS initiates accident signal. (IS) i 2

Instrument Channel -

> 410" above vessel zens A

1.

Below trip setting trips 1

Reactor Low Water tevel recirculation pumps.

]

(t.5-3-56A, B, C, 0)

La sa 2

Instrument Channel -

1 1120 psig A

1.

Above trip, setting trips j

Reactor High Pressure recirculation pumps.

j

];

(PS-3-204 A, B. C, D) w d-2 InstruLent Channel -

1 2.5 psig A

1.

Above trip setting in Drywell High Pressure conjunction with low

'a (PS-64-58A-D, SW #1) reactor pressure initiates LPCI.

2(16)

Instrument Channel -

1 2.5 psig A

1.

Above. trip setting, in Drywell High Pressure conjunction with low reactor (PS-64 -SIA -D) water level, drywell high pressure, 120 sec. delay timer and CSS or RHR pump i

running, initiates ADS.

f l

Bf N -Unit 1 a

1 4

=

.e E ",1

-z c+

TABLE 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance Channel functional Instrument Instrument Check Source Check Calibration Test 1.

SLACK a.

Noble Gas Monitor IS)

D M

RII)

Q(2) b.

lodine Cartridge W

NA NA NA c.

Particulate Filter W

NA NA NA d.

Sampler Flow Abnorinal D

NA R

Q e.

Stack Flowneter D

NA R

Q F

2.

REACIDk/IURBINEBLDGVg w

a.

Noble Gas Monitor D

M RII)

Q(2)

)

b.

lodine Sampler W

NA NA NA c.

Particulate Sanpler W

MA NA NA 7

d.

Sampler Flowneter D

NA R

Q cr-N 3.

TURBINE BiDG EXHAUSI Noble Gas Monitor (6)

D M

RIII QI2) a.

b.

lodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA d.

Sanpler Flowneter D

NA R

Q 4.

RADWASIE BLDG VLNi Noble Gas Monitor (6)

D M

RIII Q(2) 4.

b.

lodine Sampler W

NA NA NA c.

Particulate Sanpler W

NA NA NA d.

Sanpler Flowneter D

NA R

f),

5.

Of F GAS HYDROGEN ANALYlLR (H A, Hg)

D NA R(3) g l

2 6.

OFF GAS POSI 1REAIMLNI (6I Q(4)

I 4.

Noble Gas Activity Monitor D

M RIII Q 2) f b.

Sanple Flow Abnorinal D

NA R

h BfN4Jnit 1 N

E E.

.~

co

,( p m auq[o UNITED STATES g

c g

NUCLEAR REGULATORY COMMISSION y

g.

-l W ASHING TON, D. C. 20555

/

TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.144 License No. OPR-52 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated January 14, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

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

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

% 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and 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.144, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

/

Robert A. Hermann, Acting Assistant Director for Projects TVA Projects Division Office of Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: May 4, 1988 I

I l

i l

[

O ATTACHMENT TO LICENSE AMENDMENT NO. 144 FACILITY OPERATING LICENSE NO. OPR-52 00CKET 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 INSERT 3.2/4.2-14 3.2/4.2-14 3.2/4.?-15 3.2/4.2-15*

3.2/4.2-62 3.2/4.2-62 l

t i

i

1A81E 3.2.B IN51RUMLNIA110N lHAl INillAILS OR CONINOLS IHE CORE AND CONIAINMLN1 COOLING SYSILMS c,

am

• - :C Minimum No.

Operable Per N

Trip Sys(l)

Function Trip level Setting Action Remarks 2

Instrument Channel -

? 470" above vessel zero.

A 1.

Below trip setting initiated Reactor Low W ier level HPCI.

i (L15-3-58A-D) 2 Instruar.at Channel -

1 410" above vessel zero.

A 1.

Multiplier relays initiate Reactor Low W ier level RCIC.

(L15-3-58A -0) f 1

2 Instrument Channel -

1 378" above vessel zero.

A 1.

Below trip setting initiates Reactor Low W ter Level CSS.

(LIS-3-58A-D) i Multiplier relays initiate

,d LPCI.

w) 2.

Multiplier relay from C55 initiates accident signal (15).

n 1

2(16)

Instrument Channel -

> 378" above vessel zero.

A 1

Below trip settings, in Reactor Low W ier Level

~

conjunction with drywell (L15-3-58A-0) high pressure, low water l

level permissive, 120 sec.

delay timer and C55 or I

J RHR ptmp running, initiates ADS.

)

i 1(16)

Instrument Channel -

1 544" above vessel zero.

A 1.

Below trip setting permissive Reactor Low mter Level for initiating signals on ADS.

Permissive (L15-3-184, 185)

Instrument Channel -

> 312 5/16" above vessel zero. A 1.

Below trip setting, prevents Reactor low s ter level 12/3 core height) inadvertent operation of (L15-3-52 and 62) containment spray during accident condition.

i

=

4 2

Bf N-Unit 2

=

b s

1 u

1ABLE 3.2.8 (Continued) cw Minimwn No.

Operable Per Trip Sys(l)

Function Trip Level Setting Action Resnarks N

2 Instrument Channel -

15 p52.5 psig A

1.

Below trip setting, prevents Drymell High Pressure inadvertent operation of (P15-64-58 E-H) contaisument spray during accident conditions.

1 2

Instro ent Channel -

$ 2.5 psig A

1.

Above trip setting in con-Drywell High Pressure junction with low reactor (PS-64-58 A-0) pressure initiates CSS.

Multiplier relays initiate HPCI.

2.

Multiplier relay from CSS initiates accident signal. (15) 2 Instrument Channel -

> 410" above vessel zero A

1.

Below trip setting trips Reactor Iow Water level recirculation pumps.

(L15-3 -56A-0) 2 Instrument Channel -

$ 1I20 psig A

1.

Above trip setting trips Reactor High Pressure recirculat,on pumps.

m i

(PIS-3-204A-D) s~

2 Instrument Channel -

$ 2.5 psig A

1.

Above trip setting in Drywell High Pressure conjunction with low m

[

(Pl5 58A-D) reactor pressure initiates

LPCI, l

2(16)

Instrimment Channel -

-< 2.5 psig A

1.

Above trip setting, in Drywell High Pressure conjunction with low reactor (P15 44-57A-D) water level, drywell high pressure, 120 sec. delay timer and C55 or RHR pump running, initiates ADS.

4 I

J Bf N 4) nit 2 4

A 1

1

5

-x r*

TABLE 4.2.K N

Radioactive Gaseous Ef fluent Instrismentation Surveillance Channel functional Instrisment Instrument Check Source Check Calibration Test 1.

SIACK Noble Gas Monitor (5)

D M

RIII Q(2) a.

b.

lodine Cartridge W

NA NA NA c.

Particulate Filter W

NA NA NA d.

Sampler Flow Abnonnal D

NA R

Q e.

Stack Flomaneter D

NA R

Q 2.

REAC10R/IURBINEBLDGVg

'n 4.

Noble Gas Monitor D

M RIII Q(2)

)

b.

Iodine Sanpler W

NA NA NA c.

Particulate Sampler W

NA NA NA d.

Sampler Flomaneter D

NA R

Q e"

3.

luRB'.WL BLDG EXHAU51 Noble Gas Monitor (6)

D M

RII)

QI2) 4.

b.

todine 54 spier W

NA NA NA c.

Particulate Sampler W

NA NA NA d.

Sampler Flousneter D

NA R

Q 4.

RADWASIL BLDG VENT Noble Gas Monitor (6)

D M

RII)

Q(2) 4.

l b.

Iodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA d.

Sampler Flowneter D

NA R

Q a

5.

DIF CAS HYDROGLM A84ALYZLR (H A, H 8)

D NA R(3) g l

2 2

6.

Of F GAS POSI 1REAIMLNI ISI 4.

Noble Gas Activity Monitor D

M R(I)

Q((4) b.

Sample Flow Abnonnal D

NA R

Q 2) g

,ng BIN-Unit 2 2

.=

i

UNITED STATES NUCLEAR REGULATORY COMMISSION 3"

j j

WASHINGTON, D. C. 20555

'g..V...

TENNESSEE VALLEY AUTHORITi DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendinent No.119 License No. DPR-68 1.

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated January 14, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

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

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

a m

n v

7

,n-

4 6 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-68 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.119, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION W

Robert A. Hennann, Acting Assistant Director for Projects TVA Projects Division Office of Special Projects A

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 4, 1988

e ATTACHMENT TO LICENSE AMENDMENT NO. 119 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.

REMOVE INSERT 3.2/4.2-61 3.2/4.2-61 4

0 L

a l

I i

i

...,,.,., - -. ~ - -.. - -..- -.,

o E$

TABLE 4.2.K Radioactive Gaseous Effluent Monitoring Instrumentation

-2 eo Instrument Check Source Check Calibration Test w

Instrument Noble Gas mnitor ISI D

M RIII Q(2) 1.

STACK a.

l b.

todine Cartridge W

NA NA NA 4

c.

Particulate Fi3ter W

NA NA NA d.

Sampler Flow Abnonnal D

NA R

Q e.

Stack Flowneter D

NA R

Q 2.

REAC10R/10RBINE8tDGVg 4.

Noble Gas Monitor D

M RII)

Q(2) b.

Iodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA d.

Stack Floumeter D

NA R

Q 3.

IUR81NE BLDG EKHAUST Noble Gas Monitor (6)

D M

RII)

Q(2) 4.

b.

Iodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA d.

Stack Flowneter D

NA R

Q Y

w 4.

RADWA51E BLDG VENT Noble Gas Monitor (6)

D M

kII)

QI2) 2 a.

b.

Iodine Sampler W

NA NA NA 7

c.

Particulate Sampler W

NA NA NA e

d.

Stack Floumeter D

NA R

Q 5.

OIF GA5 HYDROGLN ANALYZER (H A, H 8)

D NA RI3)

Q l

2 2

6.

DFF GA5 POST TREAlMLNT (5) 4.

Noble Gas Activity Monitor D

M RIII QI4) b.

Sample Flow Abnonnal D

NA R

Qt2)

BfN-Unit 3 F

R S

n W