ML19259B637

Amend 48 to DPR-33 Changing Tech Specs Re Trip Levels & Surveillance Requirements for Instruments That Initiate Rod Blocks

ML19259B637
Person / Time
Site:	Browns Ferry
Issue date:	02/08/1979
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML19259B638	List: ML19259B637 ML19259B639 ML19259B641
References
NUDOCS 7903130483
Download: ML19259B637 (11)

Text

.

N UNITED STATES

[#

r NUCLEAR REGULATORY COMMISSION v

4

{j'*..

WASntNGTON, D. C. 20555 O

y

%~*

S***

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-33 1.

The Nuclear Regula v y Commission (the Commission) has found tha,t:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated September 8, 1978, as supplemented by letters dated October 5, 1978, November 30, 1978, December 5, 1978, December 14, 1978, January 8,1979, January 9,1979 and January 23, 1979, 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 fortn 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 nf the Comission.

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health arid 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 accoraance with 10 CFR Part

~

51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

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

(2) Technical Soecifications The Tecnnical Specifications contained in Appendices A and B, as revised through Amencment No. 48, are hereby incorporated in the license.

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

7903130473

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Thomas K? p dt.

Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors

Attachment:

~

- Changes to the Technical Specifications Date of -Issuance: February 8,1979 e

ATTACHMENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. OPR-33 DOCKET NO. 50-255 Revise Appendix A as follows:

1.

Remove the following pages and replace with identically numbered pages:

69/70 71/72 101/TU2 T59/160 2.

The underlined pages are those being changed; marginal lines on these pages indicate the revised area. The overleaf pages are provided for convenience.

e

TABI.E 3.2.5 (Continued)

Hinimua No.

Operable Per Trip Sys (1)

Function Trip Level Setting Action Remarks 54 1(3)

Core Spray 1.oop A 0 - 500'psig Indicator (9)

D 1.

Part of filled disefiarge pipe Discharge Pressure requirements. Refer,to Section 4.5.

(PI-75-20) 1(3)

Core Spray toop B 0 - 500 psig Indicator (9)

D 1.

Part of filled discharge pipe Discharge Pressure requirements. Refet to Section 4.5.

(PI-75-48) 1(3)

RitR Loop A Discharge 0 - 450 psig Indicator (9)

D 1.

Part of filled discharge pipe Pressure (PI-74-51) requirements. Refer to Section 4.5.

1(3)

EllR Loop B Discharge 0 - 450 psig Indicator (9)

D 1.

Part of ft11ed discharge pipe Pressure (PI-74-65) re'quirements. Refer to Section 4.5.

1(10)

Instrument. Channel -

N/A A

1.

Starts RIIR area cooler f an when RI'.R S t a r t respective Ri!R motor starts.

_ 100*F A

1.

Above trip setting starts RilR area 1(10)

Instrument channel -

Thermostat (RilR Area Cooler cooler fans.

Fan) 2(10)

Instrument Ch,nnel -

N/A A

1.

Starts Core Spray area cooler fan Core Spray A or C Start when Core Spray motor starts 2(10)

Instrument Channel -

N/A A

1.

Starts Core Spray area cooler f an Core Spray B or D when Core 3 pray motor starts 1(10)

Instrument Channel -

< 100* T A

1.

Above trip setting starts Core Spray Ther,sostat (Core Spray Area area cooler fans Cooler Fan)

TABLE 3.2.n (Continued)

Minlaua No.

Operable Per Bip Sys (1)

Function Trip Level Setting Action Remarks 1(10)

KilR Area Cooler Fan Lostc N/A A

1(10)

Core Spray Area Cooler Fan 1.ogic 1/A A

1(11)

Instrument Channel -

1. /A A

1.

Starts RllRSW rurups Al & DI Core Spray Motors A or D Start 1(11)

Instrument Channel -

N/A A

1.

Starts RifR$W puwpe D1 & C3 Core Spray Hotors B or C Start 1(12)

Instrument Channel -

N/A A

1.

Starts RIIRSW puups A3 & C3 Core Spray Loop 1 Accident Signal (15) e, 1(12) lustrument Channel -

A/A A

1.

Starts Rl!RSW' pumps 01 & DI Core Spray Loop 2 Accident Signal (15) 1(13)

RitRSW Initiate Logic N/A-(14)

I til"I' logic N/A

( l'( )

1.

Tripn recirculation piun g.:.

on t.urbine cont rol, vnl ve fan t, clontare or ut.e,p va l v.

clonute > 30% Iwwcr

NOTES FOR TABLE 3.2.8

~

1.

Whenever any CSCS System is required by section 3.5 to be operable, there shall be two operable trip systems except as noted.

If a requirement of the firrt column is reduced by one, the indicated action shall be taken. It the same function is inoperable in more than one trip system or the first column reduced by more than one, action 5 s, hall be taken.

Action:

A.

Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the function is not operable in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, take action B.

B.

Declare the system or component inoperable.

C.

Immediately take action B until power is verified on the trip

. system.

D.

No action required, indicators are considered redundant.

2.

In only one trip system.

3.

Not considered in a trip system.

4.

Requires one channel from each physical location (there are 4 loca-tions) in the steam line space.

5.

With diesel power, each RERS pump is scheduled to start immediately and each CSS pump is sequenced to start about 7 see later.

6.

With normal power, one CSS and one RRRS pump is scheduled to start instantaneously, one CSS and one RHRS pump is sequenced to start after about 7 sec with similar pumps starting after about 14 see and 21 sec, at which time the full complement of CSS and RERS pumps would be operating.

7.

The RCIC and HFCI steam line high flow trip level settings are given in terms of differential pressure. The RCICS setting of 450" of H 0 3 corresponds to 300% of rated steam flow at 1140 pois and 210% at 165 pois.

The HPCIS setting of 90 psi corresponds to 225% of rated flow at 1140 pois and 160% at 165 pets.

8.

Note 1 does not apply to this iteu.

f.

The head tank is designed to assure that the discharge piping ficm the CS and RllR pumps are full. The pressure shall be maintained at or above the values listed in 3.5.1, which ensures vatst in the discharge piping and up to the head tank.

71

_ NOTES FOR TARIE 3.2.B (Continued) 10.

Only one trip system for each cooler fan.

11.

In only two of the four 4160 V shutdown boards. See note 13.

12.

In only one of the fcur 4160 V shutdown boards. See note 13.

13. An emergency 4160 V shutdown board is considered a trip system.

14.

RERSV pump would be inoperable. Refer to section 4.5.C for the

. requirements of a RHRSW pump being inoperable.

15. The accident signal' is the satisf actory completion of a one-out-of-two taken twice logic of the drywell high pressure plus low reactor pres-sure or the vessel low vster level (* 378" above vessal sero) originating in th'a core spray systes trip system 7 16.

The ADS circuitry is capable of acccmplishing its protective actica with one operable trip system. Therefore one trip syntes =ay be taken out of service for functional testing and calibrarien for a period not to exceed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Two RPT systems exi.,t, either of which will trip both recirculation

.17.

e pumps.

The systems will be individually functionally tested monthly.

If the test period for one RPT system exceeds 2 consecutive hours, the system will' be declared inoperable.

If both RPT systems are inoperable or if 1 RPT system is inoperable for more than 72 consecutive hours, an orderly power reduction shall be initiated and the reactor power shall be less than 85% within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

O 72

e.ne t a n.. i j Function Functtonal Test Calibration Instrument t' heck RilR Area Cooler 7an logic Teste.1 during II/A ta/A functional test of in s t rurien t channels..

KlR motor start and*

the nno s t s t (RUR area r.ooler f an). No other t e_s t requitcJ.

Core Spray Area Cooler Fan logic Teste.1 durtnr. lor.ic N/A N/A system functions 1 test of inst nament channels, core spray anotor start and thertso-stat (core spray area cooler fan). No other test required.

Instrument Channel -

Tested during functional N/A N/A c3 Core Spray Hotore A or D Start test of core spray pump (refer to section 4.5.A).

Ins t rumen t Cha nnel -

Tested during functional N/A N/A Cure Spray Hotora B dr C Start test of core spray pump (refer to section 4.5,A).

Inst ru:nent Cluonnel -

Tested during logic ti/A 4/A Core Spray 1.oop 1 Accident system functional Signal test of core spray system.

Instrursent Channel -

Tested durlog logic

• H/A N/A core Spray teop 2 Accik systein functional Signal test of core spray system.

N/A PHR$W Initiate IAgic once/(. seonths H/A lil'T l ull.inte los;1c once /mont.h y/A

gjf, Ill'T breaker once/operatinr. Cycle N/A H/A

TABLE 4.2.C SURVEILLMCE REQUIPDElffS FOR INSTRU!!DfTATION T1 TAT INITIATE ROD BLOCKS Punctien Functional Test Calibration (17)

Instrument Check APRM Upscale (Flow Blas)

(1)

(13) once/3 months

' once/ day (8)

APRM Upscale (Startup Mode)

(1)

(13) once/3 months once/ day (8)

APRH Downscale (1)

(13) once/3 aanths once/ day (8)

APRM Inog,erative (1)

(13)

N/A once/dsy (8)

RBM Upscale (Y1ou Blas)

(1)

(13) once/6 months once/ day (8) 1111 Dounseale (1)

(13) once/6 months once/ day (8)

REM Inoperative (1)

(13)

N/A once/ day (8) h IRH Upscale (1)(2)

(13) once/3 months once/ day (8)

IRH Downscale (1)(2)

(13) once/3 mans.hs once/ day (8) 1RH Detector not in Startup (2) (once/ opera-once/ operating cycle (12)

N/A Position ting cycle)

IRH Inoperative (1)(2)

(13)

N/A N/A SRJi Upscale (1)(2)

(13) once/3 months once/ day (8)

SRH Downscale (1)(2).

(13) once/3 moths once/ day (8)

SRH Detector not in Startup

/2) (once/ opera-once/ operating cycle (12)

N/A rosition ting cycle)

SRH Inoperative (t)(2)

(!3)

N/A N/A Flou BIse cos,psrator (1)(15) once/ operating cycle (20)

N/A Flou Dias Upscale (1)(15) once/3 months N/A RoJ Block Logic (16)

N/A N/A RSCS Restrutnt.

(1) once/3 months N/A

gmr ttggey. eU?llyMrNTS LDeiflW" CONtstTtnNS Fnt OPFR/.TinN 4.5.H Maintensnee of Tilled Discharme Pise

.5.M Maintenanee or rilled Discharge Pipe We suction of the RCIC and HPCI pumps 1.

Every month prior to the t; sting dall be alirned to the conder. sate of the RXRS (LPCI and Containment storage tank, and the pressure suppres-Spray) and core spray systems, the sion chamber head tank shall norually discharRe piping of these systema be aligned to serve the discharge pipint, shall be vented from the high point of the r'st and CS pur:ps. The condensate and water flow determined.

head tank may be used to serve the RHR and CS discharge piping if the PSC head 2.

Following any period where the LFCI tank is unavailable. The pressure or core spray syacens have not been indicators on the discharge of the R13 required to be operable, the dis-and CS pumps shall indicate not less charge piping of the inoperabla sys-ta= shall be vested from the high than listed below, P1-75-20 40 rsig point prior to the return of the F1-75 L6 L8 psig

,y,g,,g,,,,,ge,,

F1-74-51 L8 Psis 71-7L-65 t.g psis 3.

Whenever the H=CI or RCIC systes is lined up to take suction from the

1. Average Planar Linear Heat Generation condensate storage tank. the dis-charge piping of the HPCI and RCIC Race shall be vented frca the high point During steady reste power operation, the of the sy. ora and water flow observed tiaximus Average Planar Heat Generation Rate (MAPLHCR) f or each type of f uel as on a monthly basis.

a function of average planar exposure shall not exceed the limiting value 4.

When the RER$ and the CSS ara 're-lIf at any time during operation itahown in Tables 3.5.I-4-2,-3,-g-5 /-6.

quired to be operable, the pres ore indicators which nealter the d H-is charge lines shall be ser.itored Jetermined by normal surveillance that daily and the pressure recordad.

the limiting value for AFLHCR is being escoeded, action shall be initiated with-in 15 minutes to restore operation to vithis the prescribed limits. If the AFLMCR is not retvined to within the prescribed limits wLthin two (2) hours, the reactor sh.all be brought to the Cold 2.

Maximum Averaee Planar Linear Heat Cenern-Shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

tion R. ate (.M.PLNCR)

Surve111so.:e and corresponding action shall con inue until reactor operation The MAFLHCR f or each type of fuel aa a fu.ic-is within the prescribed limits.

tien of average planar exposura shall be datermined daily during reactor operation

7. Linear Haat Ceneration Rate (LHCR) at > 25% rated tharsal p* 1r.

During steady state power operation, the limaar heat generation rate (LHCR) of J.

Linear Heat Ceneration Rate (LHCR),

any rod in any fuel assembly at any axial location shall not 0-aged the The LHCR as a function of core h41451 shal,.

maximum allowable LHCR as calculated by e e ac ed dauy during reactor geratin at the following equation:

f,, 23% rated thersal power.

159 Amendment No. 33. 47 jg 17 W3

~~--~~

a

..:q-1

- :7 r.. x - _sca.!; - / :

O./.7)}

e

= A.

l "e a.gn.iice:

~. a ::.

'or *x?f c! l 2

i_ - 'y

-(t far

'~nel L PJF) 9.ax t=us x..r: aptitna penalt.

cAx..),a;o ;or

.ot.

t),6?j] ?gr iX3 3 tas'I a

LT - Total core leng:n 1Lil t eet ter TX7 fuel

= 1;.2 feet for BXS fuel I

=.s.xial position aheve bottom of core If at any time durinc Operation 1: is de:er-

=ine d by no r=al sur. eil'.ance that :he it=1 ting

'*a l u a for LHCR is being exceeded, ac: ton shall be initiated vi:hin 15 ninutes to restore operation to within :ne. prescribed limits.

If the LHCR is not returned to vi:hin :ne prescribed limits vi:nin' two (2) hours, the reac:or shall be broych: :o :he Cold Shutdown condi: ion within 36 heurs.

Surveillance and corresponding action shall con:inue until reacter cperation is witnin the prescribed 10:1:s.

"inte.un c itical Power Fatto ("CPR)

A-Min inum Cri tical Powe r P.ac to r

( *.C? U

• CPR sperating lir.i: from the beginning

- e

-.;1e 3 to the enc cf cycle 3 minus MCYR shall be determined daily 20 a "Ud / : is 1.20 for 7'O fuel andl.24 for curi ; re:c::: pever :; era:ica at R::5 and SXSR fuel; :he limit frem the end of 1 25: ra ted :her=al ;isir and f ol-

cc.e 3 minus 2000 mwd /t to the 10W1"4

""Y Ch* se in power level er end et cycle 3 isl.25 fer 7X7 fuel andl.30 disertbution th:: wauld cause opera fer 6XS and SZSR fuel.

These limi:s apply to (loa with a limicias centrol red s:eady s:ste power operatien a: rated power pat:ern as described in the bases f and ' lev. Ter core flevs c:her than rated, Specification 3.2.

he", PR shall be greater than the above limi:s.

tires F...

Er is the talue shown in Figure If'at any t Lme during operat ien 1: is determined by r.:r=al serveillance : hat the I f elt ing va lue f or CPR is being exceeded, ac:ian shall be ini:1ated within 15 cinutes to restore dpera: ion :o n:hin the prescribed 1*:1: 3.

'l che st'eady"r.: ate MCTR is not returned to sithin t he prescribed li=its within twe (21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />, the reae:ar shall be brough: cc

he Cold Shutdown condi:lon wichin 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Surveillance and corresponding action shall i

cen:tnue un t 11 r e.ie:et eperat ien 13 within the prescribed Itettg.

I 4

.eporitne Ney's t r e=en t s i

d 1

If an? et the limiting ilu** iilent i t ivd in 2:ecif!:st!ces 3.5.1... Or M are n eced

.]

..d

ne sreciflec re=ediai Acti:n is :agea, :ne ev-n: sta*1 be leggee and re7erted

. a U_

p.

vr i t o n reper:-

t 2. 5 Fee f fa r-8xS E Suel

u

.