Text

Amend 83 to License DPR-66,changing Tech Specs to Clarify Conditions Under Which Safety Action of Protection Sys Channels Manually Bypassed or Blocked by Sys Logic
	ML20099J156
Person / Time
Site:	Beaver Valley
Issue date:	11/13/1984
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
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ML20099J158	List: ML20099J156; ML20099J166;
References
	NUDOCS 8411280539
	Download: ML20099J156 (25)
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UNITED STATES

b

^

NUCLEAR REGULATORY COMMISSION n

3 j

WASHINGTON. D. C. 20555

, e mQ DUQUESNE LIGHT COMPANY

. OHIO EDIS0N COMPANY PENN3YLVANIA POWER COMPANY

.f DOCKET N0. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMEipMENT TO FACILITY OPERATING LICENSE Amendment No.83 License No. DPR-66 1.

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

A.

The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated July 14, 1983 and supplemented by letters dated

... September -22, 1983 and July 3,1984, 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 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; 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 o# this amendment is in accordance with 10 CFR Part 51 of the Comission's rdgulations 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-66 is hereby amended to read as follows:

8411280539 841113 PDR ADOCK 05000334 P

PDR

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 83, are hereby incorporated'in the license. The licensee shall operate the facility in accordance with the Technical j.

Specifications.

r' 3.

This amendment is effective on issuance, to be implemented no latbr than 30 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing

Attachment:

Changes to the Technical Specificitfdns Date of Issuance: November 13, 1984 4

l O

Q O

ATTACHMENT TO LICENSE AMEN 0 MENT AMEN 0 MENT N0. 83 'TO EACILITY OPERATING LICENSE N0. OPR-66.,,

DOCKET NO. 50-334 Revise Appendix A as follows:

Remove Pages*

Insert Pages 2-7 2-7 2-7a B2-8 B2-8

'f 3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 3-7 3/43-7/8 3/4 3-8

.3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-15 3/4.3-15 3/4 3-18 3/4 3-18 l

3/4 3-19 3/4 3-19 3/4 3-19a 3/4 3-19a 3/4 3-19b 3/4 3-20 3/4 3-20 3/4 3-21 3/4.3-21 3/4 3-245 3/4 3-31b-

~~

83/4 3-1 B3/4 3-1 B3/4 3 la

The licensee requested to remove Pages 3/4 2-14, 3/4 2-15 and 3/4 2-16.

Such has already been accomplished by, Amend' ment No.

9 dated July 12, 1977.

.i

TABIE 2.2-1 (Continued) f RFACIOR 'IRIP SYS'ID4 INS'IHNENPATIQI 'IRIP SEITOINTS I

W EU CTIO4AL IMIT TRIP SEITOINF AllDRBLE VAIDES D

c-t Q

I 2 11% of narrow range instrument

13. Steam Generator Water 212% of narrow range instrument Icvel-Im-Iow span-eachsteamgenergtor span-each steam generator g

U

14. Steam /Feedwater Flow f 40% of full steam flow at 4 42.5% of full steam flow at W

Misnatch and Im Steam RA'ITD '11IERML POWER doincident RATED 'IllEIVEL POWER coincident -

Generator Water Icvel with steam generator water level with steam generator water. level A 25% of narrow range instru-2 24% of narrow range instru-nent rpan-each steasa generator ment span-each steam generator

15. dndervoltage-Reactor 2,2750 volts-each bus 2 2725 volts-each bus

~

Coolant Ptmps I

{

16. Underfrequency-Reactor 2 57.5 Hz - each bus 2 57.4 Hz - each bus Coolant PLups

17. Turbine Trip A.

Auto stop oil pressure 45 psig 1 5 psig 4

B.

Turbine Stop Valve A 1% open 21% open

18. Safety Injection Input Not Applicable Not Applicable k

fran ESF n

19. Reactor Coolant Punp Not Applicable Not Applicable Breaker Position Trip sn

20. Reactor Trip System o

Interlocks 8

-10

~11 A.

Intennodiate Pange

.2 1 x 10 Anps g 6 x 10 Anps tieutron Flux, P-6 i

y s

".e t

8

TABLE 2.2-1 (Continued)

=

Cg REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINT a

g t

h 20.(Continued)

Q i

e FUNCTIONAL UNIT TRIP SETPOINT

)

ALLOWABLE VALUES I

E G

B. Power Range Neutron Flux, P-8 130% RATED THERMAL POWER 6 31% RATED THERMAL POWER r

C. Power Range Neutron Flux, P-9 649% RATED THERMAL POWER 6 51% RATED THERMAL POWER D. Power Range Neutron Flux, P-10

> 9% RATED THERMAL POWER

>9% and <.12% RATED THERMAL POWER '

(Input to P-7) e E

E. Turbine Impulse 672 PSIG Chamber Pressure, P-13 6 66 PSIG (Input to P-7) p i

it 8

n

.O

- i..~

8

LIMITDG SAFETY SYSTEM SEITINGS BASES Safety Injection Irout frm ESF If a reactor trip has not already been generated by the reactor protective instrumentation, the ESF autmatic actuation logic channels will initiate a reactor trip upon any signal which initiates a sak ty injection.

'Ihis trip is prwided to protect the core in the event of a ILCA. 'Ihe E3F in=L.wentation channels which initiate 6. safety injection signal are shown in Table 3.3-3.

G Reactor Coolant Puno Breaker Position Trip I

'!he Reactor Coolant Pmp Breaker Position Trips are anticipatory trips-which prwide reactor m re protection against DNB.resulting frm the opening of two or nere punp breakers above P-7.

'!hese trips are blocked belm P-7. '!he open/close position trips assure a reactor t-ip signal is' generated before the low flow trip set point is reached.. No credit was taken in the am-4 dant analyses for operation of these trips.

'Iheir functional <-= Phi 14ty at the open/close position settings is required to enhance the overall reliability of the Reactor Protection Systen.

I Reactor' Trip' Systen Interlocks

'Ihe Reactor Trip System Interlocks perform the following functicns:

-P-6 Above the setpoint P-6 alle the manual block of the Source Range reactor trip and d: csgizing of the high voltage to the detectors.

Below the setpoint Source Range level trips are autmatically reactivated and high voltage restored.

P-7 Above the setpoint P-7 autmatically enables reactor trips on low.

flow or coolant pung breaker operf 'in nere than one primary molant _ loop, reactor coolant pung bus undervoltage. and underfrequency, pressurizer low pressure and pressurizer high level.

Below the setpoint the above listed trips are autmatically blocked.

P-8 Above the. setpoint P-8 autmatically enables reactor trip on low flow in one or nere primary coolant loops.

Below the setpoint l

P-8 autmatically blocks the above listed trip.

P-9 Above the setpoint P-9 autmatically enables a reactor trip _ on l

turbine trip.

Below the setpoint P-9 autmatically blocks a reactor trip on turbine trip.

P-10 Above the setpoint P-10 allows the manual block of the Intamad4=te Range reactor trip and the low setpoint Power Range reactor trip; and autmatically blocks the Source Range reactor trip and de-energizes the Source Range high voltage power. Belcw the setpoint the Intemediate Range reactor trip. and the law setpoint Power Range reactor trip are autmatically reactivated.

Prwides input to P-7.

~

P-13 Provides input to P-7.

BEAVER VAILEY - UNIT 1 8 2-8 Amendment No. 83

Tt LE 3.3-1 U

RETCIOR 'IRIP SYSTEM INSTMMENTATIOi

!)

MINIM M

'IUPAL NO.

CIANNELS OIANNEIS APPLICABIE h

RRCPIONAL UNIT OF OIANNEIS

{ 'IO TRIP OPERADIE KDES ACTIOi 1

1.

Manual Peactor Trip 2

1 2

1, 2, 3*,4*,

12 E

and 5*

G 5

r 2.

Ibwer Range, Neutron Flux a.

liigh Setpoint 4

2 3

1, 2 2

b.

Iru Setpoint 4

2 3

IIII, 2 2

3.

Power Range, Neutron Flux 4

2 3

1, 2 2

Iligh Positive Rate 4.

Power Rdnge, Neutron Flux, 4

2 3

1, 2 2

{

liigh Negative Rate 5.

Intermediate Range, Neutron Flux 2

1 2

lIII, 2, 3*,

3 4*, and 5*

6.

Source Range, Heutron Flux (Delow~P-10)

F A.

Startup 2 '"

1 2

2(2) 3*,

4*,

4 and 5*

c2.

ll B.

Shutdown 2

0 1.

3, 4 and 5 5

~

a 7.

Overtaperature AT.

_,,6

'Ihree Ioop Operation 3

2 2

1, 2 2

'Iko Ioop Operation 3

1**

2 1, 2 9 ' ' '

8 8

ChrerIowerAT

['

'Ihree loop Operation 3

2 2

1, 2 2

.i

+

'Iw loop Operation 3

1**

2 1

1, 2 9

9.

Pressurizer Pressure-Irw 3

2 2

1, '2 7

(Above P-7) r u,

' %'3.,

O

TABLE 3.3-1 (Continued)

RCACIOR TRIP SYSTD4 INS'ITutENTATION N

h (1

MINI >m e

'IUTAL NO.

LQIAtNELS OlMNEIS APPLICABE EUCTIONAL UNIT OF OIANNEIS l'IO 'IYtIP OPERABE MIES JCTICN h

~

O J

10.

Pressurizer Pressure-Iligh 3

2 2

1, 2-7 U

11.

Pressurizar Water Icvel-Iligh 3

i 2

2 1, 2 7

~

( h e P-7)

~

.12.

Ioss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1

7 (N ove P-8) any oper-each oper-ating loop ating loop 13.

Ioss of Flow - M Icops 3/ loop 2/ loop,in 2/ loop 1

7 4

(Above P-7 and below P-8) two oper-

, each oper-

[

. ating loops ating loop i

14.

Steam Generator Water 3/ loop 2/ loop 2/ loop 1, 2 7

Icvel-Iow-low (Irop Stop Valves Open) level 1/ loop-level 1/ loop-level 1, 2 7

2/loopId 15.

Steam /Feedwater Flow at coincident and Misnatch and Iow Steam Generator Water Icvel 2/ loop-flow with 2/ loop-flow Ej-mismatch 1/ loop-flow mismatch or mismatch in 2/ loop-level g

same loop and n

1/ loop-flow z

mismatch o>

16.

Undervoltage-Peactor Coolant 3-1/ bus 2

2 1

7 Punps (Above P-7) l

'l 17.

Underfrequency-Beactor Coolant 3-1/ bus 2

2 1

7 Punps (Above P-7) g s-

% 'y,

i k

4

TABIE 3.3--1 (Continued)

RE/CIDR TRIP SYSTEM DISTIENENTATICH to C

MINIMJM SUTAL NO.

CIMIEIS O!ANNELS APPLICADLE

,j

=

EucrIGIAL UNIT OF OlM41EES TO '11tIP OPERADIE IMODES JCPICN l

r-

18. "Ibrbine Trip (Above P-9)

E A.

Auto Stop Oil Pressure 3

2 2

1-7 d

B.

Turbine Stop Valve Closure 4

4 4

1 8

f e

f c

19.

Safety Injection Input frca ESF 2

g 1

2 1, 2 1

e 20.

Peactor Coolant Ptmp Breaker r

Position Trip (Above P-7) 1/ breaker 2

1/ breaker 1

11 per oper-ating loop Z

21.

Peactor. Trip Breakers 2

1 2

1, 2, 3*,

I 4*, and 5*

22. Autanatic Trip logic 2

1 2

1, 2, 3 *,

1

.4*, and 5*

23.

Reactor Trip System Interlocks A.

Intennediata Range 2,,

1 1

2 3

g Neutron Flux, P-6 D.

Power Range 4

2 3

1 12 I

Neutron Flux, P-8 cu 5

C.

Power Range 4'

2 3

1 12 Neutron Flux, P-9 2

O D.

Power Range 4

2 3

1 12 ~

Neutrco Flux, P-10 E.

'Ibrbine Inpulse 2

1 1

1 12 ;

O wiber Pressure, P-13 g

e 4

g i

~

i

1 TABLE 3.,3-1 (Ccntinued) i TABLE NCTIATICN 1

I

(

With the reactor trip system breakers in the closed position and the control rod drive system < apable of rtid withdrawal.

i'

- . The channel (s) associated with the protecti.ve functions derived frcm the out of service Peactor Coolant Icep shall be placed in the tripped coadition.

s (1) Trip function my be manually bypassed in'this Ltde above P-10.

~ i (2) Trip fth. may be mam: ally bypassed in this Mode above P-6.

ACTICN STATIMNrS

~ With the m:mber of channels OPERABLE one less than required by ICrICN 1 the Mininun Channels OPERABLE requirements, be in ECTF SDNDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

IcrICN 2 With the rumber of OPERABLE channels one less' than the Total Nunber of Q:annels and with the 'DIERMAL PCWER level:

a.

Iass than or equal to 5% of PATED 'DfERMAL PCNER, place t.he inoperable channel in the tripped condition within

" '"~ "

i hour and restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after increasing 'DIERMAL POWER above 5% of PATED. 'DIEBMAL POWER; othelvise reduce the_M power to less than 5% PATED 'DIEPMAL POWER within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

Above 5% of PATED 'DIERMAL POWER, operation may continue provided all of the folicwing conditions are satisfied:

1.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.

'Ihe Mininun Channels OPJ3ABLE requirement is met; however, one additicnal channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specif-cation 4.3.1.1.

3.

Either, THERMAL PCWER is restricted tod75% of RATED ME and the Pcwer Range, Neutron Flux trip set-point is reduced tof 85% of PATED ME PGER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the CUADRANr POKER TILT RATIO is nenitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With the nu: er of channels OPEPABLE one less than recuired by ICICN 3 the Minimra Cwmels OPERABLE requirement and with the THEPNAL PGER level:

BEAVER VALLEY - CNIT 1 3/4 3-5 Amendment flo. 83 6

~

.- 7 D ALE.3.0-1 (continued) -

M CN 9 With a channel associated with an operating loop inoperable, '

restore the inoperable channel.to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in Hor SENDBY within the next 6 bcurs; however,-

one channel associated with an operating icop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification

4. 3.1.1. -

>d M ON 10 Notr applic'able.

's M CN 11 With less than the Mininun NLmt:er of Channels CPERABLE, operatica ray continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

~

E CN 12 With the nutt:er of channels OPbRABLE one less than required by the Mininun Channels CPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be

~

in eof SD NDSY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

nn

c c

SEAVER VALL:Y - UTT I 3/43-7/8 Amendment No. 83

TABLE 4.3-1 RDCIOR 'ITIIP SYSTEM INS'IPLNENTATION SURVEILIANCE RBJUIRENENTS OlAttEL MJDES IN MIIQI OIA!REL OIAttEL EUNCTICNAL SUINEILLANCE N

FUCTIONAL UNIT QUrK CALIBRATIQi -

TESP REQUIRED i

f 1.

Manual Reactor Trip N.A.

N.A.

S/U(1)

N.A.

r-N 2.

Power Range, Neutron Flux a.

liigh Setpoint S

D(2), M(3)

M 1, 2 and Q(6)

.=.

s b.

Iow Setpoint S

N.A.

S/U(1) 2 u

3.

Power Range, ibutron Flux, N.A.

R M

1, 2 2

liigh Positive Rate Y

4.

Power Range, Neutron Flux, N.A.

R.

M 1, 2

[

liigh Negative Rate 5.

Intennediate Range, S

N.A.

S/U(1), M(7) 1, 2, 3*,

tbutron Flux 4*, 5*

6.

Source Range, ibutron Flux N.A.

N.A.

S/U(1), M(8) 2, 3*, 4*

E (Below P-10) and 5*

m h

7.

Overtm perature T S

R M -

1, 2 m

s" 8.

Overpower T S

R H

1, 2 5

9.

Pressurizer Pressure-Iow S

R H

1, 2 b

i 10.

Pressurizer Pressure-liigh S

R M

1, 2 I

11.

Pressurizer Water Invel.-High S R

H 1, 2 12.

Ioss of Flow - Single Icop S

R

'M 1

f

.- 4 TABIE 4.3-1 (Continued)

RF1CIOR 'IRIP SYSTEM INSTRLNENTATIO1 SUINEIIJANCE RDQUIRENENTS OIM41EL KDES IN WIIOi auna aiMeiEn

sucr10w, SURvEu2aNcE rn EUCTIORL UNIT QiEEK CALIBRATIOi TEST RDQUIRED r

13.

Ioss of Flow

'Ibo Icops S

R N.A.

I

\\

r$

14.

Steam / Generator Water level-S l

R

.M 1, 2 d

low-Iow i

15.

Steam Feedwater Flow Misnatch and S R

M 1, 2 c:

M Iow Steam Generator Water Ievel 4

16.

Undervoltage - Peactor Coolant N.A.

R M

1 Pmps 17.

Underfrequency - Reactor Coolant N.A.

R M

1 Pmps u

18.

Turbine' Trip u

8 A.

Auto Stop Oil Pressure N.A.

N.A.

S/U(1) 1, 2 g

B.

'Ibrbine Stop Valve Closure N.A.

N.A.

S/U(1) 1, 2 19.

Safety Injection Input frcun ESF N.A.

N.A.

M(4) 1, 2 20.

Reactor Coolant Pmp Breaker N.A!

N.A.

R N.A.

g Position Trip m

s k

21.

Peactor Trip Breaker N.A.

N.A.

M(5) and S/U(1) 1, 2, 5*

a 22.

AutcxTatic Trip Iogic N.A.

N.A.

M(5) 1, 2, 5*

2 O

23.

Peactor Trip Syst(sn Interlocks 8

A.

P-6 N.A.

N.A.

M(9) 1, 2 B.

P-8 N.A.

N.A.

M(9) 1 C.

P-9 N.A.

N.A.

M(9) 1 D.

P-10 N.A.

N.A.

M(9) 1 E.

P-13 N.A.

R

. M(9) 1

- c..

e f

i rr o,

' Dam 4.3-1 (Continued)

MW With the reactor trip system breakers closed and the control

' 'd red drive system capable of rod withdrawal.

r

~~*

(1)

If not perfented in previous 7 days.

(2)~

Beat halaw only, above 15% of RATID 'EERMAL PCHER.

(3)

Ccarpare incere to exoore axial talance above 15% of RATED

'EERMAL POWER.

Becalibrate if absolute difference 2 3 pe.rcent.

~ ~ -

(4)

Manual ESF functional input check every 18 nanths.

~

(5)

Each train tested every other renth.

(6)

,,,,p. detectors may be excluded frcm CHTNEL CALIBRATIN.

(7)

Below P-10.

(8)

Below P-6.

Pequired cnly when below In+arlmk Trip Setpoint.

(9) 2 l

l EETNER VAL 2Y - CII" 1 3/4~3-13 Amendment No. 83 i

1 i

L

TAB E 3.3-3 DGUEERED SAFETY FFRIURE N3UATICN SYS'IYN INS'IRMWPATIN as C

a 9

MINDEM

'IUPAL NO.

OlM4ELS r QlMREIS APPLICABE EUCTICNAL UNIT CF OlM NEIS

'IO 'IRIP ! OPERABm KDES ACTICH E

T 4

1.

SAFE!rY DUECTICN MD E

FEWWATER ISOIATICN n

a.

Manual Initiation 2

1 2

1,2,3,4 18 2

1 2

1,2,3,4 13, 36 l

g g tic Actuation b.

c.

Contalment 3

2 2

1,2,3 14 Pressure-liigh s

d.

Pressurizer 3

2 2

1, 2, 38 14 Y

Pressure-Im G

e.

Im Steamline Pressure (Loop stop valves open)

'Ihree Icops 3/ loop 2/ loop 2/ loop 1, 2, 38 14 Operating any loop any loop Ng

'Iwo loops 3/ loop 2/ loop any 2/any 1, 2, 38 15' g.

operating operating operating g

100P ICOP O

i g

e r

l e

I

TABM 3.3-3 (Cmtinued)

DCINEERED SAFEIY FENIURE JCIUhTIN SYSID1 IMS*1MMNFATIGI

.l usg

>=

- W E

'Ioran to, o weEIS OWNEIS APPLICABM d

EUCTIWAL LNIT

& OWiMS

'ID 'IRTP OPERABM KDES JCTIN l

e l

i Si l

il 4.

STEAM LINE ISOIATIN l

a.

Hmual 2/ steam line 1/ steam line 2/ operating 1, 2, 3, 4 18 e-.

steam line b.

Autcrmtic 2

1 2

1,2,3,4 13 j

Actuation logic c.

Containnent Pressure 3

2 3

1,2,3 14 Internediate-High-High s

co d.

Iow Steamline Pressure (Loop stop valves open)

'Ihree Iceps Opera-3/ loop 2/ loop 2/ loop 1, 2, 38 14 ting Any loop Any loop

.i.

g Two Icops 3/ loop 2/locp any 2/any 1, 2, 31 15 Q

Operating operating operating -

a

,1mp 100P p

.e.

liigh ' Steam Pressure 3/ loop 2/ loop 2/ operating 30f, 4 37 l

Pate any loop loop O

u l

e a

g

.D 3 RL %8

,, we,

~.,, ~.

" - + < - * " -

TAB m 3.3-3 (Q wtinued)

DGINEERED SAFETY FEA'IURE JCIUATIO1 SYSTEN INSTIDO(PATIOi w

I4 MINIMM en

'IUPAL NO.

OINNELS CIM NE[S APPLICABM EUCTIONAL UNIT OP OIANNEIS

'IO, TRIP OPERABM MJDES M.TIOf l

b 1

c 5

5.

'IURBINE TRIP E, FEED &'IER f,

ISOIATIOi a

c a.

Steam Gener.ator 3/ loop 2 loop in 2/ loop in 1, 2, 3 14 M

Water level-any'oper-each oper-H liigh-Iligh, P-14 ating loop ating loop l

r 6.

IDSS OF PCHER a.

4.16kv Bus 1/4.16kv Bus

.m 1..Ioss of Voltage 1/4.16kv Bus 1/4kv Bus 1, 2, 3, 4 33 (trip feeder) w 8

2.

Ioss of Voltage 5

(start diesel) 1/4.16kv Bus 1/4.16kv Bus 1/4kv IMs 1, 2, 3, 4 33 b.

Grid Degraded Voltage (4.16kv Bus) 2/4.16kv Bus 2/ Bus 2/ Bus 1,2,3,4 34 c.

Grid Degraded Voltage

.I' g

(480v Bus) 2/480v Bus 2/ Bus 2/ Bus 1, 2, 3, 4 34 5.

R E

O e

I g

,d

. t..

r e

IABLE 3.3-3 (Continued) u>

9 r}

' ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATI0tl 7-I:

HINIMUM

?

TOTAL N0.

CHANNELS,(

CHANNELS APPLICABLE

'O FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE H0 DES ACTION h

c 7.

AUXILIARY FEEDWATER f!

a.

Steam. Gen. Water leve l-Low-Low 1.

Start Turbine Driven Puhp 3/stm. gen.

2/stm. gen.

2/stm. Den I, 2, 3 14 i

any stm. Gen.

((

'~II.

Start Motor Driven Pumps 3/stm. gen.

2/stm. gen.

1, 2, 3 14 any 2 sim. gen.

e M

h.

Undervnitage-RCP

~

Start Turblue-Driven Pump (3)-1/ bus 2

2 1

1+

2 c.

,5.

1.

g, S' tart Motor-o

[

Oriven rumps See 1 above (all.S.I. Initiating functions and requirements) i 2

]

d.

Emergency Bus Undervoltage Ef Start Hotor Driven

~

rumps f/ bun 1

1 1,2,3 18 e.

Trip of Main feedwater Pumps Start Motor-l Driven Pumps 1/ pump

'l 1

1, 2, 3 18

$s 0

TABM 3.3-3 (Oontinued)

DEINEERED SAFETY FEA'IURE MlUATIG! SYSID4 INSTRLNENTATIm to 9<

MINIMUM i

y

'IUPAL NO.

OIMREUS OlM NEIS APPLICABE IuCPICNAL UNIT OF OIMtEIS

'ID 3 RIP OPERABE ICOES EP!W s

p

t 8.

ESP INTERIOCKS a.

Reactor Trip, 2

1 2

1,2,3 38-y F4

.s b'.

Pressurizer Pressure, P-11 3

2 2

1,2,3 38 c.

Irw-Irw Tavg, P-12 3

2 2

1,2,3 38 R,-

=

p 3

=

3 rt Z

ta 4

g

'e

s i

i

Table 3.3-3 (Centinued) g 6 Trip function may be bypassed in this KDE below P-H.

1. Trip function autcrnatically bypassed above P-ll, and is bypassed' below P-ll when Safety Injection on low steam pressure is not manuauy bypassed.

..a

1. 1. 1he channel (s) associated with the protective functicns derived frun y

the out'of service Peactor Coolant Icop shall be placed in the tripped node.

AcrICN SIATDfENIS ACTICN 13 With the nunber of OPERABLE Q1annels one less than the Total Lh of Chara1els, be in HOF SD.NDBY within six leurs and in CED SIUIDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ;

~..

however, one channel may be bypassed for up to tse hours for survM 11ance testing per Specification 4.3.2.1.1.,

provided the other channel is operable.

AcrICN 14 With the nunber of OPERABLE Channels one less than the

. ibtal Rrber of Channels:

..sw a.

Pelow P-ll or P-12, place the inoperable channel in the tripped conditicn within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after ewing P-ll c~r P-12; otherwise be in at least IUr STANDBY within the following sbc hours.

b.

Above P-ll and P-12, place the inoperable channel in the tripped conditicn within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; cperation may continue until perfonrance of the next required CIAMEL EUUrICNAL TEST.

ACTICN 15 with a channel associated with an cpting loop inoperable, restore the incperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT SEUIDOWN within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.

ACTICN 16 With the nt=6ir of OPEPABLE Channels one less than the ibtal E-6er of Channels:

a.

Belcw P-11 or P-12, place the inogable channel in the bypass condition;. restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding Pil er P-12; otherwise be in at least HOT ShvIIUM within the follcwing 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

EEta n vic1EY C.TI 1 3/4 3-20 Amendment No. 83

I y

TABLE 3.3-3 (0:mtinued) b.

Above P-11 or'P-12, denenstrate that the Mininum Channels OPDAB2 requirement is met within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; operation my continue with the inoperable charrel bypassed and one channel may be byp-d for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for testing per Specification 4.3.2.1.

m CN 17 With less than the Mininunt Q1 annals OPERABLE, operation may centinue provided the containment purge and

~ exhaust valves are maintained closed.

A,,

ACTICH 18 -

With the nu:rber of OPDABLE Chr.nels one less than the Total Nuuber of C1annels, restore the inoperable channel to OPDABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least hor STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and cold shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTICN 33 -

With the number of OPDABLE C1annels one less than the Total Nutrber of Qiannels, the.Dnergency Diesel Generator associated with the 4kv Bus shall'be declared inoperable and the ACTICH

~

Statements for Specifications 3.8.1.1 or 3.8.1.2, as appropriate shall apply.

~-

ACTICH 34 -

With the nunber of OPERABLE Channels one less than the Total turber of rhrmale, STARIUP and/or PCHER OPERATICH nay sw&,1 until the perfaanance of the next required Q1annel ntnctional 3

Test provided the inoperable diannel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

_.m..

ACrICN 36 -

'the block of the autcznatic actuation logic intrenwwi by a reset of safety injection shall be remaved by resetting

-(closure) of the reactor trip breakers wi. thin one hour of an inadvertent initiation of safety injection providing that all trip input si conditicms. Otherwise,gnals have. reset due to stable plant.

t the requirements of action statement 13 shall have been met, i

f ACTICN 37 -

With the nunber of OPERABLE channels one less than the

'lbtal-turber of channels, STARIUP and/or PCHE OPERATICN may proceed provided the following conditions are satisified.

a.

'Ibe inoperable channel is placed in a tripped condition within one hour.

b.

'Ihe Minimant Channels OPERABLE requiments is r:et; however, the incperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels

.per specification 4.3.2.1.1.

ACTICN 38 -

With less than the Minunum Nunter of Osannels OPERAELE, within one' hour determine by observation of the asscciated permissive. annunciator windcw(s) (bi' stable. status lichts or couputer checks) that the interlock is in its required state for the existing plant ccnditien, or apply 4

Specificatien 3.0.3.

i EVER VALLEY - (MIT 1 3/4 3-21 Amendment No. 83

...~

=

TABm 3.3-4 ((bntinued) ca 9j DEINERED SAFCIY FENIURE ACIUATION SYSTEM INSITDENTATICN 'IRIP SEffPODilS so e-r-

EUtCTIGIAI, UNIT

' IRID. SEITOINF ALIORBE VAIDES Q

i e

d 8.

ESF DTIERIOCKS H

a.

P-4

'N/A N/A b.

P-11

$ 2000 PSIG f 2010 PSIG c.

P-12 2 541*F

> 539'F O

a.

~

!?

y 3

8" Z

O e

NG)

J e

k

'W e f

TABLE 4.3-2 (Continued)

DIGINEERED SAETIT FENIURE AC'IUATIO4 SYSTD4 INSTRUMDfrATICH SUINEILIANCE REQUIRENDils S.:'

5'l OIANNEL KDES IN WilIOi

}

OLANNEL C11ANNEL FUNCTIONAL SUINEILIANCE p

RRCTIO4AL UNIT OIECK CALISRATIO4 TEST REOUIRED l'1 k

8.

ESF IITTERIOCIG N

a.

P-4 N/A 4N/A R

1, 2, 3 e

b.

P-11 N/A R

M 1,2,3 c.

P-12 N/A R

M 1,2,3 N

Y m

O.

.f' 3>

B co 3

CL B

co 3

C+

Z O

se-

)

w e

l

~

4

.T..

g

sk%g a

,~

3/4.3INSTM.F.ENTATIN

~

3/4.3.1 and 3/4.3.2 PiufLnVE'AND SGINEERED SAFEIY FEATURES (ESF) - '-

INsTmEMATIm 2e OPERABILIIY of the protective and ESF instnmentation systems and

. interlocks ensure that 1) the associated ESF action and/or reactor trip will '

be' initiated when the parameter monitored by : each enannel or ccubination s

f thereof.. exceeds its setpoint, 2) the specified' coincidence logic. is ~

raintained, 3) suffielent redundancy is maintained to permit a channel to be

?,

cut of servion' for testing er maintenance, and 4) sufficient system

.,3 functional e=nah414ty is available for protective and ESF purposes frcm t

diverse parameters.

De OPERABILrrl of these systems is required to provide the overall re14=h414ty, r=^wv4=ncy and diversity

==-d available in the facility-design for the protection and mitigation of accident and transient conditions. 2e integrated cperation of each of these systems is consistent l

. with the==$1ans used in the accident analyses.

2 e surv=411a:1ce requirernents shified for these systems ensure that ~

the overall system functional canah414ty is maintained cmparabia to the original design standards. 2 e periodic surv=411= e= tests performed at the minima frequencia= are sufficient to dentmstrate this e=nah414ty.

2e==awennnt of response time at the = pac 4fied frequencies provides i

assurance?,hatnthe pui.ective and ESF action function associated with each

^

channelTs empleted within the tine limit assumed in the =m4 dant analyses.

No credit was taken in the analyses for those channals with response tines indicated as notsapplicable.

aesponse tine - may be dencnstrated by any series of sequential, everlapping or total channel test nuasurements provided that such tests deanstrate the total channel response time as defined. Sensor response time verification usy be decenstrated by~ either 1) in place, onsite or offsite test ceasurements or 2) u+ 414~4ng replacement sensors with certified response times.

De Engineered Safety Feature Actuation System interlocks p' erform the following functicms:

P-4 FSctor tripped - Actuates turbine trip, closes main feedwater valves on T below setpoint, prevents the opening of the main avg feedwater valves which were closed by a safety injection or high steam generaticr water level signal, allows safety injection block so that %e.nts can be reset or tripped.

Beactor not tripped - prevents manual block of safety injection.

P-ll Above the setpoint P-ll automatically reinstates safety injection actuation en -Icw pressurizer pressure, autcmatically blocks s~ammline isolatien on high steam pressure rate, enables safety injection and steamline isolaticn on (Icep. Step Valve Cpen) with

~

low steanline pressure, and enables auto actuatien of the pressurizer ICWS.

5F.'.VER VP7 "! - UNIT 1 B 3/4 3-1 Amendment No. 83

P-ll, Continued Below the setpoint.P-ll allows the manual block of safe'ty injection actuation on low pressurizer pressure, allows marasal block of safety injection and s+a=14ne isolation en (Icop Stop Valve Open) with Iow s+a=14ne pressure and enabling s+a=14ne isoleion on high steam pressure rate, autmatically rii<ahles auto actuation of the pressurizer POF.V's unless the Beactor Vessel Over Pressure

~

Fwi.cction System is in service.

P-12 Above 'the setpoint Ps12 autmatically reinstates an armirg signal -

to t)e steam dunp system.

Below the setpoint P-12 blocks steam Q

dung and allows manual bypass of the steam dung block to cooldown

~

cxrdan=ar dung valves.

~

9 l

l BEAVER VALLW - UICT 1 B 3/4 3-la Amendment No. 83 4

ML20099J156

Text

Attachment:

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