ML18096B261

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Proposed Tech Specs 2.2, Limiting Safety Sys Settings & 3/4.1.1, Reactor Trip Sys Instrumentation
ML18096B261
Person / Time
Site: Salem  PSEG icon.png
Issue date: 02/05/1993
From:
Public Service Enterprise Group
To:
Shared Package
ML18096B260 List:
References
NUDOCS 9302170068
Download: ML18096B261 (12)
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Text

l 9302170068 930205 PDR ADOCK OS000272 P

PDR ATTACHMENT 2 MARKED UP PAGES

I OI N

FUNCTIONAL UNIT

13.

Ste** Gener*tor W*ter Level--Low-Low Mh*etch en Generetor Ueter Level

15.

Undervoltege*leector Cool*nt Pu*p1

16.

Underfrequency-leector Cool*nt Pu*p*

17.

Turbine Trip A. Low Trip $y1te*

Pre11ure I. Turbine Stop Velve Clo1ure

18.

Sefety lnjec~lon Input fro* SSPS

19.

leector Coolont Pu*p lreeker Po*l~lon Trip TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP SETPOl!IT

~ 161 of n*rrow range ln1tru*ent

  • p*n-eech ate** generetor

~ 401 of ful I *tea* f I QM *t IATED THERMAL POWEi coincident with 1tee*

~ 2900 volt1-eech bu1

~ 56.5 Hz - eech bu1

~ 45 p1lg

~ 151 off full open Not Appllceble Not Appllceble ALLOWABLE VALUES

~ 14.BX of nerrow range ln1tru*ent spen-eech 1te** generator

!. 42--5 x 0-f-f.u..W-~

THERMA c

ent with 1te**

gener*tor weter level > 241 of 1p*n--e*ch

~ 2850 volt*-**ch bus

~ 56.4 Hz - eech bus

~ 45 p1lg

~ 151 off full open llot Appllceble lot Appllc*ble

LIBITI~SMETISl-~~S=E=TI~IN~G_S ________

  • ___________ _

BASES through the pressurizer safety valves. No credit was taken fc7 operation of this trip in the accident analyses; however, its~funccional capability at the specified trip setting is required by this specification to enhance the overall reliability of the Reactor Protection System.

.ass of Flow The Loss of Flow trips provide core protection to prevent DNB in the event of a loss of one or more reactor coolant pumps.

Above 11 percent of RATED THEBMAL POWER, an automatic reactor trip will occur if the flow in any two loops drop below 90% of nominal full loop flow.

Above 36% (P-8) of RATED THERMAL POWER, automatic reactor trip will occur if the flow in any single loop drops below 90% of nominal full loop flow. Tilis latter trip will prevent the minimum value of the DNBR from going below the design DNBR value during normal operational transients and anticipated transients when 3 loops are in operation and the Overtemperature ~T trip set point is adjuste~ to the value specified for all loops in operation. With the Overtemperature ~T trip set point adjusted to the value specified for 3 loop operation, the P-8 trip at 76% RATED THERMAL POWER will prevent the minimum value of the DNBR from going below the design DNBR value during normal operational transients and anticipated transients with 3 loops in operation.

Steam Generator Water Level The Steam Generator Water ~evel Low-Low trip provides core protection by preventing operation with the steam generator water level below the minimum volume required for adequate heat removal capacity. The specified setpoint provides allowance that there will be* sufficient water inventory in the steam generators at the time of trip to allow for starting delays of the auxiliary f eedwater system.

dw.a.t~J.~w Mi-smataa and Law Steam Cene!'ateP Water Level The Steam/Feedwate e with a Steam Generator Low Water Level trip is arid accident analyses but is included capa61 i e s ecif ied SALEH - UNIT 1 B 2-6 Amendment No. 96

LIMITING SAFETY SYSTEM SETTINGS BASES Undervoltage and Underfrequency - Reactor Coolant Pump Susses The Undervoltage and Underfrequency Reactor Coolant Puq> bus trips provide reactor core protection against !J'9 as a result of loss of voltage or underfrequency to more than one reactor coolant puq>.

The specified set points assure a reactor trip signal is generated before the low flow trip set point is reached.

Time delays are incorporated in the underfrequency and undervoltage trips to prevent spurious reactor trips from momentary electrical p~er transients. For undervoltage, the delay is set so that the time required for a signal to reach the reactor trip breakers following the sinultaneous trip of two or more reactor coolant pu!J1) bus circuit breakers shall not exceed 0.9 seconds.

For underfrequency, the delay 1s set so that the time required for a signal to reach the reactor trip breakers after the underf requency trip set point is reached shall not exceed 0.3 seconds.

Turbine Trip A Turbine* Trtp causes-. &**direct: reactor: *tMp when* operating, above. P-9.

Each.

of the* turbine-trips provide-turbine. protection and reduce the. severtty of the ensuing transient.

No credit was taken in the accident analy*ses for operation of these trips. Their functional capability at the specified trip settings is required to enhance the overall reliability of the Reactor Protection System.

SALEM - UNIT l B 2-7 Amendment No. as

I

"'.. -I i -

I w

I...

f

~ t

~..

a 0

fVllCTIQIW, UNIT

11.
12.

ll.

14 *

11.
11.

Preaaurlaor Uater...,,.l--Hl9h Lo** of Fllaw - 8lntl* Loop CAboY* *-Ot Lo** of Fllow - two......,.

CAbowe._,, and below P-8t ate.. Generator Water Lewel--

Low-Low underwoltage -

llea~or coolut.....

Underlrequeacr - lleactor coolut._..

TAILI J.l-1 <<eontinuec1a BIAC'lpl 'J'llP IXITM lllDUHlmTJ(Jll TOTAL *UMBll Of QINIBILI l

l/loop l/loop l/loop 4-1/bu*

4-1/bu*

CHANNELS

'l'O TllP 2

2/loop ln

  • nr oper-at 1119 loop 2/loop in tvo oper-at i"9 lOOJP9 2/loop in.
  • or oper-at 109 loop*

1/2 twice 1/2 twice

TABLE 3.*3-2 <<Continued)

R£ACTQR TRIP SYSTEM J~STRUHENTATION RESPONSE TIMES FUNCIIONAL UNIT

12.

Loe* of Flow - Single Loop (Above P-8)

13.

Losa of Flow -

Two Loops (Above P-7 and below P-8)

14.

Steam Generator Water Level-- Low-Low

~-Steam/t:eedwater Flow Mismatch andL(nJ

~\\..e-,1"'~

St.eam Sencuat.er Wat.er Le..,el

16.

Undervoltage-Reactor Coolant Pumps w

I -

0

17.

Underfrequency-Reactor Coolant Pumps

18.

Turbine Trip A.

Low Fluid Oil Pressure B.

Turbine Stop Valve

19.

Safety Injection Input from ESF

20.

Reacto~ Coolant Pump Breaker Position Trip

21.

Reacto~ Trip Breakers

22.

Automatic Trip Logic RESPONSE TIME s 1.0 seconds s 1.0 seconds s 2.0 seconds NOO:' APPUCABLE s 1.2 seconds s 0.6 seconds NOT APPLICABLE NOT APPLICABLE NOT APPLICABLE NOT APPLICABLE NOT APPLICABLE NOT APPLICABLE I

e I

I IABLI t.l-1 CCgptlnytd)

BIACTQB IBIP IX8DH ll8DUf11UATJOI IVBVllLJMCI BIOIJIBlfllNTS nDICJ'Igw. UHI'I

13. Lo**of rlaw - 'Im l.ooP9 1*. *t*.. Gencuablr.. tor Le**l--

Low-Low CllAllUL Clllcg 15-1.?J*t*.. /r**......_ *law Nl.. *tch *

~v,,.. ***- Aenen*or Mater r.-*

))W w

I....

IN I f

" :s I...

N....

16, Vnder.oltage - Reactor Coolant

17. Vnderfrequ*ncy - a.actor Coolant
  • .A,
18. Turbine Trip A,

Low Auto*top Oil Pr***ure Turbine *top Val** Clo*ur*

19. **f*tr lnjeictlon Input from ar 11.a.
20. ileactor Coolant Pulap Brea.. r

~ltlon Trip

21... actor Trip Brea.. r
    • A.
22. Automatic Trlp Loglc ft.A.

CALIIBATJOI CIUUINBL FUNCTIONAL TIST II II II II S/UCll 8/U(ll 11(.clt (St B

8/U( lOt, 11(11,lll, 8A(l2,llt and ll(Ht 111(5~

NODBS IN Wlllat SURVBILLANCI RIQUIR£D 1

1, 2 l, 2 1

1 1, 2 1, 2 1, 2 1, 2 and

  • 1, 2 and
  • I e

fUICTI OHAL UN II

13.

Ste** G*n*retor Weter Level* *Low*Lll)lil Generetor Wener Level

15.

Undervolt~1**leector Coolent Pu*p*

16.

Underfrequency*Reector Coolent Pu*p*

17.

Turbine Trip A. Low Trip Syate*

~

Preaaure m

I. Turbl~~ Stop Velve Cloeur11

18.

Sefety Injection Input fro* SSPS

19.

aeector Coolent Pu*p lroeker Poaltlon Trip TABLE 2.2*1 (Continyedt REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TRIP SETPOIU

?.. 161 of n*rrow rent* lnatru*ent apen***ch at*** t*n*r*tor rrow r*n1* lnatru*ent *p*n****ch et*** generetor

?.. 2900 volt****ch bua

?.. 56.5 Hz - **ch bua

?.. 45 p*it

~ 151 off full open Not Appllceble Not Applfceble ALLOWABLE VALUES

~ 14.BX of nerrow range tnatru**nt 1pen*eech at*** generetor generetor wet*r level ~

ner tru*ent apen****ch 1tee* generetor

~ 2850 volt****ch bua

~ 56.4 Hz - eech bus

?.. 45 pale

~ ~51 off full open Not Appllcebl*

Not Appllceble I

LI~ITI~G SAFETY SYSTEH SETTINGS BASES Loss of Flow The Loss of Flow trips provide core protection to prevent DNB in the event of a loss of one or more reactor coolant pumps.

Above 11 percent of RATED THERMAL POWER, an automatic reactor trip will occur if the flow in any two loops drop below 90% of nominal full loop flow.

Above 367. (P-8) of RATED THERMAL POWER, automatic reactor trip will occur if the flow in any single loop drops below 90% of nominal full loop flow. This latter trip will prevent the minimum value of the DNBR from going below the design DNBR value during normal operational"transients and anticipated transients when 3 loops are in operation and the Overtemperature delta T trip set point is adjusted to the value specified for all loops in operation. With the Overtemperature delta T trip set point adjusted to the value specified for 3 loop operation, the P-8 trip at 76% RATED TltERMAL POWER will prevent the minimum value of the DNBR from going below the design DNBR value during normal operational transients and anticipated transients with 3 loops in operation.

Steam Generator Water Level The Steam Generator Water Level Low-Low trip provides core protection by preventing operation with the steam generator water level below the minimum volume required for adequate heat removal capacity. The specified setpoint provides allowance that there will be sufficient water inventory in the steam generators at the time of trip to allow for starting delays of the auxiliary f eedwater system.

-Steam/i'.eedwater Flow Mismatch and Low Steam-Generator Watar~euel SALEH - UNIT 2 B 2-6 Amendment No. 72

DILi J,l a:golilo11aa IVI I BIACTOI Ill! lllhd 11111011111111111

!I MINIMUM

~AL llUHllBlt CllAllNIU CllANNILS APPLICABLlll c

IVllCTIOIN. VIII Of CllNIMILI m n1r QPEMILI llOQIS 3

ftCTIQN

11.

Pr***urlaer ~ater Level J

2 2

1,2 6.,

I

--Hl9h

12. Lo** of Flow - 11.. le l.aop J/loop 2/loop ln 2/loop in 1

11 CAbove P-11

  • nr oper-each oper-ati119 loop
  • ting loop lJ. Lo** of Flow -

'llWO LooP9 J/loop 2/loop ln 2/loop in 1

11 CAbov* P-'1 and Mlow P-lt two oper-each oper-atift4) loop*

atlng loop

14. Ste.. Generator ~ater l/loop 2/loop in 2/loop in 1,2 11 Level--Low-Lov any oper-each oper-ating loop*
  • ting loop

~

3/-loop"" level llloo and coincident loop-flow with

  • 1-tc 1/loo l/liDOp-flow 11
  • Unclervolta.,.-ia.actor
  • -1/bu*

1/2 twlc*

1 6

c:aolant,_,.

17.

Unclerf recpaencr-aoactor

  • -1/bu*

1/2 twice l

1 6

coolant,_,.

JI l *

~.

c:

z 0-1

-t N

w

~

w I

0 TABLE 3.3-2 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNH

12.

loss of Flow - Single Loop (Above P-8)

13.

loss of Flow - Two loops (Above P-7 and below P-8)

14.

Steam Generator Water Level--Low-Low t-5-.

~water flew Mis111atch aAd t/~~

0 Steam GeneFatoF WateF Le~el

16.

Undervoltage-Reactor Coolant Pumps

17. "Underfrequency-Reactor Coolant Pumps
18.

Turbine Trip A.

Lew Fluid Oil Pressure B.

Tur~ine Stop Valve

19.

Safety Injection Input from ESF

20.

Reactor Coolant Pump Breaker Position Trip

21.

Reactor Trip Breakers

22.

Automatic Trip Logic RESPONSE TIME

~ l.O seconds

~ l.O seconds

~ 2.0 seconds NQT APPLICABLE

~ 1.2 seconds

~ 0.6 seconds NOT APPLICABLE NOT APPLICABLE NOT APPLICABLE NOT APPLICABLE NOT APPLICABLE NOT APPLICABLE

0 en i

  • u1L1 t.l-1 <<Cgntinu*dl

~

BIACTQR TRIP SXIDH INIT8lJlllNTATIQN IUByllLLAUCI UOUIBIUN'l'S H...

CHANNEL HODES IN WHICH N

CllAllNSL FUllCTICRAL SURVEILLANCE rllJIC'HQIW, Vilt

ClllCI, CAI,llftATIQll TIST BIOUIR£D lJ. Lo** of Flow - Ttlll Laop9 8

R N.A.

1 14.. It*.. Generator Water Lewel--

R II 1, 2 Low-Low e

15 9

K 1, 2

\\.£1\\'£V~ =~:-.:::::.:

~(

16. Under.altage - a.actor coolant R

K 1

w Pwlp9 w

11. Unclerf r9f1U8DCJ - Reactor coolant II.A.

R I

II 1

Pullp*

N

18. Turbine Trlp
a. Low Auto*top 011 Pr**aur*
  • .A..

S/U(lt II.A.

b. 'l'urblne Stop llal** Clo11ur*

M.A.

S/U(l)

M.A.

19.. safety Injection Input f roa saw K(4)(5) 1, 2 I

I 20.. Reactor Coolant !Pump areU.r R

N.A.

I Po*ltlon Trlp 21

  • a.actor Trlp areak9r II.A.

II.A, 8/li(lO),

1, 2 and

  • f 11(11, ll)'

SA(12,1Jl) and R(U) 0 w

22. Aut011Atlc.Trip Logic M.A.

II.A.

II( 5) 1, 2 and *

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