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

ATTACHMENT 2 MARKED UP PAGES l__

9302170068 930205 PDR ADOCK OS000272 P PDR

TABLE 2.2-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOl!IT ALLOWABLE VALUES

13. Ste** Gener*tor W*ter ~ 161 of n*rrow range ln1tru*ent ~ 14.BX of nerrow range ln1tru*ent Level--Low-Low *p*n-eech ate** generetor spen-eech 1te** generator

~ 401 of ful I *tea* f I QM *t IATED !. 42--5 x 0-f-f.u..W-~

Mh*etch en THERMAL POWEi coincident with 1tee* THERMA c ent with 1te**

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

15. Undervoltege*leector ~ 2900 volt1-eech bu1 ~ 2850 volt*-**ch bus Cool*nt Pu*p1 I

OI 16. Underfrequency-leector ~ 56.5 Hz - eech bu1 ~ 56.4 Hz - eech bus Cool*nt Pu*p*

17. Turbine Trip A. Low Trip $y1te* ~ 45 p1lg ~ 45 p1lg Pre11ure I. Turbine Stop Velve ~ 151 off full open ~ 151 off full open Clo1ure
18. Sefety lnjec~lon Input Not Appllceble llot Appllceble fro* SSPS
19. leector Coolont Pu*p Not Appllceble lot Appllc*ble lreeker Po*l~lon Trip N

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 TAILI J.l-1 <<eontinuec1a

  • BIAC'lpl 'J'llP IXITM lllDUHlmTJ(Jll I

i TOTAL *UMBll CHANNELS fVllCTIQIW, UNIT Of QINIBILI 'l'O TllP

11. Preaaurlaor Uater ...,,.l--Hl9h l 2
12. Lo** of Fllaw - 8lntl* Loop l/loop 2/loop ln CAboY* *-Ot *nr oper-at 1119 loop ll. Lo** of Fllow - two ......,. l/loop 2/loop in CAbowe ._,, and below P-8t tvo oper-at i"9 lOOJP9 14
  • ate. . Generator Water Lewel--

Low-Low l/loop 2/loop in .

  • or oper-w I at 109 loop*
11. underwoltage - llea~or 4-1/bu* 1/2 twice coolut .....
11. Underlrequeacr - lleactor 4-1/bu* 1/2 twice coolut . _ . .

f~

t..

~

a 0

TABLE 3 .*3-2 <<Continued)

R£ACTQR TRIP SYSTEM J~STRUHENTATION RESPONSE TIMES

.... FUNCIIONAL UNIT RESPONSE TIME

12. Loe* of Flow - Single Loop (Above P-8) s 1.0 seconds
13. Losa of Flow - Two Loops (Above P-7 and below P-8) s 1.0 seconds
14. Steam Generator Water Level-- Low-Low s 2.0 seconds

~-Steam/t:eedwater Flow Mismatch andL(nJ NOO:' APPUCABLE

~\..e-,1"'~ St.eam Sencuat.er Wat.er Le..,el

16. Undervoltage-Reactor Coolant Pumps s 1.2 seconds
17. Underfrequency-Reactor Coolant Pumps s 0.6 seconds w

0 I 18. Turbine Trip A. Low Fluid Oil Pressure NOT APPLICABLE B. Turbine Stop Valve NOT APPLICABLE

19. Safety Injection Input from ESF NOT APPLICABLE 20.

21.

Reacto~

Reacto~

Coolant Pump Breaker Position Trip Trip Breakers NOT APPLICABLE NOT APPLICABLE I e

22. Automatic Trip Logic NOT APPLICABLE I

I IABLI t.l-1 CCgptlnytd)

BIACTQB IBIP IX8DH ll8DUf11UATJOI IVBVllLJMCI BIOIJIBlfllNTS CIUUINBL NODBS IN Wlllat CllAllUL nDICJ'Igw. UHI'I FUNCTIONAL SURVBILLANCI Clllcg CALIIBATJOI TIST RIQUIR£D Lo**of rlaw - 'Im l.ooP9 13.

  • * **** 1 1*. Low-Low
  • t*.. Gencuablr . .tor Le**l-- *
  • II 1, 2 15-1.?J*t*. ./r**......_ *law Nl . .*tch *

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

  • II l, 2

))W 16, Vnder.oltage - Reactor Coolant

  • II 1 w

IN I

17. Vnderfrequ*ncy - a.actor Coolant *.A,

" II 1

18. Turbine Trip A, Low Auto*top Oil Pr***ure
    • **** **** S/UCll 1, 2 Turbine *top Val** Clo*ur*
        • **** 8/U(ll 1, 2
19. **f*tr lnjeictlon Input from ar 11.a. **** I e
20. ileactor Coolant Pulap Brea..r ..... ****

11(.clt (St B

1, 2 I ~ltlon Trip f" 21. ..actor Trip Brea..r ** A.

        • 8/U( lOt, 11(11,lll, 1, 2 and *
s 8A(l2,llt and I ll(Ht N 22. Automatic Trlp Loglc ft.A.
        • 111(5~ 1, 2 and
  • TABLE 2.2*1 (Continyedt REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS fUICTI OHAL UN II TRIP SETPOIU ALLOWABLE VALUES
13. Ste** G*n*retor Weter Level* *Low*Lll)lil

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

~ 14.BX of nerrow range tnatru**nt 1pen*eech at*** generetor I

Generetor Wener Level generetor wet*r level ~

rrow r*n1* lnatru*ent *p*n****ch ner tru*ent apen****ch et*** generetor 1tee* generetor

15. Undervolt~1**leector  ?.. 2900 volt****ch bua ~ 2850 volt****ch bua Coolent Pu*p*
16. Underfrequency*Reector  ?.. 56.5 Hz - **ch bua ~ 56.4 Hz - eech bus Coolent Pu*p*
17. Turbine Trip A. Low Trip Syate*  ?.. 45 p*it  ?.. 45 pale

~ Preaaure m I. Turbl~~ Stop Velve ~ 151 off full open ~ ~51 off full open Cloeur11

18. Sefety Injection Input Not Appllceble Not Appllcebl*

fro* SSPS

19. aeector Coolent Pu*p Not Applfceble Not Appllceble lroeker Poaltlon Trip

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 BIACTOI Ill! lllhd 11111011111111111

... I.

!I MINIMUM

~AL llUHllBlt CllAllNIU CllANNILS APPLICABLlll c3 IVllCTIOIN. VIII

11. Pr***urlaer ~ater Level Of CllNIMILI J

m n1r QPEMILI llOQIS ftCTIQN

"' 2 1,2 6 .,

--Hl9h 2

I

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

  • .~

TABLE 3.3-2 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES c:

z 0-1

-t FUNCTIONAL UNH RESPONSE TIME N

12. loss of Flow - Single Loop (Above P-8) ~ l.O seconds
13. loss of Flow - Two loops (Above P-7 and below P-8) ~ l.O seconds
14. Steam Generator Water Level--Low-Low ~ 2.0 seconds w

....... t-5-. ~water flew Mis111atch aAd t/~~ Steam GeneFatoF WateF Le~el 0

~ NQT APPLICABLE w

I

16. Undervoltage-Reactor Coolant Pumps ~ 1.2 seconds 0
17. "Underfrequency-Reactor Coolant Pumps ~ 0.6 seconds
18. Turbine Trip A. Lew Fluid Oil Pressure NOT APPLICABLE B. Tur~ine Stop Valve NOT APPLICABLE
19. Safety Injection Input from ESF NOT APPLICABLE
20. Reactor Coolant Pump Breaker Position Trip NOT APPLICABLE
21. Reactor Trip Breakers NOT APPLICABLE
22. Automatic Trip Logic 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--

Low-Low

  • R II 1, 2 e

\.£1\'£V~ =~:-.:::::.:

15  :  :;:  :

9

  • K 1, 2

~( .

w

16. Under.altage - a.actor coolant **** R K 1

...... Pwlp9 w

N I 11. Unclerf r9f1U8DCJ - Reactor coolant Pullp*

II.A. R II 1

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 Po*ltlon Trlp

        • **** R N.A.

I.. 21

  • a.actor Trlp areak9r II.A. II.A, 8/li(lO),

11(11, ll)'

1, 2 and

  • f 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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