ML20079B932

Proposed Tech Specs Revising Tech Specs Tables 2.2-1,4.3-1 & Associated Bases to Accomodate Replacement of Existing RTD Bypass Sys W/Rtd Thermowell Sys

ML20079B932
Person / Time
Site:	Wolf Creek
Issue date:	06/11/1991
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML19302E608	List: ML20079B922 ML20079B928 ML20079B932
References
NUDOCS 9106180204
Download: ML20079B932 (9)

Text

Attachment VI to ET 91-0073 Page 1 of 9 ATTACIIMENT VI PROPOSED TECIINICAL SPECIFICATION CilANGES k

9106180204 910611 PDR ADOO: O'5000482 P PDR

IN TABLE 2.2-1 ggn o

5 REACTOR TRIP _SYSTEH IllSTRUMEllTATIO!! TRIP SETPolilTS 0 SEllSOR e[-

' TOTAL ERROR fut1CT1011AL UtilT ALLOWAllCE (TA) Z (5)__ IRIP SETP0lliT ALLOWABLE VALUE g ff. A. m E 1. Manual Reactor Trip  !{. A. ft. A. ff. A. ii. A.

~

~ e

- 2. Power Range, tieutron Flux 6

a. I!igh Setpoint 7.5 4.56 0 .-<109% of RTP" -<112.3% of RTP*

b. Low Setpoint 8.3 4.56 0 $25% of RTP* $28.3% of RTP*

Power Range,lieutron Flux, 2.4 0.5 0 <4% of RIP

• with <6.3% of RTP* with  !

3.

tiigh Positive Rate i time constant a time constant I 12 seconds 12 seconds

4. Power Range, tieutron Flux, 2.4 0.5 0 $4% of RTP* with $6.3% of RTP* with m

liigh fiegative Rate a time constant a time constant 12 seconds 12 seconds

5. Intermediate Range, 17.0 8.41 0 $25% of RTP* $35.3% of RTP*

ticotron Flux Source Range, P.utron Flux 17.0 0.01 1105 cps $1.6 x 105 cps 6.

3. .72 7.2 See tiote 1 See tiote 2

7. Overtemperature AT . .

5.5 43-- ~ See riote 3 See tiote 4 S. Overpower AT .

3.7 0.71 2.49 11875 psig 11866 psig y 9. Pressurizer Pressure-Low Pressurizer Pressure-liigh 7.5 0.71  ?.49 $2385 psig 12400 psig

} 10.

11. Pressurizer Water Level-liigh 8.0 2.18 1.96 $92% of instrument $93.9% of instrument span span y

y ' rip = RATED Ti1ERMAL POWER

'I oop design flow = 95,700 gpm .

I I

??

TABLE 2.2-1 (Continued) =g o 00 7 G; TABLE NOTATIONS o, f n

A NOTE 1: OVERTEMPERATURE AT "" c m --

{K, - K 2 I 1 + r,5) * ) 1 7 1

• o

AT( (1 + 5) r2 1 + f a5) < AT0 (1 + IsS) [T (1 + Tc5) - T'] + K 3 (P - P') - f1(AI)} n3 z -4 Z -

e)

~ Where: AT =

Feasureda}(f,RIO"_arfcidInstrumentatiEE{)

_ ______ __ _ _ - _ _ _ _- [

a 1 + r'5 = lead-lag compensator on measured AT;

-a to 3, 3 t i, r2 = Time constants utilized in lead-lag compensator for AT, 1 = 8 s, 3 12= 3 s; 1

= Lag compensator on measured AT; m

B 1+1 35 N

13 = Time constant utilized in the lag compensator for AT, 13 = 0 s; ar o = Indicated AT at RATED THERMAL POWER; Ki = 1.10; K2 = 0.0137/ F; i

1 + r4S = The function generated by the lead-lag compensator for T

'5 cynamic compensation; #9

=

T 4, 13 Time constants utilized in the lead-lag compensator for T, ,14 = 28 s,

13 = 4 s; T = Average temperature, F; 1

'9 C *E*"5" "" " **'*"#*

avg; 1 + tcS l

t,; =

Time constant utilized in the measured I, lag compensator, tc = 0 s;

u> i c5 TABLE 2.2-1 (Continued) $"  !

ro g I

G ur (,

' 9 g NOTE 1: .

(Continued)

TABLE fl0TATIONS (Continued) d e"

f n <

T' 5 588.5*F (Nominal T,,, at RATED THERMAL POWER); $ i l 5 K3 = 0.000671; ~ r, t

l P = Pressurizer pressure,~psig; i l,  !

l P' =

2235 psig (Nominal RCS operating pressure); S w

I j i i

5 =

Laplace transform operator, s 1; t

and f i (al) is a function of the indicated difference be'. ween tap arid bottom detectors of the power range neutron ion chambers; with gains to be sels:cted based on measured instrument l response during plant STARTUP tests such that:

~ ,

E (i) for qt gbbetween -27% and + 7%,3 f (al) = 0, where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and q +q tS t b total THERMAL POWER in percent of RATED THERMAL. POWER;

{

i l (ii) for each percent that the magnitude of qt qbexceeds -27%, the AT Trip Setpoint shall be automatically reduced by 1.57% of its value at RATED THERMAL POWER; and  !

(iii) for each percent that the magnitude of q t Ob exceeds +7%. the AT Trip Setpoint j

! shall be automatically reduced by 0.85% of its value at RATED THERMAL POWER. I i l

f40lE 2

The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 6  !

! 64- of oT span. "

l t c.  !

n .

t i

6

. . -, i5

~.

o>

TABLE 2.2-1 (Continued) $%

r *E O TABLE NOTATIONS (Continued) #5 S

m NOTE 3: OVERPOWER AT e"-:

AT(1(I+*1b) ( I ) -K ( '7b ) ( I 1 + tc5 ) T - Kc [T (1 + tc5) - T"] - f (AI)}

4 3 2 o e

25) (1 + 1 5)3 < ATo {K 1+1 75 E O e

- Where: AT =

Measured AT;(IITO mAri(50 ~iiM-tit 4]ene {

= lead-lag compensator on measured AT; f

ri, 12 = Time constants utilized in lead-lag compensator for AT, 1 1

= 8 s. T 2 = 3 5; 1 = L g compensator on measured AT; 1+1 S 3 7 13

= Time constant utilized in the lag compensator for AT, 1 3 = 0 s; e

AT g = Inclicated AT at RATED THERMAL POWER; K4 = 1.08; K3 = 0.02/*F for increasing average temperature and 0 for decrc sing average temperature; The function generated ty the rate-lag compensator for T, dynamic y{7 73

=

compensation;

= Time constant utilized in the rate-lag compensator for T ,17 = 10 s; ty 1

=

1 + tcS Lag compensator on measured T g; tc

= fime constant utilized in the measured T, lag compensator, Ic = 0 s;

%N

!5 TABLE 2.2-1 (Continued) %E m

TABLE NOTATIONS (Continued) a n o%

1. 10TE 3: (Continued) 'E

=

c Ks 0.00128/*F for T > I" and Ks = 0 for T < T"; G

= Average temperature, 'F; r

} T

~

~ w 1" = '

Indicated T,yg at RATED TilERMAL POWER (Calibration temperature for AT g instrumentation, f 538.5*F);

5 = Laplace transform operator, s 1; and f 2(al) = 0 for all al.

~ t0TE 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 4 -

. /+-ik of AT span. l 3

n 2

o O

J T

^

_ _______M

1 TABLE 4.3__1 l 6 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 2 o c.

n TRIP

, ,Q R

W ANALOG CHANNEL ACTUATING DEVICE MODES FOR WHICH o5

• o

. CHANNEL CHAf:NEL OPERATIONAL OPERATIONAL ACTUATION o SURVEILLANCE c- FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS RE0tilR[0 5 I r+

1. Manual Reactor Trip N.A. N.A. N.A. R(11) N.A. 3*. 4'. 5*/

]

1, 2,

2. Power Range, Neutron Flux

a. High Setpoint e 5 D(2,4) Q(14) N.A. N. A. 1, 2 7 ,

M(3, 4)

Q(4, 6) 8 R(4, 5) y

b. Low Setpoint 5 R(4) S/U(1) N.A. N.A. 1###, 2 m 3. Power Range, Neutron Flux, N.A. R(4) Q(14) N.A. N.A. 1, 2

) High Positive Rate

4. Power Range, Neutron Flux, N.A. R(4) Q(14) N A. N.A. 1, 2 High Negative Rate S. Intermediate Range, S R(4,5) S/U(1) N.A. N.A. 1###, 2 Neutron Flux i

6. Source Range, Neutron Flux 5 R(4. 5, 12) S/U(1),Q(9.14) N.A. N. A. 2##, 3, 4, 5

7. Overtemperature AT S F Q(14) N.A. N.A. 1, 2 y 8. Overpower AT S R Q(14) N.A. N.A. 1, 2 O

g 9. Pressurizer Pressure-Low 5 R Q(14) N.A. N. A. 1

" 10. Pressurizer Pressure-High 5 R Q(14) N.A. N.A. 1, 2 I

11. Pressurizer Water Level-High 5 R Q(14) N.A. N.A. I m

12. Reactor Coolant Flow-Low 5 R Q(14) N.A. N.A. 1

r __-

Attachment VI to ET 91-0073 Page 8 of 9 1ABLE 4.3-1 (Continued)

TABLE NOTAll0NS (13) CP*'EL CT,LIBMTIO" ;hal' inclwie-the "TD bypee leep; f!e- ate.

(14) Each channel shall be tested at least every 92 dajs on a STAGGERED TEST BASIS. ,

1 (15) The . surveillance frequency and/or MODES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable.

(16) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(17) Local manual shunt trip prior to placing breaker in service.

(18) Automatic undervoltage trip.

i l

/

l WOLF CREEK - UNIT 1 3/4 3-12a Amendment No.12,26

Attachment VI to ET 91-0073 Page 9 of 9 LIMITING SAFETY SYSTEM SETTINGS

% \

BASES Intermediate and Source Range, Neut ron Flux The Intermediate and Source Range, Neutron Flux trips provide core protection during reactor startup to mitigate the consequences of an un-controlled rod cluster control assembly bank withdrawal from a subcritical condition. These trips provide redundant protection to the Low Setpoint trip of the Power Range, Neutron Flux chtnnels. The Source Range channels will initiate a Reactor trip at about 105 counts per second unless manually blocked when P-6 becomes active. The Intermediate Range channels will initiate a Reactor trip at a current level equivalent to approximately 25% of RATED THERMAL POWER unless manually blocked when P-10 becomes active.

Overtemperature AT The Overtemperature AT trip provides core protection to prevent DNB for all combinations of pressure, power, coolant temperature, and axial power distribution,providedthatthetransientisslowwithresgecttopiping _

transit delays from the core to the temperature detectorsu 2cyt_ j ;ccond Q and pressure is within the range between the Pressurizer High and Low Pressure trips. The Setpoint is automatically varied with: (1) coolant temperature to correct for temperature induced changes in density and heat capacity of water and includes dynamic compensation for piping delays from the core to the loop

. temperature detectors, (2) pressurizer pressure, and (3) axial power distribution.

With normal axial power distribution, this Reactor trip limit is always below the core Safety Limit as shown in Figure 2.1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the Reactor trip is automatically reduced according to the notations in Table 2.2-1.

Overpower aT The Overpower aT Reactor trip provides assurance of fuel integrity (e.g., no fuel pellet melting and less than 1% cladding strain) under all possible overpower conditions, limits the required range for Overtemperature AT trip, and provides a beckup to the High Neutron Flux trip. The Setpoint is automatically varied with: (1) coolant temperature to correct for temperature l induced changes in density and heat capacity of water, and (2) rate of change of temperature for dynamic compensation for piping delays from the core to the loop temperature detectors, to ensure that the allowable heat generation rate (kW/ft) is not exceeded. The Overpower aT trip provides protection to mitigate l- the consequences of various size steam breaks as reported in WCAP-9226, " Reactor Core Response to Excessive Secondary Steam Releases."

WOLF CREEK - UNIT 1 B 2-5

- - -- - . ~- - - - - . -

Proprietary Information Notice Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant-specific review and approval.

In order to conform to the requirements of 10CFR 2.790 of the Commission's regulations concerning the protection of proprietary inforraation so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets and where the proprietary information has been deleted in the non-proprietary versions only the brackets remain, the information that was contained within brackets in the proprietary versions having been deleted. The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (g) contained within parentheses located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or on the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in sections (4)(ii)(a) through (4)(ii)(g) of the affidavit accompanying this transmittal pursuant to. -

10CFR2.790(b)(1).

Copyright Notice The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, i suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.790 regarding i restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection not withstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the i public document room in Washington, DC and in local public document rooms as may be required by NRC regulations it the number of copies submitted is insufficient for this purpose. The NRC is not authorized to make copies for the personal use of members of the public who make use of the NRC public document rooms. Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.

1 e

- - - . - - - - - , , - v-.