ML20247M666

Forwards Corrections to Tech Specs Reflecting Implementation of WCAP-10271,Suppl 2 & Rev 1,per NRC 890222 Request.List of Attachments Providing Requested Info Submitted

ML20247M666
Person / Time
Site:	Comanche Peak
Issue date:	07/25/1989
From:	William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-89475, NUDOCS 8908020181
Download: ML20247M666 (37)

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M.E E Log # TXX-89475 1

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File # 836(3/4.3)

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-Ref. # 10CFR50.36-

' nlELECTRIC July 25, 1989 ww. m h.

Executive Vice President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C.

20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445' CPSES UNIT 1 TECHNICAL SPECIFICATIONS REF:

Letter dated February 22, 1989 from C. E. Rossi of the NRC to R. A. Newton of Westinghouse.

Gentlemen:

In the above referenced letter, the NRC provided the Safety Evaluation accepting the use of WCAP 10271, Supplement 2, and WCAP 10271, Supplement 2 Revision 1.

Attached are corrections to the CPSES Unit 1 Technical

' Specifications reflecting the implementation of the above WCAP supplement and-11 its revision.

In addition, the NRC requested: 1) clarification concerning the relationship between Technical Specification Figure 2.1-1, " Reactor Core Safety Limit" and-1 FSAR Figure 15.0-1, " Illustration of Overtemperature and Overpower N-16 Protection for Comanche Peak Unit 1": and 2) additional justification for Action'30 of Technical Specification Table 3.3-6.

l The following.is a list of attachments providing the above described information:

Attachment A:

Inforf.ation requested by the NRC.

Attachment B:

Description of changes to the CPSES Unit 1 Technical Specifications for implementing WCAP 10271, Supplement 2 and WCAP 10271, Supplement 2, Revision 1.

Attachment C:

Marked-up pages of the certified CPSES Unit 1 Final Draft Technical Specifications.

Attachment D:

Typed version of the proposed changes to the certified CPSES Unit 1 Technical Specifications.

00Y I

( t 8908020iel 890725 PDR ADOCK 05000445 A-PDC 400 North Olive Street LB81 Dallas, Texas 75201

._ua________.__.-.____

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TXX-89475 July 25, 1989 Page 2 of 2 i

i l

If you have questions concerning the attached changes, please contact Jimmy Seawright at 214/812-4375.

Sincerely, 1l.

9Ybhr/4.0 yhk William J. Cahill, Jr.

By:

$4 h Mr Rdge~r D. Walker Manager, Nuclear Licensing JDS/vid Attachments c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3)

I

my f

<4, Attachment A to TXX-89475 July 25, 1989 iE,

Page 1 of'1 h

1)

FSAR Figure 15.0-1, Relation to T/S Figure 2.1-1 FSAR Figure 15.0-1 is intended to illustrate the' protective features of the

.overtemperature and overpower N-16 reactor tr ps. Shown in this figure, among i

other things, are the loci of points which represent conditions where the Departure from Nucleate Boiling Ratio (DNBR) is equal to the DNBR limit value or which are outside the range of the DNBR correlation.

The DNBR may be most

. limiting'in a thimble channel or in a standard channel where no thimble is present.

In either case,1the limiting DNBR is shown in Figure 15.0-1, whether it be in a thimble or a standard channel.

In addition, the conditions may be outside the range of the DNB correlation for some situations.

For all cases, the overtemperature and overpower N-16 protection setpoints are determined such that a reactor trip is initiated prior to the time that any of the above conditions are realized.

The core safety limits shown in the Technical Specification Figure 2.1-1 are established in'a conservative manner such that the reactor will be in a more safe condition than the limits shown in.FSAR Figure 15.0-1.

In some situations, the'11mit lines may be the same for the two figures.

In general, the limit lines shown in the Technical Specification Figure are selected to bound several conditions, some of which are beyond the scale of Figure 15.0-1.

2)

Discussion on T(hot) and T(cold) Accident Monitoring Requirements Each RCS loop has one wide range (thermowell mounted) RTD located in the hot leg prior to the steam generator inlet and in the cold leg downstream of the reactor coolant pump discharge.

Since transients can be postulated that result in different thermal-hydraulic responses in each loop, the temperature measurements (one per loop) are not considered redundant to each other, i.e.,

the temperature response in one hot leg is not indicative of the response in the other loops during that transient. Therefore, sufficient instrumentation 1s required to indicate in the control room the thermal-hydraulic conditions in each RCS loop following a postulated transient.

The Technical Specifications require that the T(hot) and T(cold) instrumentation discussed above be operable in Modes 1. 2 and 3.

The Action l

- Statement that applies when a T(hot) and/or T(cold) instrument channel is l

inoperable requires a diverse means of providing similar information.

For T(hot) and T(cold), the diverse variables are Core Exit Thermocouple and l

Steam Generator Pressure, respectively. During the time period when the diverse variable is being used, there is no safety significance since the equivalent information from redundant channels remains available.

Because there is no safety significance, a 90 day allowance has been set to allow the primary indicator to be out of service but, during that time, en effort will be initiated to return the inoperable channel to service within as soon as practical.

L

p.

.AttaEhment.34to.TXX-89475

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CPSES' T/S AMENDMENT DETAILED; DESCRIPTION Page 1.

2-~

2 p,g, (as amended)'

Group. ' Description

{

3/4 3-8 2

.See Page No(s):9. 10, 13 Changes made to implement Westinghouse Topical Reports WCAP-10271 Supplement 2 and WCAP-10271 Supplement 2. Revision 1.

Revision:

4 Staggered testing is no longer required for the reactor trip system., Note 8 modified and Note 15 removed.

Change Request Number: TS-89-091 SER/SSER Impact: No'

'3/4 3-16 2

See Page No(s):19-21, 24-26, 35-39. 41 Changes made to implement Westinghouse Topical Reports WCAP-10271 Supplement 2 and WCAP-10271 Supplement 2. Revision 1.

Revision:

The Revision is consistent with the letter dated-Feb. 22, 1989 from C.E. Rossi of the NRC to R.A. Newton of Westinghouse.

l>

Change Request Number: TS-89-091 SER/SSER-Impact: No f3/4 3-19. (4.e)-

2

.See Page No(s):24 (Note e)

Changes made to implement' Westinghouse Topical Reports WCAP-10271 Supplement 2 and WCAP-10271 Supplement 2. Revision 1.

Revision:

Although not specifically addressed by the SER, i

these functions are CPSES specific by-nomenclature and perform the same function as the specific items listed in the Topical Report; therefore, these functions are also considered approved for implementation based upon the Topical Reports and the concurrence of Westinghouse.

Change Request Number: TS-89 091 SER/SSER Impact: No l'

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TABLE NOTATIONS a

Trip function may be blocked in this MODE below the P-11,(Pressurizer Pressure Interlock) Setpoint.

b Trip function automatically blocked above P-11 and may be unblocked below P-11 by blocking the Safety Injection on low steam line pressure.

C Not applicable if each affected main steam isolation valve and its associated upstream drain pot isolation valve per steam line is closed.

d The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

"The channel which provides a steam generator water level control signal (if one of three specific trip channels is selected to provide input into steam

/, Lor.s generator water level control) must be placed in the tripped condition within Q. W and maintained in the tripped condition with the exc ion that the channel may be taken cut of the tripped condition for up t ours to allow testing of recundant channels, q

INot applicable if Preferred Offsite Source Breaker is open.

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-TABLE 4.3-1 (Continued) TABLE NOTATIONS (Continued) l(8) The MODES specified for these channels in Table 4.3-2 are DRAFT more restrictive and,therefore, applicable. (9). Quarterly surveillance is MODES 3a, 4a, and Sa shall-also include verification that permissives'P-6 and P-10 are in' their required state for existing plant conditions by observation of the permissive annunciator window. Quarterly surveillance shall include verification of the Boron Dilution Alarm Setpoint of less than or equal to an increase of twice .the count' rate within a 10-minute period. (10) Setpoint verification is not applicable. (11) The TRIP. ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY.of the undervoltage and shunt trip attachments of the reactor trip breakers. (12) At.least once per 18 months during shutdown, verify that on a simulated Boron Dilution Doubling test signal the normal CVCS discharge valves close and the centrifugal charging. pumps suction valves fros'the RWST open. (13) With the high voltage setting varied as recommended by the manufacturer,.an initial discriminator bias curve shall be measured for each detector. Subsequent discriminator bias 2 curves -shall be obtained, evaluated and compared to the initial curves. (14) The TRIP ACTUATING DEVICE OPERATIONAL TEST-shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s). (15) (NOT USED) DRAFT (16) local manual shunt trip prior to placing breaker in service. D (17) Automatic undervoltage trip. D COMANCHE PEAK - UNIT 1 3/4 3-13 DRAFT R D D D D l l l l N ITC 6 2 7 7 A 1 1 1 1 ^ 4 4 F 8 I 3 3 3 3 B S A R C E 2 2 2 2 I E L R P 1 1 1 1 P A N ITR E W E IR S S T E S B L I C E B t3 e A I 9 I t ER 2 2 2 3 f N t F h B C I C T I C S Y S 2 e f ) IC I f T 3 o IE 3 T 1 T E C L t A E e S e S L P E h E I T E I R s M W ( 9 W T 1 1 2 2 1 E A I O E C T F YTEFAS D ER S E . L E E o E N N M I A C L B I A C 2 2 3 4 I T O F T O n r , i o o t s c q m t a c , e a e i n t t S n r p l o s s o o i r o i y , i t r e o l t S n n S t o T y t C e a p o o t c a s l n m n i i C a e C l - e n r t e , o o u o t t b E o r n e < n i n s i P i a a 1 ( s e i g e e D o I t t u u I t b r e c i a y a t t h n e r e F o y t t l e i c c g o " p c a n i r t A A t i r i A s u n, a n r e t p i n H e hc T E t " e n c e e V n s r n e d e - z T c e , m o C g p e e I i n m e i I e e F p o i r O t V t t t a n r r f j s m o t , e n n a l a s i u u R n a y u R a n m r e l e W a m c y a s s t I h r P l o E o m a m u o i a t s s d. P ia l u i t n i n e n t g l n e e y n o c t , a i t i c a u o e o r r ne t e r r a r r a n a i M A L R C P P v e p 1 v t i l e e t e t v l f i 4 i n c o t n n s n r b c d S T A D C R I W G C E C S a r o e s a e o s o e i. a r mu a 1 OO3p2OIm mD# 4 CZmH

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!=1 li le! 11 s t,! l 31 3 si 31', i l' IllIll!illll! liI ]ilI y 1! 31 !il 12 si ia at i e e COMANCHE PEAK - UNIT 1 3/4 3-21 DRAFT ' & *9 dlT TABLE 3.3-2 (Continued) TABLE NOTATIONS 1 a Trip function may be blocked in this. MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint. D b Trip function automatically blocked above P-11 and may be unblocked below P-11 by blocking.the Safety Injection on low steam line pressure. D c Not applicable if each affected main steam isolation valve and its associated upstream drain pot isolation valve per steam line is closed. D d The provisions of specification 4.0.4 are not applicable for entry into MODE 3. O e The channel which provides a steam generator water level control DRAFT signal (if one of three specific trip channels is selected to provide input into steam generator water level control) must be placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and maintained in the tripped condition with the exception that the channel may be taken out of the tripped condition for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to allow testing of redundant channels. f Not applicable if Preferred Offsite Source Breaker is open. lD ACTION 3TATEMENTS ACTION 12 - With the number of OPERABLE channels one less than DRAFT the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE. ACTION 13 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following i conditions are satisfied: a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and b. The Minimum Channels OPERABLE requirement is met; howevei, one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels per Specificat. ion 4.3.2.1. COMANCHE PEAK - UNIT 1 3/4 3-24 DRAFT p, '/p _ a[ M TABLE 3.3-2 (Continued) ACTION STATEMENTS (Continued) ' ACTION 14 - With the number of OPERABLE channels one 1ess than D .the Total Number of Channels, operation may proceed provided the inoperable channel _ is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional DRAFT channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for-surveillance testing per Specification 4.3.2.1. ACTION 15 - With less than the Minimum Channels OPERABLE-D requirement, operation may continue provided the containment pressure relief valves are closed - within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and maintained closed. ACTION 16 - With the number of OPERABLE channels' one less than D the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. ACTION 17 - With the number of OPERABLE channels one less than D the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: a. The inoperable channel is placed in the DRAFT tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and b. The Minimum Channels OPERABLE requirement is ORAFT met; however, one additional channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for' surveillance testing of other channels per Specification 4.3.2.1. ACTION 18 - With less than the Minimum Number of Channels D OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3. l COMANCHE PEAK - UNIT 1 3/4 3-25 DRAFT E- -- _ _- - - - , (1,[ n .f. TABLE 3.3-2 (Continued) ACTION STATEMENTS (Continued) ACTION 19 -- With the number'of OPERABLE Channels one less than DRAFT the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one' channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE. ACTION 20 - With the number of OPERABLE channels one less than D the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ACTION 21 - With the number of OPERABLE channels one less than D the Total Number of Channels, restore the inoperable channel to OPERABLE status within 4B hours or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5. ACTION 22 - With the number of OPERABLE channels one less than DRAFT the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE. ACTION 23 - With the number of OPERABLE channels one less than D the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: a. The inoperable channel is placed in the DRAFT tripped conditfon within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and i b. The Minimum Channels OPERABLE requirement is { met. ACTION 24 - With the number of OPERABLE channels one less than D l the Minimum Channels OPERABLE requirement, restore i - the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or initiate and maintain operation of the Control Room Emergency Recirculation System. COMANCHE PEAK - UNIT 1 3/4 3-26 DRAFT R D l EC I 4 4 E UJ 3 3 C J 3 I I R Z S W E 2 2, 2 E T t O t e C O U 1 1 1 I F S . ~ E v Y a T A. A. A t S I a E S F T N Q N R E T 1 T A T ) A. A. S I S EL E M N ( N M R D I T I S C E I T T N R C ) A. t G 1 0 I T A. T C D ( A I N M N EF I S E I L R E T G I S N C N I I I T E T L C A t I I R T P U B S I T V E S A. A. T r R C E F E S N T A D C T R N N Y m S o ) NIR s 2 I c LL f T a 3 o G R E E 4 t m C 1 T L I a C t G E T t. A e A I R T E A t 4 N I n s l E S A.. e L k A. a t E I. I C C T N N Q P i S a W I P E ( t I A W I 2 E A v w L N RF s E O Y I I T C T E L I A E T I F E t S l A B A.. 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E KC s M I E N N I E C C ,p e i n , y on r i n T b o c i r i n t r u t e a e y T a g t t r l r s S e y o e n t e la, c s m, n t n p , a d n n n I E n B l u e o o s a u imp g r, i i y r e r t t S S A n e t e a a p C e m e, t r t n m C , v E e W p. i P o a e o o u n E( n i d o r a e o I t i c 1 i D c e g a y t i n t o F n r t l e a g n i l o . n o a v n s ) i o o e a r R i o n i r , l t e t p t L i t i t o t l r i t n E T e s o o o r e e n o n a e mr i C e t V t t I i o u m I I M ) t t n n n a t i t n n " r n a t e e l t W l a t c. i e t I A e o l n G u a a e o a A y a. m L t c u e r i n e u c u t m y a c n r i t i c n t t d t n e t e w , r e e a n a i a u c n e o ,r L c e s d p i p s t e t v M A A a R C E I f a e i e m e n s n r u N T a h e r e c i o s o e EI C S P F T R c D C E C 5 a b e R 42 H t C F 1 W b WEWW QN3a = nQ5MZm TQ# e CZ 4 a 2 s t l?l' r R R D D l ~ EC 4 C I ) ~, 3, 4 N 4 4 E A I L E 3 3 3 3 3 E I R S; W E I 2, E V U 2 2 2, 2 .2 D R R Q 1 C O U E 1 1 F S R 1 1 1 3 E T V A T A. 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