ML20215B938

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs,Adding Requirements for Two Flow Control Valves to Table 3.4-1, RCS Pressure Isolation Valves
ML20215B938
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 06/10/1987
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20215B933 List:
References
TAC-R00153, TAC-R00154, TAC-R153, TAC-R154, NUDOCS 8706170518
Download: ML20215B938 (7)
v • d • e


Text

r;.:

l.

ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANCE' SEQUOYAH NUCLEAR PLANT' UNITS 1 AND 2 DOCKET.NOS.-50-327 AND 50-328

.(TVA-SQN-TS-87-35) 1 LIST OF AFFECTED PAGES Unit 1

. 3'/4 4-15a Unit 2 3/4'4-20 l

-I' 8706170518 870610

- PDR ADOCK 05000327 p- PDR ,

., .n ua L - a ..a:x. a:. ... x ,- - a m

1 TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER FUNCTION

~63-560 Accumulator Discharge 63-561 Accumulator Discharge

63-562 Accumulator Discharge 63-563 Accumulator Discharge 63-622 Accumulator Discharge 63-623 Accumulator Discharge 63-624' Accumulator Discharge 63-625 Accumulator. Discharge 63-551 Safety Injection (Cold Leg)63-553 Safety Injection'(Cold Leg)63-557 63-555 Safety Injection (Cold Leg)63-632 Safety Injection (Cold Leg)63-633' Residual Heat Removal (Cold Leg)63-634

. Residual Heat Removal (Colo Leg)

Residual Heat Removal (Cold Leg).63-635 63-641 - Residual Heat Removal (Cold Leg) '

l Residual Heat Removal / Safety Injection (Hot Leg)63-644 Residual Heat Removal / Safety Injection (Hot Leg)63-558 Safety-Injection (Hot Leg)63-559' Safety Injection (Hot Leg) ~"63-543 Safety Injection.(Hot Leg)63-545 Safety Injection (Hot Leg)

'63-547 Safety Injection (Hot Leg)63-549 Safety Injection (Hot Leg)63-640 Residual Heat Removal (Hot Leg)63-643 Residual Heat Removal (Hot Leg)87-558 Upper Head-Injection 87-559 Upper Head Injection.87-560 lR.43 Upper Hea'd Injection 87-561 Upper Head Injection 87-562 Upper Head Injection 87-563 Upper Head Injection FCV-74-1* Residual Heat Removal i

i FCV-74-2* Residual Heat Removal i

  • I

^These valves do not have to be leak t sted followin; manual or automatic actuation or flow through the valve.

FC v- 87 7 >

FCV-81-8* W

  • WWD U7fet Head Tna% (Chaje3 l4&er} }

I l

= r, xx SEQUOYAH - UNIT 1 3/4 4-15a

/ '=dnat R Z .

, r "? 1. xJu m:n e.h Ab %W **+M'" **'^'#'#

C TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISCLATION VALVES VALVE NUMBER FUNCTION 63-560 Accumulator Discharge 63-561 Accumulator Disenarge 63-562 Accumulator Discharge 63-563 Accumulator Discnarge '63-622 Accumulator Discharge 63-623 .

Accumulator Discharge 63-624 Accumulator Discharge 63-625 Accumulator Discharge 63-551 Safety Injection (Cold Leg)63-553 Safety Injection (Cold Leg)'63-557 Safety Injection (Cold Leg)63-555 Safety Injection (Cold Leg)63-632 Residual Heat Removal (Cold Leg)63-633 Residual Heat Removal (Cold Leg) '63-634 Residual Heat Removal (Cold' Leg)63-635 - Residual Heat Removal (Cold Leg). i 63-641 Residual Heat Removal / Safety Injection (Hot Leg)63-644 Residual Heat Removal / Safety Injection (Hot Leg)63-558 Safety Injection-(Hot Leg)- 63-559 Safety Injection (Hot Leg)  ;63-543 Safety Injection (Hot Leg) ) i 63-545 Safety Injection (Hot Leg)63-547 Safety Injection (Hot Leg)63-549 Safety Injection (Hot Lag)63-540 Residual Heat Removal (Hot Leg)63-643 Residual Heat Removal (Hot Leg)37-558 Upper Head Injection i 87-559 Upper Head Injection l 87-560 Upper Head Injection [

87-561 Upper Head Injection l 87-562 Upper Head Injection 87-563 Upper Head Injection FCV-74-1* Residual Heat Removal FCV-74-2* Residual Heat Removal  ;

~

Upper ned LiecM*^ho<3 i n3 O 4per }{ enol Tejetb(OW3 ig IbMW "Tnese valves co not have to be leak tested following manual or automatic

. actuation or flow through the valve. ) {

SEQUOYAH - UNIT 2 3/4 4-20 i

a*Mb 4% # '.,E h4T &# if ,*.Af. Y ,-'.d fsis . L.hv GM mvmdM#h

.a , .

l ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS, 50-327 AND 50-328 (TVA-SQN-TS-87-35)

DESCRIPTION AND JUSTIFICATION TO ADD REQUIREMENTS FOR REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES.

l.

i

' I.

,C<

* '"#" "S**'!'*A

  • O*UWwA*Y '

c f

ENCLOSURE'2 Description of Change The proposed change'will add requirements for two flow cont'rol valves-(FCV-87-7 and FCV-87-8) to Table 3.4-1, " Reactor Coolant-System Pressure

' Isolation Valves."

Reason for Change The referenced safety 7 evaluation report (SER) identified the need for

? inclusion of valves FCV-87-7 and FCV-PT-8 to table 3.4-1. These valves are: located in~a line connecting the 14 quid waste disposal system to the-upper head' injection (UHI) system. The purpose of 'this line is leakage testing of the'UHI' check valves.- =The valves in table 3.4-1 are required to be operable in order to prevent leakage from the reactor coolant system ,

(RCS) into a-lower pressure system. The inoperability of these. valves 1 creates the potential of an.intersystem loss of coolant accident (LOCA). j

.As such, the subject valves:should be listed in table 3.4-1 to ensure the {

appropriate limiting conditions.for operation (LCO) and surveillance' j requirements are satisfied. l y

Justification for Change i i

'The UHI-system,.which'has a design pressure below the RCS operating zpressure, is" connected to the RCS through two main injection lines'that branch into. four ' reactor head injection lines. The. main' injection lines d lare isolated from the'RCS with series check valves. Test and drain lines connect between the series check valves.- Each test and drain line has an air-operated globe valve which serves a pressure isolation function to protect the UHI system from pressures which exceed its design limit.

The UHI system is shown in figure 6.3.2-15 of the Final Safety Analysis l Report (FSAR). TVA valves FCV-87-7 and FCV-87-8 are designated 1-9984A j

'and 1-9984B on the FSAR figure since it is'a vendor' drawing. These valves are located in a line connecting the UHI system to the liquid waste disposal system and perform this pressure isolation function. These

' valves are designed, installed, and maintained as RCS pressure isolation valves. The subject' valves are leak rate tested to the requirements of

-Surveillance Instruction (SI)-166.11. "UHI Check. Valve Integrity." These valves have inadvertently been omitted in table 3.4-1. Since these valves are air-operated valves, it is not necessary to perform testing following manual or automatic actuation or flow through the valve. .This is indicated by the asterisk in table 3.4-1.

The proposed change will add requirements to table 3.4-1 to include flow control valves FCV-87-7 and FCV-87-8. Inclusion of the subject valves

.will ensure that the condition of these valves is adequate to maintain j redundant isolation and system integrity.

Reference l T. M. Novak's letter to H. G. Parris dated April 5, 1985, " Safety Evaluation Report on Sequoyah Inservice Test Program for Pumps and Valves  !

-(IST)."

w.ad.._a h am a w d h j

1 F '

Ia ,

d

c. r ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANGES i 1

SEQUOYAH NUCLEAR PLANT-UNITS 1 AND.2 l DOCKET NOS. 50-327 AND.50-328

(TVA-SQN-TS-87-35)

DETERMINATION OF NO SIGNIFICANT' HAZARDS CONSIDERATIONS i

'FOR ADDITIONAL' REQUIREMENTS FOR REACTOR COOLANT 'l l

' SYSTEM PRESSURE ISOLATION VALVES 4

l J

I f

M-s Y {3b .gr,,f $f $t* il gy 'k ,,,go . _ , , ',,,41

+

e'4\Lj f' ' , p ;&Q 'gg _'

g, .j -

g ,

ENCLOSURE 3 SIGNIFICANT HAZARDS CONSIDERATIONS J

. 1.: Is.the probability of an occurrence or the consequences of an accident previously evaluated in the safety analysis report significantly increased?

No. The proposed amendment to the technical specifications changes

. Table 3.4-1, " Reactor Coolant System Pressure Isolation Valves," to I include flow control. valves FCV-87-7 and FCV-87-8. The omission of the subject 1 valves from table 3.4-1 was an oversight. The subject valves. currently undergo testing as pressure isolation valves as identified in Surveillance Instruction (SI)-166.11, " Upper Head Injection' Check Valve Integrity." .The proposed change will provide.

for the two valves to be subject to the. limiting condition for operation for pressure isolation valves and the corresponding surveillance requirements (SRs), Thus, the proposed amendment will  :

provide for increased administrative controls over the subject valves.

- 2. Is the possibility for an accident of a new or different. type than evaluated previously in the safety analysis report created?

No. Flow control valves FCV-87-7 and FCV-87-8 are designed, installed, and maintained as. reactor coolant system (RCS) pressure isolation valves. The proposed amendment does not involve a change in hardware capabilities or a modification in the operation of the plant.

3. Is the margin of safety significantly reduced?

No. The margin of safety has actually been increased. -The proposed amendment will provide additional assurance that FCV-87-7 and FCV-87-8 will perform their intended function and provide for remedial action should it be determined that the valves are inoperable. Continued operability of these valves will ensure redundant isolation and system integrity are maintained.

4

..m,- . v . w w m a _ w a:a m e u.n;a a w -

Retrieved from "https://kanterella.com/w/index.php?title=ML20215B938&oldid=3239875"