Text

Proposed Tech Specs Re Containment Isolation Valves
	ML20043B075
Person / Time
Site:	Sequoyah
Issue date:	05/21/1990
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20043B072	List: ML20043B071; ML20043B075;
References
	NUDOCS 9005240151
	Download: ML20043B075 (10)
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ENCLOSURE l' PROPOSED TECHNICAL SPECIFICATION CHANGE' SEQUOYAH NUCLEAR PLANT UNITS 1~AND;2 DOCKET-.NOS. 50-327 AND:50-328'

-(TVA-SQN-TS-90 14)

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s2 TABLE 3.6-2 '

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f g CONTAINMENT ISOLATION VALVES

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VALVE NUMBER ', FUNCTION

. . . . c MAXIMUM ISOLATION TIME (Seconds) 3 A.

y. PHASE "A" ISOLATION '

i 1. FCV-1-7 SG Blow Dn

!@Of

" 2.

3.

FCV-1-14 SG Blow Dn 10*

10*

FCV-1-25 SG Blow Dn

.; 4. FCV-1-32 10*

' SG Blow Dn 10*

5. FCV-1-181 SG Blow Dn R41 it 6. FCV-1-182' 15*

'* SG Blow Dn 15*

7. FCV-1-183 SG Blow Dn

! 8. FCV-1-184 15*

SG Blow Dn

]. -

N 9.

10.

FCV-26-240 Fire Protection isol.

15*

20 FCV-26-243 . Fire Protection isol.

j 11. 20 2

[* FSV-30-134 Cntat B1dg Press Trans [.. 4*

U ,

Sense Line

? 12. - FSV-30-135 Cntet Bldg Press Trans , .

P 4*

Sense Line ,

13. FCV-31C-222 CW-Inst Room Cirs

i 14. 10*

FCV-31C-223 CW-Inst Room Cirs

15. .. 10* g FCV-31C-224 .

CW-Inst Room Cirs

,._ ' 16. ~~

10*

FCV-31C-225 CW-Inst Room Clrs \

10* R74

d- 17. FCV-31C-229 CW-Inst Room Cirs 10*

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y!: 18. FCV-31C-230 CW-Inst Room Cirs 10*

f I- 19. FCV-3iC-231 CW-Inst Room Cirs Td 20. 3 10*

FCV-31C-232 CW-Inst Room C1rs

[6 21.#vfEV-43-2 / Sample Przr Steam Space 10*

UM 22. & M 43-3 f . Sample Przr Steam Space 10*

YE 23.MVfEV-43-11 Sample Przr Liquid 10*

10*

k3 24.rsvfEV-43-12 Sample Przr Liquid 10*

.'E 25.ssvfEV-43-22 Sample RC Outlet Hdrs-7 10*

26.73V-FEV-43-23 Sample RC Outlet Hdrs 10*

Efw 27.EstfEV-43-34 -Accum Sample 5*

28.fsVfEV-43-35 Accum Sample : 5*

? 29.75Y-FEV-43-55 SG Blow Dn Sample Line

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n m TABLE 3.6-2 (Continued) j j CONTAINMENT ISOLATION VALVES

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VALVE NUMBER FUNCTION g - c MAXIMUM ISOLATION TIME (SeccMs),

Jg { A. PHASE "A" ISOLATION (Cont.)

z-30.F5V fEV-43-58 p ;[}' 31. IWFEV-43-61 SG Blow Dn Sample Line 10*

SG Blow Dn Sample Line 10*

y 32. nVfCV-43-64 SG Blow Dn Sample Line

g 33.nV-FEV-43-75 10*

Boron Analyzer 5*

34./W-FEV-43-77 Boron Analyzer

35. FCV-61-96 5*

- Gylcol Inlet to Floor Cooler 30*

2 36. FCV-61-97 . Gylcol Inlet to Floor Cooler

37. FCV-61-110 30*

, Gylcol Outlet to Floor Cooler 30*

38. FCV-61-122 ':

't R*

39. FCV-61-191 ' . ' Gylcol Outlet to- Floor Ice Condenser GylcolCooler In 30*

I 40. 30* R7 FCV-61-192 7. Ice Condenser - Gylcol In g ? 41. FCV-61-193 30*

j- . '" Ice Condenser - Gylcol Out 30*

Es 42. FCV-61-194 l; Ice Condenser - Gylcol Out 30*

t 43. FCV-62-61 ,T RCP Seals i: 44. 10 FCV-62-63 .0 RCP Seals

! 45. FCV-62-72 10 46.

CLetdownLine 10*#

FCV-62-73 ~3 Letdown Line

47. FCV-62-74 10*#

+',.

's Letdown Line 10*#

48. FCV-62-77 .. Letdown Line F__ 49. FCV-63-23 20 M% Accum to Hold Up Tank 10*

50. FCV-63-64 WDS 2N to Accus

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51. FCV-63-71 10*

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TABLE 3.6-2

'h. 5 '

g

( -< CONTAIMMENT ISOLATION VALVES

[ ^ f. ~ E VALVE NUMBER FUNCTION y/ c A. PHASE "A" ISOLATION MAXINUM ISOLATION TIME (Seconds)

M 5

" 1. FCV-1-7 h: 3 ?. 2. FCV-1-14 SG Blow Dn SG Blow Do 10*

g 3. FCV-1-25 10*

i Iu/ 4 FCV-1-32 SG Blow Dn

.SG Blow Dn 10*

f" 5. FCV-1-181. 10*

! 6. SG Blow Dn 15 R29 FCV-1-182 SG Blow On

.i 7. FCV-1-183 15*

8. SG Blow Dn 15*
FCV-1-184 SG Blow Dn
9. FCV-26-240 15*
Fire Protection Isol.
10. FCV-26-243 20 ,.
1 {[ Fire Protection Isol. 20
{ 11. FCV-30-134 Cntet B1dg Press Trans Sense Line 4* r.
$ T 12. FCV-30-135 * .
U Cntat B1dg Press Trans 4*
iJ i Sense Line
13. FCV-31C-222
y. 14. FCV-31C-223 CW-Inst Room Cirs 10* -
li CW-Inst Room Cirs 10*
15. FCV-31C-224 .
g CW-Inst Room Clrs ., 10*
16. FCV-31C-225 ,
CW-Inst Room Cirs 10*
17. FCV-31C-229 CW-Inst Room Cirs ,
18. FCV-31C-230 , 10*
CW-Inst Room Cirs 10*
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19. FCV-31C-231 :
CW-Inst Room Clrs k'. . 20. CV-31C-232 ;. 10* R62
Q[;l 21 2 CW-Inst Room Cirs .
10* -
.s 22! FEV-43-3 Sample Przr_ Steam Sppce 10*
j .,e l F 23f*fEV-43-11 Sample Przr Steam Space - 10*
i i 'g< $ 24PfEV-43-12 Sample Przr Liquid 10*
j.: & Sample Przr Liquid 10*
25PjFfy-43 Sample RC Outlet Hdrs f... ;;; E 26PfEV-43-23 Sample RC Cutlet Hdrs -
10*
M;" 27.6TEV-43-34 Accum Sample 10*
I aE 28.5'FfV-43-35 Accum Sample.
5*
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SG Blow Dn Sample Line 10*
.. - . 30.* W V-43-58 SG Blow Dn Sample Line 10*
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m TABLE 3.6-2 (Continued)
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CONTAINMENT ISOLATION VALVES -
h VALVE NUMBER 4- . FUNCTION- '
MAXIMUM ISOLATION TIME (Seconds)
![i i+ -
.g A. PHASE "A" ISOLATION I~ " ,
" 31?fsV-43-61 SG Blow h Sample Line j[.' 32PF6V-43-64 SG Blow Dn Sample Line Id.10*
33Pf6Y-43-75 Boron Analyzer
.I 10*
. (i' 34FF6V-43-77 5*
'7 35. FCV-61-96 Boron Analyzer e 2,
5*
36. FCV-61-97 Gylcol Inlet to Floor Cooler 30*
37..FCV-61-110 Gylcol Inlet to Floor Cooler 30*
38. FCV-61-122 Gylcol Outlet to Floor Cooler 30*
39. FCV-61-191.- Gylcol Outlet to Floor Cooler 30*
-40. FCV-61-192 Ice Condenser - Gylcol In 30*
R
41. FCV-61-193 Ice Condenser - Gylcol In 30*
42.- FCV-61-194 Ice Condenser - Gylcol Out 30*
i! T 43. FCV-62-61 Ice Condenser - Gylcol Out 30* 8 0 E 44.'FCV-62-63 '
RCP. Seals' 10
!O s RCP Seals
45. FCV-62-72 '~
. 10 il 46. FCV-62-73 Letdown Line 10*#
d 47. FCV-62-74 . Letdown Line 10*#
48. FCV-62-77 Letdown-Line- 10*#
I 49. FCV-63-23 Letdown Line' 20 1
50.-FCV-63-64 Accum to Hold Up Tank 10*
ti . 51. FCV-63-71 WOS 2N to Accum
. - 10
fjy ::,.
52. FCV-63-84 :Accum to' Hold Up Tank- 10*
17. . 4 E' 53. FCV-68-305 Accum to Hold Up Tank 10*
M g E 54. FCV-68-307' . WDS 2N to PRT ' 10*
115e2 "E 'PRT to Gas Analyzer ~ 10*
'i;3 55. FCV-68-308 GE"
- 56. FCV-70-85 : PRT to Gas Analyzer 10*
i
57. FCV-70-143 CCS from Excess Lt Dn Hx 16*
lf4F - g'E 58. FCV-77-9
S + fxcess Lt Dn Hx -60*
$: ' 59. FCV-77-10 A ' ' .W Disch- 10*
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60. FCV-77-18 C' Nao Disch 8#D f ad 1T to V H 10*
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ENCLOSURE'2 PROPOSED-TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1-AND ?J h DOCKET NOS. 50-327 AND 50-328
-(TVA-SQN-TS-90-14)
. DESCRIPTION AND JUSTIFICATION FOR CHANGE TO TECHNICAL SPECIFICATION TABLE'3.6-2 i
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. . . .. . . . . ~ .. .. . . . . . . . . . . . . . . . . .
L ENCLOSURE 2 l
Description of Change Tennessee Valley Authority proposes to modify the Sequoyah Nuclear Plant (SQN) Units'l and 2 Technical Specifications (TSs) to revise valve nomenclature in TS Table 3.6-2. .The proposed change modifies 14 sampling-valves in the TS table from flow control valve (FCV) to flow solenoid valve (FSV). The change in valves is associated with plant modifications that support TVA's commitment for upgrading SQN Units 1 and 2 to meet the guidelines of NRC Regulatory Guide'(RG) 1.97, " Instrumentation for Light Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident." These plant modifications are currently in progress for-the Unit 1 Cycle 4 refueling outage. Similar modifications are scheduled for the Unit 2 Cycle 4 refueling outage that is projected to begin in October 1990.
Reason for Change The 14 air-operated FCVs as listed in SQN TS Table 3.6-2 are being replaced with FSVs. SQN's current FCVs have limit switches that are'not environmentally quallflable. The valve stroke is too small (3/8 inch) to have functional and-environmentally-qualified.11mit switches. .Therefore these valves will be replaced with FSVs that are totally enclosed and'have-reed switches internal to the valve. This changeout at SQN is. required as part of TVA's commitment for complying with RG.I.97 (refer to, License Condition-2.C.(24) of the SQN Unit 1 Facility Operating License DPR-77 and License Condition 2.C.(14) of the SQN Unit 2 Facility Operating License DPR-79).
Justification for Change
.The valve change was evaluated under TVA's 10 CFR 50.59 process. The evaluation determined that an unreviewed safety question does not exist.
The change in nomenclature for-14 sampling valves from FCV.to FSV does not affect the containment isolation function for these valves. Closure times for the new FSVs was evaluated to ensure that these valves will meet the 5- and 10-second maximum ~ isolation time requirements in TS Table 3.6-2.
The new FSVs are designed to close against a pressure drop of 2,485 pounds per square inch gauge with a temperature of 640 degrees Fahrenhelt'.
Therefore, these valves will be compatible with SQN's reactor coolant' system (RCS) and capable of closing against RCS-pressure. With the exception of four steam generator blowdown (SGBD) sampling valves,' local leak-rate testing will be conducted as a premodification test-to.-determine "as-found" leak rate in accordance with 10 CFR 50 Appendix J and again following installation for "as-left" leak rate to demonstrate acceptable leak-rate criteria for containment integrity. The SGBD sampling valves at SQN are a part of the steam generator secondary side piping and are-located outside containment. By design, the SGBD piping employs.two barriers to prevent fission product release from containment following a loss of coolant accident (1) the secondary side is a closed system inside containment and (2) SG water level provides a water seal.
.i
. j
L These containment isolation barriers thereby exempt the.SGBD valves from
-the Appendix.J leak-rate test program. (Refer to SQN Final Safety Analysis' Report, Table 6.2.4-1; notes for Containment Penetrations X-14A, B, C, and 0.) ;
Environmental Impact Evaluation The proposed change request does not involve an unreviewed environmental.
question because operation of SQN Units 1 and 2-in accordance with this change would not:
1. . Result in a significant increase in any adverse environmental-impact previously evaluated in the Final Environmental Statement (FES):as modified by the Staff's testimony to the. Atomic Safety and Licensing Board, supplements-to'the FES, environmental impact appraisals, or decisions of the Atomic Safety and Licensing Board.
2. Result in a significant change in effluents or power levels.
3. Result in matters not previously reviewed. in the licensing basis for SQN that may have a significant environmental impact.
4
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g-e ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANGE-SEQUOYAH NUCLEAR PLANT-UNITS'1-AND 2' DOCKET NOS. 50-327-AND 50-328' (TVA-SQN-TS-90-14)
DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION'
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. ~L p .3 ENCLOSURE 3.
Significant. Hazards Evaluation TVA has evaluated the proposed _ technical specification (TS) change and-has determined that it does not represent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). . Operation of Sequoyah Nuclear Plant (SQN) in accordance with the proposed amendment will not:
(1) Involve a significant increase in the. probability or consequences of i an accident previously evaluated. 1
-TVA's proposed change to TS Table'3.6-2 d_oes not change the ,
containment 1 solation function for these valves.. The-valve changeout from air-operated FCVs to solenoid-operated FSVs'was' evaluated under TVA's 10 CFR 50.59 process. TVA's evaluation determined that an.
unreviewed safety question'does not exist.-. This changeout is required to support TVA's commitment for' Regulatory Guide l.97 l compliance. The installation of FSVs with totally enclosed reed j switches provides environmental qualification of these' valves "
resulting in improved reliability for.CIV. position-indication during and following an-accident._ The.' closure times for the FSV design also provides improved isolation response times'. In addition, 10 CFR'50,
- Appendix J leak-rate criteria;for.the FSVs will not-be compromised by q this change. ' Consequently, TVA's proposed!TS change does not' l increase the probability or consequences of an accident previously i evaluated. ' '
l (2) Create the-possibility of a new or different kind of accidentLfrom any previously. analyzed.
~
TVA's proposed change does'not' introduce (the' possibility for a new:or j different kind of accident from those.previously analyzed. The proposed TS change was evaluated under the 10'CFR 50.59. process.
TVA's evaluation determined that there is not impact to SQN's containment integrity or containment isolation times. No new failure modes are introduced in the system and/or components, therefore,no ,
new unanalyzed accident scenarios are' created.by this change. :. !
(3) Involve a significant reduction in a margin of safety. !
The proposed change from FCV to FSV in: Table 3.6-2 kill not affect the containment isolation function for these valves. The change in ;
valve design from air operated to solenoid operated provides an' )
environmentally qualifiable valve, resulting in improved CIV position i indication postaccident. This valve changeout will~.not impact the
' 5- and 10-second maximum isolation time requirements in TS ;
Table 3.6-2. Therefore the proposed TS change does not reduce the '
margin of safety.
h l

ML20043B075

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