ML20062E009

Proposed Tech Spec Change 90-14,Rev 1 Re Containment Isolation Valves

ML20062E009
Person / Time
Site:	Sequoyah
Issue date:	11/13/1990
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20062E005	List: ML20062E001 ML20062E009
References
NUDOCS 9011190195
Download: ML20062E009 (4)

Text

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ENCLOSURE 1' .

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' PROPOSED TECHNICAL SPECIFICATION CHANGE r

SEQUOYAH_ NUCLEAR PLANT; UNIT 2-DOCKET No.-'50-328 ,

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' I (TVA-SQN-TS-90-14)- , _

LIST OF AFFECTED PAGES '

l Unit 2 ,

3/4 6 3/4 6-20

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9011190195 901113 ..

PDR ADOCK 03000327 '

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m TABLE 3.6-2 -

E g CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds)

A. PHASE "A" ISOLATION

" 1. FCV-1-7 SG Blow Dn 10*

2. FCV-1-14 .SG Blow Dn 10* ,

3. FCV-1-25 SG Blow Dn 10*

' 4. FCV-1-32 SG Blow Dn 10*

5. FCV-1-181 SG Blow Dn 15* R29

6. .FCV-1-182 -SG Blow Dn 15*

7. FCV-1-183 SG Blow Dn 15*

8. .FCV-1-184 SG Blow Dn. 15*

9. FCV-26-240 -

Fire Protection Isol. 20

10. FCV-26-243 Fire .'rotection Isol. 20

{ 11. FCV-30-134 Cntet Bldg Press Trans 4*

. Sense Line

[ 12. FCV-30-135' 'Cntmt Bldg Press Trans 4*

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Sense Line'

13. FCV-31C-222 CW-Inst Room Cles. 10*

14. FCV-31C-223 CW-Inst Room Cirs '10*

15. FCV-31C-224 CW-Inst Room Clrs 10*

16: FCV-31C-225 CW-Inst Room Cirs 10*

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

'18. FCV-31C-230

'CW-Inst Room.Cirs- 10*

.19. FCV-31C-231 CW-Inst' Room Clrs'- 10*' -

R62' FCV-31C-232 CW-Inst Room'Clrs 10*. -

21.f-5UC-V-43 20 ,

Sample Przr Steam Space 10*

.-- 22. FCV-43-3 Sample Przr Steam Space. 10*

2: E ' 23 % 11 Sample.Przr Liquid 10* ,

x $ 24. FCV-43-12 ' Sample Przr Liquid -10*

E 25 m ev-43 Sempie.RC Outiet.adrs .10*

$ 26. FCV-43-23: . Sample RC Outlet Hdr's. 10*

g" 27PfeV-43-34 Accum Sample 5*

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28. FCV-43-35 ..'Accum Sample 5*

2 29'5 SG Blow On Sample ~Line 10*- '

1309 % 43 '

. .o hEV-43-58:. SG Blow Dn Sample Line 10*

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m TABLE 3.6-2 (Continued)

E g CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds) g A. PHASE:"A" ISOLATION

" 31. 61 SG Blow Dn Sample Line 10*

32 64 SG Blow Dn Sample Line 10*

33N C-V-43-75 Boron Analyzer 5*

34. FCV-43-77 Boron Analyzer. 5*

35. FCV-61-96

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Gylcol Inlet to Floor Cooler 30*

36. FCV-61-97 Gylcol Inlet to Floor Cooler 30*

37. FCV-61-110 Gylcol Outlet to Floor Cooler 30*

38. FCV-61-122 Gylcol Outlet to-Floor Cooler - 30*

39. FCV-61-191

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Ice Condenser .Gylcol In ~ 30*

40.'FCV-61-192 Ice Condenser - Gylcol'In 30*

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• 41. FCV-61-193 Ice Condenser - Gylcol-Out -30*

42. FCV-61-194- Ice Condenser - Gylcol Out. 30* "

i '43. FCV-62-61

-RCP Seals. 10 :

E$- 44. FCV-62-63'- RCP Seals 10

-45.-FCV-62-72 Letdown Line- -10*#-

46. FCV-62  : Letdown Line'~ '10*#

i 47. FCV-62-74 Letdown Line: -10*#~

48. FCV-62-77:- Letdown Line 20-

49. FCV-63-23 Accum to Hold Up Tank :10*

~50. FCV-63-64 ._ W OS.N 2 :to Accum_ 10*' _

S1. FCV-63 lAccum to Hold Up Tank;- 10*

~52. FCV-63-84

_Accum to Hold Up Tank- 110*~ . .

5> EI 53. FCV-68-305: M)S N2 to PRT- :10*'

E" 54. FCV-68-307 ' PRT to Gas _ Analyzer..- 10*

5%

C; - $

55. FCV-68-308 PRT to' Gas Analyzer.

10* .

56. FCV-70-85' CCS'from Excess Lt Dn Hx 10*

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57. FCV-70-143 -CCS to Excess-Lt Dn Hx - 60*'

GE 58. FCV-77-9 . RCDT Pump.Disch -10*

59. FCV-77-10

'RCDT Pump Disch 10*

~ g 'k 60. FCV-77 RCDT and PRT to V H -10*

R691.

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. ENCLOSURE 2 ,

l L Description of Change i

In Technical Specification (TS), Change 90-14, submitted Mayf21, 1990.1 '

Tennessee Valley Authority proposed to modify the Se,quoyah Nuclear Plant; (SQN) Units 1 and 2.TSs to revise valve nomenclature in TS Table 3.6-2.

The proposed change modified 14 sampling-valves in the TS table from flow: ,-

control valve (FCV) to flow solenoid valveL(FSV). The change in valves;is:

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associated with plant modifications that' support TVA's commitment for- ,

upgrading SQN Units'1 and 2 to meet-the guidelines of NRC Regulatory: Guide?

l (RG) 1.97, " Instrumentation for Light Water-Cooled. Nuclear Power Plants ltol '

i Assess Plant and Environs Conditions During and~Following an. Accident."' '!

The modifications _have been completed as planned'for Unit li but five ofK the originally planned modifications for Unit 2 will not be made. ,

Reason for Change l . l For the-reasons discussed in the originalfsubmittal, the noted 14, t i

air-operated FCVs were replaced-with FSVs in Unit 1. .For_ Unit 2,_however, five FCVs will not be replaced' by FSVs as - originally planned. These five valves are located in the annulus and can accommodate a-microswitch-type ;i limit switch that is environmentally qualifiable. ;The limit. switches are scheduled for installation during the Unit 2-Cycle 4 refueling outage.

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Justification for~ Change l

i The valve changes have been evaluated under TVA's'10 CFR.50.59l process.

l The evaluation determined that an unreviewed safety question does not! '}

exist. The change-in nomenclature does not affect the containment isolation function for these valves. ,

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