Text

Hydraulic Isolation Valve Static Timing Tolerance Increase
	ML20214J981
Person / Time
Site:	Sequoyah
Issue date:	07/24/1986
From:	Watson M; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20214J962	List: ML20214J960; ML20214J967; ML20214J981;
References
	NUDOCS 8608150256
	Download: ML20214J981 (26)
	v • d • e

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MPEAEMM i P.7 JUL 25 '06 13:45 WEC MNC g 2 Sequoyah Upper Head Injection System "HydaulicIsolationValve

Static Timing Tolerance Increase" i

8608150256 860808 PDR ADOCK 05000327 P PDR g, g. hiat$0n July 24, 1986 e

Attachment to Letter (FSD/CWBS-264 05025.D281.D

JUL 25 '86 13:45 WEC MNC MM1 tam l .P. 8 I. Introduction This report is an evaluation on the Seq oyah Unit 1 & 2. Upper Head Injection (UN! system. Specifically, t concerns the tolerance ontheUHIaccu)mulatorisolationvalves(9982A.8and9983A.B)place and on the level switch repeatability. Sequoyah has found difficulty in meeting the required closing time accuracy of 3.61 05 seconds at an oil arcumulator pressure range of 2800-3200 psig during static testing of the valves. Sequoyah requested Westinghouse to broaden this tolerance to an improved operability limit. Westinghouse has determined an acceptable

.rsnge on the isolation valve clo n re times, but in so doing has found it necessary to modify tolerances on several other variables which make up the total uncertainty in isolating UHZ delivery. The level switch repeatability accuracy has to beireduced from 5.6 inches to 2.0 inches.

This is justified by the fact tnat Sequoyah's new 1sval switches. Static

- '0" Ring (SLR).haveshowngoodrepeatabilitymeasurementsinrecent testing. The other variable which must be changed is the pressure range )

on the four hydraulic accumulators which supply oil to the isolation valves. Wherear before the pressure of nitrogen in the accumulators ranged from a low alarm of 2800 psig to a high alam of 3200 psig, now it must be from 2900-3200 closing time to be set at psig.Thesechangeswillenablethevalvestatic j

' .5 1 14 sec.

i II. Method of Calculation i A calculation was performed in order to find the best combination of these variables which will yield an acceptable system.

The calculation uses information from static valve closing test and from a high pressure blowdown test which simulates a LOCA situation. The L blowdown test data was.taken at Sequoyah on 12/15/78. The following j

variables contribute to the range on the valve closing time during the blowdown:

o Volume of hydraulic acewnulators o Charge pressure of nitrogen in the hydraulic accumulator for static conditions o Static closing time of isolation valve o Charge pressure of N2 during high pressure blowdown test i

o Actual closing time of valves during blowdown test t

From bis information Westinghouse detemined a resistance factor for the valve during static conditions and a friction force for the valve i

t which is.present during valve closure during the blowdown. A minimum 3 t

and maximum dynamic valve elesing time was calculsted based on possible combinations of operating conditions.

05025.0281.D l

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JUL 25 '86 13:46 WEC g P.9 i l

The variance in closing time from the nominal 4.0 seconds is converted to the uncertainty in water volume delivered through the valves. The uncertainty from the valve closure is greater than it had been previously; and therefore, the level switch repeatsbility toleran,ce was lowered in order to meet the total allowable uncertainty in UNI water volume delivery.

Based on the calculation results, the following values on the UNI system will be modified as indicated:

~

1) Static set time on isolation valves.

Old value: 3.5 + .06 seconds New value: 3.5{.14 seconds

2) Low alam pressure of nitrogen in hydraulic accumulator.

Old value: 2800 psig

New value: 2900 psig

3) Level switch repeatability.

Old value: + 5.6 inches New value: I2.0 inches This Technical Spec'ification change does not affect the volume delivery i

reautrements and therefore does not affect plant safety. This change is only to improve the flexibility in perfoming surveillance on the valves.

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05025.0281.D

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S2qu:yth Nuclear Plant DISTRIBUTION C var Page 1 1C Plrnt Msetsr File

) Pwr Plant Superintendent Asst Pwr Plant Supt. , (Oper.)

SPECIAL TEST Asst Pwr Plant Supt., (Maint.)

Asst Pwr Plant Supt., (H&S)

Administrative Supervisor SQ-STEAR-INST-83-13 Maintenance Supervisor (H)

Assistant Maintenance Supervisor (H)

Maintenance Supervisor (E)

RELIABILITY TEST OF STATIC-0-RING (SOR) Assistant Maintenance Supervisor (E)

IU Haintenance Supervisor (I)

LEVEL SWITCil FOR UHI WATER ACCUMULATOR Engineering Supervisor Operations Supervisor Quality Assurance Supervisor Health Physics Supervisor UNIT 2 % Public Safety Services Supv.

Chief Storekeeper

)e Preop Test Program Coordinator Field Services Supervisor Chemical Engineer (Engineering) '

Radiochem Laboratory

} ,

, IC Instrument Shop j

' Reactor Engineer (Engineering)

Instrtunent Engineer (Haint. I) i Mechanical Engineer (Engineering)

Plant Services Supervisor

! Prepared By: Jeff Zysk Training Center Coordinator Public Safety Services - SQNP Shift Engineer's Office Revised By: N/A Unit Control Room Health Physics Laboratory Submitted By: bqksb. bb h IC Nelr Document Control Unit-C s) Supervisor U IU Pwr Plant Superintendent, WBNP Pwr Plant Superintendent, BFNP PORC Review: P'[2.2/f-3 Pwr Plant Superintendent, BENP D/te IU NEB,-K Resident NRC Inspector - SNP Approved By: Te n al Support Center gwrPltSuperintendent Unit Control Room #2 V Compliance Section Staff Supv.

Date Approved: P!23/f-J

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Reactor Systems Group-C IU Eng & Control Engineering, 1300 CST 2-C The current revision level *of this instruction is: 0 .

Reason for current revision (include all temporary change numbers) Special test to determine if the prototype SOR model 103 d/p switch is a suitable replacement for Harton model 288 d/p switch.

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'S:quoych Nuc1:cr Plcnt SPECIAL TEST INSTRUCTION C ,v;r Sh:: t P:g2 2 SQ-STEAR-INST-83-13

f,-- Hirt:ry cf R;visicns R v. Level Date Revised Pages Rev. Level Date Revised Pages o ll100 2 31983 All ,

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SQNP

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' SQ-STEAR-INST-83-13 P:ga 1 cf. 3

, Rev. 0 1.0 Objective The purpose of this special test is to determine if the prototype SOR model 103 d/p switch is a suitable replacement for the Barton model 288 d/p switch. The prototype SOR d/p switch will be installed in parallel with one of the Barton 288 d/p switches which monitor UHI water accumulator level. The Instrument Maintenance Section will adjust and record calibration data for the SOR prototype once a month to obtain base line reliability data.

2.0 Prerequisites 2.1 Inform the senior reactor operator (SRO) and the assistant shift engineer (ASE) of test procedures before the installation of the prototype SOR d/p switch. Also inform the SRO that LS-87-21 will be removed from service during the installation of the SOR d/p switch.

Performed by / ('/29[S

3. 0 Precautions '

There are no special precautions, limitations, or actions necessary to protect plant employees and equipment during this special test. The switch will be installed during a refueling outage; therefore, no action statement will be entered.

4.0 Instructions Installation of Prototype Switch 4.1 Open breaker 6 on 120-V ac vital power boar I to electrically remove LS-87-21 from service. Hold order no. '200 /

Performed by &# NE / f/n/n

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Verified by / / rN VMJ

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4.2 Isolate LS-87-21 as follows.

Close high-side panel isolation valve Open equalizing valve Close low-side panel isolation valve Performed by / ,E. / 3 Verifled by St- / PI' +'

/

43 Install Son d/p switch on panel 2-L-490 in parallel with LS-87-21 such that the piping is connected to the calibration tees through a 3-valvo manifold (or equivalent valve arrangement). See attached erformed by / JM

//~V Verified by '/Nf7- / [!2/ /- *

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. ggyu SQ-STEAR-INST-83-13

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Rev. O Initial and Periodic Calibration Notes: 1. For initial calibration, skip steps 4.4 through 4.6 and enter "N/A" on the data sheet.

2. Steps 4.4 through 4.12 may be performed in conjunction with the periodic calibration of LS-87-21 if desired.

3 Multiple copies of the data sheet for steps 4.4 through 4.12 are attached to this test. One copy should be used for each calibration. All completed copies are to remain attached to the test.

4.4 Inform SRO that LS-87-21 will be removed from service during the calibration of the prototype 30R d/p switch.

4.5 Open breaker 6 on 120-V ac vital power board 1-I to electrically remove LS-87-21 from service. Hold order no. 14e/

4.6 Isolate LS-87-21 as follows.

Close high-side panel isolation valve Open equalizing valve Close low-side panel isolation valve 4.7 Isolate SOR d/p switch as follows.

Close high-side isolation valve Open equalizing valve Close low-side isolation valve 4.8 Calibrate the SOR d/p switch to 141.4 +2.0-inch WC. Record as-found and as-left values on the data sheet.

Note: If the as-found setpoint is within the desired tolerance of +2.0-inch WC, no setpoint adjustments should be made.

4.9 Valve in LS-87-21 and ensure sense lines tre properly filled.

4.10 Valve in prototype SOR d/p switch and ensure sense lines are proporly filled.

4.11 Close breaker 6 on 120-V ne vital power board 1-I to electrically return LS-87-21 to service.

4.12 Inform SHO that LS-87-21 has been returned to service.

Note: Steps 4.4 through 4.12 will be repeated at least once per month until sufficient data is obtained to determino the reliability of the switch.

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, ,. SQ-STEAR-lNST-83-13 P g2 3 cf 3 R;v. O Removal of Prototype Switch and Return to Normal Status 4.13 Notify ASE and SRO that LS-87-21 will be temporarily out of service for removal of the SOR /p switch.

Performed by F / s ( V y

4.14

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Open breaker 6 on 120-V ac vital power b6ard 1-I to electrically remove LS-87-21 f. rom service, old o no. W Performed by /[ 8 /5 /O F'V Verified by .~ % / /f v 4.15 Isolate LS-87-21 as follows.

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Close high-side panel isolation valve Open equalizing valve Close low-side panel isolation valve Performed by o/ :rd, _

//o /85 </

Verified by r m e /6 (

4 4.16 RemoveprototypeSORd/pswitchfrompane/ l 2-L-490 and restore permanent piping to original configuration.

Performed by 'k0 lha iD f_bn / di/M t/

Verified by c - 2e . / / %YSy 4.17 Valve in LS-87-21 and ensuf'e sense lines ,are properly filled.

Performed by c $1 im 6ttfio / 85Y Verifled by e- , / ks 7 4.18 Close breaker 6 on 120-V ac vit 1 p I / /

y ard 1-I to electrically return LS-87-21 do se .

Performed by .i/' / S' Verified by d v

7

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,- f 4.19 Inform SRO that LS-87-21 has been returned to service and this test is complete.

Performed by 4 - t o +- y / 9V 4 / '/

5.0 Acceptance Critoria None required. This test is used to obtain reliability data only.

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l Page 1 of 2 ,

Date P Vo 8(/

Sequoyah Nuclear Plant ST-INST 13 Data Sheet (4teps 4.4 - 4.12)

Rev. 0 4.4 SRO informed that LS-87-21 will be remo d from vice during calibration of SOR d/p swit Ferformed bf fln e sw valid > /3 x20 EY

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g. sy -19 #

45 openbreaker6on120-Vaovitalpowerboard,q(toelectrically -I remove LS-87-21 from service. Hold order no." 2/A 141//

Performed by Cl4 t L) / X-80-0 Verified by ~

10E u C71ss. /3 :20 *S T I

l 4.6 Isolate LS-87-21 as follows.

Close high-side panel isolation valve Open equalizing valve Close low-side panel isolation valve Performed by N Mt/# / JL24Aik Verified by bhrdiC /3 U 4.7 Isolate prototype SOR d/p switch as follows.

Close high-side isolation valve Open equalizing valve Close low-side isolation valve Performed by .4244tt / T-M Verified by Y 5L Q /5 10'34

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Page 2 of 2 Date 3-20 R4 Sequoyah Nuclear Plant ST-INST-83-13 Data Sheet (Steps 4.4 - 4.12)

Rev. 0 4.8 Calibrate SOR d/p switch to the listed setpoint.

Note: If the as-found setpoint is within the desired tolerance of +2.0-inch WC, no setpoint adjustments should be made.

Desired . As- As-Setpoint Found Left (in. WC) (in. WC) (in. WC) IN Signature /Date 141.41 2.0 l'll.40 14L40 IE 2 Lo %Y (Reset) /33 2.0 / 3:1. 2.0 >_' L .2 Q fr,2_6 F 4.9 Valve in LS-87-21 and ensure sense lines are properly filled.

Performed by fA w / 3rff f Verified by OTfIt /. N O - P '(

4.10 Valve in prototype SOR d/p switch and ensure sense lines are properly filled.

Performed by 3V/}) wss9h--- / 3rAf fl/

Verified by b bQ3'-t- /34 s,e 4.11 Close breaker 6 on 120-V ao vital power board h I to ,. ,.,. ~

electrically return LS-87-21 to service.

Performed by # /./. J / ,Y r24-df Verified by ,1 ,

/.9-26-89 4.12 Inform SRO that LS-87-21 has been returned to service.

, Performed by +;lh / 7 .24.ff'/

JTZ:VD 7/13/83 B4194B.VD I

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Page ? of 2 Date 2/1)} W Sequoyah Nuclear Plant ST-INST-8313 . .

Data Sheet (Steps 4.4 - 4.12)

Rev. 0

4.8 Calibrate SOR d/p switch to the listed setpoint.

Note: If the as-found setpoint is within the desired tolerance of +2.0-inch WC, no setpoint adjustment.s should be made.

Desired , As- As-Setpoint Found Left (in. WC) (in. WC) (in. WC) IM Signature /Date 141.4 2.0 $9.2. I N L3 . hg4 $,./ /Qt (Reset) ' JD. */ /23.V

A r<,s /.1 dL!br 4.9 Valve in LS-87-21 and ensure sense lines are properly filled.

Performed by .e J/l2. s's.1-e /2-A/Eb Verified by l$,- /c 7' '

/ 2 AuA-v 7

4.10 Valve in prototype SOR d/p switch and ensure sense lines are properly filled. '

Performed by Mo /.c a/ M ierified by

/

hAAC/ W / d bil k /

4.11 Closebreaker6on120-Vaovitalpowerboar*AItofc*b

electrically return LS-87-21 t,o servico.

Performed by h R O e m ca /.3 *)/-?I f 7&A/t f Verified by sys!' / //A> Ef 4.12 Inform SRO that LS-87 21 has been returned to service.

Performed by _'Ibsdfft ? d / 2,/AI/f4 JTZ:VD 7

7/13/83 B4194B.VD .

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Page 2 of 2 Date /-d7-I Y Sequoyah Nuclear Plant ST-INST-83-13 Data Sheet (Steps 4.4 - 4.12)

Rev. O e

4.8 Calibrate SOR d/p switch to the listed setpoint.

Note: If the as-found setpoint is within the desired tolerance of +2.0-inch WC, no setpoint adjustments should be made.

Desired , As- As-Setpoint Found Left (in. WC) (in. WC) (in. WC) IM Signature /Date p ,

/ '

Verified by k l h fie ___, /l<2 ~b"<f 3 4.11 Close breaker 6 on 120-V ao vital power board k-I to te I""' 3 electrically return LS-87-21 t service.

Performed b [ //a/M[d Verified by ,

//> .2.Pf3 4.12 Inform SRO that LS-87-21' has/ been rettfrned to service.

Performed by c I/r. Dt-um /, ,h JTZ VD / / '

7/13/83 -
B4194D.VD .
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Page 2 of 2 Date /0 .7/-13 Sequoyah Nuclear Plant ST-INST-83-13 -
Data Sheet (Steps 4.4 - 4.12)
Rev. O s
4.8 Calibrate SOR d/p switch to the listed setpoint.
Note: If the as-found setpoint is within the desired tolerance of +2.0-inch WC, no setpoint adjustments should be made.
Desired . As- As-Setpoint Found Left (in. WC) (in. WC) (in. WC) IM Signature /Date 141.4 2.0 ]$l,5'l /Yl>59 h f.% //d Of h3 (Reset) JMY /33,57 9%1a , /m y 5 4.9 Valve in LS-87-21 and ensure sense lines are properly filled.
Performed by < k k U T1 i *
//odld3 s
f ."a .:
Verified by TD M //d -3/+ $
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4.10 Valve in prototype SOR d/p switch and ensure sense lines are properly filled.
Performed by f Es / l6 -3l 8 %
Verified by 7 . I k & ,- /s .)- V .? :
4.11 Close bre.*nas G on 1*0-V ao vital poucr'boirrt N-T to 16 D
electrically return LS-87-21 to service.
Performed by //d-31 #3 Verified by / M /'r
v j
/ /
4.12 Inform SRO that LS-87-21'has been returned to service.
Performed by CGik /JD41-LS JTZ:VD
7/13/83 B4194B.VD '
s
c. ? ;-
mam Page 2 of 2 Date /l-2 T 9.*3 Sequoyah Nuclear Plant ST-INST-83-13 Data Sheet (Steps 4.4 - 4.12)
Rev. 0 '
S 4.8 Calibrate SOR d/p switch to the listed setpoint.
Note: If the as-found setpoint la within the desired tolerance of +2.0-inch WC, no setpoint adjustments should be made.
Desired , As- As-Setpoint Found Left (in. WC) (in. WC) (in. WC) IM Signature /Date 141.4 2.0 IVl,97 141.97 )$'AdlSeh l/jZPJ (Reset) '/7 /,4t t' .4,33.F5' fpf/dJL J /gggyy 4.0 Valve in LS-87-21 and ensure sense lines are properly filled.
Performed by :Nhffrz, /ll.,'/3 Verified by c *te l
/h 5 /i 3
/
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4.10 Valve in prototype SOR d/p switch and ensure sense lines are properly filled.
Performed by k )'& / ll . L ' *-
Verified by E g a-, / #In 't 4.It Llose breaker e on leu-v 30 vit,41 powas Lo .
I a rr M*3#
l electrically return LS I to service.
Performed 'us d,'! S / /!*/Y Verified by [g/ M } //d ef*p 4.12 Inform SRO that LS-87-21' has been returned to service.
Performed by c5/. %kW /4' T ' b.
/ /
JTZ:VD 7/13/83 B4194D.VD '
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Page Date 2fA of2/#.
2, F Sequoyah Nuclear Plant ST-INST-83-13 Data Sheet (Steps 18.4 84.12)
Rev. 0 18 . 8 Calibrate SOR d/p switch to the listed setpoint.
Note: If the as-found setpoint is within the desired tolerance of +2.0-inch WC, no setpoint adjustments should be made.
Desired As- As-Setpoint Found Left (in. WC) (in. WC) (in. WC) IM Signature /Date 1851.11 1 2.0 p// /.! /// /.2. d'E_NL /. t k e 'I.e (Reset) /Js .3 .
23d. ;/ 6M. (L L ' / .js.qsi) 11 . 9 Valve in LS-87-21 and ensure sense lines are properly filled.
Performed by
/UI _ _ / f/*e'.'1 Verified by
.d' r. / fd%/.b ' *.
al 11 . 1 0 Valve in prototype SOR d/p switch and ensure sense lines ire properly filled.
Performed by f/ '
/ VS * #f 1 Verffind by / k m ._ * . . . / 9/ L/D r
14 . 1 1 Close breaker 6 on 120-V no vital power 6 rd k-I to 7 0 +/ * ' W electrically return LS-87-21 to service.
Performed by /[. D [., d i A-v Verified by P /
11.12 Inform SRO that LS-87-21 h.1s been returned to service.
Performed by
.//I.. _ / 0/b / s .i JTZ VD 7/13/83 Dil19flD.VD O
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. /d E# c d 6 4)e f C -
Page 2 of 2 Date 6- A4 -U Sequoyah Nuclear Plant ST-INST-83-13 Data Sheet (Steps 4.4 - 4.12)
Rev. 0 4.8 Calibrate SOR d/p switch to the listed setpoint.
Note: If the as-found setpoint is within the desired tolerance of +2.0-inch WC, no setpoint adjustments should be made.
Desired As- As-Setpoint Found Left (in. WC) (in. WC) (In. WC) IM Signature /Dato
. 141.4g2.O 11/A l'll Y h'$ / tb/h5 (Reset) 4,/A i M '1 W6 /
f 4.9 Valve in LS-87-21 and ensure se.tse lines are properly filled.
Performed by /I//k / $ Yi )
Verified by h /h ,f/
4.10 Valvo in prototype SOR d/p switch and ensure sense linco are properly filled.
Performed by b / #5+hf Verified by [ -t* / /Y'
/
4.11 Closebreaker6on120-Vaovitalpowerboardf-Ito Id b ' #
elcotrically return LS-87-21 to service.
Performed by ))//) /
Verified by AJ/h* /
/
4.12 Inform SRO that LS-87-21 has been returned to service.
Performed by /$V/!!fY / ikY JTZrVD 7/13/83 M 19fID.VD .
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/DCiEff/l)Cd'~ L .
.r Page1or/.22, Date t f /f9' .
Sequoyah Nuclear Plant W ST-INST 13 m Data Sheet
(, Steps 4.4 - 4.12) 5 Rev. O n
4.4 SRO informed that LS-87-21 will be removed from service during calibration of SOR d/p switch. '
l'a Performed by d a1 [
d / 4/.1/ /
y Sc. . ser l 3,0 ,
4.5 Open breaker 6 on 120-V ao vitsi power board M to electrically ;'
remove LS-87-21 from service. I old order no. A/4 N* "
Performed by t u rd , to, / ,3 J f -r*/
Vertfled by p
/
/*> Yke r-t- / t /4 //Pyi 4.6 Isolate LS-87-21 as follows.
Close high-side panel isolation valve Open aqualtzing valve Close low-side panel isolation valve Portormed by Y l kruon / .1 ' 2 ' 'XV Veritted by . f]rsujl _ ord /Jl1llf'Y a '
4.7 Isolate prototype SOR d/p switch as follows.
Close high-side isolation valve Open equalizing valve Close low-side isolation valve Performed by tru~ /'22/-S'f Verttled by i: Al w/ /4/1)llY
. 1
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Page 1 of 2 Date /- A f 81 Sequoyah Nuclear Plant ST-INST 13 Data Sheet (Steps 4.4 - 4.12)
Rev. 0 4.4 SRO informed that LS-87-21 will be removed from servloe during calibration of SOR d/p switch.
Performed by ,3 ( lieu / /' M ')V 3 g . f og
i 'J o *.
4.5 I Open breakerfrom remove LS-87-21 6 on 120-V service. Iloldao vital order no.power board [$ j/.1I I o electrically Performed by M 1da0 u . A< A l-l'N bo*
Verified by -
% / / '.1 7 >1 4.6 Isolate LS-87-21 as follows.
Close high-side panel isolation valve
Open equalizing valva close low-side panel isolation valve Performed by W//)'}m . . / /.23 'PV Verified by / lt)N w / / *.'J T J (
47 Isolate prototype SOR d/p switch as follows.
Close high-side isolation valve Open equalizing valve Close low-side isolation valve Performed by [/7'/,, i a n / / J't-n'/
Verified by / / t >10, .. / / n-a v a
'* . ' * , ~ggra# ( M C Z--
Page 1 of g, Date /1lWh'**,
i !
Sequoyah Nuclear Plant ST-INST 13 Data Sheet (Stepa 4.4 - 4.12)
Rev. 0 4.4 SRO informed that LS-87-21 will be removed from servios during calibration of SOR d/p switch Performed by s_ ( + ~/ / /4b Md'*,
)
{ ( / 1s*1*l'*,3,,
4.5 Openbreaker6on120-Vaovitalpowerboardd.-I t eatrically remove LS-87-21 from service. Ito d order no.
Performed by & /pii . F //d 4l.? $
Verifled by c .[ 4 . ,- % // air [..
4.6 Isolate LS-87-21 as follows.
Cicse t.ic.-side Mr.al is:latim valva Open equalizing valve Closelow-sidepanelisolatio/vlye Performed by C$ el A c.d. / / Al[1[S3 Verified by -Ar77A e , w //,,3 /M .78-fd f
4.7 Isolate prototype SOR d/p switch as follows.
Close high-side isolation valve Open equalizing valve Close low-side isolation valv Performed by " '- % / /4 nv *:f, Verifled by *Yt*0t Lin ( $ / / 2 0t?*tfd r -
s
, ' ', ggFcdEA)< d' E-Page 1 of 2 Date / /-294*'8 3 Sequoyah Nuclear Plant ST-INST-83 13 Data Sheet (Steps 4.4 - 4.12)
Rev. 0 4.4 SRO informed that LS-87-21 will be removed from servios during onlibration of SOR d/p switch.
Performed by (c ///,2I'Y3 g ., s *> s P 4.5 Openbreaker6on120-Vnovitalpowerboardi-;dtoeleNr'ically remove LS-87-21 from service. Hold order no. AJ/
Perforacd by $$)/1) h,a a / /J-:2 YW Verified by [Tfn ///~.2P63 4.6 Isolate LS-87-21 as follows.
Close high-side panel isolation valve Open equalizing valve Close low-side panel isolation valve Performed by l$/].,/ w sh rs*t? / J/-f f Y.1 Verified by 'd do ///78-83 4.7 Isolate prototype SOR d/p switch as follows.
Close high-side isolation valve Opon equalizing valve Close low-side isolation valve Performed by A$)l,lbe ,wnd}/ //9 b" F Verified by 'k 8-Nit ///-A.P~[b
., LEFtKENCE 7-Page 1 of 2 Date /d - 7/- $' ?
Sequoyah Nuolear Plant ST-IllST 13 Data Sheet (Steps 4.4 - 4.12) kw. 0 4.4 SRO informed that LS-87-21 will be removed from service during calibration of SOR d/p switch.
Performed by No / /a-AJ 81u ' g ,, , , 3,5 g
4.5 Open breaker 6 on 120-V no vital power board 5-I t,o e1 9 pyioally removo LS-87-21 from service. Iloid order no. A) M f(
/)/T; M.
Performed by /f5m7/-1.$
Veriflod by - / AJ - 1 ^ P .)
4.6 Isolato LS-87-21 as follows. I h
Closo high-side panel isolation valve Opun equalizing valve Close low-side panol isolation valve Performed by ITIR2 / /d -r3 /-A.7 Verified by Tbe / < '8 a k*- h*J 47 Isolate prototype SOR d/p switch as follows.
Close high-side isolation valve Open equalizing valve Closo low-sido isolation valve Performed by $/ T((A, Verified by T Q v-., -
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References My memorandus'to,you dated July 29, 1983', eseguoyah Nuo m e-l Plant Unit 2. '.Special Test - Reliability Test of Proto?
Statio.4-Ring (302) ,
D/F Switch" (L28 830722 811) .
..w,- .t i The subject spoo,ial test was performed to determine the M11 ability of a '
C4 prototype SOR model 103 d/p 'suitch. ' This test'uma initiated because of the excessive onlibration drift s'nd nonrepeatability ofi.the UNI water accusaalator O levelswitches(Bartoo'mo'd'~1[268). e The following information documents j , the test results and.prwides ' conclusions / recommendations ooooerning the i switch m 11 ability. ' j %*.;j.;*, .. .
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I i The SOR switch una installedfm tulit 2 and initially'ealibrated in August 1983 '
The test procedure required the evitch onlibration tolbe' periodically verified.
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No adjustments were to be ande if the setpoint had not drifLed by more than two M inches of water. '
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The. switch onlibration was checked monthly for a period of seven months.
c3 During this period, the switch setpoint was never adjusted and did not drif t outside thagdesired tolerance. (The acttsal calibration data is O logged in the special test package as a permanent rec.ord.) j s .
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o 50R d/p switch, it appears to be very reliable. Please note, however, that (
the Barton model 288 switches'also have indicatore, whereas the MOR switch does not. If the indication function is not necessary (as was the case l with the Ul!I water accum41stors), we recommend this switch as an moceptable r replacement. Final approval to use this switch is pending resolution of ,;
class 1E environmental qualification concerns. (The Division of Engineering .
l Design is currently working with SOR to ensure all requiromants are net.) . i
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ENCLOSURE 3 Proposed Technical Specification Change SEQUOYAH NUCLEAR PLANT Docket Nos. 50-327. -328 (TVA SQN TS 74)
Determination of No Significant Hazards Considerations for Proposed Change to UNI Level Switch Setpoint Tolerance l
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SIGNIFICANT HAZARDS CONSIDERATIONS
1. Is the probability of an occurrence or the consequences of an accident previously evaluated in the safety analysis report significantly increased?
No. The upper head injection (UNI) system is designed to supply additional inventory to the reactor vessel during the blowdown phase of a loss of coolant accident which rapidly or uncontrollably
, depressurizes the reactor coolant system (RCS) below its initiation l setpoint. In order to passively supply this water to the RCS, the i
UHI is pressurized by use of a Nitrogen (N 2 ) supply. Due to the potentially harmful effects of introduction of N2 into the RCS, the UHI is equipped with automatically isolating valves which actuate upon receipt of a low level signal which is predetermined to deliver adequate RCS coolant makeup but to preclude introduction of N2 into the reactor vessel. The performance of the surveillance to test the actuation of UNI isolation valve closure is intended and analyzed to ensure the performance of the intended function of these
' valves. The reduction of the level setpoint tolerances as currently present in Technical Specification is a trade-off to relax an unrealistically short tolerance for UHI isolation valve closure.
The Westinghouse analysis (attached) concludes that the changes to
' actuation tolerance and hydraulic accumulator pressure will result in no change to the water delivered by the UHI to the reactor vessel (i.e., within prescribed tolerances). Therefore, the UNI system will continue to satisfactorally provida its intended dec1gn j function and no significant changes will occur in the probability or consequences of previously analyzed accident.
2. Is the possibility for an accident of a new or different type than evaluated previously in the safety analysis report created?
No. The change to the actuation tolerance to the UNI isolation valves presents no modification to the plant hardware or testing methods. As such the setpoint change only potentially effects the l analysis for accidents previously considered feasible. Since the j Westinghouse analysis concludes that the system will continue to operate as presently expected for these accidents the change in actuation setpoint causes no new or different accident possibilities.
3. Is the margin of safety significantly reduced?
No. The margin of safety provided by the UHI system is based upon the expedient delivery of the designed volume of water and the automatic isolation of the system prior to the introduction of Nitrogen to the system. The attached Westinghouse analysis concludes that the potential changes to the delivered volume of water are sufficiently low as to be within designed tolerances and present no reduction to the margin of safety.
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ML20214J981

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