ML20134B233

Rev 4 to CVCS Inservice Valve Test

ML20134B233
Person / Time
Site:	Wolf Creek
Issue date:	11/09/1994
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20134B204	List: ML20134B201 ML20134B211 ML20134B215 ML20134B220 ML20134B225 ML20134B233 ML20134B240
References
STS-BG-206, NUDOCS 9701290367
Download: ML20134B233 (12)

Text

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i h K02-007B AITACIIMENIJ SURVEll.f ANCE TEST ROlmNG SHFET l,

(STRS)

STS/STN NO: STS DG-206 REY. 4 " TEST FREQUENCY:

1 (CIRCLE ONE) **DUE DATE/IIME: pg 9 of 14 TITLE: CVCS INSERVICE VALVE TEST " LATE DATE/ RIME: MA 94-080

• • T/S REQUIRED MODEt

" PROCEDURE REQUIRED MODE:

4 INITIATING DOCUMENT #(s) 1 "RESPONSIBLb UROUP: "SUPloRT OROUP(s):

PRF-TEST COMMENTS a

" OITIONAL INFORM ATION NOT REQUIRED TO RE FILLED IN

'. I jEsT-4TER 1).

'ORMbMS SIG/DATE

'lP / y hi/;4 Procedure verified to be the correct revision with all temporary changes W A 1 N itAtOC)

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~/ 4.% f y attached__ and $ incorpprated.

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/ (CIRCLE) / / i l / (AS APPLICABLE) / /

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3)

• TEST DEFICIENCY

[,/

j DESCRIPTION.

j \ /

4) *T/S FAILURE YES / NO /

(CIRCLE ONE) S/S SIGNATURE 4

IF NO-JUSTIFICATION:

\ DATE

\

j

\

5) ACTION I AKEN \

LOL# T WRff

'SECllONS 3,4,AND $ ARE COMPLETED TEST SUSPENDED /

IF A TT3T DEFICIENCY OCCURS, OTHERWISE MARK N/A YES / NO [ / /

(CIRCLE ONE) SS SIGNATURE / UA'l E

^

6) POST 1 ESI' REvibWS TOTAL M AN HOURS: l SIG/ DATE / TIME TEST PERFORMER M rO,_ / Jolev/qi/ / /3o9

SS/SO REVIEW /NOTIF f/2 fpO'd'- / IO/WI9V / I '3 E2 GROUPSUP. hMfmw / /o-2 7.& /

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,,TII 34dk / F 2fe< A COMPLETE PARIIAL D. s /

SC/SURV. TECHNICIAN 7 /W / //-9 -f f (GROUP SUP. CIIECK ONE) l 7) ADDillONAL COMMEN I S:

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ADM 01300 Rev, h Page 26 of 33 9701290367 970122 PDR ADOCK 05000482 G PDR _ r'r" -

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roi o r ssc-oo4-o. a v or rag 1 of 3 ON TIIE SPOT CHANGE (OTSC) ~

OTSC Nunder- 8Y-d$O/

Document Number- ST.S_BG-706 Current Revision Number: 4 7acument Title. MS INSERVICE VALVE TEST Originator: Larry R. Veeder 1/M / 9 <f Prmt Name Daw Reason For Change:(Explam)

Delete prerequiste condnion to stop all RCPs. Seal nyection is maintained throughout this test as well as CCW to the RCP thermal barrier. No need exists to secure the RCPs O Continued on attached OTSC SCREENING (A YES answer to any ofthe following questions indicates an GTSC can runt be perprmed.) l

1. Is this a change to the intent of the procedure as defined in the purpose or scope? O YES @ NO l

2. Will this change decrease or modify a hold point requirement or Quality inspection point? O YES @ NO I

3. Will the change result in a reduction of personnel or equipment safety? O YES N NO 4 Will the chance involve a USQD7 0 YES @NO ,

@ A marked up copy of the proposed change is attached.

@ Regulatory Screenings and/or Evaluations (form KGF-115) has been completed and attached as required by KGP-1220.

SCREENING AND EVALUATING CllANGES. TESTS. AND EXPERIMENTS.

APPROVA1,l'OR IMME:DIATE t:SE l

Approved By: / / l CallSuperintendent (for ACPs only) Date Approved By: -

M Wk"c! /4 /2//9!,

VCNOCSWjfMer r PrmtName Date '

s

\pproved By: N De5 N *3 t k

<l 10 /,M/,1f Cogniz Supernsor* Print Name Date

• For Operations Departmen r - dures, must hold a Senior Reador Operator license per TS 6 8.3.

The remainder of tidsjdrm shall he completed within 14 days as required by Technical Specification 6.8.3. _ _ _ _

QUALIFIED REVIEW Cross-Disciplinary Review Required By: O NONE REQUIRED D Quality Assurance O Quality Control O Surveillance Coordinator O Other (Npecify)

All cross-disciplicary reviews have been completed, reviewer comments have been resolved.and the recommended disposition of this , j O'ISC has been identified in the FINAL APPROVAL section of this form.

/ / j Qualified Reviewer Prmt Name Date '

FINAL APPROVAL Approved: O Disapproved, cancel. remove from OTSC file, and initiate PIR Maintain in active OTSC file until incorporated into future revision. Incorporated by DRR number; or OTSC uumber:

O Maintain in active OTSC file until specified date / /

This section for A dmimstrative Control Procedures Only)

O . Approved O Disapproved PSRC Meeting No: / /_

PSRC Chairmain (Initials) Date Vice-President Plant Operations Date

~/ /

Responsible Manager (For all GTSC except A CP 's) Date

--. - - , - -s,,,,,,,..

._ . . .- - - -.- - --. - -..-. _ .-~ - .- -- - - . - - . - -

roRM KGF-115 SHEET 1 OF 3 REV. 4/04 gg y i

No.59 SCREENING FOR LICENSING BASIS CHANGES Page 1 of 3 i Document Number. STS BG-206 Revision: 4 Description of Proposed Change: )

Delete requirement to secure RCPs prior to running this surveillance....RCP. seal flow is .

maintained throughout the test as is CCW flow, in addition, RCS temperature remains less than 200 F. Stopping RCPs at this time could cause surge line temperature swings and potentially " cock" the RCP seals. Plant stabil;ty is enhanced by leaving the RCPs running l during the performance of this test.

Screening Questions: (Notz All questions must be answered except as provided in questions 1 and 2)

1. Has this change been previously 0 YES No further screening is required approved for WCNOC by the NRC or Document #

covered by another Unreviewed Safety Justify in "Clarificatien" Section Question Determination (KGF-117) if referencing a previously performed USOD, contact Ucensing to update USOD log. .

5 NO l Note: If referencing another Unreviewed Safety Question Determination, ensure that it has been l approved by the PSRC prior to implementing the change. I

2. Would the change result in a revision to O YES Change may NOT be implemented prior  ;

1 the Operating License including to approvalof a License Amendment Appendices? (this includes the (Note: No further screening is required Technical Specifications) since NRC approval must be obtained prior to implementing the change.)

@ NO

3. Wou!d the change involve one or more of the following:

a. a change to plaat structures, systems, components or equipment as outlined, summarized or described in the USAR such that accomplishment of the change would make information in the USAR no longer true or accurate, or would violate a requirement stated in the USAR?

b. a change to procedures or administrative controls as outlined, summarized, or described in the USAR such that accomplishment of the change would make information-in the USAR no longer true or accurate, or would violate a requirement stated in the USAR?

c. tests or experiments NOT described in the USAR?

A formal Unreviewed safety Question O YES Determination using KGF-117 must be completed prior to implementing the change.

9 NO Identify USAR sections considered in answering these questions.

ections Reviewed

5.4.1, 9.3.4 l NOTE: If yes, evaluate need for a USAR Change Request in accordance with KGP-1225.

(REF. KGP-1220)

< FORM KGF-115, SHEET 2 OF 3, REV. 04/94 g ggf I , Document Nurnber:

' SCREENING FOR LICENSING BASIS CHANGES STS BG-206 4 (continued) No.59 Page 2 of 3

4. Does the proposed change involve one or more of the following:

a. a change in the rate, volume, concentration, composition or flow path of nonradiological liquid or gaseous effluents?

b. a change in the volume, concentration or composition of nonradiological solid waste?

c. an increase in the thermal power above the current licensed level and/or an alteration in the magnitudes of thermally affected effluents?

d. a physical change in an crea cutside of the owner controlled area boundary which was not disturbed by previous construction?

O Yes An environmentalirnpact determination must be @ No completed by the Supv. Environmental Management using KGF-116 prior to implementing the change.

5. Could the change potentially result in a revision to:

a. the Security Plan,

b. the Safeguards Contingency Plan, or

c. the Guard Training and Qualification Plan?

O Yes An evaluation must be completed in accordance @ No with 10CFR50.54(p) prior to implementing the change. This evaluation must be performed by the Manager Security or Manager NPE-Wichita using KGF-116.

6. Could the change potentially result in a O Yes An evaluation must be completed in revision to the Operating Quality accordance with 10CFR50.54(A)(3) by Assurance Program commitment the Manager QA using KGF-116 pnor described in Chapter 17 of the USAR7 to implementing the change.

@ No

7. Could the change potentially result in a O Yes An evaluation must be completed in revision to the Fire Protection Program accordance with license NPF-42 paragraph described in USAR Section 9.5 and 2.c(5) by the Manager Operations or Appendices? Manager System Engineering using KGF-116 prior to implementing the change.

@ No (REF. KGP-1220)

j . . . _ _ . . .

i -

1 FORM KGF-115, SHEET 3 OF 3, REV.04/94 07sc, Qz/.My l' [ , Document Number:

SCREENING FOR LICENSING BASIS CHANGES STS BG-206 4

?~ ' (continued) No. 59 l v l Page 3 of 3 i 8. Could the change potentially result in a revision to the Radiological Emergency Response Plan?

! O Yes An evaluation must be completed in accordance 8 No l with 10CFR50.54(q) by the Manager Technical

} Services using KGF-116 prior to implementing the j change.  ;

9. Could the change potentially result in a revision to the Licensed Operator Roqualification Program as described in USAR Section 13.2.1.27

! O Yes An evaluation must be completed in accordance @ No i with 10CFR50.54(i-1) by the Manager Training using

KGF-116 pnot to implementing the change.

I i 10a. Could the change potentially result in a change to an NRC commitment?

I O Yes An evaluation must be completed by the Manager 8 No

Regulatory Services using Form KGF-116 prior to implementing the cfiange.

l j 'Ob. Could the Change potentially result in changing or nullifying an INPO commitment?

i O Yes The basis for accepting the change will be provided E No '

below in the clarification section by the responsible i manager. Coordinate with the Manager Plant Support to provide a basis for accepting the change to an INPO commitment.

f Clarification:

i i

Disposition: Further Action Needed (Mark answer and explain below): - -

l All Questions answered no. O Yes

}

4 i @ No Prepared by: / _ __ Date: /v/c y/9 c/

Approved by

A/

)# / Date: 1 o /J.y / S y TEF, KGP-1220) 4

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$ WOLF CREEK NUCLEAR OPERATING CORPORATION 4 :- 1 l

l WOLF CREEK GENERATING STATION l /.

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1 -. E i CVCS INSERVICE VALVE TEST i.

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! " STS BG-206 E 4

Revision 4 h.

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COGICIAlPW GROUP $UPERVISOR DA A

PSRC SUBCO MITTEE CHAIRMAN APPROVAL DA$1 j l

1 OkA PSRC APPROVAL RECOMMENDATION (Revision 0 only) DATE .

rJkA VICE PRESIDENT PLANT OPERATIONS APPROVAL (As required per 6.9.7.1) t tdkA QUALITT EllGINEERING (As required per 6.13.3) DATE  ;-

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1.0 PURPOSE' fag <2 43 1.1 The purpose of this surveillance procedure is to demonstrate Chemical Volume Control System (CVCS) check valve *BG-V591, Charging To Seal Inj Filters Check Viv, operability. -

1.2 This surveillance will perform check valve close testing as required by ASME/ ANSI OMa-1988, Part 10.

l 1.3 This procedure satisfies CVCS check valve operability.

surveillance requirements of Technical ,

Specification 4.0.5.

l l

2.0 DISCUSSION 2.1 Scope l 2.1.1 Check valve operability is verified by observing a maximum allowable pressure increase across valve.

2.2 Precautions. Limitations And Acceptance Criteria 2.2.1 Precautions ,

2.2.1.1 None 2.2.2 _ Limitations 2.2.2.1 Report any irregularities or component malfunctions to SS/SO immediately. __

2.2.2.2 CVCS check valve testing, per this surveillance, shall be performed in Mode 5 or Mode 6.

2.2.2.3 n ::ter Cec 1:nt rumpe (RCP) ch:11 not be ir cer7EEe

- eher tacti.;; 2C yS91.

OcarnrD , ,

2.2.2.4 Centrifugal Charging Pump PDG05A (CCP "A") or PBGOSB (CCP "B") shall be in service when testing BG-V591. IF PDP is in service, THEN shif t from PDP to CCP in accordance with SYS BG-201, " Shifting Between Positive Displacement And Centrifugal Charging Pumps".

2.2.2.5 Boron Injection shall be available and operable to provide a flowpath through Boron Injection Tank (BIT) as required by Technical Specification 3.1.2.3.

STS BG-206 Rev. 4 Page 1 of 6'

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t i Ei Accentamos critaria

• 2.2.3 1 y

EEEs Failuze to meet Acceptance Criteria given belou  :

any constitute a failure to comply with e 9echnical Specifications. C b

2.2.3.1 Each check valve disk shall .be veriTied to travel to f.

( respective safety function positioh.. Pfassure shall t.

! not increase >50 psig to verify valve closure. .IZ h

! required change of valve disk position is not obtained, 3lEEE valve shall be declared inoperable and corrective

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l

' action shall be initiated using ADM 01-057, " Work ,

i Request" and ADM 02-024, "To g eal Specification l Operability". ,-

. .2.3 Definitions

2.3.1 None i i -

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REFERENCES '

< 3.0 i

3.1 ADM 01-300, " Surveillance Testing ^- i j 3.2 ADM 05-200, "ASME Code Testing Of Pumps And Valves"

) 3.3 ADM 01-057, " Work Request" '

2 l 3.4 ADM 02-024, " Technical Specification Operability" i

3.5 PIR TS 92-0491

?

3.6 PIR TS 92-0485 l ,

3.7 PDR TS 91-0238 , , _

3.B SYS BG-201, "ShTfEkng Between Positive Displacement And [

Centrifugal Charging Pumps" 3.9 Generic Letter No. 89-04, " Guidance On Developing Acceptable Inservice Testing Programs" 3.10 WCOP-02, Inservice Testing Program For Pumps And valves * ...

3.11 ASME/ ANSI OMa-1988, Part 10, "Inservicg Testing Of valves In Light Water Reactor Power Plants" 4.0 TEST EQUIPMENT 4.1 None ---

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STS BG-206 Rev. 4 Page 2 of 6

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07sc W-asot 5.0 PRERROUTSITES Py 34 8 l JNTT/DATE 5.1 Consult with SS/SO and review following required prerequisites prior to I perfoima oo u eillance l

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PERTO R

/SS/[O) l 5.2 CVCS is filled and vented. ]

5.3 Plant is in Mode 5 or Mode 6.

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5.' PEE 0l?., TEE 01B, PBBO4C--OP PEE 01D, Ec cter #O cmm i . - n.-~ reces ogg ., d t-- i retiem I I l

1 5.5 Boron Injection is available and operable -

to provide a flowpath through DIT (Refer to Technical Specification 3.1.2.3).

5.6 Required Precautions, Limitations and Acceptance Criteria have been reviewed.

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6.O PROCEDIiRE ,

6.1 BG-V591. Reactor Coolant Pump Seal Wateg l Supply Check Valve. Exercise Test 6.1.1 Place in service or verify CO? "A" or CCP "B" is in service. .IT. PDP is in service, M shift from PDP to CCP in accordance with SYS BG-201, " Shifting Between Porsitive Displacement And . - -

Centrifugal Charging Pumps". Indicate below CCP placed in service: '

CCP "A" in service:

Yes no CCP "B" in service:

Yes No -

6.1.2 Shift RCP Seal Injection from normal supply to emergency supply by opening BG HV-8357A or BG HV-8357B, CCP Disch To Seal Water Injection Filters Iso Valves, corresponding j to CCP in service. Circle below valve opened: '

Q. . . - - - - ~ ~ - -.HV-0357A-opened]

BG IIV-8357B - opened STS BP,-206 Rev. 4 Page 3 of 6 )

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INIT/nATE C

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6.1.3 Unlock and close BG-8483B, CCP X/B d f:

Dsch Hdr PCV-121\ Outlet Iso viv. L.Y.J s l'

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6.1.4 Unlock and close BG-8388, PDP Dsch Man i

. Iso Viv. E p.-

6.1.5 At panel RL001 close or verify close ._

P.. l BG HV-8105, Charging Pumps To Regen HX/CIV, E, l

by observing green light is illuminated * .

for handswitch BG HIS-6105. (

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! 6.1.6 At panel RL001 close or verify close p BG HV-8106, Charging Pumps to Regen EX Iso ,,

4 Viv, by observing green light is illuminated q for handswitch BG HIS-8106. -

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6.1.7 Verify an operable Boron Injection flowpath f

through Boron Injoction Tank (BIT), as '

(

required by Technical Specification 3.1.2.3. .

e I 6.1.8 Record below pressure as ind g ed on /mbdf j computer point BGP0120:

l BGP0120 M, psig 4

l 6.1.9 After 5 minutes record final pressure below as indicated on computer point j BGP0120: /// be44<

t BGP0120 psig .

[

6.1.10 Calculate pressure increase below: IF /tdd's '

t-n I BG-VS91 CLOSURE TEST ACCEPTANCE CRITERIA 1

PRESS PRESS ACTUAL NAX ALLOWABLE 6.1.9 6.1.8 PRESS N '5~O - /3 - 7 5 50 peig 6.1.11 .IF, pressure calculated in Step 6.1.10 was 5 50 psig, THER check valve closure .

test for BG-V591 was. acceptable. (,II, pressure increase is greater than 50

• psig, 2333 follow requirements of .

) j f 2.2.3.1 and this step is N/A). - e /iNW% ,

STS BG-206 '

Rev. 4 s Page 4 of 6 o

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1 7.0 RESTORATIGE INIT/DaTE {

l 7.1 Lock open BG-8483B M/ rbtM# I' 9%M I.

' 2nd 7 7.2 Lock open BG-8388 @>/Ioldy y

/elzt/9/ E

/ 2nd

a m 7.3 Shift RCP Seal. Injection froe-emergency A supply to normal supply by closing i BG HV-8357A or HV-8357B corresponding g to CCP in service. Circle below valve {

l closed: krf['r / elr4SO '

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, 2nd ,

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( BG HV-8357A - closed .

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i BG HV-8357B - closed 7.4 At panel RL001 open BG HV-8105 using handswitch BG HIS-8105. '

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N //dttle ' .

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7.5 At panel RL001 open BG HV-8106 using .

, d /f4/24/14 handswitch BG HIS-8106. A  ;

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2nd 7.6 Verify,affected systems and/or components have been aligned and/or returned to service as directed by SS/SO. //t/u/#

i STS BG-206 i Rev. 4 Page 5 of 6

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