ML19332C428
| ML19332C428 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/15/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-89734, NUDOCS 8911280113 | |
| Download: ML19332C428 (75) | |
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EEEEIEE! Log # TXX-89734 ;
- . .:: File # 10010 t r = 905.4-1UELECTRIC November 15, 1989
Walism J. Cahill, Jr.
Executive Vke President
~ U. S -. Nuclear Regulatory Commission ,
-Attn: Document Control Desk
' Washington, D. C. 20555- -
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50-445 (
UNIT 1. INSERVICE-TESTING PROGRAM PLAN, INTERIM f CHANGE REQUEST N05. IST-R3-001 AND IST-R3-002 REF: TU Electric letter, TXX-89565, from W. J. Cahill, Jr., to USNRC, dated August 21, 1989.
Gentlemen:
Enclosed please find two (2) copies of Interim Change Request (ICR)
Nos. IST-R3-001 and IST-R3-002 to the CPSES Unit 1. Inservice Testing (IST)- -
Program Plan, Revision 3. Copies of the ICR's=are also being sent to the Region.IV. office, the NRC Resident Inspector, the Texas Department-of Licensing and Regulation, and the Hartford Steam Boiler.
ICR Nos.=IST-R3-001 and IST-R3-002 are accompanied with the revised pages to be -inserted into the controlled copies of the CPSES Unit 1. IST Program Plan, Revision 3. . Included in these ICR's are changes involving valve additions and .:
valve numbering. In addition, the ICR's are added into-Appendix D of the IST
Program Plan, Revision 3.
During the course of the IST program review, the NRC noted inconsistencies in f_ the CPSES Unit 1, IST Program Plan,-Revision 3. The TU Electric responses to these inconsistencies, with applicable comments / justifications to support conclusions, are attached.
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M Box M2 Glen Rw,hm NM2
, '8911200113 89'1115
'> : PDR . ADOCK 05000445
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'TXX-89734 Page 2 of 2 Should any questions arise regarding the responses or these ICR's,-please p contact Norman Hood,-at (214) 897-5889.
Sincerely, William J. C ill, Jr. ,
DAR/dar.
Attachment .
Enclosures c - Mr. R. D. Martin, Region IV Resident Inspectors,=CPSES.(3)
Texas Department of Licensing and Regulation Boiler. Division E. O. Thompson State Office Building P 0. Box 12157 Capitol Station Austin, Texas 78701 Attn. George Bynog Hartford Steam Boiler 15415 Katy Freeway.
Houston, Texas ~ 77094 Attn. Tom Barbara L
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Attachment to TXX-89734 Page 1 of 4 REQUEST FOR ADDITIONAL INFORMATION NRC IHCONSISTENCIES, IDENTIFIED DURING THE REVIEW OF THE IST PROGRAM Inconsistencies in the licensee's programs noted during the course-of the IST program _ review:
NRC IST Program Inconsistency No. 1: .
In relief request No. P-11, the licensee stated that pressure a7d temperature instrumentation for the safeguard building sump pumps is not installed, that vibration measurement is impractical because of the pump mounting configuration, and that flooding and draining the sumps every three months for testing would create a hardship, The licensee has proposed performing a functional test once every two years during which only the pump flowrate will be measured. The licensee's basis for not performing vibration measurements does not provide the detail necessary to evaluate whether this Code requirement is indeed impractical. Further, the proposed testing is not a reasonable alternative-to the Code requirements since measurement of flow alone would not provide a reasonable assurance of operational. readiness for these pumps, Additional details relative to pump mounting configuration is needed to justify the impracticality of vibration testing. Also, the licensee'should address the applicability of installing pressure instrumentation to assure the
-operational readiness in accordance with 10CFR50.55a.
TV_ Electric Response:
Relief Request Number P-11, has been revised to reflect the testing program for these pumps to be in accordance with code requirements, Vibration, flow and pressure are to be measured during the inservice test to evaluate the pumps condition.
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Attachment to TXX-89734 Page 2 of 4 NRC IST-Program Inconsistency No. 2:
During a working meeting between CPSES NRC, and INEL on July 19 and 20, 1989, Item E-3 was identified as an open item involving the auxiliary feedwater isolation check valve testing. The licensee was told they .
i should determine the maximum back leakage through those check valves that the auxiliary feedwater system could tolerate and this leakage limit should be incorporated into the testing of the valves. The licensee has responded as follows:
-It is the owner's responsibility to define the ASME Section XI valve category for each valve to be tested. Check valves for which seat ,
leakage is not limited to a specific maximur amount by Technical Specifications or the FSAR are categorized as "C" only in the CPSES IST plan. Verification of closure will be positive means.
In the CPSES' reply to NRC IE Bulletin 85-01 dated May 17, 1988, the licensee committed to monitoring the auxiliary feedwater pump discharge temperature by touch to determine if the temperature is at or near ambient conditions each shift. The licensee feels that this monitoring combined with quarterly [ cold shutdown] category C closure testing of the auxiliary feedwater isolation check valves will provide adequate assurance that this system's operability will not be jeopardized by back leakage, It should be noted, however, that the auxiliary feedwatcr pumps are located a
. considerable distance from the isolation check valves and that monitoring the temperature by touch near the auxiliary feedwater cump may not provide t an adequate indication of individual check valve back leakage. Additional '
information is needed to demonstrate that the proposed testing for these check valves is adequate to insure that the valves are capable of performing their safety function in the closed position.
TV Electric Response:
A. To clarify the proposed Auxiliary Feedwater Isolation Check Valves Testing.
Closure testing (as well as forward flow testing) is performed at cold shutdowns: not quarterly as the above NRC question suggests.
Cold shutdown testing is reasonable, as indicated by a review of the flow diagram configuration.
Temperature monitoring performed three (3) times per day on the AFW pumps discharge piping is a reasonable method of detecting ercessive feedwater back leakage. Regardless of the distance from the feedwater header back to the pumps; if saturation conditions do not exist in the piping and pump casings then the pumps are not inoperable due to feedwater back leakage (i .e. steam binding) and the check valves are sufficiently closed.
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1 Attachment to TXX-89734 Page 3 of 4 TV Electric Response (continued):
B. To expand on the AFW Isolation Check Valves cold shutdown testing.
Forward flow testing is accomplished by flowing through the valves and simulating design flowrates. Therefore .this testing verifies check valve operability in the open direction on the " running pump" ;
headers, and further verifies check valve operability in the closed direction on the "non-running pump" headers as evidenced by the net
- flow to the steam generator criteria being met.
Additional closure testing is performed on each check valve
-individually by isolating the line which contains the valve and impressing a delta pressure across the valve in the closed. direction using an external pressure source (usually demineralized water).
Check. valve back leakage is observed by opening an upstream (of the l check valve) test connection and/or pressure decay on the supplying system.-
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Attachment to TXX-89734 Page.4 of 4 i
NRC IST Program Inconsistency No. 3:
The check valves identified in valve relief requests Nos. 16.6 and 16.7 were discussed during the July 19 and 20, 1989, working meeting (Item P-2 of the meeting minutes). The response for this item indicated that these valves would either be identified as non-safety-related or they would'be removed from the IST program. However, the licensee subsequently included these valves in Revision 3 of the IST program as Category C valves that perform a safety function in the closed position.
Given that these check valves are safety related, relief requests Nos.16.6 and 16.7 do not provide an adequate basis for not verifying -
valve reverse flow closure during cold shutdowns by leak testing or other positive means as provided for in Section XI Paragraph IWV-3522. The licensee stated that testing during cold shutdown would require containment entry, plant manipulation, and test equipment setup.
These activities are part of the normal testing process and are not seen as being impractical or as constituting on excessive burden to the licensee.
Generic Letter 89-04 states that valve disassembly can be used as a i positive means of verifying closure capability of check valves, if this verification cannot be performed by monitoring system parameters such as pressure or reverse. flow. Also, this approach may be performed during reactor refueling outages. However, the licensee has not demonstrated that~it is impractical or burdensome to test these valves by some positive means during cold shutdowns and that the valves can only be tested by disassembly and' inspection. Additional input is needed to resolve this issue.-
TU Electric Response:
Relief Requests Numbers 16.6 and 16.7, have been revised to indicate a cold shutdown test frequency of the subject check valves.
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Page 4 of 4 3 l
NRC IST Program Inconsistency No. 3: I The check valves identified in valve relief requests Nos. 16.6 and 16.7 were discussed during the July 19 and 20. 1989.. working meeting (Item P 2, ,
of the meeting minutes). The response for this item indicated that these '
valves would either be identified as non-safety related or they would be removed from the IST program. However, the licensee subsequently included
.these valves in Revision 3 of the IST program as Category C valves-that perform a' safety function'in the closed position.
Given that these check valves are. safety related,-relief requests Nos. 16.6 and 16.7 do not provide an adequate basis for not verifying valve reverse flow closure during cold shutdowns by leak testing or.other positive means as provided for in Section XI, Paragraph IWV-3522. The licensee stated that testing during cold shutdown would require containment entry, plant manipulation, and test equipment setup. :These activities are part of the normal testing process and are not seen as being impractical or as constituting an excessive burden to the' licensee.
Generic Letter 89-04 states that valve disassembly can be used as a ,
positive means of verifying closure capability of check valves, if this verification cannot be performed by monitoring system parameters such as
. pressure or reverse flow. Also, this approach may be performed during reactor refueling outages. However, the licensee has not demonstrated ;
that it is impractical or burdensome to test these valves by some positive i means during' cold shutdowns and that the valves can only be tested by disassembly and inspection. Additional input is needed to resolve this issue.
TV Electric Response:
Relief Requests Numbers 16.6 and 16.7. have been revised to indicate a cold shutdown test frequency of the subject check valves.
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. INTERIM CHANGE REQUEST G IST Plan Revision 3 ICR No. IST-R3-001 1}
Reference:
Page. See Below l
, Table See Below Relief Request, and/or Component: lAF-009, 1DD-064, IDD-066, IPV-4552, IPV-4553, .
IPS-193 IPS-194, IPS-195, IPS-196.
Reason for Change:
- 1) Table of Contents: Required to be updated per this ICR.
- 2) IPV-4552, 1PV-4553: These control valves were not included in the " Notes" Section.
- 3) 1AF-009: This valve is installed in the fill path for the Condensate Storage
- Tank and is required to prevent the. tank from draining.
t -4) 1DD-064, IDD-066: These valves are installed in the fill path for the Reactor Make-up Water Storage Tank and are required to prevent the tank from draining.
1
- 5) IPS-193, IPS-194, IPS-195 IPS-196: These valve numbers have been changed to
- i. IPS-500, IPS-503, IPS-501 and IPS-502 respectively.
- 6) Appendix D: Required to be updated per this ICR.
I A Proposed Revision:
J- Remove and discard the Table of Contents; " Notes" page 1; Table 4 pages 3, 4, and 5; Table 5 page 5;. Table 7 page 1; Table 9 page 3; and Relief Request V-5.
- 1) Insert the attached, revised Table of Contents.
! 2) Insert the attached, revised " Notes" section and Tabic 5 page 5 which adds IPV-4552 and IPV-4553 to the IST Program. I
- 3) Insert the attached, revised Tabic 4 pages 3, 4 and 5 which adds lAF-009 to l the IST Program.
- 4) Insert the attached, revised Table 7 page I which adde 1DD-064 and IDD-066.to l the IST Program. Insert the attached, revised Relief Request V-5.
- 5) Insert the attached, revised Table 9 page 3 which revises the valve numbers as described above.
- 6) Add this ICR to Appendix D.
E5coce ldArv W /A$b rpe/Mes g/gm Initiatof ' Department ' phte Approved: l Yes l[l No 6 6"M4b 'ifsC[8 7 4 CPE f E Section XI Coordinator Date' Reason for Disapproval:
O ECE 2.26-02 Rev. 1
(,) Date: 11/9/87
.Page 7.2 - 1 of 1
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-- EBUIS8sB 8 ICR Not IST-R3-001~
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-IST-R3-001 Table of Contents Remove page numbers from Appendix D.
09/15/89 Section III, " Notes" Add valves IPV-4552 and 1PV-4553 ,
to the CCW System note.
Page 1
.Section III Table 4 Add valve 1AF-009.
Pages 3, 4 and 5 Section III, Table 5, . Add valves IPV-4552 and 1PV-4553.
Page 5 Section~III, Table 7 Add valves 1DD-064 and IDD-066.- -
Page 1 Section III Table 9, Correct. revised valve numbers.
Page 3 ,
Appendix A. Relief Add valves 1DD-064 and IDD-066.
Request V-5 Appendix D Add ICR Index and ICR IST-R3-001.
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ICR No: IST-R3-001 :
1
- .s A k TABLE OF CQFTTJITS FAGE po.
SECTION IjEd I GElfERAL R8QUIRDellTS 3
1.1 M A R SE................................................................
Isf M ap Ft M T........................................................ 3 1.3 1.8 AFFLICABLE CCDE DATES 415 REQUIRBERTS . . . . . . . . . . . . . . . . . , , . . . . . . . . . . . . 3 1.4 MBfPR0BAM......................................................5 VALVE PRORAM .............. ............. ................ ... ..
.. .3 1.5
........ ...... .... .. .8 +
1.6 RELIEF REQUESTS.............................
1.7 BW " UEED FW VALVE TEST PROEAM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 II Plat TESTIIIG PhomAM fabis 0 -
I!! VALVE TESTIS 0 PaomAM Table 1 Station Service Water Table 2 Steen Generater Foodweter Table a Main steen Reboet and steam Dup Table 4 Aus111ery Feedweter-Table 5 Campenent Cooling Water Table 8 Reestor Coolant System Table 7 ' Dominere11eed and Reacter Makeup Water Table 8 Vente and Draine - Contalsment Building Table 9 Frecess Sempling Table 10 Compressed Air '
Table 11 Liquid Weste Processins and RC Drain Tank subsystem l Table 12- Ventilatten Chilled Water Table 13 Centelement Spray Table 14 Reeldual Seat Removal Table 15- Seroty Injection Table 16 Cbesical and Volume Control Table 17 Safety Chilled Water l
Table 14 Centeinment Ventiletten Table is spent Fuel Feel Coeltog and Cloenup Table 20 Fire Protection - Containment Building Table 21 Emergency Diesel Generator
..... ..... .. . ........ . .. .67 Fases AFFEIIDIX A RELIEF REQUESTS. .... ....
.. 6 Pages AFFEllDIX 3 VALVES TESTED AT COLD 85UTDOWIl3 AllD REFUELIIIG OUTAGES.
FLOW DIAGRAM (P&ID) REFEREIICE*, . . . . .. - * ' I'8" AFFEllDIX C 1
1 AFFEllDIX D INDEX TO IllTERIM CHA180E REQUESTS I
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[ CpBBS INSERVICE ftSTINS 20 mum PLAN ,
- ,, RevisI0s 3 ICR No: IST-R3-001
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t This section of the Cemenche took steen riectric station 1sf tien conteine explanettons or I clari!!catione for the testing that is performed on some componente contained in the volve tables.
Manually operated valves are not subject to caercise testing by the IST Flan. These velves are either routinely operated or are sub,tect to normal preventive maintenance prostame, '
Aus111ery Feedwater B M.es Accumuletor check valves for auxiliary foodwater velves 1 FV 2453A/S,1 FV 2454A/5,1 EV 2450, 15V 2460, P5V 2441, and 1 NY 2482 beve been listed in the 1st plan and will be tooted as e single unit. Thie to appropriate for the design function of these valves. A pressure decay test will be performed en the occumulator units, with the upstream test connection for the accumulatore vented to stanophore. Tble test method will meet the intent of IW-3430, to demonstrate the seet leak tishtness of Category A velves. ;
Qtg gal and volume Centrol Sveten 1
Check valves 1CS 4364 A,5,C and D ase normally open and remain open durins poet accident conditione. They are pressurised in escoes of contoimeent pressure from en ESF source which meets einslo failure criteria. Closure le not relied en for esotainment teolation.
Commonent Coolina 68eter Sveten i
Valves XFV 3543, IFV 3584, XFV 3545, XFV 3S86, FCV 511sA, FCV-Blist 1FV 4552 and 1FV 4553 control the flew of component coolins water to the Control Poem A/C U.P.S. A/C and Nuclear Chiller ,
condensere to maintain a minieman sondensing pressure. T, wee velves are asempted from inservice testing in accordance with IW-1200 ao control valves. FCV-5118A, FCV 511st, IFV-4552 and
'1FV-4553 are required to fail open.
Containment Ventilatico Svetem Sydrogen purse system valves 15V SS40,18V 3541,18V-S$42 and 15V SS43 are velves in a non essential bookup system to the Nydrogen Reseabiners. The Sydrogen Recombiners are the oefety )
related componente required to remove hydrogen durins poet accident scenarios. These velves are locked closed in modes 1, 2, 3 and 4 i Main Steam Reheat and Steam Dumma Sveten Manual valves 1EV*23338,15Y-23349,15V 233SS,1EV-23368, M 364,1MS-387, M 300, M-303, M 711 and M *712 are listed as performins a containment feeletion function in Technical Requitas, ente Manual Table 2.1.1 have been listed in the IST plan. The position of these valves is administratively controlled.
Reeldual Beet Removal Svetem l
Check velves 1 R8*470$A and 1-RR 67058 provide thermal overpressurisetton protection for the normally isolated RER system inlet pipins. J I
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Page 3 CPEES UNtf 50. 1.
, TMLE W. 4 ICR No: IST-R3-001 lesEnvlCE ftsflus/ mEVISION 3 4
$YSTEN: MELILISET FEE 9tETER
't SECT.
SFTT FLOW MI FLimi
' DIAG. VLV ACT. ElWI4L FUCT ELIEF TEST es sere VALVE CteE maeEn class Comm. gL P_ Ass TTeg sI2E_ im A m anewsf aEe. etAenan .
0/C NT/o w1-e206 Arv ss Isot. (see ustes) 1 Pv-2453e 3 s-2 s GL 3.800 A0 0 FST Plf 0 0/C NT/0 N1-0206 AfW 95 Isot. (See Notes) .
3.000 A0 1 Pv-2454A 3 0-1 8 GL FST Plf 0/C NT/e M1-0206 AfW SS Isot. (see notes) 1-Pv-24548 3 5-5 s et 3.000 A0 0 FST 4
PIT j
l Cv/9 mi 0206 02 CST Fitt Peth 3 0-1 C CK 3.000 SA C C.
1AF 009 sear P tuction Check 0 Cv/o M1-0206-01 1AF-014 3 8-2 C CK 6.000 SA C l
0 Cv/0 M1-0206-01 scartr Suetten Check 1AF-024 3 3-3 C CC 6.000 24 C 0 Cv/s mi-0206-91 T9APW Surtlen Check 1AF-032 3 s-5 C CK 8.000 SA C l
0 -tv/e #1-9206-91 AFW 9eche. Check 1AF 038 3 E-4 C CK 8.000 S4 C t
0 Cv/o #1 8206-01 AfuP nectre. Chect i 1AF 045 3 E-4 C CK 3.000 SA C l
Cv/o ut 8206 01 AfW 9echg. CM ,
CK 6.000 SA C 0 l 1AF 051 3 E-3 C l
0 CV/o M1 0206 01 AR P Socire. Chett 3.000 SA C 1AF-057 3 E-3 C CK O CV/e' M1 9206-01 Af w Deche. Deeet 1AF 065 3 E2 C CK 6.000 SA C l
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ISOEnvl M TESites/ EEvlstou 3 ICR No:- IST-R3-001 i STSTER: m mtLIART Fft3IRTER f-l SECT.
I FLond XI SFTT CIDE DIAS. VLv ACT. =am FUCT RELIEF TEST Flett
- VALVE ag=====
umsEn Cts: C0 cap. SAL 35g m Size m Pos sm asawST m staenAn 1
1AF-069 3 E-1 C a 3.000 SA C 0 Cv/e at 0206-01 Afur aceirc. Check ,
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4.000 SA C O/C cv/CS N1-8206 seArty to es Check (WE muPEWIN B) l 1AF-075 3 C-4 C CK 4.000 SA C O/C cv/CS N1-8296 Tsaftp to SS Check (WE APPEWIN f) -
1AF-078 3 D-4 C' CK j ~*
4.000 SA O/C cv/CS N1-0206 genew to es Check (SEE APPEmin s) 1AF-083 3 C3 C CK C 1AF-086 3 0-3 C CK 4.000 SA C 0/C Cv/CS N1 8206 Tenfte to SG m ock (SEE APPE W IN 9) i 1AF-093 3 C-1 C CK 4.000 S4 'C O/C cv/CS a1-8206 seAN to ss Check (sEE f*PEWIN 9) 1AF-098 3 02 C CK 4.000 SA C O/C Ev/CS N1 0206 194ftf to SG Check (SEE APPEIBIN 8) 1AF-101 3 C-5 C CK 4.000 SA C O/C Cv/CS N1-0206 seAfw to SS Check (SEE APPE W II 8)
- 1AF-106 3 D-5 C CK 4.000 S4 .C O/C Cv/CS N1-8206 T9AN to SG (Seeck (SEE APPEWIN 8) i 8.000 SA C 0 cv/o n1 0206-02 Aftp Test eeturn mock 1AF-167 3 5-5 C CK 1AF-215/-215 3 0-4 A/C CK 0.500' SA 0 C V-5 Cv/0 mi 0218 914 Accom. Cheet volve (1-PV-2453A) ;
V-6 LT 0-4 A/C CK 0.500 SA 0 C V-5 Cv/o at 8218 91A Accisa. Choct votwe (1-PV-24538,1 Fv-2456) 1AF 217/-218 3 V-6 LT 1AF-219/-220 3 s4 A/C CK C.500 SA 0 C V-5 cv/o ut-0218-01A Accia. Check vetwe (1 Pv-24544)
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FLW XI SFTY vavE CODE DIAG. vtV ACT. NORNRL 'FUCT RELIEF TEST FLOW meeEn n see Conne. CAT Pgs tvrE size m Fos pas seamst n otAenei asumus 1AF 221/ 222 3 C-4 A/C m 0.500 SA O C V5 tv/e N1-9218-01A = thecit volve (1-M-M548,1-Fv-2657) j V-6 LT.
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1 1/F-223/-224 3 A4 A/C CK 0.500 SA 0 C V-5 tv/e N1-0218-01A Accia. Checit volve (1-w-M59) -
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1AF-226/-227 3 5-4 A/C CK 0.500 54 0 C V-5 tv/e N1 8218-014 Acces. Checit ve(we (1-w-2449) ~
v6 LT 1AF-228/-229 3 A3 A/C CK 0.500 SA 0 C V-S cv/e #1-e218-91A Accam. Chect votwo (1-w-M61) ,
v6 LT ,
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! 1AF-230/-231 3 8-3 A/C CK 0.500 SA o C V5 cv/e #1 8218-81A Accam. Chect volve (1 w-M 62)
. v-6 LT s
i 1AF-232/ 233 3 F-2 A/C CK 0.500 SA C C V-5 cv/0 N1-8218-91 amamm atan CECK vatw (1-w-M52-1) ,
' V6 LT !
i 1AF-234/-235 3 F-1 A/C CK 0.500 SA C C V-5 tv/e N1-0218 91 amamente tem watw (1-w M52-2)
1 i 1AF-249 3 C RE 0.750 SA C sev N1-0206-81 seAFWP sesetten Pipine Rif. ,
i 1AF-250 3 C RE 0.750 SA C sEv N1-ele 6-91 70AFW Suct. Pipine Elf.
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TABLE ED. T I sesenvlCE TESTlWG/ EEVISIGN 3 i
SYSTEN- seNeusmus2es e aEACTOR NMEMP WTER ICR No: IST-R3-001 4
4 r SECT.
- FLOW XI .SFTY VALVE CODE DIAG. VLV - ACT. MONIE FUCT RELIEF . TEST FLOW IReeE3 CLASS CO W . CAT PASS M SIZE TTPE POS P05. 4 WEST & pl W M l 1 W-5365 2 E-2 A EL 3.000 Ao C C NT/8 181 8362 8 Out Cntet. Isot.
- FST PIT LTJ -
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- l 1-NV-5366 2 E2 A CL 3.000 Ao C- C- WT/e N1-8262-3 sus Cntet. Isot. ,
i FST Plf +
LTJ i 100 006 3 C6 C M 3.000 SA C C W-5 CV/o 811 0241 01 Deseested Water Trene Pumps to ausf i' !
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100 016 3 0-3 C a 1.000 SA , C 0 cv/0 141-0261 01 mer esche. Flem Peth l 4
100-018 3 E-3 C a 3.000 SA C 0 cv/e #1 0261-01 asar Deche. Flow Peth 100 064 3 04 C a 2.000 SA C C v4 CV/e N1-0241-01 spaST IIskeep Flem Peth ,
100-065 3 C-6 C a 3.000 SA C C V5 Cv/e #1 0261-Ji Desereted Water Trene rispo to seest ;
100 066 3 04 C a 2.000 SA C C V5 CV/e #1-0261-01 AltfBT Nokeep Fleu Peth 100-430 2 E2 A/C RE 0.750 SA C LTJ N1-0262 8 9WE Cntet. Penet. Thornet Rif. j M00 044 3 02 C m 1.000 SA C 0 cv/G N1-0241 01 alar Deche. Flow Path ;
M00-068 3 E-2 C a 3.000 SA C 0 cv/0 N1 0261-01 asar esche. Flow Peth t
- . - ,, -~ , _. --_ --. . . . _ _ - - _ _ _ - _ _ - _ _ _ - _ - - _ _ _ _ _ ~
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. Pepe 3 '-*
CPSES tself 50. 1 [
> TABLE 50. 9 l
INSEevl E TESTINE/ EEvitieu 3 .ICR No: IST-R3-001
+ SYSTEN: PROCESS StrLINS .l SECT.
FLOW N1 SFTY-vAtvE c0DE DIAG. VLV ACT. WORNM. FUCT RELIEF' TEST FLOW g 121_),[g,, M E M R - MW M
< useER CLA$$ M CAT POS 1PS 500 2 e-3 A/C RE - 9.750 SA C LTJ N1-8228 Accuo. Ligs6d space tempte Cptet. Penet. Thornet Rif. k
- i 1PS 501 2 3-1 A/C RE 0.750 SA C LTJ M1-0228 F2R Sample (Ligsid) Penet. Thornet Alf.
?
I 1Ps 502 2 e-1 A/C RE 0.750 SA C t.TJ N-0228 PIR Samede (Steen) Penet. Theest atf.
I "
aC NL sangde Penet. Therest atf. - f 1PS-503 2 e-2 A/C RE 0.750 SA C LTJ N1 0228 i
i 1
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- _ _ _ _ _ _ _ _ _ ____ _ _ _ ___ _ __._ _ ___i_-___~__--_-_--__c . -_ _
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. CPSBS* INSERVICE ftpT1pe Fno mAM Fias , ,
'... asVIstos a ICR Not IST-R3-W1
.t '
- PMB 7 p RELIEF 3300587 IRBSER: V5 ;
.\
sTsfetts): Aus111ery Feedenter Main Steen, Reboet, and Steam D ay Compressed Air Emersemey Diesel Generator Component Cooling Water Dominere11eed Water VALVE IRBSER(8): 1AF 215,1AF 210,1AF-217,1AF 218, IAF*219,1AF 230,1AF 221,1AF 333,1&F*233,1AF 134, 1AF 334,1AF 337,1AF 884,1AF 889,1AF*240,1AP 331,1AF 233,1AF 833, IAF 884,1AF-335, '
M*640, M 601, M*S$3, M*4ta, M*See. M-845, M*S$4, M*M7, 3CI 644, ICI*645, 3CI-948, 1CI*S47, 1D0-0$4, 100-954, 180-000, 180 881, 190-083, 130-063, 130-064, 100-085, 10C-1070, 10C 1000, 10C-1981, 100-1048, lad-006, 1DD-064, 1BD-906$, 180-006 CAT 303Y: A/C C CLAS8: 3 FUNCTIom: These volves provide a safety-related ear supply to pne metteelly operated volves, h diesel eterting ear receiver tanke, or are associated with the reester makeup water storage temk.
TEST REQUIRDENT: Esercise sheek valves omoe every 3 months per IW9-3S81.
,.34818 Ftst RELIEF:- Each volve listed to one of tuo series shoek valves eseeelsted with valve eseumulatore, air receiver tanks, or seter tanke. Due to system eenfiseretten there is as typical meems, without perfesedas modifteetiens, to individually verify that, eesh valve bee been full streko emerstood. Perfesodes system modifteetiens ero semeldered hardships ht are ,
' not eempeneet.ed by en increened level of goality er oefety.
(.
ALTERNATE TESTING: These series shoek volves will beve their closure verified by peettive seene (such as pressure indiention) eueh that, et least one of W eerles check valves to elooed once overy three asethe, No addittemel teettag needs to be perfossed mises t,here is en indiestica that the closure cepebility of the pair of valves is questionable, then both valves will be declared inoperable and either he diseseeabled and visually inspect.ed or be i
repaired or repleoed prior to being returned to service, l
I LU AFFT.NDIX A
~
,_ _r. ..
+ ) l f? FIGURE 7.2 e i INTERIM CHANGE REQUEST
,n J{ i-IST Plar Revision Rev. 3 ICR No. IST-R3-002
%.J ' .
Reference:
Page See Attachment 1
Table See Attachment Relief Request, and/or Component: Relief Requests: V-6, 15.1, 16.6, 16.7, P.2, P.8, ;
and P.11, Appendix B, Tables 0 and 16 !
Reason for Change: See Attachment i
i i
i J
1 Proposed Revision: See Attachment i
l i
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i i
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Technical Support 11/1/89 Initistor
/ Department Date '
Approved: l [ Yes l[l No ner /e/<cm a/// b.ff %o ////b'7 CPE ASME Section XI CoordinatoV ~ Date i
i l Reason for Disapproval:
ECE 2.26 02 Rev. 1 Date: 11/9/87 l .Page 7.2 - 1 of 1 l
l-
ATTACHMENT
/ i FIGURE 7.2 A- INTERIM CHANGE REQUEST .
. Reason for Change: I
- 1) Relief Request V-6: Revision 3 of the IST Plan recategorized the Emergency Diesel Generator air start check valves as "C", rather than "A/C". However,
" Emergency Diesel Generator", was still .
listed on Relief Request V-6.
- 2) Relief Request 15.1: Overpressurization concerns require isolation of the flow path necessary to partial stroke check valves 1-8922A and 1-8922B when the RCS is depressurized.
- 3) Relief Request-16.6, 16.7: These valves will be tested on a cold shutdown frequency. The NRC questioned the original relief request which proposed disassembly on a refueling
~
ey frequency.
ikj These Relief Requests were
- 4) Relief Request P.2, P.8, P.11:
revised in response to an NRC inquiry on the initially proposed functional test for L these pumps-(SFGDS BLDG SUMPS). Vibration, flow, l and pressures will now be L measured during inservice l
testing. Pump design l precludes bearing temperature measurements.
l ,
- 5) Appendix B: Provides additional information on testing performed on auxiliary feedwater valves as
' requested by NRC. Deleted cold shutdown note for valves 1-8511A and 1-8511B, valves are now l tested quarterly.
- 6) Table 0: Revised to reflect testing specified in P.2, P.8, and P.11 for Safeguards Building Sump Pumps, in .
response to inquiry on Rev. 3 of the plan.
- 7) Table 16: The testing frequency of valves 1-8511A/B has been changed to quarterly to correspond with
( quarterly slave testing which defeats interlocks and strokes the valves. Testing requirements of Relief Requests 16.6 and 16.7 have also been incorporated in the Table.
l
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.l .
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,3 Proposed Revisions f
(
\-./
) Remove and discard V-6; 15.1; 16.6; 16.7; P.2; P.8; P.11; ;
Appendix B pages 1 through 8; Table 0, page 21 and Table 16, pages 3, 4 and 5.
- 1) Insert the attached, Relief Requests V-6, 15.1, 16.6, j 16.7, P.2, P.8 an'' P.11. '
- 2) Insert the attached, Appendix B, pages 1 through 8. ,
- 3) Insert the attached, Table 0, page 2.
- 4) Insert the attached, Table 16, pages 3, 4 and 5. :
- 5) Add this ICR to Appandix D. t i
k i
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6 i
4
. CPlt$.lW$tRVICE'TE$TI~3 FROGRAM PLAN REVI$1] 3
, PAGE 2
,_s INDEX
_. to !$7 Plan Interim Change Requests (ICRs)
ICR NO./DA.TJ,, Arr!CitD PAGt(s) DESCRIPfl0N OF CHANG (
~
l$T.R3 002 Section 11. Table 0 Table 0 revised to note the testing ,
10/31/89 page 62 program for the $rGD$ BLDG $ UMP PUMPS t i
Section !!! Table 16 Testing frequency for valves 18511A/B pages 3, 4. 5 changed to quarterly: Table revised to 1
incorporate testing of Relief Requests t 16.6 and 16.7.
Appendix A. Reivsed to reflect reclassification of j Relief Request V.6 Emergency Diesel Generator air htart t check valves.
t Appendix A. Revised to note limitation for i Relief Request 15.1 perfonnance of a partial stroke test of check valves 1 8922A/8 with the .
RCS depressurized. !
Appendix A. Class 1/2 boundary check valves to be ,
g Relief Request 16.6. 16.7 tested during cold shutdowns. .
s Appendix A. Relief Requests revised to upgrade $GDP !
Relief Request P.2. P.8. P.11 BLPG $UNP PUMP testing program..
Appendix B Cold shutdown note deleted for quarterly tested valves 1 8511A and 1 851181 added description of testing performed on AFW check valves.
4 1
e 6
[*%
APPENDIX D
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- CrsttalNSERVICE TE8 TING Ph00kAM l'LAN REV1810N 3 IAGE 4 7'. ..
) -- RELIEF REQUEST NUMBER: V6
(
CYSTtM($): Aval16Ary Teodwater
> Main Steam, Rehest, and Steen Dump Compressed Air Sofety injection Component Cooling Weter VALVE NUMBER (5): 1AF 21$,1AF-216, IAF 217,1M*210,1AF 219, IAF 220,1AF-221, IAF 222, IAF 223, IAF 224, 1AF 225,1AF*226,1AF 227,1AF 220,1AF 220,1AF 230, IAF*231,1AF 232,1AF 233,1AF 2M, 1AF*235, IMS 660,1H5 f.81,1MS t,82,1MS 683, IMS 666, 1MS-68$, IM$-668, IMS 687, ACI 646,
' ICl*645, ICl*646,101-667,181 166,181 167,181*166,181 It.D. ICC-1079, ICC 1060, 1CC 1061, 100 1082 5$-
CATEGORY: A/C
'CLAts: '3 3 FUNCTION: Frovide a safety *selsted ett (and nitrogen) supply to pneumstically operated velves and the diesel starting air receiver tanks.
TEST REQUIREMENT 1. Category A volve leek rate testing requirements of 1W 3421, IW 3426, and IW 3426.
BAS 18 FOR kELIEft. Two check velves in eerles are ut!!! red at oech class 3 to NNs piping bounJery, Rollef to requested from IW 34ft1 to individually leek test each series check volve, n
Due to the system configutetton there le no typical means, without perfterming teodifications, to individually verify the leek tightness of each volve in addition toe test date for this to, sting will fiot lend itself to analysis in accordt.nce with 1W 3426 due to the relatively rigid acceptance critorie which will Med to be spFlied, Forformat,g systeen modifications would result in herdships that are not compenotted by en increened level of quality or safety.
ALTf.KNATE TESTING: The respective series check velves will be leek teste1 in pairs, A pressure decay test or functional test w!!! be performed to verify the pressure retaining intestity of et least x
one of the cerles check volves with the normal supply system ootured and vented to stanosphere upstreme of the Class 3/NN8 piping boundary. No edJitional testing need6 to be e performed unless there is en indication that the leek tightness capab!11ty of the gets of
. valves is questionable, then both volves will be declared in9perable and either be itsessembled and visually inspected or be repaired or replesed prior to being t oturnwd tt, service.
AfflNDIX A L
!$T-R3-002
. ICR No: [
l v
'*4' CPS $$>!NBBRVICE TSSTINS PRORAM PLAN c e: REV!$10N 3 c., r,. ..
s RELTtr R$0' Jest Nt>tER '- 15.1
.['Qj} - ?
SYETDb ' Sofety injection !
'o ;
VALVE NUMstR: 1 8922A, l 1*D9228 }
- CAft00RY: C h 7: ;
. et. Ass FUNCTION! $atety injection Pump Discharge 1 solation Check Velve fttf REQUIREMENT: Esorette volve to position required to fulfill their function et, least once every 3 monthe' j (IW*3 $20 ) .
LO BASIS FOR RELitF Power Operation + No positive means exist to full stroke esortise these valves since the ,
only full flow path avantable is into the RCS and the 51 pumpe eennot develop suffletent discherse head to pump into the RCS, In addition, e partial stroke test cannot be {
performed with the RCS depressurated below 1700 pois. The safety injection test header is !
not evellable as e flow path. The safety injection pumpe are required per Technical ,
Specification 3.5.3.2 to be isolated from the RC5 to prevent RCS overpressurssetton. I, Cold Bhutdown
- Full stroking thesa volves utilising the El pumps to pump into the RC5 could result in RCS low temperature overpreseurisation which would exceed the design ;
limitations of the system and adversely offect plant safety. i
]T /:
?
I ALTERNI.TE TE8TINO: Portorm partist stroke quarterly when the RCS is pressurised above 1700 pois and full- l.
stroke exercise valve et each refueling outage. I' +
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/ ArrtNorx A ;
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- 1
( s:.A'
, f -- JCPSBS72NSERVICE TESTIh0 PROGRAM PLAN 7 v REvts!0N 3 FADE 64:
?
'/ ) -= RELIEF REQUEST NUMBER: 16.6
- \. j m,
L SYSTDt: -Chemical and Volume Control VALVE MlDSER ,
'1CS*B3SOA,B,C,D I 3C8 6367A,B.C,D L.
CATE00RYr C r
CLASS: 1 l'. '
FUNCTION: Class 1 / Class 2 Pres 6ure Boundary
- , . TEST REQUIRDENT
- . Exercise valve to the position required to fulfill its function at least once every 3 monthe. Relief is also requested from the requirement to test each p series check valve.
BASIR FOR RELIEF: Power 01 oration - These sortes check valves provide the ASML boundary between f Close 1 RCS and Class 2 CVC5 as required by ANSI N18,2a. These valves eso not
-leak tested, and are not listed as RCS pressure isolation valves in Technical i- Specification Table 3.4 1. These valves perform their sofety function in the<
closed position therefore partial otroking is not applicable. Full atroke, i- l. -
' exercising during power operation would require soturir.s seal injection flow to the reactor coolant pumpe..The interruption of this flow would result in equipmeat damage,
, /-w -
In addition, relief le requested from exercisint both series check valvos to N '
the closed position, due to the absence of test connections.
ALTERNATE TESTIN0t Verify operability of the valves during cold shutdowns when the RCPs are
'~
secured. The series check valves will be verified closed by positive means, Ne additional testing noe6s to be parformed unless there is an tr.dicottor, that the closure capability of the pair of valves to questionable, then both valves will be declared inoperable and either be disassembled end visually inspected or repaired or replaced prior to being returned to service.
L t
- f APPENDIX A
.ICR Not . I ST- R3-002 '
7 t
- g. ._ ,
,. ., CFSEs-IN$tkVICE TESTING PROGRAM PLAN
^
, . kEVISION 3
- iFACE 65 y
RELIEF REQUEST NUMBERt 16.7
) .-
L.)
SYSTEMr Chemical and Volume control eu VALVE NUPSERI. 1CS*837sA,B 1C$*6370A,8 C/.TE00kY C CLAS8 1-
'FilNCTION - Charging and Alternate Charging Line Flow Path
< . TEST REQUIREMENT: Esercise valve to the position required to fulfill its function at least once overy 3 monthe, BASIS FOR AELIEFA Power Operation
- These series check valvus ptovide the ASME boundary between Class 1 RCS and Class 2 cvC8 as required by AN$1 NIB,2a. These valves ete not
, leak tested, and are not listed es RCS pressure isolation valvts in Technical
~
Specification Table 3.4+1, These valves perform their safety. function in the closed position therefore partial stroking is not applicable. Full stroke exercising during power operation would require securing normal and etternate a
changing flow. The interruption of this flow cculd result in a loss of
, pressuriser level control and cause a plant trip.
.. g--( In addition, relief is requested from exercising both series check valves to
,( ) the closed position, due te the absence of test connections.
v ALTERNATE TESTING: Verify operability of the valves during cold shutdowns. The series check valves will be verified closed by positive means. No additional testing needs to be performed unless there is an indication that the closure capability of the pair of valves in quastianable, then both valve will be decisted inoperable and either be disassembled and visuelly inspected or be repaired or replaced prior to borng returned to solvice.
e m
APPENDIX A lim u;
I g *e 4 Ei?
w - 4. .. . ICR Not IST-R3-002 ;
e 3 -;. CP888*1NSERVICE TESTING PROGRAPI PLAN f
. AEVISION 3 j Pact to- !
-t
,y. r
- ( )- RELIEF REQUEST Ift#SER
- P*2
.\ / '
w ,
PUMP NUMBER: cpl *8WAP8W-C1, cpl *$WAPSW-02, cpl *WPAPS$*01, cpl *WPAPSS-02, cpl *WPAPSS-03, cpl *WFAPSS*04 f
i SYSTEMr Service Water, Vente and Drains (Satosuard 21ds, Sump Pumps) t t
.. I L '
CLA$$1 3 r..
I TEST REQUIREMENT: Ot> serve proper lubricant level or pressure, (!WP 3100) !
6 I
p- Basts POR RELItri- These pumps are submersed. The bearings for these pumps are internet and water cooled. .l therefore lube oil level and pressure observation is not applicable. The parameters that ,
I- shell be measured es delineated in the proposed Alternate Testing, provides suf ficient {
information for evaluating the condition of the Service Water Pumps and Befoguard Blds. !
Sump Pumps and thus does not ondenser life or proprersy or the conenon defense and security j of the public.
f.
t ALTERFATE TESTINO: The other test parameter measurements indicated in Table 0 will be performed. .
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APPENDIX A i
.x.-. , . -, -. , . _ . . . , _ . _ - . - . - - . . . _ - . . _ -.,..__,,..--.,_.,..~._.a_.,_.-.,-_..... .
3 -
ICR Not ~ !$T-R3-002 -
CPSBS* INSERVICE TSSTING PROGIUM PLAN C
,,- REVISION 3
. PAGE 16 3
.- g RELIEF REQUEST NUMBER: Pg-
.-(
-s /
?-
"~
, PUMr NUMBER:- All pumps listed in Table D.
$YSTEM(8):- Vertous CLA88: 2 and 3
[.
" Per IWP 3300, eiessure bearing temperature yearly.
TEST kEQUIREMENT:
BASIS POR RELIEh Relief to requested from the requirement to yearly eeasure pump bearing temperatures per
(; IWP 3300 due to the design limitations for some of the pumps in the IST program which prevent direct bearing temperature measurement. Rollef is further requested for the remeining pumpa in the !$7 program. Industry detr. has shown that bearing temperature thenges due to' degrading bearings only occure efter major degradation has ocrurred at the bearing, Prior to this, vibretton monitoring would more likely provide information to
- identify chang's in the condition of bearinge, keliance on vibretton monitoring would allow corrective actions to be taken prior to the f ailure of a bearing and damese to the j' pump. Bearing temperature measurements for the Service Water, Realduel Heat Removal.
Doric Acid Transfer, Safeguard Blds, Sump Pwnpo, and Safety Chilled Water Pumpt are not rossible due to pump design.
ALTERNATE TCETING' Hoosure Vibration Velocity es part of a predictive maintenance program outside of the IST Program.
5
.(/
4 9
l-i AFFENDIX A l -.
ICR No: IST-R3-002 l I
j ;CP388+1NBERt1CE FESTING Ph00RAN PLAN l
!Ei- _.
- REV1810N 3. !
=
. pagg gg . I I
t l '3 RELIEP REQUEST Nt2SER: P-11 j
\u ) ,i
' PUMP NUMBER:' cpl *WPAPSS 01. CP1-WPAPSS-02 i 5 ~ CP1 WfAPSS 03, CPI-WFAP58 04 !
t
. , SYSTEM (8)r Vents and Distne (Setosuard Bids, Swap Pumps) .(
re CLASS 1, 3 (x l l: t L.
v TEST REQUIRDENT: _, Measure the test quantities of f able IAP-31001 on each pump every three months during _
j normel plant operation.
BASIS POR RELIEPi ' These pumpe are located in dry oumps, at. is impractical to supply the required fluid r inventory necessary to test these pumps on a quarterly inservice test frequency, 'Any water introduced into the pumps for test purposes must be treet,d as redweste end disposed of accordingly, Plooding and d'aining r the sumps every three months to perform testing f creates e. hardship that as not compensated for by an increused level of quality or safety. j i
ALTERNATE TESTINO: Perform a functirnal test'of these p apa et least once every two years, en sussested by' the. current ASME code on pump testing. (Reference OH-6).
'?
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4 APPENDIX A i
N:> .
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- - , . , + . . + , . , . , .m-. . . . , ., _
,-w.. -.. , , , , ... . . _ _ . , , - .-
u..
5b, .
- s. - -
, ICR No: IST-R3-002 '
o j CPSE8*1N&tRVICE TESTING PROGRAM PLAN !
^4' IJVISION 3 !
TAGE 1
-/^ j tll f l% i 6
k i
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J 1
APPENDIX B i
4
- A ,
-I
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I i.
t 4
i 5
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. . , . , .- -. . . . , . . . _ . , _ . . ...__.y.. . - . . - . . ,, , . _ _ ., , . . . ,_,.m_,._,,,_ , , _ , , . , , . , _ ,_...,,.,,,,,...y, . _ . _ . _ , _ _ _ , . , _ . ,
y-
.ICR No: IST-R3-002 CFSE8 INSERVICE TESTING PROGRAM FLAN - ;
I.. .
REV18!ON 3 FACE 2 ;
VAINES TESTED AT C01.D SHUTDW AND REFUEt1NG OUTAGES
.The following are Category A, B, C, and A/C valves that meet the esercising requirements of A5ME Section X1, and iare not full-stroke esercised every three months dutir:g plant operation. These valves sto full-stroke esercised ,
during cold shutdowns. Testing these valves during power operation is not practics1, due to the valve type and ,
location or system design. These valves are listed below and grouped according to the system in which they are '
-located.
b STEAM GENERATOR TEEDWATER SYSTEM i
- Cotomory B Valves .
Valves 1-HV-2134, 1 HV 213$,1 ifV 2136, and 1 HV 2137, main feedwater 'to steam generators isolation valves, cannot be full stroke esotelsed during power operation. Closing these valves to accemplash stroke time testing results in
, an interruption of foodwater flow, resulting in a steam generator level transient which would cause a teactor trip.
b .These valves will be partial stroke esercised quarterly and full stroke exercised during cold shutdowns.
L ' Valves 1FV*2193, ITV-2194, 1FV 2195 and ITV 2196, feedwater preheater bypass velves, cannot be full or partial ;
l.' c stroke exercised during power operation. Opening these valve to accornplish stroke time testing to the closed v ;
position results in a temporary diversion of feedwater, the resultant steam generator level perturbation may result B in a teactor. trip. These valves will be fu11* stroke esercised during cold shutdowns, i
Valves 1FV-2161, 1FV 2162, 1FV 2183 and 1FV 2184, feedwater split flow bypass valves, sannot be full or partial
. stroke exercised curing power operation. These valves are interlocked with the feodwater isolation valves and ;
e function to prevent flow induced tube f ailures in the probmer region of the steam generator by divertirg a '
,A s portion of main feedwater flow to the steam generator auxil ury foodwater nostles. Valve closure during testins tri I diverts 2002 of feedwater flow through the main feedwater nostle. The resultant flow induced vibration could .
Y tesult in premature steam generator tubo damage. These valves w!!! be full-stroke esercised during cold shutdowns-i
. Valves 1 HV 2185,1-HV 2166,1-HV*2187 end7 1 HV 2168, feedwater isolation bypass va' ves, cannot be f ull or partial ,
- stroke exercised during power operation. These valves ato in parallel with the feedwater isolation valves and ano interlocked against opening with the feedwater isolation valves in the open position during power operation. l
(
Testing these valves at power would requite defeating the system interlocks and could possibly result in unstable
~ feedwater flow. These valves will be full stroke esercised during cold shutdowns.
Catomory C Valves ,
Valves 1FW-70,1FW 76,1N 82, and 1W-60, Feedwater Check Valves, cannot be full or partial stroke exercised during unit operation, Stroke testing these valves to the closed position requires escuring feedwater ficw to the associated operating steam generator, t.be resultant level transient would result in a plant trip, These valves will be verified closed when feed to the associated steam generator is secured during cold shutdown.
3 Valves 1FW-195, IFW-196, 1FW-197 and 1FW-196, tempering line backflow to steam generators check valves, cannot be
[
full or partial stroke exercised during power operation. Exercising these check valves could cause potenttal
' damage to the aust11ery foodwater nostles. The auxiliary foodwater flow necessary to stroke these valves as not preheated and therefore, would cause unnecessary thermal shock to the S/G auxiliary feedwater nostles; A cycle of thersel shocks to these nossles would eventually result in nogale degradation. These valves will be full-sttoke j
< exercised to the open position during cold shutdowns.
, s .
\d:
4 AFFENDIX B
'1 4
. . ICR No: IST-R3-002 :
CPSES !NSERVICE TESTING 190KAM PLAN 4
+- _ REVISION 3- :
FACZ 3 ~ !
s
( MAIN STEAM, REHEAT AND STEAM DUMP SYSTEMS l 4 Cutomory B Valves ;
i Valves 1 PV 2325, 1-FV 2326, 1 pV-2327 and 1*PV-2328, power operated relief valves cannot be full or partial stroke ,
exercised during power operation since this would cause a secondary pressure transient. The isolation of these valves, by closing the manuel inlet isolation volve, to accompitsh testing in turn could che11enge a main steam '
safety valve: These valves will be full stroke exercised during cold shutdowns.
f Valves 1*lfV 2333A,1 ifV-2331A,1*HV-233SA and 1 HV-2336A, main steam isolation velves, cannot be f ull stroke exercised during power operation. Closing these valves to accomplish st.roke time testing could result in an interruption of main oteam flow from the associated steam generator to the high pressure turbine and could result in a plant trip. These valves will be portial stroke esercised quarterly and full stroke esercised during cold shutdowns.
Qa11 gory C Velvel Velves 1MS-1st and IMS 163, main steam to turbine driven ATWP, cannot be exercised to Lheir closed saf ety positaon during power operation. Full stroke testing to the open position will be aitomplished quarterly by passing steam flow which is equal to or grestet than the accident required flow through the valve. Itowever, closure testing at' power would require isolating the check valve under test from its respective steam generator by shutting the manual upstream isolation valve. To verify closure hash pressure steam would then have to be v6nted upstream of the check which is a safety concern. The closure test for t.hese check valves will be performed during cold shutdowns w5en testing can be safely accomplished.
~'
AUXILIARY FEEDWATER SYSTEM V Catemory C volves l'
Valves 1AF-075, 078, 083, 086, 096, 101 and 106, auxiliary feedwater to the steam generators, are required to open to deliver flow to the bonstatore on well as to close to prevent a running pump from recirculating back through a non running pump. These check valves also have a secondary function in the closed position to prevent back leakage from the main feedwater system, These valves cannot be fully or partially stroked during power operation.
Exercising these check valves t.o the open position or to the open position and back to the closed position could result in damage to the sumi11ery feedwater tostles. The auxiliary feedwater floi! necessary to strche these valves is not preheated and, therefore, would cause an unnecessary thermal shoca to these nostles. A series of thermal shocks to the auxiliary feedwater nossles would eventually result in nostle degradation. These volves will be
~ full
- stroke exercised to the open position and to the closed position during cold shutdowns. Cold shutdown testing includes forward flowing through the valves wit.h an auxiliary foodwater pump which exposes the adja :ent nou running pump's check velves to a reverse differential pressure. Check valve operability, in this case, is demonstrated by verification of the required minimum flow delivered to the steam generator. It is recognised that these check valves perform their closed safety function in series with ot.her system check valves (ie. pump discharge check valves h Thus, additional testing is performed during cold shutdowns to demonstrate closure individually. The check valves are isolated upstream and downstream and a reverse differential pressure is impressed across the valve
,through a test, connection. Subsequently,' an upstream vent is opened and a leakage observation is made to ascertato valve closure. Further, when the plant is at power, the closure of t.he check valves is monitored continuously.
During each shift, the pump casings and discharge piping are checked for increases in tempers'.ute above ambient.
.()
+ <
APPENDIX B i
! , ICR No: IST-R3-002 I CPSES INSERVICE TESTIN3 PROGRAM PLAN
,~ REVISION 3.
FAGE 4 Also, temperature elements located downstream of the subject check valves are connected to indicators (0 200 F) on
) the main control board. The temperature indicators provide evidence cf foodwater back leakage into the aux 111ery feedwater system. Other temperature elements are located in the feedwater piping upstream of the normally closed check valves 1FW-0195, 0196, 0197, 0196. These elemer.ts are connected to control room alarms to warn of steam or feodwater back leakage into the normally cool portion of the feedwater system, into which t.he turillary feedwater system injects.
COMPONENT COOLING WATER SYSTEM Cetetory A Velves I~
Valves 1 HV 4096,1-RV 4700,1 HV-4101,1*HV 4706 and 1 HV 4709, component cooling water containment isolation
.E valves, cannot be full or partial stroke exercised during power operation. Closing these valves to accomplish stroke time testing could cause damage to plant equipent. Closure of the valves interrupts component cooling water flow to the reactor coolant pump thermal barrier coolers, lower bearios lube oil coolers, upper bearing lube oil coolere and motor air coolers. Securing flow could rewult in reactor coolant pump damage. These valves will L be full stroke exercised during cold shutdowns when the reactor coolant pumps have been removed from operation and component cooling water can be secured without the risk of pump damage.
Categorv B Valves Valves 1-HV 4524, 1 HV 4523, 1 HV 4526 and 1 HV 4527, component cooling water to non safeguards loop isolation
, valves, and 1 HV 4699, CCW supply to containment, cannot be full or partial stroke exercised during power operation. Closing these valves to accomplish stroke time testing could cause damage to plant equipent. Closing these velves isolates cooling to the reactor coolant pump thermal barrier coolers, lower bearing lube oil coolers,
_ upper bearing lube oil coolers and motor air coolers. Securins !!ow could result in reactor coolant pump damage.
In addition, flow would be secured from equipment necessary for plant operation: letdown heat exchanger. seal
)
\ ,/ water heat exchanger and reactor coolant pump coolers. These valves will be full stroke exercised during cold shutdowns when the reactor coolant pumps have been removed from operation and component cooling water can be secured without the risk of pump damage.
Valves 1 FV 4650 A and B, component cooling water to ventilation chillers isolation valves, cannot be full or partial stroke exercised during power operation. Closing these valves to accomplish stroke time testing could cause containment temperatures to exceed limitations imposed by the Technical Specifications. Eecurit s flow to the ventilation chillers results in their tripping off, after reopening the valves, the ventilation chillers must be manually r,estarted. The subsequent recovery is slow and during this absence of cooling flow, containment temperatures rise due to the high heet loads. As a result, a potential to damage environmentall; qualified electrical components exista. These valves will be full-stroke exercised during cold shutdowns when coolins to the ventilation chillers can be safely secured.
REACTOR COOLANT SYSTEM Category B Valves Valves 1-HV-3607, 1-HV-3608, 1-HV-3609 and 1 HV-3610, reactor vessel head and pressuriser vent isolation valves, cannot be full or partial stroke exercised during power operation since this would unnecessarily Jeopardtse the in'egrity of the reactor coolant system by relying en single valve isolation of the RCS pressure boundary. These valves will be full-stroke exercised during cold shutdo n .
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ATFENDIX B L
-ICR No: IST-R3-002 e o j t.: CPBES+1HSERVICE TEST 1W0 PROGRAN PLAN iEa REV1 TION P
'PAGE $-
h- KRV's,1*PCV 4$5A and 1*PCV-456, are not recaired to shut down the reactor to the cold shutdown condition. They t
are, however, required to k*o available during power operation to prevent eballeriges to the pressuriger safety valves. They tr.ay be required during shutdown operation to provide overpresture protection. In order to minimsre the sansequence of a PORV sticking open.,these valves will be fu11' stroked exercis6d durit.4 cold shutdowns.
L' COMPRESSED AIR SYSTEM i
y Cattacry A Velves' l
Valve 1*HV-3487, instrument air to containment cannot be full or partial stroke exercised during power opetation.
' Closing this valves to accomplish stroke time testing isolates instrument att to the sontattaent and this air is b tequired for plant control.- Testtng could result, in a plant trip and/or operational transient. This valve will t.e full stroke exercised during cold shutdowns when instrum.ent air to the contairment can be secused without havir;g an impact on plant operaticns.
VENTILATION ClllLLED WATER SYSTEM Catomory A Velves Valves 1 HV 6082, 1*HV 6083 and 1 HV 6064, ventilation thilled water W and from containment isolation valves, eennot be full or partial stroke esercised during power operation. Closing these valves to accomplish strrske time testing teolates all ventilation chilled water system heat loads in t.he containment. In addition, valve failute during testing could result in exceeding contalement temperature Technical specification limits and possibly result in damage to environmentally qualified electitcal equipment. These valves will be full stroke esercised duraris cold shutdowns when ventilation chilled water cooling to the containment can be safety secured, t
x (v RESIDUAL HEAT RD0 VAL SYSTEM Catomory A Valves Valves 1*8701 A and B and 16702 A and B, RC5 hot los to RHR isolation valves, cannot be full or partiet stroke esercised during power operation since these valvee are interlocked with RCS pressure which prevents opening these valves when RCS pressure is greater than 425 pois. These valves will be full-stroke exercised during cc4d shutdowns.
Catemory B Valvee Valves 1*B716A and 1 87168, RHR crosstie valves, in accordance with IE Information Notico No. 87*01, will not to L exe cised during power operation. Ts11ure of either valve in the closed position, concurrent with the fattute of an kHR pump results in ECC5 injection flow to only two of the required four reactor coolant system cold less.
- 4bese valves will be full-stroke esercised during cold shutdowns when they can be exercised without challengar.g RHR ECCS capabilities.
Cetomory C Valves Valves 1 8730A and 1 87308 RHR pump discharge check valves, cannot be full stroke esercised during power
' operation. There is not a full flow path eve 11able to full stroke esercise these valves at power. One po* ential full flow path discharges to the Reactor Coolant System. The kHR pumps, being low head in,tection pumps will not overcome RC8 nominal operating pressure. The alternate flow path through the normally isolated test line to the
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I -
AFFENDIX B C
e .
t . -ICR No: ' !$T.R3-002 CPSES;1NSERVICE TESTING 200 RAM PLAN
] .
,- REV1810W 3
- FA3E 6 i RWSI, ethnot be utilised with the plant et power. The valve eligreent and resultant kHR con!!guration represents o ,
[ degreded asfety condition, tendering the KHR system thoperable. 1EN*87 01 *kHR Valve Misaligtnent Causes [
Degradetion of ECCS in PWRs*' discusses hc= operability testing of RNR systema et several pWks (Westir shouse NSSS) has resulted in systwn configurations outside design bases et several plants. These volves will be partial stroke ;
I eterrated quarterly and full stroke exercised at cold shutdown. i SAFETY INJECTION SYSTEM ,
~
Cotesory A Velves Valves 18&C3 A and B, RHR injection to RCS cold legs isolation valves, cannot be full or partiel stroke esercised
- s. ' during power operation str ce this would cause a loss of the required number of cold leg, low head safety injection i flow paths. In addition Technical Specification Burveillance Requirement a.$.2.s requires these valves 1o in the [
Open position with power to t.be valve operators removed in Modes 1, 2, and 3. These valves will be full-stroke I
[. ;
exercised during cold shutdowns, a
p Valve 1*8835, $1 pump discharge to RCS cold les injection isolation volve, cannot be full or partial stroke (
exercised during power operation since failure in the closed position would isolate the SI pump to all RCS cold lege injection flow paths. In addition Technical Specification Survelliance Requirement 4.$ 2.s requires this .
valve be in the Open position with power to the valve operator removed in Modes 1, 2. and 3. This velve will be full stroke erorcised during cold shutdowns.
, Valves 1 8802A, 1 8802B, and 1*8840, normally closed motor operated gate valves in hot les injection lines, cannot be full or partial stroke exercised during power operation since Technical Specification 4.5.2,a requires these velves to be maintained in the closed position with power removed from the operators in operation Modes 1, 2. and
- 3. These valves will be full
- stroke otorcised during cold shutdowns.
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b) Valves 1*8811A and 1 8611B, RHR contairment recirculation sump isolation valves, cannot be full or partiet stroke
)
exercised wi'.h the plant at power, The stroke test of those valves requires isolating the RHR pumps from the RWST to prevent gravity drotning the RWST t.o the containment sump. The obsence of a check valve in the RHR suction inne potentially could push wetst into the contstroent sump which would then require removal. The RHR pump suction header would then have to be partially drained to prevent water back flow to the s'ap tendering the pumpe .
Anoperable._ An additional concern tr'volves the ability to adequately vont and fall tts system after testing. The edditional risks encountered and amount of time to perform testing do not justify the additional assurance gained
-by quarterly testing. These valves will Le full stroke esercised during cold shutdown when the proper precautions con be tak,en without impacting operation.
Cetoaory B Valves
. Velves 1*8804A and B, Charging Pump Suction from RHRS 10(, cannot be full or partiet stroke exercised during power operation duw to interlocks. 1 8804A and 1-88048 are opened by operator action during the recirculation mode of
$15 operation rollowing a LOCA to supply the auctions of the Charging and Safety Injection Pumps. The volves are interlocked with ECCS velves 1 8813. 1*8814A and 1 88148. These valves must be closed to open 1 8804A and 1 88048.
Valve 1-8813, as noted below, is required to be open with the plant et power to protect the SI pumps by providing a minimum flow protection path. These valves will be full-stroked outing cold shutdowns.
Velve 18808, SI pump suction from the RWST isolation valve, cannot be full or partial stroke exercised during power operation since f ailure of this valve in the closed position would render both trains of 81 inoperable. in addition, valve 1*8806 is required to be in the open position, with power to the velve operator removed, during Modes 1, 2, and 3 por Technical Specification 4.5.2.e. These valves will be full-stroke exercised during cold shutdowns.
7 k /~
w AFPENDIX B L
{ >
a _
ICR Not ISTw RV^2 t
, , CPSES 1MstRVICE TECTIMO Pm00 HAM PLnN !
' ~
4 hfVIS!!* 3 l
@ PAGE F ;
Valve 1*661), mantmum flow socirculation f rom $1 pumps consnun aselotton valve, Jennot t4 full or partial stio6e [
j esercised dustr pcmet operation since this could tender both 81 pumps without inanimum flow retarculation I
' ptet et t. ton , in addition. Technical $pettistation Requisement 6,$.2.e Joyuntos the volve to t.e an the Open !
posit &pn, with power to the valve opet et.ot s omoved dutit s Modes 1, 2, and 3. This volve will be f u11*stic4 e eseactaed during cold 6hutdowns, Valves 16804A,188088,1860gC and 1 $t06D, occumuistor isoletion valves connot be full et tattlet stroke esercised du Ins power opetetten. These valves age requited to 1>e it the open positach, with power to the valve h og+teter tossoved in Modes 1, 2 and 3 per Technstol Specificatlon 4,$,1,1, These volves are considered possive for !
their safety function in the open position, procedure 11y, t.hese valves are seguised to be closed prior to ;
detteasing 3, actor coolant passaute beltw 600 pais These valves will be full stroke tested to the closed position dusing cold shutdowns.
[ l CifEMICA1 AND VOLUME CONTROL [
t (M u gry A Velves Valves 1*8152 and 1*stf>0, CVCs letdown contalement isoletion volves, cannot be f ull or g esttel stroke esentised -
duttna powes operation. Closing these valves to accomplish stroke testing could cause the istlute of these valves duttrig testitig which could teault in tio loss of piessurtso: level control end a teactor trip. These volves wt11
{.1 be full strobe esercised during cold shutdowns, Valves 1*0100 and l'ellt, RCP seal leak of f contatteent isoletton valves, cannot be full or peittal attoke esercised during power opesetton. Closing these volven to scetunpitsh stiche teetti.g could sesult an equyaent damage. Volve closure intestupts seal water flow f rom the RCP's which could sosult in seal damage, these velves
.X . will be fullastroke esercised during told shutdowns.
'j \
t b) . Velves 1*0351 A, B, C, and D. RCP seat injection contatteent isolation valves, cannot be full et rettial stroke I- eseacteed during power opetetton. Closing these valves.to accomp116h stroke testing could result an equiseent l damese, Velve closure would Isolate seal watet anjection flow which could result in RCP seel damase, These valves w!!1 be full stroke asettised during cold shutdowns.
Valve 1*610$, normal charging isolation volve, cannot be full or partial ottoh, evertised during power opetetton since this would interrupt noteel charging flow, Velve closure could result in loss of pressurteet level contion and a plant trip. This valve will be full stroke esercised during cold shutdowns, Cateacry 8 V h Valve 1*0106, normal charging Asolation valve, cannot be full or portant stroke esegrased during l>ower op+:stion since thte would Interrupt normal charging flow which could result in loss of pressurtset level control and a plant trip. This velve will be full stroke exercised during cold shutdowns.
Valves 1*LCV 112 D and E, charging pump suction from RWST anoi tion valves, cannot be full or pas ttal stroke esercised during power opetetton since this would result in defeating the chemical balance attained by normal use of the CVCS, The subsequent teactivity transtent could result. An en uncontrolled plant shutdown. These valves will be fullastroke esercised during cold shutdowns.
Valves 1*LCV-112 8 and C, volume cont.gol tank outlet isolation valves, caanot be full or partial stroke exercised
- during power operation etnce this would cause a loss of the following: pressurtser level control, RCP seal injecLion, and letdown tegenerative heat, eschanter tooling. These valves will be full *stnoke esercised during cold shutdowns,
/N I k n >
h, APPENDIX 8 L ._
G .
, ICR No: . IST-R3-002 CPSE811 $8RVICE 7E371N0 MLOG1WI P1.AN
.'"' REV1810N 3 PAGE 6 p j-- Yhives 1 NV*t220 and 1 HV*6221 allow gasts in the contrifugal and chargitis pumps piping to vont to the VCT and
/ c.nnot be futi or p.ruet suoko ex.rcised durant power op. ration. These vatves are interlocked with 1-tev-lize end 1 LCV-112C, and do not have their own handswitch. These valves will be full stroke exercised during cold shutdowns with 1 LCV 11EB and 1 LCV 112C.
I f~ Valves 1 LCV 4$9 and 1 LCV-4 M . Class 1 RCS to Class 2 CVCS boundary volves, cannot be full or partiel stroked lJ durit.g power operation since this would interrupt charging flow. Valve closure could therefore result in a loss of' C pressurager level control and cause e plant trsp. These valves will be full etroke exercised during cold t shutdowns.
L Valve 1 4146, pressuriser euxiliary sprey isolation valve cannot be full or partial stroke exercised during pomer operation since stroke testing could result in a pressusiser pressure transient. This valve will be full stroke esercised during cold shutdowns.
Valve 1-0104, essergency boration isolation valve cannot be full or partis 1 stroke exercised during power operation.
Stroke testing this valve to the open position could cause boric acid to be delivered to the kCS and the increase
! in borte acid concentration, should the valve fail open, wtruld result in a plant trip. This valve will be full-stroke exercited at cold shutdowns, Catemory C Velves Yelve 1CS 6442, emergency boration flow path check valve cannot be full or partial stroke exercised during power operatic.ti since stroking would require flow through the emergency boration flow path which would cause e seectivity l . transient resulting in plant shutdown. This valve will be full
- stroke exercised during cold shutdowns
_g. _
Valve 1C8 4377. euxiliary oprey check valve cannot be full or partial stroke exercised because this reautres the
>'{ initiation of ausiliary sprey. The initiation of auxiliary oprey during power operations could cause a pressuriger k/ pressure transient. This check valve will be full stroke exercised during cold shutdowns, when 10145 is exeteised.
f.
i CONTAlsIMENT YTNTILATIOP l_~ Cateaory A Velveg I
Valves 1HV $$38, 1*HV SS37. 1-HV 5530 and 1 HV-S$39. cooteinment purge system valves, perform a containment isolation, function. These valves cannot be full or partial otroke i.zercised during power operation. Technical Speci!! cation LCO 3.6.1.7 requires these valves to be locked closed in Modes 1. 2. 3 and 4, 'These valves will be full stroke exercised during cold shutdowns.
Y b
v APPEND 1X B
6 (s\ ,7 i ICR No:
~
IS 002[*
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/
CPSES LMIT NO.1 Page 3 -]
TABLE No. 16 INSERVICE TESTING / REVIStom 3 SYSTEM: CMEMICAL & 'JULtM CONTROL
~
SECT.
FLOW XI SFTY VALVE- CODE DIAG. VLV ACT. NORMAL FUCT RELIEF ' TEST FLOW NUMBER CLASS C0040. CAT PASS M SIZE TYPE POS POS. REoVEST REO. DIAGRAM REMARKS 1 8351A 2 0-5 B GL 2.000 MO o C MT/CS M1-0253 RCP Seet Inj. Cntet. Isot. (SEE APPENDIM 8)
PIT 1-83518 2 0-5 8 GL 2.000 NO O C MT/CS M1-0253 RCP Seat Inj. - Cntet.1 sot. (SEE APPENDIN 8)
PIT-1-8351C 2 0-5 s GL 2.000 M0 0 C MT/CS M1-0253 RCP Seal Inj. - Cntet. Isot. (SEE APPENDIN B)
PIT 1-8351D 2 0-5 8 GL 2.000 MO O C MT/CS M1-0253 RCP Seal Inj. - Cntet. Isol. (SEE APPEN0lx B)
PIT 1-8378A 1 8-5 C CK 3.000 SA O C 16.7 CV/CS M1-0253A CLASS T/2 90UNOARY 1 83788 1 85 C CK 3.000 SA 0 C 16.7 CV/CS M1-0253A CLASS 1/2 80puoARY 1-83794 1 85 C CK 3.000 SA O C 16.7 CV/CS M1-0253A CLASS 1/2 80UNDARY 1 83799 1 B-5 C CE 3.000 SA O C 16.7 CV/CS M1-0253A CLASS 1/2 90LMDARY 1-8381 2 E-3 A/C CK 3.000 SA O 0/C 16.1 LTJ I41-0253A CVCS Chrg. - Cntet. Isot.
CV/o 1-8481A 2 E-4 C CK 4.000 SA C O/C 16.4 PS/o M1-0255-01 Charging Pump Oschg.
CV/RR 1-64818 2 E-5 C CK 4.000 SA C O/C 16.4 PS/0 M1 0255-01 Charging Puup Dschg.
CV/RR I
1 1 8497 2 D-2 C CK 3.000 SA O C CV/o M1-0255 01 Pure Discharg- Check
n _
,~,\ ,.-.,
) ICR No: 157 2 ..
(J . \s CPSES Luli MO.1 Peyr 4 TA6LE 40.16
> l# SERVICE TESTleG/ REVIS105 3 SYSTEM: CMEMICAL & VOLtME CONTROL MG.
FLOW NI SFTY VALVE CODE DIAG. VLV ACT. NonstAL FUCT RELIEF TEST FLOW WIAWER QASS COORD. CAT PASS S M SIZE TYPE POS POS. REGUEST REO. 01AGRAM REMAN S 1-8510A 2 E-4 C RE 1.500 SA C SRV M1-0255 01 Nigh need '41 Miniflow Rtf.
1-85106 2 E-5 C RE 1.500 SA C S*V M1-0255 01 nigh need St Miniflow Rif 1-85113 2 0-4 8 GL 2.000 M0 C O/C MT/0 M1-0255-01 Nigh need St Miniflow Isot.
P1T 1 85118 2 0-5 8 GL 2.000 Mo C O/C MT/o M1-0255-01 Nigh Meed St Miniflow Isot.
PIT 4
1-85123 2 D-4 8 % 2.000 MO O 0/C RT/c M1-0255-01 Charging Pwo Miniflow Isot.
- PIT 1-85128 2 D-4 8 GL 2.000 MO O 0/C MT/o M1-0255-01 C%arging Pwp Miniflow Isot.
PIT 1 -8%6 2 C-6 C CK 8.000 SA C 0 16.5 PS/CS M1-0255 RWST to Chrg. Pump Sutt.
CV/RR 1-CS-8350A 1 0-4 C CK 2.000 SA 0 C 16.6 CV/CS M1-0253 CLASS 1/2 BauucARY 1-CS-8350s 1 0-4 C Cr 2.000 SA 0 C 16.6 CV/rs A1-0253 CLASS 1/2 60UwDAkV 1-CS-8350C 1 0-4 C CC 2.000 SA 0 C 16.6 CV/CS M1-0253 CLASS 1/2 80L*04RY 1 C5-03500 1 D-4 C CK 2.000 SA 0 C 16.6 CV/CS M1 0253 CtASS 1/2 80uncARY 1 CS-0367A 1 04 C CK 2.000 SA O C 16.6 CVtCS M1-0253 CLASS 1/2 BOUNDARY
n -. . - -. .- - _-
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'V v CPSES unif =0. i P. ,e 5 TA8LE m0. 16 INSERVICE TESTIWGI REVISION 3 SYSTEM: CMENICAL & VOLtPE CouTWOL SECT.
FLOW x1 SFTY VALVE CODE DIAG. VLV ACT. 40 MAL - FUCT PELIEF TEST FLOW ,
utsWER CLASS C00RD. CAT PASS TYPE SIZE TYPE POS POS. WEQUEST #ES. DI AG8M REsenpKS 1-CS 8367B 1 D-4 C CK 2.000 SA o C 16.6 Cv/CS mi-0253 CLASS 1/2 00UnoAeY 1-CS-8367C 1 0-4 C CK 2.000 SA o C 16.6 CV/CS M1-0253 CLASS 1/2 90tMDARY t-CS-8367D 1 04 C CE 2.000 SA o C 16.6 Cv/CS #1-0253 CLASS 1/2 90UNDARY 1 CS-8368A 2 D5 C CE 2.000 SA o wT #1-0253 acP Seat Inj. - Cntet. Isot, (See motes) 1-CS 83688 2 D-5 C CK 2.000 SA o af m1-0253 aCP Seat ini. - Cntet. Isot. (See motes) 1 CS-836BC 2 0-5 C CK 2.000 SA o sT m1-0253 eCP Seat inj. - Cntet. Isot. (See metes) 1-CS-83620 2 0-5 C CK 2.000 SA o wT M1-0253 aCP Seat Inj. - Cntet. Isot. (see motes?
1-CS-8377 1 8-6 C CK 2.000 SA C o Cv/CS #1-0253A Asmitiary Spray Cfweck Valve (SEE APPEucir s) 1-CS 8473 3 C-4 C CK 2.000 SA C 0 cv/0 mi-0257 9ATP DscN.
1 -CS-8487 3 C-4 C CK 2.000 SA C 0 CV/o al-0257 BATP Dsc h .
1 NY-8220 2 E-2 S GL 1.000 So o C mT/CS M1-0255 ECCS operation (SEE APFEtDir 8)
FST PIT 1-ev-8221 2 E-2 s GL 1.000 SD 0 C *T/CS mt-0255 ECCS Operation (SEE AFFEmDIN B)
FST PIT T LCV-1128 2 E-6 8 GA 4.000 no O C MT/CS 41-C255 VCT Isot. (SEE Ar*TuCIR 8)
PtT
_ . . . . _ _ , - . ... . _ . ~ . .
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, . FIGURE 7.2
.INTERIN CHANCE REQUEST
'~
,7 j IST Plan Revision 3 ICR No._IST-R3-001 s '/
Reference:
Page See Below
, Table See Below Relief Request, and/or Component: 1AF-009, IDD-064, IDD-066, IPV-4552, IPV-4553, IPS-193, IPS-194, IPS-195, IPS-196.
Reason for Change:
- 1) Table of Contents: Required to be updated per this ICR.
- 2) IPV-4552, IPV-4553: These control valves were not included in the " Notes" Section. 1
- 3) 1AF-009: This valve is installed in the fill path ior the Condensate Storage Tank and is required to prevent the tank from draining.
- 4) 1DD-064, IDD-066: Thtsse valves are installed in the fill path for the Reactor Make-up Water Storage Tank and are required to prevent the tank from draining.
- 5) IPS-193, IPS-194, IPS-195, IPS-196: These valve numbers have been changed to IPS-500, IPS-503, IPS-501 and IPS-502 respectively.
- 6) Appendix D Required to be updated per this ICR.
[] Proposed Revision:
V Remove and discard the Table of Contents; " Notes" page 1; Table 4 pages 3, 4, and $;
Tabic 5 page 5; Table 7 page 1; Table 9 page 3; and Relief Request V-5.
- 1) Insert the attached, revised Table of Contents.
- 2) Insert the attached, revised " Notes" section and Table 5 page 5 which adds IPV-4552 and IPV-4553 to the IST Program.
- 3) Insert the attached, revised Table 4 pages 3, 4 and 5 which adds lAF-009 to the IST Program.
- 4) Insert the attached, revised Tabic 7 page I which adds IDD-064 and IDD-066 to the IST Program. Insert the attached, revised Relief Roquest V-5.
- 5) Insert the attached, revised Table 9 page 3 which revises the valve numbers t as described above.
- 6) Add this ICR to Appendix D.
l NOc 2 - AN FJ k rpE/pf(s cyl;cQp,9 '
~
Initiatot ' Department ' Dkte l
1 Approved: l Yes l[l No 6 6'mb 9/tr/* 7 l
' Da te' 4 CPE f E Section XI Coordinator Reason for Disapproval: 1 (N ECE 2.26 02 Rev. 1 Date: 11/9/87
.Page 7.2 1 of 1 4
Q m merne m M WHBIEB 4 ICR Not IST-R3-001
.. See a .
uns i
w ast n o ameem esmee asemene tsmst h am m , assusum assuas IST-R3-001 Table of Contents Remove page numbers irom Appendix D.
09/15/89 Section 111. " Notes" Add valves IPV-4552 and 1PV-4553 Page 1 to the CCW System note.
Section III, Table 4 Add valve 1AF-009.
Pages 3, 4 and 5 Section III. Table 5 Add valves 1PV-4552 and IPV-4553.
Page 5 Section III. Table 7, Add valves 1DD-064 and 1DD-066.
Page 1 Section 111. Table 9. Correct. revised valve numbers.
Page 3 Appendix A. Relief Add valves 1Db-064 and 1DD-066.
Request V-5 Appendix D Add ICR Index and ICR IST-R3-001.
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I assERAL R30Utaserfs 1.1 M ................................................................ 3 l 1.8 151 ELaB F13thf . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 AFFLICABI.R CIMA bafER m R50 DIE 38578. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 [
1.3
- FIREPRMdN..................................................... .$ ,
1.4 i VALVE m ............................................ ....... ..3 l 1.5 RELIEF BRREBfB........................... ...................... ..6 1.8 33E(3.3 UgED f13 VALVE TEsf. FMadM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 I 1.7 II Flee TESf!!a3 FROSAM i fable 0 t
!!! VALVW TEsf!se FRoadM fable 1 stetten Service Water Table 8 Stem Generator Foodwater Tabte , ,,sta .t._ -et e.d 8,e. D e ;
fable 4 Auxiliary Feedwater .
i Table 5 Caepenoot Coolias Weter fable s Reacter Coolent System C
r Table 7 Deinere11eed and Reester Makeup Weter
\ Voets and Draine
- Centeisment building fable 8 Table 9 Presees templine Table 10 Compressed Air Table 11 Liquid Weste Freesssine and RC Drain Tank Suberates Table 12 Yeattletten Chilled Water Centelament Spray [
Table 13 Residual Boot Removal j Table 14 Table 15 Safety Injoetion Table 16 Chemical and Vol me Coatsel Table 17 Safety Cbilled Water ,
Table it Centeinment Vent 11etten Table le Spent Fuel Peel Coettas and Cleemup Table 20 Fire Protection - Containment Building fable 21 Emergency Diesel Generator
,67 Pages APPENDIX A RELIEF REQUESTS... ................. ...... . ....... ... . ,
.. , ,.8 Peses APPEllDIX 3 VALVES TESTED AT COLD SNUTD0beIS AIC REFUELING OLTTAGE8. .
.. ... . .. ... A Peses l APPENDIX C F14W DIAfmAM (P&ID) REFERENCES.. ... .
AFFEllDIX D INDEX TO IlrTERIM CEANGE REQUESTS i
\
i e
Cftts INS BY1CE TRSTING Ph0 SeM PLAN , r
, navistas 3 .
' ICR Not IST-R3-001 l 1
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nie eeeuse of no Cemenche Pod Sten Elettrie Steuen !$f Flan contenu upleuuene er J eteettueusew ter ne teettas not a perfumed en een compenenu conteined to the velve talu. )
i Mennuy operated n1vu ere met oubject to eseruee tuttae by no Ist Plan. neee nivu no einer :
rouunely operated or are subjut to rarmet preventin metatenance preerene.
{
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Acc uiner ebut vetvu ter euetuary feed =ner nine 1 rV 3453Ats,1 rV 2454 Alt,1 sv 24So, 1 sv 34eo, 1 ev 34st, and 1 sv sess ho w been iteted in the tot plan and 611 be toeted se a ,
etnote mat. Yhte a appropriete for ne deeton tunettom er those volves. A preeeure deeer test win be pertermed on ne accouluer unite, win ne opetroen teet unnocuen for the 6ceumuletore vented to aseephne. nas tut moned , tit meet the totent et zw 3430, to demonstrete the ...t leek ushteen of C.eoery A volves. 6 6 e t
Cheet nivu ics sles A.s,C and o are mermany open and remain open duttas poet uudent undauene, ner are pronurned ti essen er eentussent preuvre trem en sat source ehten mene etnote renure eraerte. Clueure a no seued en ter contetement toelaten.
- Coeune .r et .
Velves EFV 3543, EFY M64, XFV 3HS, XFV 3544, FCV B1164. FCV Bites IFV*4352 and 1FV 4SS3 control (
the rios of esmponent eeoitus water te no Centrol Room AIC, U.P.S. A/C and pusleer Chtuer condeaeore to maintetn a minte m condensing pressure. These volves are esempted from inservies teettas in secordance eith IW 1200 u contres wolves. FCV 5116A, FCV 81168, IFV 4552 and 1FY 4SS3 ero required to foil opea.
Centstament Ventiletten Bretas Nyere6en purge eyeten volves 15Y SS40,1EV S$41,15V S$42 and 15V SS43 are n1ves in a non eesentiel bookup system to the Dydresen Recombiners. The tydrogen Recombinere are the safety rolsted componente required to remove hydrogen during poet necident econeries. These volves are 1eeked eleted ta modes 1, 3, 3 and 4 Noin Steen Robeet and Steam D e ze 8 votes s
Manuel veine 159 33HB,1EV 23348,15V 233SS,1BV 13365 M 364, IMB 387 M 300,1MB 393, M 711 and M 718 are iteted u perforetas a centstament leeletten fumetten in fuhnteel Requiremonte Manuel Table 3.1.1 have been iteted in t.he IST plea. The peutten of thus vune to adotaistratively contre 11ed, j Residual Beat Removal 8,etes I i
I i
Check velvoe 1 R8 8705A and 1*RB*tF05B preytde thermal overpreneurtsetten preteetten for the i
normally tselsted k m system inlet piping.
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trars mit so.1 rese 4 TacLE W. 4 tussevics TEstras/ eEvtsson 3 ICR No: IST-k3-001 STSTBt: estittaRT Fe BInteR SECT.
j FLthf II 9FTT j valve (XeE elAG. vtv ACT. WWWhL fWCT WLIEF TEST Flat impWER GLAGS p . CAT _ PA$s M SIZE M_
FW & W h HW M .
1AF-esp 3 E-1 C '(K 3.see SA C 0 Cv/e m1-0206-e1 arer socirc. S ect 1AF-eF5 3 C-4 C a 4.ees SA C O/C cv/CS st1-8206 saarer to es caneck (ME APPEGIR e) -
tv/CS W1-0206 tenfer to es tsieck (mE apre s ta e) 147 878 3 04 C CK 4.see sa C c/C
' leaFer to es check (sEE apreets a) 1AF ee6 3 D3 C CK 4.000 SA C e/C cv/Cs mi etes 4
4.ees sa C e/C tv/CS W1-ste6 seem to es chest teEE appsusta e) i 1AF-093 3 C-1 C CK 4.000 SA C O/C Cv/CS N1-0206 TenPW to ss Cheet (sEE appenDIE e) 1AF-098 3 02 C CK 1AF-101 3 C-5 C CK 4.ees sa C O/C cv/cs w1-eles searv to es theet (SEE apressu e) 1AF-106 3 0-5 C CK 4.tes sa C 6/C Cv/Cs N1-ele 6 TeaMi to ss Ostk (WE aF9eW:N e) f i 1AF-167 3 e5 C CK e.cos sA C o Cv/s w1-ele 6-e2 meir test netw n chect 4
1AF-215/-216 3 0-4 A/C CK 0.500 se o C V-5 cv/s m1-0218-eta a,,*=. Cheet vetwe (1-Pv M53A)
V-6 LT 1AF-21T/-218 3 0-4 A/C CK 0.50s SA 0 C V-5 cv/s #1-0218 e14 Access. theck ve4we (1-PV M53e,1-Fv-M56) v-6 LT 1AF-219/-220 3 e-4 A/C CK 0.50s SA 0 C W-5 cv/e at-8210 814 Access. Check volve (1 Pv-24544)
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, valve case esas. vtv .aCT. senunt FuCT netteF Test numen ne sash sat Paan m -1st m n!E *n!b. m essT
- asus ammans 1CC-10TT 3 C3 C a 2.000 m e C 5.4 tv/m set 251-A ACP M orest terrier Check i 1CC-tors 3 C-4 C Ex 2.cos- m e C 5.4 Crian Nt-EB1 A atP M erest terrier m eek -
iCC-to79ftee0 3 s-4 Art tu e. set sA e e v-5 cvie m-stu-e1 of w eer em est (1-Pv-4552)
V-6 l
1CC 1981/1982 3 G4 A/C M 0.500 SA 9 0 T-5 cv/e M1-et u-91 LT Assasadeter mock (1-Pv-4853)
V-6 1LV-4500 3 C-2 e eL 3.000 as C e M/e m-SE9-A FST ttM Surge Teset Wy.
PIT i
1Lv-4500-1 3 C-1 e et 3.000 AD c e m/s W1-GE29-4 FST ttN Surge Tapet Spty.
PST 1LV 4501 3 e-2 e et 3.030 as C e utte N1-GE29-A FST CEN Surge Teset Spiy.
Ptf PCV-u114A 3 A-4 B PL 1.000 AD 9 FST N1 M 29-A CEN to trS A/C thdt (See estee)
PCV-u114e 3 F-3 8 PL 1.000 A0 0 PST 881-8229-8 CEN to tPS A#C thdt (See setee)'
1-PV-4552 3 D-4 S PL 3.000 80 0 FST R1-SE29-A CNN to aucteer thitter (See setee) 1-Pv-4553 3 e-4 s PL 3.000 ao e PST N1-eEE9-e CEN to aucteer a ttler (see esees) -
NPV-3583 3 e O PL 3.000 95 9 WT W1-9229-A Ctw to Centrol Asem A/C thde (See mates)
- MPW-3506 3 'e6 S PL 3.888 ~ 910 0 ef 881-0229-5 Cru to Centret seem A/C unit (see metee)
.~ - _ - - . _ - -_
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W SES usit ED. 1- page 1 -
TABLE 50.'T IWMRvla TESTIES/ M VIS1m 3 ICR No: IST-R3-00,a-SYSTEM: 80nemsm me e samur mien SECT.
Fleu MI SFTY WALVE CIIDE DIAG. Utv ACT. siment FuCT MLIEF TEST FLef em0ER g:AS[ CCORD. gl, PASS TWE SIZE TWE 805 PE 3038_7 SE elagem egeW3 1-W-5365 2 E-2 A OL 3.000 Ao C C m/t I:1-8362 0 ens Dient. Ise4.
FST Ptf LTJ 1 w 5366 2 E2 % CL 3.000 Ao C C Ist/s est-Ge62-0 eug enemt. Isot.
FST PIT ~
< LTJ 4
1 100-006 3 C-6 C a 3.000 SA C C V-5 Cv/e ett-0261-01 genereted unter Trene Pimpo to musf j 100 016 3 03 C m 1.000 SA . C 0 cv/e 8:1-8261 01 mer teche. Fleu Peth 100 018 3 E3 C a 3.000 SA C 0 cv/s est 026101 L w teche. Flow Peth 100 064 3 0-4 C CK 2.000 SA C C v-5 tv/e I:1-8361-01 mesi sede, Flow path :
100-065 3 C-6 C CK 3.000 SA C C V5 cv/e M1 0261-01 Seeersted unter Trene Pu ye to aust ;
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! 100-066 3 04 C CK 2.000 SA C C V-5 cv/o m1 9041-01 mest auteige Flens Petti +
100-430 2 E-2 A/C RE 0.750 SA C LTJ mi 9262-0 Sus Cntet. Penet. Thornet att.
x00-044 3 0-2 C CK 1.000 SA C 0 cv/o at-9361 01 aper esche. Flens Peth NDO-048 3 E-2 C CK 3.000 SA C 0 Cv/e 181 0261 01 Mar sectie. Flow Peth .
1 I
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- TMLE 50. 9
^i-tasEevict TESTseat mEvtsien 3 ICR No: IST-R3-001 SYSTER: PEONSS SMFLles SECT.
FLOW XI SFif VALVE CERE DIAG. Utv ACT. WWut FtKT M LIEF TEST Fuht 25eER M M CAT PASS MRM PES % 6 & 9M M 1PS-500 2 3-3 A/C RE 9.750 SA C LTJ at-s2a Accuo. L W Space S W e Ovest. Penet. Thornet eff.
1PS-501 2 e-1 A/C aE 0.750 SA C- LfJ at-ENS PER Sagde (lwd) Penet. Thornet Stf.
1Ps 502 2 3-1 A/C RE 0.750 SA C LTJ m-8225 PIR Sample (Steam) Penet. Theemt att.
4 1Ps-503 2 s-2 A/C RE 0.750 SA C LTJ N1-0228 BC NL Saapde Penet. Thornet Rtf.
l
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,'! RsV sscs 3 ICR Not IST-R3-001 Fees 7
^ ~ asLisF Ragussf Im esR: -VS
- s A u 11 ory Foodseter sTsfuntsu i Mete steen, tabeet, and steen Der l
. Compressed Air
~
Imersoney Diesel Generater Campeneet Cooltas Weter j Dominere11eed Weter VALVs m8SER(Eh 1AF 215,1AF 816,1AF 817,1AF 314,1AF 210,1AF-330,1AF 131,1AF 212,1AF 223,1AF 224, ,
1AF-236, 1AF*Ah7, 1AF 334, 1AF-389, SAF-Sae, 1AF 841, 1AF 838, 1AF 883, 1AF 834, 1AF 235, M-400, M-tel. M 843, M-843, M 884, M 64$. M tet, M 687,1CI 844,1CI 645, ,
1CI-648, 3CI 647,100-0S8,150 0S9,130-000,100-081,130 062,100-083,180-044,100-045, 1CC 1879, ICC+1040,10C 1981, ICC 1983,12-000,13D-944,1BD-906S,180-048 CATIOCRT: A/C.C CLASS: 3 FUNCTION: These valves provide a estety-related ear suppir to pasimmetteetly operated valves, the diesel starties att receiver tanks, or are essestated with the reester ankoup water s
storego tank.
TEST REQUIR M NT: Emoreise sheek valves enee every 3 anothe per IWV-3S21.
BASIS PER RELIEF: Tua volve listed is one of tee series eheek valves eseesisted with volve eseumoleters, e
.(
air receiver m e, er .ete, - e. oue o e,et. e u retia. t. ore is n. 6,,iest noems, without perfoamias enditientiene, to individually wority that seek valve bee been full streke esoreised. Perfesmias erstem modifisettene are saneidered herdships that ere met osapenested by en inoroesed level of gestity or estety.
ALTERNATE TIdTIRO: These series shoek valves will have their sleeure verified by p ettive noene (such en pressure Ladiesties) such that et least ene of the series shook valves le elesed once overy three mondia. We additiemet testias needs to be porteseed misse tt. ore le en indlesties that the sleeure espebility of the pair of velves to questionable, then bath velvoo will be declared inoperehle and either be disassenhied and visually toepectot, or be repaired or repleeed prior to botas returned to service.
AFFENDIX A L
^
- - f
.v FIGURE 7.2 INTERIN CHANGE REQUEST
- ,~ -
'. i .
IST Plan Revision Rev. 3 ICR No. IST-R3-002
Reference:
Page See Attachment '
Table See Attachment Relief Request, and/or "
Component: Relief Requests: V-6, 15.1, 16.6, 16.7, P.2 P.8 and P.11, Appendix B, Tables 0 and 16 Reason for Change: See Attachment 9
f.
-(%
4 Proposed Revision: See Attachment 1
i W ' 8. M Technical Support 11/1/89 Initistor
/ Department Date l Approved: l 3 Yas l[l No ner /el,em .J/ / b. 4,n ////b'7 CPE ASME Section XI CooralinatoF 'Date l , Reason for Disapproval:
( ECE 2.26 02 Rev. 1 Date: 11/9/87
.Page 7.2 - 1 of 1 l-l-
l l- , , ,.
ATTACHMENT FIGURE 7.2
. [d.')
N INTERIM CHANGE REQUEST 4
-Reason for Change:
- 1) Relief Request V-6: Revision 3 of the IST Plan recategorized the Emergency Diesel Generator air start check valves as "C", rather than "A/C". However,
" Emergency Diesel Generator",'was still listed on Relief Request V-6.
.2) Relief Request 15.1: Overpressurization concerns require isolation of the flow path necessary to partial stroke check valves 1-8922A and 1-8922B when the RCS is depressurized.
- 3) Relief Request 16.6, 16.7: These valves will be tested on a cold shutdown frequency. The NRC questioned the original relief request which proposed disassembly on a refueling
- jr3- frequency.
- 4) Relief Request P.2, P.8, P.11: These Relief Requests were revised in response to an NRC inquiry on the initially proposed functional test for these pumps (SFGDS BLDG SUMPS). Vibration, flow, and pressures will now be measured during inservice l
testing. Pump design precludes bearing temperature measurements.
- 5) Appendix B: Provides additional information on testing performed on auxiliary feedwater valves as requested by NRC. Deleted cold shutdown note for valves 1-8511A and 1-8511B, valves are now tested quarterly.
1:
- 6) Table 0: Revised to reflect testing specified in P.2, P.8, and P.11 for Safeguards Building Sump Pumps, in .
response to inquiry on Rev. 3 of the plan.
1
- 7) Table 16: The testing frequency cf valves 1-8511A/B has been changed to quarterly to correspond with
,_s
( quarterly slave testing which defeats interlocks i' and strokes the valves. Testing requirements of Relief Requests 16.6 and 16.7 have also been incorporated in the Table.
l l
l-1 - . - -. , . . . - - - -
- . ?
,,,. Proposed Revision
(
w Remove and discard V-6; 15.1; 16.6; 16.7; P.2; P.8; P.11; Appendix B pages 1 through 8; Table 0, page 2; and Table 16, '
pages 3, 4 and 5.
- 1) Insert the attached, Relief Requests V-6, 15.1, 16.6, 16.7, P.2, P.8 and P.11.
- 2) Insert the attached, Appendix B, pages 1 through 8.
- 3) Insert the attached, Table 0, page 2. '
- 4) Insert the attached, Table 16, pages 3, 4 and 5.
- 5) Add this ICR to Appendix D. .
h t
O 1
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.. U
'O CPSES IN5tRVICE TEST!!$PROGRAIII PLAN 1 REVISION 3 I f," PA~3 2 - l 1
j.q INXX i to IST Plan Interim Change Requests (ICRs) l ICR NO./DATE AFFECTED PAGE(s) DESCRIPTION OF CHANGE j
]
+ .
IST-R3-002 Section !!. Table 0 Table 0 revised to note the testing
, 10/31/89- page #2 program for the SFGDS BLDG $ UMP PUMPS Section 111. Table 16 Testing frequency for valves 1-8511A/B pages 3. 4. 5 changed to quarterlys Table revised to incorporate testing of Relief Requests I 16.6 and 16.7. l Appendix A. Reivsed to reflect reclassification of Relief Request V 6 Emergency Diesel Generator air start check valves.-
i Apoendix A. Revised to note limitation for Relief Request 15.1 performance of a partial stroke test '
of check valves 1-8922A/B with the RCS depressurized. ,
p Appendix A. Class 1/2 boundary check valves to'be Q Relief Request 16.6. 16.7 tested during cold shutdowns.
Appendix A. Relief Requests revised to upgrade SGDG Relief Request P.2. P.8. P.11 BLDG SUMP PUMP testing program..
Appendix B Cold shutdown note deleted for quarterly tested valves 1-8511A. and 1 8511B; added description of testing performed on AFW check valves.
l.
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g APPENDIX D
_ nv
.s.
- g . IST 2
- \
- , <
'%/ %.) '
+
C013 scie PEAK STEAM ELECIRIC STATIOle UNIT 1 PtMP TEST MtOGRAM LI TABLE L PROGRAM P!JL4 RET. No. 3 .
TEST PARMETERS
- PtMP NUMETR PLMP NAPE CODE FD AND INLET DIFT FLOW VIB. StG LUBE LYL . -
- CLASS C) ORDINATES SPEED - PRESS PPISS RATE AMP. T*MP OR PRESS CP1-DOAITT-025 ' FUEL DIL TRANSFER '3 215 F-5 No 18 0 ( 6 ) 18 0 ( 6 ) YES YES 180(8) N0(6)
CPX-SFAPSF-01 SPENT FUEL POOL COOLING 3 235 C-2 NO YES YES YES YES 30(8) YES
~
CPX-SFAPSF-02 SPENT FUEL POOL CDOLING 3 235 C-5 18 0 YES YES YES YES 18 0 ( 8 ) YES CP1-3DAFRM-0) REAC.F4 MEE'.' TRhtSFER 3- 241-01 D-3 NO YES(7)' YES TZS YES N0(8) YES
~
CPX-DDAPRM .T kEACI G st%EUP TRANSFER 3 441-01 .,-4 NO YES(7) YES YE;: YES N0(8) YES CP1-WPAPSS-01 SFCD. BLDG. SUMP PUMPS (11) 3 236 C-6 No YES YES YES YES 18 0 ( 8 ) N0(2)
CPI-WPI.PSS-02 SFGD. BLDG. S'JMP PUMPS (11) 3 236 C-6' NO YES YES YES YES 'N0(8) N0(2)
CP1-WPliPSS-03 SFGD. BLDG SUMD PtEPS (11) 3 236 E-6 too YES YES TES YES te0(8) N0(2)
CP1-WPAPSS-04 SFGD. BLDG. SUMP PUMPS (11) 3 236 E-6 le0 YES YES YES YES NO(8) 18 0 ( 2 )
(1) S@e Relief Request P-1; (2) See Relief Request P-2 (3) See Relief Request P-3; (4) See Relief Request F-4; (6) See Relief Request F-6; (7) See Relief Request F-7; (8) See Relief Request P-8; (9) Deleted; (10) See Relief Request P-10; (11) See Relief Request P-11.
(
a? , ,
,- ICR No; IST-R3-002
=4- -CPSES INSERVICE TESTING PROGRAM PLAN ,
'# . REVISION 3 FAGE 6-
\ *
/ . RELIEF REQUEST NUNEER: V-6 ,
SYSTEM (B): Aux 111ery Feedwater Main Steam Reheat, and Steam Dump ,
Compressed Air Safety Injection Component Cooling Water VALVE NUMBER (S): 1 AF-215, I AF 216, I AF-217, 1AF-218, 1 AF 219, 1 AF 220, I AF-221, 1 AF-222, I AF-223, 1AF-224, IAF-221, IAF 226, 1AF 227, 1AF 228, 1AF 229, IAF-230, 1AF-231, 1AF 232, 1AF-233, 1AF-234, 1AF 235, 1HS-680, IMS 681, IMS 662, 1MS-683, 1MS-664, IMS-6tS 1MS-686, IMS-687, ICI-644, t 1C1 645,1C1 646,1CI-647,181*166,131 167,131-166,1SI-160, ICC-1079, ICC-1080, ,.
-CATEGORY: A/C CLASS: 3 FUNCTION: Provide a safety-related air (and nitrogen) supply to pneumatically operated valves and the diesel startins air receiver tanks.
TEST REQUIREMENTt Category A valve leek rate testing requiremente of IWV-3421, 1WV 3424, and 1WV-3426, BASIS FOR RELIEF: Two check valves in series are utt11:ed at each class 3 to NHS piping boundary. Relief is requested from 1WV 3421 to individually leak test each series check valve.
[]
Due to the system configuration there is no typical means, without performing modifications, to individually verify the leak tightness of each valve . In addition the test data for this testins will not lend itself to analysis in accordance with IWV-3426 due to the relatively rigid acceptance criteria which will need to be applied. Ferforming system modifications would result in hardships that are not compensated by an increased level of quality or safety, ALTERNATE TESTING: The respective series check valves will be leak tested in pairs. A pressure decey test or functional test will be performed to verify the pressure retainins integrity of at least one of the series check velves with the normal supply system secured and vented to atmosphere upstream of the Clase 3/NNS piping boundary, No additional testins needs to be performed unless there is an indication that the leak tightness capability of the pair of valves is questionable, then both valves will be declared inoperable and either be ,
disassembled and visually inspected or be repaired or replaced prior to being returned to service.
. w" %
f $
APFENDIX A
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. ICR No:- -IST-R3-002 6 .
i s' ; CPSES* INSERVICE TESTING PROGRAM PLAN ..
H- , . REVISION 3
- Fact 36
[ }; . RELIEF REQUEST NUMBER: 15.1 j-SYSTEM: . Safety Injection !
- g. VALVE NUMBER: 1 8f822A, 1 8922B CATE00RY: C ,
r CLASS: 2
.) '{
FUNCTION: Safety Injaction Pump Discharge Isolation Check Valve TEST REQUIREMENT: Exercise valve to position required to fulfill their function at least once every 3 months.
(IWV 3520).
- q o BASIS FOR RELIEF
- Power Operation - No positive means exist to full stroke exercise these valves since the only full flow path evallable is into the RCS and the SI pumps cannot develop suf ficient discharge head to pump into the RCS. In addition, a partial stroke test cannot be performed with the RCS depressurised below 1700 psis. The safety injection test header is ,
not evetlable as a flow pth. The safety injection pumps are required per Technical Specification 3.5.3.2 to be isolated from the RCS to prevent RCS overpressuratetton.
Cold Shutdown
- Full stroking these valves atilising the SI pumps to pump into the RCS-could restilt in RCS low temperature overpressurisation whicn would exceed the design limitations of the system and adversely effect plant asfety.
7"Nf
- j--
ALTERNATE TESTING: Perform partial stroke quarterly when the RCS is pressurated above 1700 pois and full stroke exercise valve et each refueling outage.
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APPENDIX A l '.-
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4 y 3
-1CR-Not IST-R3-002; g{h[~5CPSES-IN8,ERVICETESTING'PROGRAMPLAN bWk u ,
? ' REVISION 3*
', fp PAGE 64 -
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1( jy . RELIEF REQUEST NUMBER '" - 16.C' -
. } } ;>
Mi '
) 8YSTEH r .1 - Chemical.and Volume control E;
l VALVE NUMBER:-- 1C8-8350A,B,C,D-F ICS 8367A,B,C,D .]
- v. .
-l CATEGORY:l C' y- <
1 -
, 9 i
i .-CLASSi .1 '
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-filNCTIONt1 Class 1 / Class 2 Pressure Boundary - ]
h n
Exercito valve to t.he position required to fulfill its function at least once -
TEST REQUIREMENTt-every 3. months. Relief is also requested from the requirement, to test each 1 !!
series check valve,
(:
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-. BASIS FOR RELIEF: Power operation a These series check valves provide the AsME boundary betw'een $
Class 1 RCS and Class 2 CVCS ao required by. ANSI N18,2a. .These valves are not i leak' tested,.and are not listed as RCS pressure isolation valves in Technica1'- . ,
- b5 Speci!! cation Table'3i4-1. .These: valves perform their. safety function in the 7
closed position therefore partist stroking is not applicable. . Full. stroke .
3.
exercisins durins' power operet.lon would require securins seal in,)ection flow - ;
l~
4' to the reactor coolant pumps. The interruption of this flow would result in - f "
4 equipment demase.
fy ,
,2 e In addition, relief is requested from exercising'both series check valve's.t.o i
/'
.the closed position, due to the absence of test, connect. ions.
ALTERNATE TESTIN0: Verify operability of the valves during cold shutdowns when the RCPs are -. i secured. The series check valves will-be verilled closed by positive means, (*
.Na additional testins needs to be performed unless there is.an indication that I the closure capability of the pair.of valves la quest.lonable. Lhen both valves will be declared inoperable and eit.her be disassembled and visually inspected or repaired 1r replaced prior to being returned to service, i
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s' APPENDIX A t
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ICR No:- IST-R3-002 p ~ % _ f ,pggg.INSERYICE TESTINb FROGRAM FLAN .
p :.
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' -REVISION 3+
"PAGE 6$ ,
~
[Q;ys s : . .
s, i4 -RELIEF REQUEST NUMBER -36.7 E G
r 'w4 0 ;w SYSTEM:' chemieni and volume Control.
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. VALVE NUMBER:- . ICS 8378A,B 1CS 0379A.B 6:
$ CATEGbRY:.- C y; .CLASSL :1 Vn bi >
'_ FUNCTION: Charging and Alternate Charging Line Flow Path
(.: -
$! TEST REQUIREMENTI Exercise valve to the position required to fulfill ALs function at least once
.every 3 months.
' BASI 5 FOR RELIF.F Power Operation - These series check valves provide the ASME boundary between.
Class 1 RCS and Class 2 CVCS as required by ANSI N18.2a. These valves are not leak tested,.and are not listed as RCS pressure isolation valves in Technical Specification Table 3.4 These valves perform their safety function in the
,' closed position therefore partial stroking te not applicable. Full stroke-te exercisin6 during power. operation would require securins normel and alternate charging flow. The interruption of this flow could result in a loss of
, pressuriser level control and cause a plant trip.
j In addition, relief is requested from exercising both series check valves to:
~ the closed position, due to the absence of tast connections.
(y, j
'H ALTERNATE TESTING:- -Verify operability of the val'ves during cold shutdowne. The series check valves will be verified closed by. positive means. No odditional testing needs
.to be performed unless:there is an indication that the closure capability of the pair of valves is questionable, then both valve will be declared.
Anoperable and either be disassembled and visually inspected or be repaired or
' replaced prior to being returned to service.
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,, N /
3 APPENDIX A
,f.
E y
ICR No: IST-R3-002
[ ;e ' CPSES INSI.RVICE TESTING PROGRAM PLAN-l
.J REVISION 3 PAGE 10 j RELIEP REQUEST NUHBER: P2
- s. _ ' ,
- PUMP NUMBER
- ' CP1 SWAPSW-01, CPI-SWAPSW-02, CP3 WPAPSS-01, CP1-WPAPSS 02, CP1-WPAPSS-03, CP1-WPAPSS 04 SYSTEM: Service Water, Vents and Drains (Safeguard Blds, Sump Pumps)
CLASS: 3 Observe proper lubricant level or pressure. (IWP-3400) '
TEST REQUIREMENT:
E BASIS FOR RELIEP: These pumps are' submersed. The bearinse for these pumps are inturnal and water cooled, ,
therefore lube oil level and pressure observation is not applicable. The parameters that shall be measured as delineated in the proposed Alternate Testing, provides sufficient information for evaluating the condition of the Service Water Pumps and Safeguard Blds, Sump Pumps and thus does not endanser life or property or the comnon defense and security of the public.
ALTERNATE TESTING: The other test parameter measurements indicated in Table O will be performed.
~rx \
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sj 4
(_/
APPENDIX A
ICR No:
s; IST-R3-002 CPSES INSERVICE TESTINO PROGRAM PLAN
. REVISION 3 PAGE 16
/
7 RELIEF REQUEST NUMBER:.. P-8
- t ) '.
PUMP NUMBER: All pumps listed in Table 0, ,
-SYSTEM (S): Various
-CLASS: 2 and 3 TEST REQUIREMENT: For IWP 3300, measure bearing temperature yearly.
, -BASIS FOR RELIEF: Relief is requested from the requirement to yearly measure pump bearing temperatures per IWP-3300 due to the design limitations for some of the pumps in the IST program which prevent direct bearing temperature measurement. Relief la further requested for the remaining pumps in the IST program. Industry data has shown that bearing temperature changes due to degrading bearings only occurs after major degradation has occurred at the bearing, Prior to this, vibration monitoring would more likely provide information to identify changes in the condition of bearir.gs. Reliance on vibration monitoring would allow corrective actions to be taken prior to the failure of a bearing and damage to the pump. Bearing temperature measuremente for the Service Water, Roaldual Heat Removal, Boric Acid Transfer, Safeguard Bids, Sump Pumps, and Safety Chilled Water Pumps are not possible due to pump design.
ALTERNATE TESTIN0: Measure Vibration Velocity as part of a predictive maintenance program outside of the IST Program,
,,~3
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APPENDIX A
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, , '!CR No IST-R3-002
" yp
,. CPSES INSERVICE TESTING PROGRAM PLAN ~
g .. ; , REVISION 3~ 't "f;-6 ;PAGE 19 l t
2l^;,(,
RELIEF REQUEST NUMBER:- P-11
- k. -
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- PUMP NUMBERt CP1 WPAPSS-01.' CP3 WPAPSS*02 . ;
' cpl *WPAPSS 03. cpi-WPAPSS 04 ,
y .. . . .
SYSTEH(3): Vents and Drains (Safeguard Bids. Sump Pumps) f 4... ,
h -I f
~~CLASSt'. -
'3
.e F" TEST REQUIREMENT:- Heasure the test quantittee of Table IWP 3100-1 on each pump every three months during. .
normal plant operation. ;
i.
f ' BASIS FOR RELIEF:
These pumps are located in dry eumps, it is impractical to supply the required fluid '[
(' , inventory necessary to test these pumps on a quarterly inservice test frequencys Any-.
W water introduced into the sumps for. test purposes must be treated as redwaste and disposed l- '[
y .
.-of accordingly. Floodins and draining the sumps every three months to perform testins. ,
( creates a hardship that 14 not compensated for by an increased level of quality or safety. '
Perform a functional test of these pumps at least once every two years, as suggested by'
!ALTERNATETESTING:
{; the current ASME code on pump testing. (Reference CH-6).
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ICR No: IST- R3-002
.. ,.: ; CPSES-INSERVICE IESTINO PROGR#f P!.AN .
/l.~ ' REVISION 3 PAGE 1 l
)
APPENDIX B l
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, ICR No: _ IST-R3-002 ;
l -.
.CPSES-INSERVICE TESTING PROGRAM PLAN
, Ml REVISION'3 bg 8' AGE 2 t ;
i
- [ .
VALVES TESTED AT COLD SHUTDOWNS AND REFUELING OUTAGES Th'e'following are Category A, B. C[ and n/C valves that meet the exercising requirements of ASME Section XI, and '
are not full-stroke exercised every three' months durits plant operation. These valves are full-stroke exercised
~
during cold shutdowns. Testing these valves during power operation is not practical, due to the valve type and
{
. location or system design. These valves are listed below and grou;od according to the system in which they are '
located, i e
STEM GENERATOR TEEDWATER SYSTEM '[
Cetesory B Valves t
L . .
, Valves 1 UV-2134,1-HV-2135,1 HV 2136, and 1 dV 2137, main feedwater to steem generators isolation valves, cannot
' be full stroke exercised during power opera ton, Closing these valves to rccomplish stroke time testing results in I.,.
.an int'erruption of feedwater flow, resulting in a eteam generator level transient which would cause a reactor trip. ,
, These valves will be partial-stroke exercised quarterly and full stroke exercised during cold shutdowns.
valves 1FV-2193; 1FV-2194, ITV-2195 and IFV 2196, feedwater prehoster bypass valves, cannot be full or partial stroke exercised during power operation. ' Opening these valve to accomplish stroke time testing to the closed position results in a temporary diversion of feedwater, the resultant steam generator level perturbation may result- !
in a reactor trip. These valves will be full-stroke exercised during cold shutdowns, 9
Valves 1FV 2181, 1FV 2182, 1FV-2183 and 1FV 2184, feedwater split flow bypass valves, cannot be full or partial stroke exercised during power operation, These valves aie interlocked with the feedwater isolation valves and function to prevent flow induced . tube failures in the preheater region of the steam generator by diverting a .
' ' N j portion of main feedwater flow to the steam generator auxilisty feedwater nossles. Valve closure during testing 4
, diverts'1001 of feedwater flow through the main feedwater nossle. The resultant flow induced vibration could result in precature steam generator tube damage. These valves will be full stroke exercised during cold shutdowns.
Valves 1 HV-2185, 1 HV 2186, 1 HV 2187 and 'l-HV-2188, feedwater isolation bypass valves, cannot be full or partial stroke exercised during Power operation. These valves are in parallel with the feedwater isolation valves and are interlocked against opening with the feedwater isolation valves in the open position during power operation. _i Testing these valves at power would require deseating the system interlocks and could possibly result in unstable feedwater flow. These valves will be full-stroke exercised during cold shutdowns.
Cateaory C Valves Valves 1FW-70, 1FW-76, 1FW 82, and 1FW-88, Feedwater Check Valves, cannot be full or partial stroke exercised during unit' operation, Stroke testing these valves to the closed poettion requires securing feedwater flow to the associated operating steam generator, the resultant level transient would result in a plant trip. These valves
.will be verified closed when food to the associated steam generator is secured during cold shutdown.
Valves 1FW 195, 1FW-196, IFW-101 and 1FW 198, tempering line backflow to steam generators check valves, cannot be
- full or partial stroke exercised during power operation. Exercising these check valves could cause potential damage to the auxiltery feedwater nossles. The auxiliary feedwater flow necessary to stroke these valves is not prehested and theref9te, wcald cause unnecessary thereal shock to the S/0 auxiliary feedwater nozsles. A cycle of thermal shocks to thoce nossles would eventually result in nossle degradation. These valves will be full stroke exercised to the open position during cold shutdowns.
l . -
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-l APPENDIX B u
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Nu . -
ICR No: 1ST-R3-002
, ; 1df pi ,
B; ;4".3 CPSE8EINSERVICE TESTING PROGRAM PLAN l ,' REVISION.31 r> PAGE 3-N; ' HAIN STEAM, REHEAT AND STEAM DUMP-5YSTEMS
- t ja '
h J .' .
..Cetenory B Valves-
}
< Valves l1-PV 2325, 1 FV 2326.-1 PV-2327 and 1 PV 2328, power operated relief valves cannot be full or partial stroke p exerstsed during power.oreration since this would cause a secondary pressure transient. The isolation of these va'ves, l by closing the manual inlet isolation valve, to accomplish testing in turn could chs11enne a main steam I
, safety valve, ;These valves will be full stroke exercised during cold shutdowns.
' Val'ves 1*HV 2333A ' 1 HV 2334A,1-HV 2335A and .1 HV 2336A, main steam isolation valves, cannot be full stroke b - exercised during power operation. . Closing these valves to accomplish stroke time testing could result in an interruption of main steem flow from the associated steam generator to the high pressure turbine and could result-in a plant trip. These volves will be persist stroke exercised quarterly and full stroke exercised during cold shutdowns.
Cateaory C Valves
- Valves 1HS*142 and 1HS-143, main steam to turbine driven AFWP, cannot be exercised to their closed safety position during power op6tetton. Tull stroke testing to the open position will be accomplished quarterly by passing steam i flow whicn is equal to or greater than the accident required flow through the valve. However, closure testir.d at j power would require isolating the check valve under test from its respectise steam generator by shutting the manuel- l upstream isolation valvo. To verify closure high pressure steam would then have to be vented upstream of the. check F which is a safety concern, The closure test for these check valves will be performed during cold shutdowns when testing can be astely accon'plished. s fAUXILIARY TEEDWATER SYSTEM jg\.
Cateaory C Valves ,
a ~ Valves 1AF-075, 078, 083, 086, 090, 101 and 106, aux 111ery feedwater to the steam generators, are required to open
.to deliver flow to the generators as well as to close to prevent a running pump from recirculating back through a non-running pump. These check valves 'also have e secondary function in the closed position to prevent back leakage li from the main feedwater system. These volves cannot be fully or partially stroked during power operation.
. Exercising these check valves to.the open position or to the open position and back to the closed position could-result in damage to the auxiliary feedwater nossles. The auxiliary feedwater flow necessary to otroke these valves
~
.As not preheated and, therefore, would cause an unnecessary thermal shock to these nossles.' A series of thermal l shocks to the auxiliary feedwater nossles would eventually result in nossle degradationi These valves will be full-stroke exercised to the open position and to the closed position during cold shutdowns. Co.id shutdown testing includes forward flowing through the valves with an auxiliary feedwater pump which exposes the adjacent non-tanning
, < pump's check valves to a reverse differential pressure. Check velve operability in this case, is demonstrated by
- verification of the required minimum flow delivered to the steam generator. It is recognised that these check i valves perform their closed safety function in series with other system check valves (to. pump discharge check
. valves). Thus, additional testing is performed during cold shutdowns to demonstrate closure individually. The check valves are isolated upstream and downstream and a reverse differential pressure is impressed across the valve through a test connection. Subsequently, an upstream vent is opened and a leakage observation is made to ascertain i= valve closure. Further,*when the plant is et power, the closure of the check valves is monitored con *.inuously.
.During each shift, the pump casings and discharge piping are checked for increases in temperature above ambient.
4 1 ; L
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! APPENDIX B f
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N 4 . .-
, . ICR Not IST-R3-002 CPSE8-INSERVICE TESTING PROGRAM FLAN
$ REVISION 3 PAGE 4' g Also, temperature elements located downstream of the subject check valves are connected to indicators (0 200 F) on i.+ ~
j' the main c'.ntrol board. The tempereture indicators provide evndence of f oodwater back Isakage into the auxiltery feedwater system. Other temperature elements are located in the feedwater piping upstream of the normally closed check velves IFW-0195. 0196, 0197, 0196. These elements are connected to control room alarms to warn of steam or feedwater back leakage into the normally cool portion of the feedwater system. Anto which the auxiliary feedwater
- system injects.
CCHPONENT COOLING WATER SYSTEM Catesory A Valves Valves 1-HV 4696,1-HV-4700,1*HV-4701,1-HV-4708 and PHV-4709, component cooling water containment isolation valves, cannot be full or partial stroke exercised during power operation. Closing these valves to accomplish stroke time testing could cause damage to plant equipment. Closure of the valves interrupts cceponent cooling water flow to the reactor coolant pump thermal barrier coolers, lower bearing lube oil coolers, upper bearing tube oil coolers and motor air coolers. Securing flow could result in reactor coolant pump damage. These valves will be full stroke exercised during cold shutdowns when the teactor coolant pumps have been removed from operation and component cooling water can be secured without the risk of pump damage.
pat eaory B Valves Valves 1 HV-4524, 1 HV*4525, 1 HV 4526 and 1-HV 4527, component cooling water to non safeguards loop Asolation
' valves, and 1 HV-4699, CCW scpply to containment, cannot be full or partial stroke exercised during power operation. Closing these valves to accomplish stroke time testing could cause damage to plant equi pent. Closing these valves isolates cooling to the reactor coolant pump thermal barrier coolers, lower bearing lube oil coolers, upper bearing lube oil coolers and motor air coolers. Securing flow could result in reactor coolant pump damage.
1 1 In addition, flow would be secured from equipment necessary for plant operation: letdown heat exchanger, seal
\ ,/ - water heat exchanger and reactor coolant pump coolers. These valves will be full stroke exercised during cold shutdowns when the reactor coolant pumps have been removed from operation and component cooling water can be secured without the risk of pump damage.
Valves. 1-TV-4650 A and B, component cooling water to ventilation chillers isolation valves, cannot be full or partial stroke exercised during power operation. Closing these valves to accomplish stroke time testing could cause containment temperatures to exceed limitations imposed by the Technical Specifications. Securing flow to the ventilation ch111ere results in their tripping off, after reopening the valves. the ventilation chillers must be manually r,estarted. The subsequent recovery is slow and during this absence of cooling flow, containment temperatures rise due to the high heat loads 'As a result, a potential to damage environmentally qualified electrical components exists. These valves will be full stroke exercised during cold shutdowns when cooling to the ventilation chillers can be safely secured.
REACTOR COOLANT SYSTEM Cateaory B Valves
' Valves I IHV-3607, 1-HV-3608, 1-HV-3609 and 1-HV-3610, reactor vessel head and pressuriser vent isolation valves, cannot be full or partial strche exercised during power operation since this would unnecessarily jeopardize the integrity of the reactor coolant system by relying cn single valve isolation of the RCS pressure boundary. These valves will be full-stroke exercised during cold shutdoims.
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APPENDIX B
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CPSES-!NSERVICE TLSTING PROGRAM PLAN
~ i. REVIS!DN 3
( FAGE $
f.
j PORV's, 1 PCV 45$A and 1 PCV 456, are not required to shut down the reactor to the cold shutdown condition. They
_ are, however, required to be available during power operation to prevent challenges to the pressuriter safety valves. They may be required during shutdown operation t.o provide ov(rpressure protect ion, in order to minimite
, . the consequence of a PORV sticking open, these valves will be full-stroked exercised during cold shutdowns.
L --
COMPLESSED AIR SYSTEM i-Cotomory A Valves Velve 1*lfV 3467, instrument air to containment, cannot be full or partial stroke exercised during power operation.
Closing this valves to accomplish stroke time testing isolates inst.rument air to the containment and this air is required for plant control. Testing could result in a plant trip and/or operat.ional transient. This valve will be full stroke exercised during cold shutdowns whs.s instrument air to the containment can be secured wi.,hout having an
- j. impact on plant operations.
VENTILATIDH CHILLED WATER SYSTEM
' Cateaory A Valves Valves 1 HV-6082, 1-HV-6083 and 1*HV<5064, ventilation chilled water to and from containment isolation valves, cannot be full or partial stroke exercised during power operation. Closing t,hese valves to accomplish stroke time i testing isolates all ventilation chilled water system host loads in the containment. In addition, velve failure during testing could result in exceeding cont.ainment temperature Technical Specification limits and possibly result in damage to environmentally qual!!!ad electrical equipnent. These valves will be full stroke exercised during cold shutdowns when ventilation chilled watcr cooling t.o the containment can be safety secured.
1 RESIDUAL HEAT REMOVAL SYSTEM
'm.-
CMemory A Valves q
'l
< Valves 1 8701 A and B and 1-8702 A and B, RCS hot les to RHR isolation valves, cannot be full or partial stroke exercised during power operation since these valves are interlocked with RCS pressure which prevents opening these valves when RCS' pressure is greater than 425 pois. These valves will be full stroke exercised during cold shutdowns.
Catwaory B Valves Valves 1-8716A and 1-8716B, RHR crosatie valves, in accordance with IE Information Notice No. 87 01. will not be exercised during power operation. Failure of either valve in the closed position, concurrent with the f ailure of an RER pump results in ECCS injection flow to only two of the requirgrJ four reactor coolant system cold legs.
These valver will be full-stroke exercised during cold shutdowns when they can be exercised without challengang RHR ECCS capabilities.
I Catenory C Velves-Valves 1 8730A and 1-87308, RHR pump discharge check valves, cannot be full-stroke exercised during power operation. There is not a full flow path available to full-stroke exercise these valves at power. One potent.iat full flow path discharges to the Reactor Coolant System. The RHR pumps, being low head injection pumps will not overcome RCC nominal operating pressure. The alternate flow path, through the normally isolated test line to the N /
u APPENDIX B
e m ICR No: IST-R3-002 CPSES INSERVICE TESTING PROGRAM PLAN REVISION 3-( ,' PAGE 6 i
RWST, cannot be utilised with the plant et power. The velve alignment and resultant RHP configuration represents a
/. degraded safety condition, tendering the RHR system inoperable. IEN 8P01 "RHR Valve Misalignment Causes Degradetion of ECCS in IMRs" discusses how operability testing of RHR systems at several IWRs (Westinghouse NSSS) has resulted in system configurations outside design bases at several plants. These valves will be partial-stroke exercised quarterly and full-stroke exercised at cold shutdown.
SAFETY INJECTION SYSTEM Catesory A Valvee Valves 1-8809 A and'B, RHR in.)ection to RCS cold less isolation valves, cannot be full or partial stroke exercised during power operation since thir, would cause a loss of the required number of cold leg, low head safety injection
- flow paths. ' In addition Technical Specification Surveillance Requirement 4.5.2.a requires these valves be in the Open position with power to the velve operators removed in Modes 1, 2, and 3. These volves will be ful'.-s*.roke exercised during cold shutdowns.
Velve 1 8835, SI pump discharge to RCS cold les injection isolation valve, cannot be full or partial stroke exercised during power operation since failure in the closed position would isolete the SI pump to all RCS cold less injection flow paths. In addition Technical Specification Surveillance Requirement 4.5.2.s requires this
. valve be in the Open position with power to the valve operator removed in Modes 1, 2, and 3. This valve will be full-stroke exercised during cold shutdowns, Valves 1-8802A, 1-8802B, and 1-8840, normally closed motor operated gate valves in hot les injection lines, cannot be full or partial stroke exercised during power operation since Technical Specification 4.5.2.a requires these valves to be maintained in the closed position with power removed from the optrators in operation Modes 1. 2, and
- 3. These valves will be full-stroke exercised during cold shutdowns. 1 g n J i .
, _/ Valves 1 8811A and 1-88118 . RHR w ntainment recirculation sump isolation valves, cannot be full Or partial stroke exercised with the plant at power. The stroke test of these valves requires isolating the RHR purnps from the RWST to prevent gravity draining the RWST to the containment sump. The absence of a check valve in the RHR suction line potentially could push water into the containment sump which would then require removal. The RHR pumn suction header would then have to be partially drained to prevent water back flow to the sump renderins the pumps inoperable, An additional concern involves the ability to adequately vent and fill the system af ter testing. The .,
additional risks encountered and amount of time to perform testing do not justify the additional assurance gained
~
b by quarterly testing. These valves will be full stroke exercised during cold shutdown when the proper precautions can be taken without impacting operation.
Catesory B Valves Valves 1-8804A and B, Charging Pump Suction from RERS EX, cannot be full or partial stroke exerctaed during power operation due to interlocks. 1-8804A and 1-8804B are opened by operator action during the recirculation mode of SIS operation following a LOCA to supply the auctions of the Charging and Safety Injection Pumps. The valves are interlocked with ECCS valves 1-8813, 1-8814A and 1-88148. These valves must be closed to open 1-8804A and 1 8804B.
Valve 1-8813 *is noted below, is required to be open with the plant at power to protect the SI pumps by providing a minimum flow protection path. These valves will be full-stroked during cold shutdowns.
Valve 1-8806, SI pump suction from the RWST isolation valve, cannot be full or partial stroke exercised during power operation since failure of this valvo in the closed position would render both trains of SI inoperable. In i addit. ion, valve 1-8806 is required to be in the open position, with power to the valve operator removed, durtng Modo 1, 2, and 3 per Technical Specification 4.5.2.a. These valves will be full-stroke exercised during cold shutdowns, q
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APPENDIX B i
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T ICR Not IST-R3,0021 CPSE8a!NSERVICE TESTING PROGRAM PLAN REVISION 3 4-PAGE T Valve 18813. minimum flow recirculation from $1 pumps common isolation valve, cannot be full or partial stroke
, exercised during power operation since this could render both 51 pamps without minimum flow recirculation protection. In addition. Technical Specification Requirement 4.5.2.a requires the valve to be an the Open position, with power to the valve operator removed during Hodes 1, 2, and 3. This valve will be full-stroke exercised during cold shutdowns.
Valves 18608A,1-88088,1-8608C and 1-8808D, accumulator isolation valves, cannot be full or partial stroke exercised during power operation. These valves are required to be in tbo open position, with power to the valve operator removed in Hudes 1,' 2 mand 3 per Technical Speci!! cation 4.5.1.1. These valves are considered passive for their safety function in ' s open position. Procedurally, these valves are required to be closed prior to
-' decreasing reactor coolant pressure below 800 pais. These valves will be full stroke tested to the closed position f during cold shutdowns.
CHEMICAL AND VOLUME CONTROL Catenory A Valves Valves 1 8152 and 1 8160 CVCS letdown containment isoletion valves, cannot be. full or partial stroke exerctaed during power operation. Closing these valves to accomplish stroke testing could cause the f ailure of these valves during testing which could zesult in the loss of pressuriser level control and a reactor trip. These valves w!!!
- be full-stroke exercised during cold shutdowns.
Valves 1-8100 and 18112, RCP seal leak-off containment isolation valves, cannot be full or partial stroke exercised during power operation, Closing these valves to accomplish stroke testing could result in equipment damage. Valve closure interrupta seal water flow from the RCP's which could result in seal damage. These valves
- - will be full stroke exercised during cold shutdowns.
g 1
s ,i . y gy,,.g.8351 A, B, C, and D RCP seal injection containment isolation valves, cannot be full or partial stroke exercised during power operation. Closing these valves to accomplish stroke testing could result in equipment d amag e . Valve closure would isolate seal water injection flow which could result in RCP seal damage. These valves will be full-stroke exercised during cold shutdowns.
Valve 1-8105, normal charging isolation valvo, cannot be full or partial sttoke exercised during power operation since this would interrupt normal charging flow. Valve closure could result in loss of pressuriser level control and a plant trip. This valve will be full-stroke exercised during cold shutdowns.
Catesory B Valves-Valve 18106, normal charging isolation velve, cannot be full or partial stroke exercased during power operation since this would interrupt normal charging flow which could result in loss of pressuriser level control and a plant trip. This valve will be full stroke exercised during cold shutdowns.
Valves.1-LCV 112 D and E, charging pump suction from RWST isolation valves, cannot be full or partial stroke exercised during power operation since this would result in defeating the chemical balance attained by normal use of the CVCS. The subsequent reactivity transient could result in en uncontrolled plant shutdown. These valves will be full stroke exer 61 sed during cold shutdowns.
Valves 1-LCV-112 B and C, volume control tank outlet isolation valves, carinot be full or partial stroke exercised during power operation since this would cause a loss of the followir.g: pressuriser level control, RCP seal injection, and letdown regenerative heat exchanger cooling. These valves will be full-stroke exercised during cold shutdowns.
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APPENDIX B
1 -V l.-
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ICR No: IST-R3-002
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, ._ CPSES-INSERVICE TESTING PROGRAM PLAN -
REVISION 3' PAGE 6 Valves'1-HV-8220 and 1 EV 8221 ellow gases in the cet.;ritussi and churging pumps piping to vent to the VCT and x _/ cannot be full or partial stroke exercised during power operation, These valves are interlocked with 1-LCV-1128 and 1-LCV 112C, and do not have their own handstaitch. These valves will be full-stroke exercised during cold shutdowns with 1-LCV 1128 and 1-LCV-112C, Valves 1 LCV-459 and'l-LCV-460, Class 1 RCS to Class 2 CVCS boundary valves, cannot be full or partial stroked during power operation since this would interrupt charging flow. Valvo closure could therefore result in a loss of pressuriser level control and cause a plant trip, these valves will be full stroke exercised during cold
' shutdowns, i
Valve 1-8145, pressuriser auxiliary spray isoletion valve cannot be full or partial stroke exercised during power i operation since stroke testins could result in a pressuriser pressure transient, This valve will be full strcle exercised during cold shutdowns, Valve 1-8104, emergency boration isolation valve cannot be full or partial stroke exercised during power operation, Stroke testing this valve to the open position could cause boric acid to be delivered to the RCS and the increase in boric. acid concentration, should the valve fall open, would result in a plant trip. This valve will be full stroke exercised at cold shutdowns.
Cateaory C Valves Valve 1CS-8442, amargency boration flow path check valve cannot be full or partial stroke exercised during power operation since acroking would require flow through the emergency boration flow path which would cause a reactivity transient resulting in plant shutdown. This valve will be full-stroke exercised during cold shutdowns
}
. ,s Valve ICS 8377, auxiliary spray check valve cannot be full or partial stroke exercised because this requires the
" 'i ' initiation of auxiliary sprey, The tuitiation of auxiliary spray during power operatione could cause a pressuriser j.-
pressure transient, This check valve will be full-stroke exercised during cold shutdowns, when 1-6145 is exercised.
CONTAINMENT VENTILATION Cateaory A Velves Valves 1HV-S$36,1-HV-5537,1-KV-5536 and 1-KV 5539, containment purge system valves, perform e sentainment isolation function, These valves cannot be full or partial stroke exercised during power operation. Technical Specification LCO 3.6.1.7 requires these valves to be *.ocked closed in Modes 1, 2, 3 and 4. These valves will be full stroke exercised during cold shutdowns, A
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I APPENDIX B l
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/,,;). lICR No: IS 002 #
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CPSES tM1T No.1 Page 3 TA8LE NO. 16 INSERVICE TESTING / REVISION 3 SYSTEM: CHEMICAL & VOLLME CONTROL SECT.
FLOW XI SFTY VALVE CODE DIAG. VLV ACT. NORMAL FUCT RELIEF TEST FLOW NLM8ER CLASS COORD. CAT PASS TYPE $1ZE TYPE POS % REQUEST REO. DIAGRAM REMARKS 1-8351A 2 D-5 8 GL 2.000 MO o C MT/CS M1-0253 RCP Seat InJ. - Cntist..Isol. (SEE APPENDIX 8)
PIT 1-83518 2 D5 8 GL 2.000 MO o C MT/CS M1 0253 RCP Seat Inj. - Cntet. Isot. (SEE APPENDIX 8)
^
PIT -
1 8351C 2 D-5 8 GL 2.000 MO o C MT/CS M1-0253 ErP Seat In]. - Cntet. Isot. (SEE APPENDIX 8)
PIT 1 8351D 2 D-5 8 GL 2.000 MO O C MT/CS M1 0253 RCo Seat InJ. - Cntet. Isol, (SEE APPENDIX 8)
Pli i
1-G378A 1 85 C CK 3.000 SA 0 C 16.7 CV/CS M1-0253A CLASS 1/2 80UNDARY 1-83788 1 85 C CK 3.000 SA o C 16.7 CV/CS M1-0253A CLASS 1/2 800NDARY i
1 8379A 1 8-5 C CK 3.000 SA 0 C 16.7 CV/CS M1-0253A CLASS 1/2 80UNDARY 1-C3798 1 85 C CK 3.000 SA 0 C 16.7 CV/CS M1-0253A CLASS 1/2 80UNcARY 1-8331 2 E-3 A/C CK 3.000 SA o o/C 16.1 LTJ M1-0253A CVCS Chrg. - Cntet. Isot.
CV/0 1 8481A 2 E-4 C CK 4.000 SA C O/C 16.4 PS/0 M1-0255-01 Charging Puip Dschg.
CV/RR i
1-84818 2 E-5 C CK 4.000 SA C O/C 16.4 PS/O M1-0255-01 Charging Purp Dschg.
CV/RR 1 8497 2 C-2 C CK 3.000 SA o C CV/o M1 0255-01 Ptsp Discharge check
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l( )~ 'ICR No: 'IS ,
2A
% %J- ,
CPSES tm!T NO. 1 Pay 4'-
TABLE No. 16 INSERVICE TEST!uG/ REVIStom 3 SYSTEM: CHEMICAL & VoltME CONTROL SECT.
FLOW XI SFTT
. VALVE CODE DIAG. V*,V ACT. WORMAL. FUCT.. RELIEF TEST ELOW NUMBER CLASS COORD. CAT PASS A TYPE SIZE TYPE POS POS. REQUEST REO. DIAGRAM REMARKS
~ '
1-8510A 2 E-4 C RE 1.500 SA C SRV M1-0255-01 nigh Head St Miniflow Rtf.
1-8510B 2 E-5 C RE 1.500 SA C SRV M1-0255-01 uigh Head St Miniftow Rif 1-8511A 2 D-4 B GL - 2.000 M0 C O/C MT/o M1 0255-01 nigh Head St Miniftow Isol.
PIT 1 85118 2 D-5 B GL 2.000 M0 C O/C MT/o M1-0255-01 nigh Head St Miniflow Isot.
PIT 1-8512A 2 D-4 B GL 2.000 MO O 0/C MT/o M1-0255-01 Charging Ptg Miniflow isot.
Pli 1-85128 2 D-4 B GL 2.000 MO O 0/C MT/o M1-0255-01 Charging Pump Miniflow Isol.
PIT 1-8546 2 C-6 C CK 8.000 SA C 0 16.5 PS/CS M1-0255 RUST to Chrg. Ptsp Sutt.
CV/RR 1-CS-G350A 1 0-4 C CE 2.000 SA ' O C 16.6 CV/CS M1 0253 CLASS 1/2 BauuoARY 1-CS-8350B 1 D4 C CK 2.000 SA O C 16.6 CV/CS M1-0253 CLASS 1/2 BOUNDARY 1 CS-6350C 1 D-4 C CK 2.000 SA 0 C 16.6 CV/CS M1-0253 CLASS 1/2 BOUuoARY 1-CS-6350D 1 D-4 C CK 2.000 SA o C 16.6 CV/CS M1-0253 CLASS 1/2 BouwoARY 1 CS-8367A 1 04 C CE 2.000 SA O -C 16.6 CV/CS M1-0253 CtASS 1/2 BOUNDARY-
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~ ICR No: ;IST- ZiE.o Q - (,l : Q_
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'CPSES uu!T wo. 1 Page 5 ~
TABLE NO. 16 INSERVICE TFSTlWC/ Mv15104 3 SYSTEM: C a* * ' X CONTROL i
SECT.
FLOW XI SFTY VALVE CODE DIAG. Vtv ' ACT. NORMAL FUCT R...if TEST FLOW NUBGER CLASS COORD. CAT _PM TYPE SIZE TYPE POS POS. REQUEST REO. DIAGRAM REMARKS 1-CS-8367B 1 0-4 C CK 2.000 SA 0 C .16.6 'cv/CS M1 0253 CLASS 1/2 90UupARY i 1-CS-8367C 1 D-4 C CK 2.000 SA 0 C 16.6 cv/CS M1-0253 CLASS 1/2 80UNDARY 1-CS-8367D 1 0-4 C CK 2.000 SA 0 C 16.6 cv/CS M1-0253 CLASS 1/2 BOUNDARY 1-CS 8368A 2 D-5 C CK 2.000 SA 0 ut M1-C253 RCP Seat Inj. - Cntet. Isot. (See hotes) 1 CS 83688 2 D-5 C CK 2.000 SA 0 NT M1-0253 RCP Seat inj. - Cntet. Isot. (See notes; 1-CS-t;368C 2 D-5 C CK 2.000 SA 0 mi M1-0253 RCP Seat Inj. - Cntat. Isot. (See hotes) 1-CS-8368D 2 D-5 C CK 2.000 SA 0 NT M1-0253 RCP Seat Inj. - Cntet. Isot. (See Notes) 1 CS 8377 1 B-6 C CK 2.000 SA C 0 cv/CS M1-0253A Auxiliary Spray Check Valve (SEE APFCNDIX 8) 1 CS 8473 3 C-4 c CK 2.000 SA C o Cv/o M1-0257 BA!P Dschg.
1-CS 8487 3 C-4 C CK 2.000 SA C 0 cv/o M1-0257 BATF Dschg.
1 HV-8220 2 E-2 B GL 1.000 SO O C MT/CS M1-0255 ECCS Operation (SEE APPECIK B)
' FST PIT 1-H'f 8221 2 E-2 B GL 1.000 SO O C MT/CS M1 0255 ECCS Operation (SEE APPENDIX B)
FST PIT 1-LCV-112B 2 E-6 8 GA 4.000 MO O C MT/CS M1-0255 vCT Isot. (SEE APPE c lK B)
Pli
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