ML20126E458
| ML20126E458 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 11/30/1992 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20126E452 | List: |
| References | |
| PROC-921130, NUDOCS 9212290149 | |
| Download: ML20126E458 (77) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ - - - _ _ . _ _ _ _ . _ - . _ - . _ - _ _ _ _ _ _ _ _ _ - - _ - _ _ - _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ - - - _ _ _ _ _ _ _ _ . Attechnent 3 to U.602069 Revision 13 to the CPS Inservice Testing Program Appendix III t 9212290149.921223 PDR ADOCK.05000461-p PDR
ft-; Revision 13 Dato_ _11/30/9?m APPENDIX III REIJF1. REOUEST LISTING Revision 13 is to'roviso_and/or incorporato approval of Relief Requests 2008, 2014, 2033, 2034, 3002, and 3006. Rolief Request 2035 l is a new submittal. Submitted By: rk , d a .t Approved-By: h ks %* - l l. !-- WP: APP 3TITL
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ILLIN0l$ POWik C W Awf CLlWTON POW [k $1AllON GIW(RAL R(Liff RLQUE$i INDEX . kellef Request Description Date Date tcmarks Wader Sulai t ted Amrowed 1001 Maalaus allowable eatension for 6 15 92 6 15 92 (sevision 2) test f regency of valves and pros. Revised per SER 1002 Deleted i 2 t i I t v-WP APP 31A8
ILLIN013 MVR c(HPANT CLlW10N POWER $fAllON VALVE titl[F RIQUEST INDEK tellef Request De!,cription Date Date k engsr k s Ntsider Sutsul t t ed Apptoved 2001 Deleted 2002 test f reqency f or valve 1011 F122 3 09 68 9 30 91 (Revision 1) 2003 Deleted 2004 Test f requency for valves 15X016 A/B 6-30 87 9 30 91 2005 Deleted -- 2006 Deleted 2007 Deleted 2008 Test method for mater teg keep fitt 4 23 92 9 25 92 (Revision 3) ched valves. 2009 Test f requency f or the Manual Deluge 6 15 92 6 15 92 (Revision 2) Valves listed in lable 2009 1. Revised per SER 2010 Deleted 2011 Leak rate testing, differential test 12 13 88 9-30 9i (Revision 1) pressure, analysis of leakage rate arwi corrective action for contairvnent isolation valves. 2012 Test frequency for Aus valves 3 15 92 Note 1 (Revision 2) 1821.F041 8/c/v/F, F047 A/c ami F051G. Stroke time evaluation. 2013 Stroke time trending of the solenoid 6 15 92 . dote 1 (Revision 3) operated valves listed in Table 2013 1. _ 2016 Full-stroke exercising of check 4 23 92 9 25 92 (Revision 3) valves 1Et? F041 A/B/C, 1E21 F006 ard 1E22 F005. 2015 Deleted 2016 Deleted 2017 Deleted 2018 Test frequency for valve 1E12 F475, 3 09 88 9 30-91 (Revision 1) 2019 Deleted 2020 Deleted 202) Deleted Note 1: Acceptable per Generic Letter .89 04, Attachment 1, Position 6 WP: APP 3 FAB
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-i Itt INols POWER CC*4PANY '
CLINION POWER $1Afits VALVE R(Ll[F kt0VIST $NDIX j i Relief =, kequest Deserlptton Date Date Remarks Wmtier Sulnit1ed Approved D ercise test for valve 11A173. 3 09 88 2022 9+30 91 2023 CRD valve 112. 2 10 88 '93091 f 2024 CRD valves 126,127,139 aM 114. 3+15 92 Note 2 (Revision 1) 2025 CwD valve 138. 2 10 88 93091 1 2C26 DG valves 1 Duo 084 K. 3 15*92 Note 2 (Revision 1) 2027 Deleted i 2028 1c41 f 336 Exercise 12 13 88 9 30 91 (Revision 1) ! 2029 - Alt Leak Rate Testing to allow t
- 27 88 9 30-91 pressure drop tests.
2030 Deleted 2031 Deleted 2032 stroke tirre trending of the air 6 15 92 Note 3 (Revis t er, 2) operated valves listed in Table . 2032+1. { 2033 Test frequency and testing method 11 30 92 Note $ (Revision 1) for talves 1G33 F051 ard 1L33-f052A,0. 2034 Leak rate testing in grotos. 6 15 92 9-25 92 2035 Relief valve test supervisor 11 30 92 Note 4 requi rernent s , t 1 Note 2: Austaented testing requirenents which are beyond the scope of 10CTR$0.55a an'these coriponents are not ASME Class 1,-2 or 3. No WRC approvat required.
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Note 3: Acceptable per Generic Letter 89 04, Attachment 1, Positions 5 and 6. Note 4r Pending NRC review. .
- Note 5: Previously approved by 9-30 91 NRC $ER.
WP APP 31AB s
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__ .m. . _ . - _ ._ . _ _ _ . _ _.__ . ._. ~ _ - . -_ _ _ _ _ _ - . . _ . _____m ._~ .-. _ . - . ~ . . ~ .. b lj i tillhols Powta COMPAWT CllklOW POWER $1AI10N R HP RCLl(F REQUL$f INDlK . Relief Regxst cescription Date Date Remar k s ; h#ber Subst t t ed Amtowed 1 I 3001 Arrual pear.utenn'nt of top tearing 82087 9 30+91 (Revision 1)- t assaratures. i t 3002 flow rate ceasurennent of kage .s 30 92 Note 5 (Revision 3) 1D001PA,.ID001P6 and iD001PC. 3003 Flow rate sensurement of psys 3 09 88 9 30 91 (Pevision 1)
- 1C41 C001 A an.1 C0018.
3004 Deleted 3005 flaw for psrs 1C41 C001A and C0018 63067 9 30 91 to rm prior to awasuring/ observing psy parameters.
-p 3006 Ranges for marp flow rates and 4 23 92 9 25 92 (Revision 1) differentist petssure.
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Note 5: Previously awroved by 9 25 92 htc $ER. s WP: APP 3fA6 ; r f i' T'y84 % $ Tr'W t W " = AY*in+t. gygm'* $ 'p g WM p W+ f++f+eg 4 -y ,Wg y +qgb m +i w dg4'8 -+Peh 'k ee ms gr e ewnewwmyew 5-
I j ltt Ikols POWIN CCMAWY CL IW10N FW(R $1 AIION hD( R[Lilf Rf00($1 lNltlX IUTit Pet ent De sc r ipt ion Date Date t ener k s hisit e r sutaltted AM> roved 4001 wetd enamination of class 2 tires 7 29 to F 9 97 (kevision 1) which ere open-erded. 4002 Deleted 4003 rerform V13 examirations Fr 83WB4 T 29 68 T 9 97 (Revision 1) Code in lieu of att VT 3 arxl Vf 4 c a rwwina t i ons . 4004 hydroutic ornt Mechanitat trutd;ers; 12+28 88 7 9 92 (Revision 1) f re9mney of thupect ion, T er. t ing , arvj Corrective Ac tion WP:AI'P 31 AB _________-_-__-_____-____----_--_-__----____L-_--_------__._________.--_-__--__---_
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-R* quest Description Date Date Remarks !
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5001 keplacement tsot t f rig seteriet 10 20-87 - Disapproved j
$002 Reptocenent parts for conponents 10 20 67 +- Olserproved -
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I i ( ILL11101S POWER COMPAllY Clinton Power Station , ASME Section XI Rollef Request i RELIEF REQUEST 1001 (Revision 2) c All pumps and valves that are doMPollE!1T"ItiFORMATIO!1( a ' required to perform a specific
* ' 4E ' function in shutting down the reactor or in mitigating the
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consequences of an accident and are listed in Table I and Table II of the IST Program except safety and relief valves and valves not tested at three (3) month or shorter intervals. e g , . The ASME Code Section XI,
~ CODElREQUIREMENTM 4 :n "
Subsection IWP-3400 requires O nyc 4 < performing an inservice test on cach pump nominally overy throo
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(3) months. Subsection IWV-3411 requires that valves be exercised and stroke timed at least onco every three (3)-months. Subsection IWV-3521 requirca that check valves be exercised at least onco every three (3) months. (' '- e .. .,. jpgs 1. w sa The ASME Code Section XI, LRELIEFSREQUEST/ JUSTIFICATION? various subsections mentioned
- e 'c, Mt;f , 4 4 ' above, specify the test frequency . interval but . do not specify any allowablo extension. Often there are operational' t constraints or other valid concerns that make it impractical _ to perform testing within the code specified interval. It would be impractical and burdensome for ' CPS to strictly ~ follow tho*Codo esting intervals without extensions to cover necessary deviations.
Clinton Power Station Technical Specification 4.0.2 specifies a maximum allowable extension not to exceed 25% of the surveillance interval. CPS proposes to have a 25% extension which is reasonable
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for most Code specified testing and provides an acceptable lovel of quality and safety. This is. consistent with Technical Specification 4.0.5.c.. , 1: . . _ ;; ,
- Illinois Power- Company will ALTERNATE [ TESTING} PROPOSED 4, uti1izc. CPS Technica1 Specification 4.'O.2 allowable extension with the :specified interval for all pumps and valves except safety and relief valves
- and valves not tested at three (3) month or shorter intervals.
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- ILLIll0IS POWER COMPANY CLINTON POWER STATI0tt.
( SECTION XI RELIEF BEQUEST RELIEF REQUEST 110. 2002 (Revision 1) COMPO!jENT INFORMATI0!i This Control Rod Drive (CRD) Water Header Check Valve (IC11-F122) is a containment isolation' valve and prevents the back flow of reactor water when the CRD Pumps are accured. It is an ASME Section III Code Claos 2. Section XI Category A/C valvo. It is a 2 inch check valve and is highlighted on the attached drawing. CODE REQUIREMENT _ The' ASME Code Section XI, Stibarticle IVV-3521 requirca that this valve be exercised every three (3) months. - RELIEF REQUEST / JUSTIFICATION Illinois Power Company requests relief from the Code requirementa ' ' for the following reasono: ,
- This check valve is a containment isolation valve which provides
( ' . drive watcr to the hydraulic control units and seal flow to the . reactor recirculation pumps. This is a normally open valve and. cannot be tested during normal. plant operation or cold shutdowna since testing.this valve requires that the CRD system be shutdown causing the control rods' motion to be prevent ed and stop? ing ceal fl.ow to the reactor recirculation pumps. Although the reactor recirculation pumps are not required for safe shutdown of the plant, these pumps are used to assure uniform temperat.ures are maintained in the vessel during cold shutdowns. Exercising this valve would also allow air to enter the CRDs which would - require substantial venting of the' system to remove. ALTERNATE TESTING PROPOSED Illinois Power Company will exercice this valve during refueling outages. k 1 l
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ILLINOIS POWER COMPANY 4 l CLINTON POWER STATION . SECTION XI RELIEF REQUEST s.
-_. j T , RELIEF REQUEST NO. 2004 .
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- COMPONENT INFORMATION
' . , 1 i The Fuel Fool Emergency Makeup. Valves (ISX016A/D) piovide. I
. em'ergency makeup water to the Fuel Pools from,the lake. The ASME Section III Code . Class 3, Sectilon XI Category.B valves.y are -
They are 2i inch motor operated gate valves and are highlighted on the attached drawings. -
, CODE REQUIREMENT .
The ASME Code Sectl.on XI. Subsection IW-3411 requires that these valves be exercised and stroke timed every throu (3) months. . i RELkEFREQUEST/ JUSTIFICATION' .. , Illinois Power Company requests relief'from the Code requirements for the following reasons:
. Testing these valves will allow lake water into th'a fuel pools -
thereby affecting the chemistry of a large quantity of water in - j the pools. Cleanup of the fuel pool water vill generate additional solid radwaste and delay the piant'startup. Tc' sting
. thnse valves during refueling outages wi);l ensure that there is sufficient time to accomplish these activities. .
-ALTERNATE TESTING PROPOSED
. Illinois Power Company will exercise and stroke time these valves during refueling outages. .
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i ( : ILLINOIS POWER COMPANY - ' Clinton Power Station . ASME Section XI Rollef Roquest RELIEF REQUEST 2008 (Revision 3) l I r
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,. Valve 1E22-F006 in located ,
between liigh Pressure Core Spray fCOMPONENT.INFORMATIONA
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4 . (llP) water-leg ? ump and the main llP injection Itne. It is a 2- ; inch stop-check valvo, ASME Section III Class 2, Section XI Category C. It is circled on the attached drawing "A". , Valves 1E12-F085A,B,C and 1E21-F034 are located between the water- : leg pumps and their respectivo injection lines (Rosidual Heat Removal (RHR) and Low Pressuro Core Spray (LP)). They are ASME Section III Class 2, Section XI Category C valves. They are 2-inch stop-check valves of identical design. As their piping configuration is similar, only 1E21-F034 is circled on the attached drawit'g "D" . ( , < .-
, The ASME Code, Section XI, JColiE 5REQUIREMENTSb
~ '
, '. V: ic Subarticle IWV-3520 requires
,' m 'i < 4 , that these valves be full-stroke -
exercised individually every three (3) months. _ .. -. ... ..i -. Illinois Power Company. requests DRELIEFJREQUEST/ JUSTIFICATION % ^' relief from the Code 6J2 , requirer ants for the following , reasons *
, The abovo groups of valves; although located in separato systems, have similar configurations; they are check' valvos located in series with other check valvos and no toot connections provided between them to permit individual valve testing.
Each of those valves has a separato check valvo in' series. The two check valves in series, although not required by design or safety. analysis, provide an added assurance that tho :high pressure. Emergency Coro Cooling System (ECCS) line will not damage the lower - pressure water-leg piping. Illinois Power Company considers these two check valves in series as a single entity and will test them as such.
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Illinois Power Company conaldern r i : those two check valves in corico
! < iA1/rEIUTATE TESTING;' PROPOSED! .
'm a singic ontity and will perform the closure tant overy three -(3)
- months ao a single unit. Acceptanco critoria will be octablichod-i and in the event of not mooting this critoria, appropriato action will be initiated for tho entity and the deficiency will be corrected.
The open exercise of those valvoo will also be performed ovary three (3) months. 8 (. ' l F l b
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\ II,LillOI S POWElt CO!4 pally Clinton Power Station AS!4E Section XI Relief Requent RELIEF RI: QUEST 2009 (Revision 2)
These Manual Delugo Valves (cee CO!4POllEt1T I!1PORl4ATIO!L Table 2009-1) provide chutdown service water to the Standby Gao Treatment Charcoal Dedo, the fickoup Air Filter Package, and the Supply Alt Filter Package. They are all AS!4E Section III Code Claus 3 valves. Valves ISXO71A/B, 073A/B, 07 4 A/11, 076A/D, 105 A/11, and 107A/11 are ASliE Section XI category D, 3 inch motor operated gate valves. Thene valven are highlighted on the attached drawing. The ASME Code Section XI, CODE REQUIRE!4EtiTS Subarticle IWV-3411 and IWV-3521 require that thene valves be exercised and stroke timed every three (3) months.
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Illinoin Power Company requento
\ relief from the Code RELIEF ' REQUEST /ilUS'?IFICATIOli requirementa for the following rencons:
Tenting thene valves will flood the charcoal beds of the Control Room llVAC System. This would cause these trains to become inoperable and would require replacement of the charcoal. In order to avoid flooding the charcoal beds or removal of the charcoal, the Shutdown Service Water System main header would be required to be drained and declared inoperable. The Shutdown Service Water System provides cooling water to ECCS systems and various other cyctema required to be operable in all moden of operation. Both of the above options are not pocaible during cold shutdown testing. The first option would damage the charcoal beds which would require the charcoal. to be removed and replaced. This testing would require the Control Room IIVAC system'to be declared inoperabic. The second option is not possible because the plant must be shut down if the Shutdown Service Water header is drained. Illinoin Power Company will ALTERNATE TESTIIIG PROPOSED perform the required tests during refueling outagen.
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LLLINOIS POWER COMPANY CLINTON POWER STATION SECTION_XI RELIEF REQUEST j RELIEF REQUEST NO. 2011 (Revision 1) COMPONENT INFORMATION , All Section XI, Category A and A/C valves which require a leakage test per IWV-3420 as identified in Illinois Power's Pump 6 Valve Testing Program Plan. . CODE REQUIREMENT The ASME Code Section XI, Subsection IWV-3420, Valve Leak Rate = Testing, requires leak race testing for valves where/ leakage is limited to a specific amount in fulfillment of their safety function. Subsection IWV-3423, Differential Test Pressure, requires leak rate testing be performed with the system pressure differential in the same direction as it is when the valve is performing its function. Subsections IWV-3426, Andlysis of Leakage Rate', and IWV-3427, Corrective Action. require i establishing the maximum permissible leakage rate and. evaluating the test results for individual valves. RELIEF REQUEST / JUSTIFICATION Illinois Power Compc7y requests relief from the Code requirements
. for the following reasons:
A For all valves except Excess Flow ' Check Valves: The Nuclear Regulatory Commission has concluded that the applicable-leak rate test procedures and requirements for containment isolation. valves are determined by 10CFR50,-Appendix J. The ASME Code requires individual valve leak rate tests, while 10CFR50, Appendix J allows testing of valves in_ groups. In-many cases, there are no provisions to leak rate test inboard and-outboard containment isolation valves individually. There fo.re , the maximum permissible leakage rate for individual valves cannot be specified. As the purpose of these valves is to isolate che -- containment, testing in grpups, i.e., by containment p_enetration, l would verify the integrity of the containment boundary. Also, Section X1, IWV-3427(b), specifies additional requirements-for valve sizes of six inches and larger, beyond,the requirements of IWV-3427(a). These requirements involve the use of leak rate trending in determining subsequent test inrcrvals. However, . industry data has shown'that the trending of lesk- rates is not a meaningful way to predict failure. For Excess Flow Check Valves Excess Flow Cneck Valves are not required.to be individually leak race tested (Type B or Type C) per Clinton Power Station (CPS). I Technical Specification or 10CFR50, Appendix J. However, excess flow check valves are included within the Integrated Leak Rate Test (ILRT): boundaries. Although the ILRT does not measure-m / individual valve leakage races, the satisfactory completion of the ILRT verifies the-overall function of these valves. Section.XI/ISI/18 -
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JLL1NOIS POWER' COMPANY CLINTON POWER STATION - SECTION XI RELIEF REQUEST RELIEF REQUEST NO. 20ll.'(Continued)
~
-ALTERNATE TESTING PROPOSED For all valves except Excess Flow Check Valves.
Illinois- Power Company will utilize 10tFR50, Appendix J and CPS Technical Specifications to determine the. differential test pressure for these containment isolation valves. The maximum E permissible leakage rate for a specific containment penetration (inboard and outboard isolation valves combined) will be-specified instead of-a leakage rate-for individual valves as required-by IWV-3426, Analysis of Leakage Races. The, evaluation of test results will be based on the penetration leakage rate (inboard and outboard' isolation valves combined) instead of on the individual valve leakage rate as required by IVV-3427, , Corrective Action. , The trending requirements of IWV-3427(b) will not he Laplemented since meaningful trends cannot be established. For Excess Flow Check Valves . No separate test or evaluation either by individual valve-or by- j
. . penetration will be performed on excess flow check valves. These i valves -are included within the Integrated Leak Rate Test -(ILRT) i boundaries.
i 1 L' . L 1 l l. i i: - i , i - I
-Page-2aof 2 Section XI/ISI/19 ,
l k ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2012 (Revision 2) These Autonatic Depressurization System valves (1821-F041B/C/D/F, COMPONENT?INFORMATION 1B21-F047A/C, 1B21-F051G) depressurize the Reactor Pressure Vessel to allow Low Pressure Core Spray and Low Pressure Coolant Injection Systems to inject water into the reactor. They are ASME Section III Code Class 1, Section XI Category B/C valves. They are 8 in. x 10 in, safoty/ relief valves. The ASME Code Section XI, CODE REQUIREMENTS' Subsection IWV-3411 requires that these valves be exercised and stroke timed every three (3) months. Section XI, Subsection IWV-3417(a) requires trending the stroke time test results and taking appropriate corrective action. Illinois Power Company requests Code k ! RELIEF REQUEST /JUSTIFICATIONT relief from the
. requirements for the following reasons:
These valves cannot be exercised quarterly during power operations because failure of a valve .in the open position would place the plant in a LOCA condition. These valves should not be exercised during cold shutdowns in order to reduce the number of challenges to safety / relief valves as recommended by NUREG-0737 and a recent study on the subject (BWR Owner's Group Evaluation of NUREG-0737 Item II.K.3.16, Reduction of Challenges and Failures of Relief Valves). The reactor pressure is not utilized when testing these valves. A handswitch is utilized with a special tool which reduces the valve speed to avoid damaging the seating surfaces and the disk. Based upon CPS operating experience, Illinois Power Company will consider these valves as rapid acting valves. As these . valves stroke rapidly, measurement of the stroke time of these valves to the nearest second per IWV-3413 (b) means that a very small increase in stroke time could result in an extremely large percentage of change. The verification that these valves meet a specified maximum stroke time of a relatively short duration provides adequate assurance of operability of these valves. (
- . _ ..~ . . . _ _ _ _ . - _ _ . _ _ _ . _ . . _ _ _ . . _ . . . _ _ _ .
, Illinois Power Company will-exercise and-stroke time these-( / ALTERNATE STESTINGi: PROPOSED ;
valves during refueling outages. Illinois Power company will assign a maximum stroke time of two (2) - seconds for = these valves. If this limiting strokc~ time is exceeded, the valve will be declared inoperable and corrective action will'bc taken. This is in conformance with NRC Generic Letter 89-04,. Attachment 1 Position 6. 4
I ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2013 (Revision 3) These valves are various rapid
-COMPONENT INFORMATION' acting valves (see Table 2013-1) with various functions. They are ASME Section III Code Class 2 and 3, Section XI Category A and B valves. It should be noted that changes to plant design may result in revisions to Table 2013-
- 1. These changes may be implemented prior to submittal of the revised table to the NRC.
The ASME Code, Section XI, CODE-REQUIREMENTS Subarticle IWV-3417(a) requires trending the stroke time results for these valves and taking appropriate corrective action. Per Generic Letter 89-04, these RELIEF REQUEST / JUSTIFICATION: valves are defined as rapid
\ acting, where measurement of the stroke time of these valves to the nearest second per IWV-3413 (b) means that a very small increase in stroke time would result in an extremely large percentage of change. The verification that these valves meet a specified maximum stroke time of a relatively short duration provides _
adequate assurance of operability of these valves. Illinois Power Company will ALTERNATE'TESTINGfPROPOSED~ assign a maximum stroke time of two (2) seconds for these valves. If this limiting stroke time is exceeded, the valve will be declared inoperable and corrective action will be taken. e l
ILLINOIS POWER COMPANY ( CLINTON POWER' STATION SECTION XI RELIEF REQUEST Valve No. Size Valve No. Fing - 1CM011 , 3/4 1PS022 1/2 1CM012 3/4- 1PS023 1/2 1CM022 3/4 1PS031 3/4 1CM023 - 3/4 1PS032 '3/4 1CM025 3/4 1PS034 3/4 1CM026 -3/4 1PS035 3/4 1C:{047 3/4 1PS037 3/4 1CM048 '3/4 1PS038 3/4 IE12-F060A 3/4 1PSO43A 3/4 1E12-F060B 3/4 1PSO43B 3/4 1E12-F075A 3/4 1PSO44A 3/4 1E12-F075B 3/4 1PSO44B 3/4 1E31-F014 1 1PSO47 3/4 1E31-F015 1 _1PSO48 3/4 1E31-F017 1 1PS055 1/2
.1E31-F018 1 1PS056- 1/2 1PS004 3/4 1PSO69 1/2 1PS005 3/4 1PS070 1/2 1PS009 3/4 1VR035 3/4 1PS010 3/4 1VR036 3/4 I' 1PS016 1/2 IVR040 3/4 l 1PS017 1/2 1VR041 3/4 1WX019 2 1WX020 2
.. - -. . -~ . - -. .. . - - -. . - - _.
ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2014 (Revision 3) These testable -check valves
~
COMPONENT INFORMATION (1E12-F041 A/B/C,1E21-F006, and 1E22-F005) provide isolation from the reactor coolant system and the emergency core cooling systems (Residual Heat Removal,_ Low Pressure Core Spray, High Pressure Core Spray). These valves-are ASME Section III Code Class 1, Section XI Category A/C valves. Valves 1E12-F041 A,B, and C are 12" diameter and valves lE21-F006 and 1E22-F005 are 10" diameter. All of these valves are non-slam check valves. One of these valves (1E12-F041A), which is typical of the group, is circled on the attached drawing. The ASME Code, Section XI, CODEEREQUIREMENTS Subsection IWV-3520 requires that-these valves be exercised every three -(3) months unless such operation is not practical during plant operation. In this situation, the valves may be part-stroke exercised during plant operation and full-stroke exercised during cold shutdown. Exercising these valves on a RELIEF REQUEST / JUSTIFICATION- three month frequency using the emergency core cooling system
- . pumps to inject water-into the i reactor is not 'in the interest of plant safety, because this cooler water would create an undesirable power transient. _In'. addition, neither the Low Pressure Core Spray nor Residual Heat Removal pumps are capable of opening their injection valves against full reactor pressure. Mechanically exercising - these valves during reactor operation is not practical because they are located inside the drywell and-access is restricted due to radiation conditions.
Mechanically exercising these valves on a cold shutdown frequency as allowed _ by the ASME Code is not practical. because the air ! operator is not designed to_ perform a full stroke test. Although. !~ the air operator can be removed to perform the full stroke test,. this is a significant maintenance activity and could interfere with work which is necessary to restore the plant to serNice. This-would create an unreasonable hardship for Illinois Power Company. l l D
Using pump pressure'to exercise-these valves-during cold shutdown is also not in the interest of plant safety.- Although tenparature could be matched - fairly closely between the inj ection- f source (emergency core cooling systems) and the reactor,-a minor thermal mismatch between these temperatures creates'an undesirable effect-on the fatigue life of the reactor nozzles. In addition, the injection lines associated with the residual heat removal . system nozzles are not_ equipped with internal spargers.- General Electric Service Information Letter 401 identifies problems
~
in injecting wator through this flow path and the potential damage to nuclear instrumentation or fuel assemblics which could occur if this flow path were used for other than emergency' conditions. Illinois Power' Company will full ALTERNATE TESTING PROPOSED stroke exercise- the~ valves during refueling- by measuring the torque required to lift the disc and then move the disc through a full stroke. l l t ! ? l l c-
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-w_ z ILLINOIS POWER COMPANY CLINTON POWER STATION SECTION XI RELIEF REQUEST.
( RELIEF REQUEST NO. 2018 (Revision 1) COMPONENT INFORMATION Reverse flaw check valve lE12-F475 is a containment i' solation valve- and provides necessary thermal relief for the Residual Heat Removal System piping between valves IE12-F008 and lE12-F009. It is an ASME Section III Code Class 2, Section XI Category A/C valve. It is a one
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inch check valve and is highlighted on the attached drawing. CODE REQUIREMENT . l Th'e ASHE Code Section XI, Subar.ticle'IWV-3521 requires that this valve be exercised every three (3) months. RELIEF REQUEST / JUSTIFICATION Illindis Power Company 'reque'sts relief from the Code requirements for t,he following reasons: } This valve is installed in the piping of the shutdown cooling ' ' - mode of operation of the Residual Heat Removal System and is (k loca.ted inside the drywell. Daring normal operation, this line stem. Thethis is pressurized by the reactor recirculation sy. Therefore, valve is not designed to open against_this pressure. valve cannot be exercised quarterly. - This valve cannot be exercised during cold shutdowns since the shutdown cooling mode of the Residual Heat Removal System will be inservice. As this line is pressurized at all times during the cold shutdowns, an' exercise test is not feasible. In refueling - outages, the shutdown cooling and reactor recirculation can be isolated prior to reactor startup to facilitate the operating of this valve. ALTERNATE TESTING PROPOSED Illinois Power Company will exercise this valve during refueling outages. (
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ILLINOIS POWER COMPANY CLINTON POWER STATION SECTION XI RELIEF REQUEST ( RELIEF REQUEST NO. 2022 . 4 l COMPONENT INFORMATION Valve lIA175 is a % inch checkThe valve which functions as a attached P&ID depicts the
. containmedt isolation valve.
configuration of this valve in the system. CODE REQUIREMENT . The ASMY Code Section XI, Subarticle IWV-3521 requires check- ; valves to be exercised to their safety position .every three (3) ; months. , 1 l RELIEF ~ REQUEST / JUSTIFICATION Illinois Power 'ompany C requests relief from the Code requirements- i because there is no way to functionally test this valve withoute performing a-leak rate test. . No direct containment leakage path is available through this valve. The leakage path through t:21s^ , valve is limited by the pipe cap and the piping connections to the actuator. As the probability for lea?, age through these y
-(- connections is small, it appears to be excessive to leak test l this penetration on' a quarterly or cold shutdown basis.-
ALTERNATE TESTING PROPOSED' Illinois Power Company will satisfy che exercise reqOirement for l this % inch check valve upon-performance of the leak rate test. i The frequency of the exercise 1 test will be revised to coincide i with the leak rate frequency, i.e., 2 years. 9 9 i t k l Cnn*4nn YT I T R T l ') A -
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ILLINOIS POWER COMPANY CLINTON POWER STATION SECTION XI. RELIEF REQUEST. ( RELIEF REQUEST No. 2023 COMPONENT INFORMATION tvu - Valve,ll5 (typical of.145 each) is the control rod drive. accumulator supply check valves refer to attached drawing. These are Category A/C %-inch check valves. These valves allow the
- individual accumulators to be charged with sufficient pressure to scram the appropriate control rod drive upon loss of CRD header pressure. ,With a loss of header pressure, these valves must close to maintain enough. pressure in the accumulator to insert the CRDs.
CODE REQUIREMENT Section XI, Subarticle IWV-3521 requires check valves to be exercised to their safety position every threek(3) months. tested every 2 IWV-3420 requires Category A v years to verify the component',alves to be leas ability to perform function. RELIEF REQUEST / JUSTIFICATION ' Illinois Power Company requests relief from the above Code (' - . requirements because it is not' feasible to individually the reverseexercise flow these valves wi'thout securing the CRD pumps, exerc.ising *and leakage tests. of these. check valves- will be satisfied by the performance of an accumulator pressure drop This test, with the pumps secured .during refueling outages. test will verity the valve is closed by monitoring ~the. . accumulator pressure waich would indicate any leakage past the check valve. . ALTERNATE TESTING PROPOSED Illinois Power Company will satisfy the leakage and exercise e tests,for these valves-upon performance of the accumulator ' pressure drop test on a refueling outage frequency. e
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- ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2024 (Revision 1) tm e s W t % ~ & ;! w b y m Valves 1C11-126,_ 127 and 139
$qCOMI!dNES$ M wd @ 'fi yg g;9 W , (typical of 145 each) are power Q sggdM $$ % g g v s G7:;% operated valves which actuate (open) to scram the control rod drives. Valve 1C11-114 (typical of 145 each) is the scram discharge check valve. Refer to the attached schematic drawing for the system.
Valve 126 is a-power. operated, category B, 1" diaphragm operated control valve. This valve opens to allow flow to scram the control rod drive. Valve 127 is a power operated, Category B ,- 3/4" diaphragm operated control valve. This valve opens to allow flow to exhaust from the centrol rod drive to the scram discharge volume. Valve 13 9 ~1s a power operated, Category B, pilot air valve. This valve opens to relieve pressure to valves 126 and 127-which causes them to open. Valve 114 is a 3/4" check valve,- (\ Category C. This valve opens to allow flow to the scram discharge volume.
;jM Tn?MFNC pg -IWV-3411 ASME Section XI, Subarticles CODE and IWV-3413 require ML ~MEQUIREMENTSht$$
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$lgg Power %$f M valves to be operated exercised and stroke time tested every 3 months. 'IWV-3521 requires check valves to be exercised on a 3 month frequency, as well. These valves are not ASME Class 1, 2, or 3, but are included in the CPS Inservice Testing Program since the system performs a.
safety function. This relief request does not require NRC approval. These va1yes M_ M@rA &nNdMdaR ETSIG^ operate simultaneously ' when - a sc2 am
!GREUEEE$I?EQUESTJJUSTIVICnTIlONH
][yy% 1%Qyf%Q3$aggy;;p G$MOMM AsM@MNMS$hgwMO signal; is present. As these valves are skid mounted with no provisions for testing, it- is -
not-practical to individually test each valve without extensive-modifications, which would create a financial hardship to Illinois Power Company. The current testing, per Technical Specification 4.1.3.2, monitors individual rod scram time. - This testing does not - measure stroke time for the power operated valves or . provide specific exercising verification for either the pow- perated or
. check valves. However, it does assure that each valve functions
( properly to allow the rod to move _to its safety position in the- , required time.
, ,' . - m e;; 4 ..g s w w-s w Testing of the control rod .drivo .-
( ESNNG;?PROl per Technical Specification # IALTEitIWrEd:w y; yr - w g3.g ; g{0$EDhj MP " 4.1.3.2 will be performed -in
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lieu of tho' code requirements. The Technical- Specifications require all rods to be tested following any core alterations and any prolonged outages (120 days). Ton percent .of the rods are tested on a rotating basis ovary 120 days and any rod requiring, maintenance is tested upon completion of the work. - This is in accordanco Witti NRC Generic Lotter 89-04, Attachment 1, Item 7. 5
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- ILLIt10IS POWER COMPAliY CLI!1T011 POWER STATIO11
- SECTIO 11 XI RELIEF REQUEST
( RELIEF REQUEST 140. 2025 COMP 011Et1T It1 FORMAT 1011 , Valve 138 (typical of 145 each) is aValve %" Category C check valve on 138 is the CRD cooling the CRD hydraulic control units. water check valve which must'close upon reverse flow to allow the CRD to insert. Reverse flow through this check valve could See attached drawing. it: pair the function of the CRD. CODE REQUIREMENT Section XI, Subarticle 1WV-3521 requires check valves to be exercised to their safety position every three (3) months. RELIEF REQUEST /JUSTIFICATIOJ Failure of these valves to reverse flow exercise w'ould be identified by performing a " notch" test. The notch test is required per Technical Specification 4.1.3.1.2 which moves each withdrawn CRD one notch every 7 days and every 24 hours if one CRD is immovable as a result of friction. The failure of valve 138 would be determined by the inability to meet the acceptance , criteria of this surveillance. The CRD A would " double-notch" if "d6uble-notch" is'where ( valve 138 did not properly exercisc.- the CRD would not be able to move one notch at a time. ALTER!1 ATE TESTING Exercise valves by performing a " notch" test as described above (i.e., complying with Technical Specification 4.1.3.1.2) .
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-( ILLINOIS POWER COMPANY Clinton Power Station ,
ASME Section XI Relief Request RELIEP REQUEST 2026 (Revision 1) WM@0$#b M6E4MEYRE3MSi! Diesel generator (DG). air start valves,1DG008A-K are 1.5" power
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! COM PONENT$$N Fp@RMATIDNfl;yjbrpydB dM@@NMN@@!$ operated, Category B valves required to open to allow air to flow to the air motors which start the emergency Diesel Generators to supply back-up power for the plant.
Section XI, Subarticles PMdiSSQQuh 6? gg g gy .ASME IWV-3411 and IWV-3413 require yCOQEgEgyIREMW@gS@Qvegglg@7ggy valves to be
'. p p M g p Fit p eM@egpW; power operated exercised and have their stroke time measured every three (3). months. These valves, however, are not ASME Class 1, 2, or.3, but are included in the CPS Inservice Testing Program since the system performs a safety function. This ralief request does not require NRC approval.
( p@%Wl'!MessMMffiFVdMMP7QMW . These valvec , are t,otally ZIEFgREQUEST JUSTIEIOhTION .1 enclosed solenold valves with no
@EsM!MM3MIMMM5IWddN M positive means of determining valve position. It is not practical to record individual stroke time for these valves without extensive modifications, which would create a financial hardship to Illinois Power Company. Technical Specification 4.8.1.1.2 requires each diesel' generator to be tested at least every 31-days. These tests are designed--to test the diesel generator as a unit, but do not specifically verify actuation of each individual valve.
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WidME'En@WMMUNEdMimyg No stroke time testing of these air start valves will be MALTERNATEATESTINGMPROPOSEDW!&& performed. The air gauge c WSRM@65 MEQNAN@$$Nv's@$fM upstream-of each valve will be monitored to verify that a pressure drop has occurred :which-indicates that the valves have opened. In addition, diesel generator start times are monitored closely. This test will-be performed on a monthly frequency. 4
ILLINOIS POWER COMPANY CLINTON POWER STATION SECTION XI RELIEF REQUEST
' RELIEF REQUEST NO. 2028 (REVISION 1) ,
COMPONENT INFORMATION Valve IC41-F336 is a check valve' downstream of the Standby Liquid Control (SC) pump and is physically located inside the drywell. - This is an ASME S6ction III Class 1, 'Section XI Category A/C, a 4-inch check valve.- The valve is circled on-the-attached drawing.- j CODE REQUIREMENT The ASME Code, Section XI, Subarticle IWV-3521 requires that this check valve be full stroke -exercised every three (3) months. b RELIEF REQUEST / JUSTIFICATION < l Illinois Power Company requests relief from the Code requirement 1 for the following reasons: > This check valve it; downstream of the explosive injection valves- . which are only required to be opened during refueling; outages. ' The check valve is totally enclosed without any provisions ~for exercising the valve externally. ALTERNATE TESTING PROPOSED , s Illinois Power Company will full stroke exercise this check valve ( every refueling outage. The open direction exercise will b6 - verified with system flow and the closed direction exercise will be verified with a leakage test. i F l i I ! ( - Section XI/ISI/40
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F-ILLINOIS. POWER COMPANY CLINTON POWER STATION SECTION XI RELIEF P.EQUEST
- [ j
' RELIEF-P.EQUEST FO.2029.
COMPONENT INFCM'ATION_ Various'Categcry.A/C check val.ves whoec-function is'to hold l pressure for a specified- time in an air accumulator / receiver. .--q l See attached list.- ' CODE REQUIREMENT _ The ASME Code Section XI,-Subarticle IWV-3424,. specifies-the- .! methodology to be used for leakage testing. l
-J
-RELIEF REQUEST /JUSTIFICATIO_N l the Code requirements Illino s Power Company requests re..ief froct ]
for-the following reasons: The design of these piping. systems does not facilitate the. , measuring of' actual leak rate through these check: valves.
-ALTERNATE TESTING PROPOSED !
Illinois Power Company will leak test these check valves as. g follows: .
. i k In: lieu of monitoring actual leakage rates throughi cach chec valve, a pressure drop- test .over a -specified timeiwill: bei performed.- This pressure drop. test will not only verify the check valve has seated but'will also: verify,the.. integrity of the!
piping system. 1 u-. l. I' a
-. -_. ._ _. _ "V
ILLIMOIS POWER col".PANY CLit! TON POWER STATION SECTION XI RELIEF REQUEST RELIEF REQUEST No. 2029 A t t a c htr.e n t 1 1 B 21 -: v _' 9 f> 1B21-F039C IB21-F039D 1821-F039E 1B21-F039H 1821-F039K IB21-F039S - 1DC168 1DGl69 1DG170 1DGl7L 1DG172 1DGl?3 ( 1
( ILLINOI POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEP REQUEST 2032 (Revision 2) This Relief Request refers to COMPONENT _INFORMATION Power ( Air) Operated valves with a stroke time of 10 seconds or less (see Table 2032-1). It should be noted that changes to plant design may result in revisions to Tabic 2032-1. These changes may be implemented prior to submittal of the revised table to the NRC. The ASME Code Section XI, CODE. REQUIREMENTS.. Subarticle IWV-3417 (a) requires increasing the testing frequency to monthly for a 50% increase from the previous stroke time test. ( Per Generic Letter 89-04 these RELIEF REQUEST / JUSTIFICATION valves are defined as rapid acting (with a normal stroke time of less than 10 seconds), where a 2 second increase can cause the testing frequency for the valves to be increased from quarterly to monthly. CPS's operating - experience has shown that when placed on increased frequency for minor increases in stroke time (1 - 2 seconds), none of these valves were found to have a physical problem and all ^ were subsequently returned to normal frequency.
' Illinois Power Company prol.oses ALTERNATE 1 TESTING PROPOSED : to evaluate the test results for the air-operated valves on Tatle 2032-1 in accordance with Generic Letter 89-04, Positions 5 and 6, and the Minutes of the Public Meetings on Generic Letter 89-04, page 26, Response to Question 40. Specifically, CPS has established a reference value for each valve in Table 2032-1 based upon each valve's performance history and average stroke time when it is in good condition and operating properly. Should any valve's stroke time increase by more than 50% from the valve's reference value, CPS will concider this to be an indication of potential valve degradation and increase the valve's testing frequency.
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( Should any valvo'n otroko tino increaso beyond the valvo's limiting ' stroke tino valuo, the valve will bo-declared inoperable. 2 2 Ao this position in in accordance with the positions. stated in NRc- .i Generic Letter 89-04, no further HRC approval is rtquired. t i t i i e k r i d } 3 e
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1SA031 1SX010A ,
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ISX209 , (^ IVQ002 1vo003 IVOOO4A i IVQ004B 1VOOO5 1VR001 A 1VR0018 ' 1VR006A ; IVR006B 1VR007A + 1 1VR007B-i k s
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6 ILLINOIS POWER COMPANY Clinton Power Station ASME Section X1 Helief Request RELIEF REQUEST 2033 (Revision 1) Valves 1G33-F051 and 1G33-COMPONENT INFORMATION FOS 2A/B are the injection check valves-which complete the flow path between the Reactor Water Cleanup (RT) System and the Reactor Pressure Vessel. These valves are ASME Section III Code Class 2, Section XI Category B valves. They are 4-inch check valyco of identical design and are circled on the attached drawing. The ASME Code, Section XI, CODE REQUIREMENTS Subarticle IWV-3520 requires that these valves be full-stroke exercised individually every three (3) months. 1G33-F052A/B are parallel valves RELIEF REQUEST /JUSTIFICATICH in the piping system and both of these valves ar6 in series with 1G33-F051. These valves are located in series with no test connections provided totween them to permit individual valve testing. i These valves cannot be individually exercised every three (3) months since they are located in the Gteam Tunnel and physical access is restricted during normal plant operation d',m to the high radiation-field in this area. Testing these valves during cold shutdown will either require the Reactor Water Cleanup -(RT) System to.be out of service or_will require flow to be bypassed to the condenser. Testing these valves with RT system flow bypassed to the condenser may create spurious dif ferential flow nignals and may cause containment isolation valves in this system to isolate and subsequently trip the RT pumps, which will=likely rhquire filing a
. Licensee Event Report (LER). Either method will cause the RT system to be out of service and create potentini delay for_ plant
- startup. This will cause unnecessary hardship for Illinois Power .
Company without any significant gain in safety. ALTERNATE TESTING PROPOSED. Illinois Power will test.those valves on a refueling frequency using either a sample disassembly and inspection program or a non-intrusive method. gg'g--spe+-gaay w w-e +-9g- rmmy-+--rm- qtv e g-'-g+-aTje-tw'w. Hf
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\' ILLIllOIS POWER COMPA!1Y Clinton Power Station ,
ASME Section XI Rollof Roquest
-l RELIEF REQUEST 2034 i
+
'Q ^ twi fon XI, Category .A_ .
.COMPollENT INFORMATIONL , d if y v J anos luolation valvos A j e b h wqMre a leakago test por.
@ = up an identified in Illinois Power's Pump & Valvo Testing yyoqram Plan.
4 The ASME Codo Section XI, CODE ~ REQUIREMENTS 1 Subsection IWV-3420, Valvo Leak ' Rato Testing, requiros _loak rato testing for valvos whero leakage
-is limited to a specific amount in fulfillment of. their safety function. Subsection IWV-3423, Differential Test pressure, .
requires leak rato testing be performed with the system proscuro differential in the same direction as it is when the valvc is performing its function. ( , _
._ 7 Illinois Power Company requests RELIEF REQUEST / JUSTIFICATION ro110f from- .the Codo
- requirements for g tho - following m~ m roanonst ,
The Nuclear Regulatory Commission has concluded that the applicable t leak rato test proceduros and requirements for containment isolation valves are determined by 10CFR50, Appendix J. The ASME- , Codo requires individual valvo leak rate tests, while 10CFR50,
- Appendix J allows testing of valvos in-groups. By establishing conservative acceptance critoria- for a valve group (containment-ponotration) such that nono _ of -tho - valves can be significantly >
degraded, considerable savings in personnel radiation exposure and scheduling flexibility can be achieved. This approach is = of ' bonofit to Illinois Power and providos equivalent levels of quality and safety to those achieved through-individual testing. As the purpose of those valvos is to isolate the containment,. testing in. , groups, i .e., by containment ponotration, would verify the integrity of the containment boundary. By catablishing conservativo acceptanco critoria, the condition "of the valvos-within reasonable limits can also be established by this method. The maximum permissiblo-loakago JALTERNAT@ TESTINGfPROPOSEDi rato for a specific containment penetration (inboard' and i 1 _ _ outboard isolation valves T- combinod)' will be specified utilizing conservativo acceptance crite'ria which allows for_ detection of valvo degradation within
..__.___..._-_....______.__.._.._.._.__._._._._._...._m._ _ _ . _ . _ . . _ ,
I reasonable .11mits instead of a loakago rate for individual valvos ' ( as required by IWV-3426, Analysis of Leakage Ratos. . Attachment 1 to this relief request providos a technical ' basis
; for tho-
. acceptanco critoria. The ovaluation of test results will be based on the ponotration leakago rato (inboard and outboard isolation '
valvos combined)- instead of on the individual valvo leakage rato as i required by IWV-3427, correctivo Action.
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Relief RcQttell_2334 - Attachment 1 ( The following is an idealized model of valvo leakago as diagramod in Figuro 1. The purposo of this modelis to demonstrato that leakago, typical of the typo of leakage ' which would be created by abrasivo particles bcing ground across the valvo sont, can be measured prior to component degradation using an acceptanco critoria of 20,000 standard cubic contimotors por minuto (secm). Using this acceptanco critoria, leakago path size is calculated using a given differential pressure. This is typical of a problem oncountored in the field when perforrning local leak rato testing (LLRT). 1 For the purpose of this calculation, the leakago path is assumod to be a square edged ) orifice. This assumption is representative of a scratch across a valvo seat mado by a ) abrasivo particle or the type of leakago path which an LLRT is designed to measure. l Using the Roactor Coolant System as an examplo, the normal or averago particio sizo l' Is 18 microns 1, or 7.1 x 10 4 inches. As the calculation will demonstrato, 20,000 scem is a conservative acceptanco critoria which will allow adequate monitoring of component degradation prior to failure. Further, a valve which falls to fully seat will produce leakage rates which are soveral orders of magnitudo greator than the acceptance critoria used for valve testing. (' ELGURE__t
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Whore: ( O = flowrato in standard cubic contimeters por minuto (cccm) (for this calculation the flowrato is 20000 secm) (Pj-P 2)e pressuto differential in pounds per square inch (psid) (for this calculation the differential pressuro is 9 psid) 3 X = the density of the medium in pounds mass por cubic foot (Ibsm/ft ) ( for this calculation the tost rnodium is air with an assumod density of 0.076 lbo m ffg3 )2 0 = the full diamotor of the tost or component body 1 D2= the orifico or corrosivo particN diamoter Aj = the cross-sectional area of the 100 or componont body A2= the cross-sectional area of the orifico pl = tho numorical constant 3.1415927........ ... Using the Bemoulli obstruction thoory3 for a generalized flow obstruction, which can be written as follows: Q 2(P3 - P2) k 5" 4 This theory is based on tho assumptions of incompressible, steady, frictionless, flow. The validity of these simplifying assumptions for the range of test paramotors of concern for valve testing (small differential pressures and low flow rates) was verified via experimentation using an LLRT machine and precisely machined orificos of various sizes. The results of this experimentation are tabulated in Table 1 of this discussion and are compared with calculated values using the same flowrates and differential pressuios. Solving for D2 one obtilns the following expression: 2 D,=4 4 Q
~
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(' Decause the orifico diameter D2 is very small in folation to the component dlarnoter Dj theterrn
~
can be considorod approximately equal to 1. This further simpliflos the expression for D2 to the following: O D$uP-A f(l'i .TJ Insorting numerical values and the appropriato conversion factors ylolds: 4 4 1 ( i D "g 2 f32.2 ft3 f12 in} f60 sec}, 9 ( 1 ft J (1 minj l 2(finlbs3 2
; 2 U UMfl2in)3 D2 = 2.00 X 10 -3 in2 D2 = -QA45Jn. QI&l11[y,,Jimigt 2/,Q1,,"
An orifico of this sizo is approximately equal to the size of 11_ .n*1ximum leakago path allowed using an acceptance critoria of 20,000 secm. This is oquivalent to 100 scratches of " normal" 10 mleron size, which would represent valvo wear over many cycles, or a significant leakage path 100 timos the size of a path created by one 18 micron abrasive particle. Thus, a 20,000 seem critoria can be utilized to monitor for degradation of several valves in the penetration group and is sensitivo enough to identify si ! jnificant problems. l \
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- flow (secm ) dif f. press.( psid) : test dia.( in) a3% 13% t .02 % : : ::' .' :: ..:.' ..
( 0.0139 11.4 1950 9.48 0.0 t 56 0.0313 0.0263 16.0 7000 9AS 5.00 x 0.I25 0.113 9.76 94000 ,
/ h, N_ _ /~~~~ . . _
this was the highest differential pressure the LLRT stand could maintain at this large of an crifice size. nitrogen testing medium - density = 0.07307 lbm /I! 2 As Table 1 shows, the error between the calculated data and the experimentally measured data is acceptable. The Bernoulli model used in this calculation may be considered ideal and is not necessarily identical to what is encountered in the field, However, for the range of values required, the additional effects of non-ideal conditions. friction and compressibility. etc. are negligible when compared to field. ' conditionc and instrument accuracies. i ( - Reference 1: CPS Plant Modification RT-029 FECN 24600 Reference 2: CRC Handbook of Tables for Applied Engineering Science Reference 3: Fluid Mechanics Second Ed.: White F. M. ; McGraw Hill i m.:
b ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEP REQUEST 2035
~~~
This Relief Request pertains to DISCUSSION the qualification of personnel performing supervision of safety valve and relief valve testing. The ASME Code, Section XI, CODE-REQUIREMENTS Subarticle IWV-3532, requires safety valve and relief valves to be tested in accordance with ASME PTC 25 3-1976. ASME PTC 25.3-1976, Subsection 3.02, Qualification of Person Supervising the Test, states that a person who has obtained a degree in a branch of Engineering from a recognized school of Engineering and in addition, has had at least two years practical experience in fluid flow measurement, may be considered qualified to supervise the test. Illinois Power Company requests RELIEF REQUEST /JUSTIFICI. TION using OM-1 for qualification of relief valve test supervisor in lieu of ASME PTC 25.3-1976. The 1989 Edition of ASME Section XI has been incorporated by rulemaking into 10CFR50.55a. IWV specifies that, for inservice testing of valves, OM-10 provides the requirements. OM-10, Subsection 4.3.1, states that safety and relief valves shall meet test requirements of OM-1. OM-1 places the responsibility on the , Owner for qualification of personnel who perform maintenance and' testing and requires that testing activities be conducted in accordance with the Owner's Quality Assurance Manual. I 1 Power Illinois will qualify PROPOSED A II T E R N A T E - safety / relief valve test REQUIREMENTS- supervisors in accordance with l the Illinois Power- Quality Assurance Manual. l l l l u-nw--a _ w e.- J- - s.,_.p. %A g ,,prew4 m + .e-wyr .y y' - --
ILLINOIS POWER C0!iPANY l CLI!!T0li POWER STATION SECTIOli XI RELIEF REQUEST RELIEF REQUEST No. 3001 (Revision 1) COMP 0t1EllT INFORMATION These pumps (see Table 3001-1) are to safely shutdown the reactor or to mitigate the consequences of an accident. They include all of'the pumps in the IST Program except the RCIC Pump. These pumps are identified in Table 3001-1 by their Equipment
- Identification Number, Name, and ASME Section III Code Class.
CODE REOUIREMEtiT The ASME Code Section XI, Subsection IWP-4310 requires the measurement of these pumps' bearing temperature annuall'y, RELIEF REQUEST / JUSTIFICATION Illinois Power Company requests relief from the Code requirements for the following reasons: The measurement of these pu=ps ' bearing temperature annually does not increase cny confidence in the reliability of the pumps-because bearing temperature rises just minutes prior to failure of the pump bearing. In order to measure this parameter, bearing ((. - temperature,is required to be stabilized per IWP-3500(b), which requires the pump .co be running at least an hour. Since this bearing temperature measurement does not increase any confidence in the pumps' reliability and will reduce the pumps' life due to the time recuired to run the pump, this measurement does not provide' meaningful data. Ther' efore, measurement of these pumps ' , bearing temperatures annually as required by the Code will not .be performed. ALTERNATE TESTING PROPOSED . None. I Section XI/ISI/60
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( . Table 3001-1 (Revision 1) l l Identification Pump ASME Section III. ! Number - Name . Code Clasa 1C41-C001A St'andby L'iquid Control (SLC) , 2 Pump A. - 1C41-C001B Standby Liquid Control Pump B
- 2 Diesel Oil Transfer Pump-A 3 1D001PA 3 1D001P3 Diesel Oil Transfer Pump B ,
Diesel Oil Transfer Pump C 3 1D001PC 2 Residual Heat Removal-( M ) 1E12-C002A Pump A 1E12-C002B Residual' Heat Removal Pump B' 2 1E12-C002C Residual Heat Removal Pump C' 2 Waterleg Pump- 2 1E12-C003 Low Pressure Core Spray (LPCS) 2 1E21-C001 Pump Waterleg Pump ' 2-1E21-C002 2 1E22-C001 High Pressure Core Spray (HPCS) Pump Waterleg Pump 2-
- 1E22-C003 '
2 4 1E51-C003 Waterleg Pump ' ( 1FCO2PA Fuel. Pool Cooling and Clean-Up Pump A 3 1 . 1FCO2PB Fuel Pool Cooling and Clean-Up Pump B- 3 . r' ISX01PA Shutdown Servico' Water Pump A 3 , 3-Shutdown Service Water Pump.B' ISX01PB Shutdown' Service-Water Pump C 3' ISX01PC - 3-OVC08PA Concrol Room HVAC Chilled Water > Pump A _3 OVC08PB Control Room HVAC Chilled Water Pump B ,4 . - - Section XI Tables /ISI/5 -
.- _ _ . _ . . _ _ . . . __ - . . - , _ _ _ .~.._.; _ _ . . . . _ _ . _ _ ..
1 i 4 ILLINOIS POWER COMPANY Clinton Power Station l ASME Section XI Relief Request RELIEF REQUEST 3002 (Revision 3) This relief request refers to COMPO!1ENT INFORMATION three (3) Diesel Fuel 011 (DO) , transfer pumps (1D00lPA, ' 1D001PB, and 1D001PC). These pumps are used to transfer diesel fuel from the diesel storage tanks to the diesel fuel day tanks. The pumps are ASME Section > III, Code Class 3. All of the pumps are Delaval IMO type N3DBS-137. CPS tests the pumps at a fixed dif ferential pressure (DP) of 13 psid, with baseline flow rates ranging from 16.424 to 18.13 gpm. The ASME Code, Section XI, CODE REQUIREMENTS Subsection IWP-3210 tabulates the allowable-- rangos of inservice test quantities (flow rate) in relation tc the reference or baseline values. Table IWP-3100-2 requires an acceptable flow rate range of 0.94 to 1.02 of baseline flow rate, and an Alert range of 0.9 to 1.03 of baseline flow rate. l These pumps do not have flow RELIEF REQUEST / JUSTIFICATION rate instrumentation installed. A calculation is used to determine a flow rate. Because the 00-pumps operate at a low flow and the code specified acceptable ranges are based upon a percentage of the baseline, an increase in flow of less than 0.5 gpm (1.02 x baseline flow rato) - is sufficient to force any of the pumps into the Required Action range. (SEE GRAPH 1) The design- required fuel delivery rates for each of the diesel generators (supplied by the day tanks which the DO pumps maintain) is considerably less than the rated; fuel delivery of any of the three Do pumps. The diesel engines are e pipped with skid mounted pumps which supply fuel oil at a rate of 4 gpm per engine. The engines consume less than 3 gpm per engine with the excess routed back to the day tank. Pumps 1DOO1PA and 1D001PB supply 2 engines each and therefore- 8 gpm has been determined to be the limiting flow rate required - for these pumps to ensure adequate fuel , delivery. Pump 1D001PC supplies only l' engine and- therefore has a = limiting flow rate of 4 gpm.. CPS believes ~that due to the low flow characteristics of the DO-pumps and the significant margin of safety between the flow 9
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_ _._ _ . ~ _ - ._ . . _ _ . . _ _ _ . _ _ _ - - _ .__._ _ _ _ ..._. _ _ _ _ _ _ _ _ _ _ _. i h requirements of the diesel generator and the baseline flow rate provided by the Do pumps, compliance with the Code requirements ' constituto a hardship with no appreciable gain in safety. 1
~~
Illinois Power will calculate ALTERNATE TESTING PROPOSED the flow rate (Q) of the Diosol Fuel 011 Transfer- Pumps by - dividing the change in level of i the diesel fuel day tank by the time the Diesel Fuel 011 Transfor Pump is in operation. , 1 Illinois Power will utilize the following Allowablo, Alert, and ! Action ranges for Diesel oil pump flowrates. Acceptablo Range 2 .94 and $ 1.10 of baseline flow i Alert Range b .90 and < .94 of baseline flow Action Range < .90 of baseline flow
> 1.10 of baseline flow ,
1 Based upon CPS's operating experience, Illinois Power believes that the revised upper ranges will provide good indication of pump degradation without the unnecessary burdon of requiring the pumps- j to be tested on an increased frequency or declared inoperable for , minor ( < 0. 5.gpm ) variations in flowrates. (SEE GRAPH'2) 1 t
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@ PUMP tDOO1PA PERFORMANCE 10 , , , . . , , t APR JJN SEP RD MAR APR JUL OCT F8
( 1991 - 1992 )
h m ean.w.er; m mry- *;.:.r , _ _ 2 n- r y :"1 - - - _: :; $U.; . . . _ . _ , _ ILLINOIS POWER COMPANY CLINTON POWER STATION I SECTION XI RELIEF R2 QUEST , ( I RELIEF REQUEST No. 3003 (Revision 1) , l COMPONENT INFORMATION ! The Standby Liquid Control (SLC) Pumps (1C41-C001A.and C001B) . supply a neutron absorbing solution into the reactor in sufficient concentration and quantity to overcome the maximum They are ASME Section III Code Class 2 , positive reactivity, itivo displacement pumps which are pumas. These are pos - Liightlighted on the attached drawing. . CODE REQUIREMENT The ASME Code Section XI, Subarticle IWP-4600 requires meascring the pump's flow rate. 'Subarticle IWP-4100 specifies the requirements for instrument {tccuracies, ranges,'etc, RELIEF REQUEST / JUSTIFICATION Illinois Power Company requests relief from the Code requirements for the following reason These pumps do not have a flow rate measuring instrument i installed which mecca the above Code requirements. - ( ALTERNATE' TESTItlG PROPOSED Illinois Power Company will calculate the flow rate (Q) of the SLC pump by dividing the change in level of the SLC test tank by . the time the.SLC pump is in operation. l . l 1
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- e' , t 'HTON PdJER STATION SEL 1N XI RELIEF REQUEST
( . . g RELIEF REQUEST NO. 3005 , COMPONENT INFORMATION
~
The Standby Liquid Control Pumps (lC41-C001A and C001B) supply a neutron absorbing solution into the reactor in sufficient concentration and quantity to overcome the mdximum positive reactivity. .These pumps arc ASKE Section III: Code Class 2 and arc. highlighted on the attached drawing. CODE REQUIREMENT , The ASME Code Section XI, Subsection IWP-3500(a) requires that when measurement)of the b. caring. temperature is not req.uired, - these pumps shall be run at l' east five (5) minutes under con'ditions as stable as the-system permits. At the end of this time, at,least one measupement or observation.of each of-the-quantities specified shall be made and recorded.
, RELIEF REQUEST / JUSTIFICATION Illinois Power Company requests relief from the Code requirements for'the following reasons:
( r.
,i' Plant domineralized water is utili:cd to perform the quarterly
- tests for these pumps. The discharge of these gumps is collected in the Test Tank. The capacity of.the. Test Tani does not permit running these pumps for.five (5) minutes.
Since these p~ umps are positive displacement type pumps and the inlet water is at a constant temperature, the flow conditions will be stabilized within a few seconds of' starting the pumps.. Letting the pumps run one (1) minute before measuring / observing the required parameters will ensure the flow conditions are stabilized.
- ALTERNATE TESTING PROPOSED Illi,nois Power Company will perform the required testing ..
quarterly and all of the requiredLparameters will be observed / measured and recorded after the-pumps have been running. at least one minute but prior to running fo~r five minutes. ;
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y , c - Section:XI/ISI/64 i
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1 LL111013 POWElt C0!4 pally Clinton Power Station ASl4E Section XI Itellof Itequent itELIEF IREQUEST 3006 (Itevision 1)
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This relief request pertains to
.C0!4PollE!1T 111Folt!4ATIOli the four (4) water-leg pumpa (1E12-C003, 1E21-C002, 1E22-C003, and 1ES2-C003) in the CPS IST program. Thane pumps are required to unintain the water level in the annociated ECCS nystems to ensure the prevention of a water-hammer transient in the event of an ECCS initiation. In addition, these pumpa have nimilar chara teristica. All four are Gould model 3196 ST, with the primary dif ference being impeller diameter. They are tected at flows ranging from 50 to 64.5 gpm with baccline diff crential preunuren (DP) ranging from 44.4 to 40.3 paid for the 1E12-C003, 1E21-C002, and 1E22-C003 pumpn and 29.4 paid for 1E51-C003. All pumps are ASliE Code Clacs 2.
The AS!4E Code Section XI, CODE lllEQUIREliE!JTS Subsection IWP-3210 tabulates the allowable and alert rangen ( - of incorvice test quantitles (differential preocure (DP)) in relation to the reference, or baneline, valucc. Table IWP-3100 -2 r,qquirca an acceptable DP range of 0.93 baseline DP to 1.02 baceline DP and an alert range of 0.9 baseline DP to 1.03 baceline DP. Locause the water-leg pumps RELIEF REQUEST /JUSTIFICATIott operate at a low DP and the. Code cpecified acceptable rangen are baced on a percentage of the baseline, a small increase in DP can result in the pump reaching the alert or action range when the pump in operating within design parametern. Using data for the !!PCS water-leg pump (1E22-C003) as a representative example, which han a baseline DP of 48.5 psid, the Code-required acceptable range varien from 45.1 to 49.5 paid, or less than 4.4 paid (SEE GRAPfl 1) . Likewise the Code-required alert range for 1E22-C003 varico from 43.7 to 50 paid, f or a range of 6.3 paid. CPS believen the lower acceptable and alert range boundaries (0.93 ; and 0.9 of baseline DP) are achievable without undue hardship, j l llowever, baned upon the Code required upper acceptable and alert 1 range boundaries of 1.02 and 1 03 baseline DP) a deviation of only l((r l 1.0 psid above baseline DP is sufficient to force any of the CPS waterleg pumps onto increased frequency, and an increace greater l l i l l l
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i than 1.5 paid above the baselino DP will place the pumps in the j ( action rango. , w : . _ Illinois PoWor will utilize the'
-~ ALTER!iATE $TESTl!1G j PROPOSED, following allowablo, alert, and -t s -
g - action rangen for water-lag pump t differential pressure. Acceptablo Rang _ (0.93 to 1.05) x (bacclino dp valuo) Alert Rango , (0.90 to 1.10) x (baselino'dp valuo) Action Rango < (0.90) x (baselino dp value) '
> (1.10) x (baselino dp value) ,
Based upon CPS's operating experience, CPS fools that the revised upper ranges will provido good indications of pump degradation without the unnecessary burden of requiring the pumps to be-tested , , on increased frequency or declaring them inoperable for minor (1.to 2 paid) variations in DP (SEE GRAPil 2). CPS has ovaluated minor , fluctuations of this type and has determined that this performanco 7 is not an indication of pump degradation, and the pumps are ! operating within design allowable limits.
'g In addition, as theco pumps are normally running,-lino pressure is continually monitored via pressure transmittorn by the Main Control l- Room and any failure will be immediately observed-by control Room l personnel.- ,
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ILLINOIS POWER COMPANY ; CLINTON POWER STATION SECTION XI RELIEF REQUEST l RELIEF REQUEST NO. 4001-(Revision 1) C_0MPONENT INFORMATION Several ASME Class 2 lines are open-ended as defined by Code Case N-408. These lines meet the Code Case requirements of not containing water during normal plant operating conditions. Page " 2 of this request lists each line for which relief from - examination is requested. { CODE REQUIREMENT The ASME Code Section XI, Subsection IWC-1220,- IWC-2500 and Table: IWC-2500-1 require that welds in Class 2 piping systems'be ' selected for examination. Subsection IWF-2510(a) and Table IWF-2500-1 require selection of component supporta for those , components required to be examined under Subsection IWC-2500. t RELIEF REQUEST /JUSTlFICATION ,
. .t Illinois Power Company requests thr.t the lines on page 2 and associated component supports be exempt from the Code requirements for the following reasons: ,
f Each of these lines is open-ended beyond the last shutoff valve and does not contain water during normal plant *
-( operating conditions. Code Case N-408,(a)(6) and (b)(4),
j allows lines meeting the above conditions to be exempt fro'm ; the Code requirements of IWC-2500. Although Illinois Power does not intend to invoke this-Code Case in it's entirety, , this relief request is based on the Code Case's exemption from examining certain open-ended pipes and the fact that-leakage from any of the associated welds on these pipes would be-insignificant land would have no adverse safety impact on " the plant. . ALTERNATE REQUIREMENTS PROPOSED NONE. P (, , Page11 of 2
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l ILLit101S POWER COMPA!1Y CL111 TON POWER STATION SECTI0li XI PELIEF REQUEST RELIEF REQUEST NO. 4001 [ , Class 2 Open-Ended Lines The following lines are-in open-ended systems and require relief from examination: 1DG08AA-36" 4 1DG08AB-36" 1DG08AC-24" 1DG08BA-24" 1DG08BB-24" - 1DG08CA-20" 1DG08CB-20" 1DG10AA-36" 1DG10AB-36" 1DG10AC-24" 1DG27AA-16" 1DG27AB-16" 1DG27AC-16" lifG05AA-6" liiG05AB- 6" i 11!G05BA-6" 111G05BB-6" l lilG05CA-6" 1 111G 05CB-6"
-( i 1HG06AA-10" l l
ll!G06AB-10" lilG06AC-10" 11tG06AD-10"
- 1 1Ril30BA-12" i IRl!30 BU- 12" - 1 1
1Ril30CA-12" 1Rll30CB -12" 1' 1RH30DA-12" 1RH30DB-12" l 1R108B-12" 1RIO8C-12" . L l l .- 1 '
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p . l, =: _ Page 2_of-_.2 l L . :.rm ::r nnt!?L _ _ _ . , . _ _ _
1 I ILLIt401S POWER COMPANY CLIt4 TON POWER STATION SECTIOt1 XI RELIEF REQUEST RELIEF REQUEST NO. 4003 (Revision 1) k' ,COMPON E NTN0 4TA ION I F f0 Al' :omponent supports rcquiring VT-3 and/or VT-4 examinations. i
.0DE REQUIREMENT Jubarticle IWF-2500 and Table IWF-2500-1 regt ~ re that a visual examination, VT-3 and/or VT-4, be performed each inspection interval for the supports described above.
RELIEF REQUEST / JUSTIFICATION Illinois Power Company requests relief from performing any VT-4 i examinations for the following reasons:
- 1. The definition of VT-4 cxamination in the 80W81 Code does not clearly identify the attributes to be conside.ted in developing the inspection criteria,
- 2. Functional testing of snubbers required by Clinton Power Station (CPS) Technical Specifications is more stringent than this Cc,Je requirement.
- 3. The 83W84 Code has been clarified by combining the Visual Examinations VT-3 and VT- 4.
( If relief is granted, Illinois Power will update the applicab_- procqdures to not only delete the references to VT-4, but to include the revised VT-3 examination requirements from the 83WE4 Code in our program. ALTERNATE TESTING PROPOSED Illinois Power will perform VT-0 examinations using the definition from the 83W84 Code in lieu of performing VT-3 and VT-4 examinations in accordance with 80W81 requirements. Functional tecting will be performed in accordance with CPS Technical Specifications. s Sec t-i on KT /T ST /fn _ _ . _ _ _ _ _ - - _ _ _ __ _ _ _ _ _ _ - _ _ _ _ - _ _ _ - _ _ _ _ _ - _
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~ ILLINOIS ?OWER COMPANY-CLINTON POWER-STATION SECTION XI RELIEF REQUEST
- RELIEF REQUEST NO. 4004-(REV.- 1)
L l- COMPONENT INFORMATION-Ilydraulic and. mechanical snubbers associated wit:h t.he -piping lines included in the Clinton Power Station-(CPS) Inservice Examination Program Plan.
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[ CODE REQU,IREMENT o -- The ASME Code specifies visual inspection frequencies for the: l above supports-in Table 'IWF-2500-1 and functional testing- i frequencies in-Subarticle IWF-5400. In addit'on, corrective- y actions with regard to' selecting additional supports are " , specified in IWF-2420, IWF-2430, and IWF-5500. RELIEF REQUEST / JUSTIFICATION Illinois Power Company requests relief from the requirements
' identified above wi th regard to frequency o.f inspection 1and testing, and corrective action. '
a. 55 This relief request is-justified because the CPS Technical 3 Specification 4.7.4 specifies inspection and;tecting frequencies for these supports which are generally more restrictive than the s Code requirements. . Tracking the compiction of inspection and testing activities with regard to both ASME Code and technical , specification requirements creates additional administrative 1 work -
" 'without'significant' benefit in snubber reliability.
ALTERNATE TESTING PROPOSED m Visual inspection and functional testing frequencies and corrective action for selecting additional or ' successive supports -
- for testing willibe. as :specified by CPS Technical Specifications.=
Visual inspection of those snubbers initially. selected for functional testing during each outage will be performed.in accordance with.ASME Code requirementsEfor-VT-3 inspection,. All other' visual inspections.will-be performed in'accordanceLwith CPS-
-Technical Specification requirements. .
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