Text

Rev 14 to CPS IST Program,App III
	ML20034E746
Person / Time
Site:	Clinton
Issue date:	02/23/1993
From:	; ILLINOIS POWER CO.
To:	;
Shared Package
ML20034E745	List: ML20034E746; U-602104, Forwards Rev 14 to CPS IST Program,App Iii.Rev Revises Relief Request 4001 to Delete Application to Number of open-ended Piping Lines Associated W/Dg Sys & Improved Ref Drawings for Several Relief Requests;
References
	PROC-930223, NUDOCS 9303010290
	Download: ML20034E746 (75)
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Attachment to U-602104 y

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I Revision 14 to the l

CPS Inservice Testing Program l

Appendix III t

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Revision 14 I

Date 2/8/93 i

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APPENDIX ~III l

j RELIEF REOUEST LISTING l

Revision - 14. is to.' revise Relief Request 4001 and to substitute better quality drawings for existing drawings in numerous Relief Requests.

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ILLINDIS POWER COMPANY CLINTON POWER STATION GENERAL RELIEF REQUEST INDEX 3etief Request Description Date Date Remarks l

Ntaber Submitted Approved 1001 Maxima attowable extension for 6-15-92 6-15-92 (Revision 2) l test freq;ency of valves and gxmps.

Revised per SER l

1002 Deleted I

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ILLINDIS POWER COMPANY CLINTON POWER STATION 1

VALVE RELIEF REQUEST INDEX j

i Relief i

ReqJest Description Date Date Remarks thmber submitted Approved j

I 2001 Deleted 2002 Test frequency for valve 1C11-F122 3-09-88 9-30-91 (Revision 1) 2003 Deleted 2004 Test freqJency for valves 1Sx016 A/B 6-30-87 9-30-91 2005 Deleted 2006 Deleted a

2007 Deleted 2008 Test method for water leg keep fitt 4-23-92 9 25-92 (Revision 3) check valves.

i 2009 Test frequency for the Manual Deluge 6-15-92 6-15-92 (Revision 2) valves listed in Table 20091.

Revised per SER 2010 Deleted j

l 2011 Leak rate testing, differential test 12-13-88 9-30-91 (Revision 1)

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pressure, analysis of leakage rate and corrective action for containment isolation valven.

2012 Test frequency for ADS valves 3-15-92 Note 1 (Revision 2) 1821-F041 B/C/D/F, F047 A/C and F051G. Stroke time evaluation.

2013 Stroke time trending of the solenoid 6-15-92 Note 1 (Revision 3) operated valves listed in Tabte 2013-1.

2014 Futt-stroke exercising of check 4-23-92 9-25-92 (Revision 3) valves 1E12 F041 A/B/C,1E21-F006 and 1E22-F005.

2015 Deleted 2016 Deleted 2017 Deleted 2010 Test frequency for valve 1E12-F475.

3-09-88 9-30-91 (Revision 1) 2019 Deleted 2020 Deleted 2021 Deleted 1

Note 1: Acceptable per Generic Letter 89-04, Attachment 1, Position 6

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5 ILLINOIS POWER COMPANY CLINTON POWER STATION VALVE RELIEF REQUEST INDEX l

s Relief Request Description Date Date Remarks l

Number Submitted Approved 2022 Exercise test for valve 11 A175.

3-09-88 9-30-91 f

2023 CRD valve 112.

2-10-88 9-30-91 2024 CRD valves 126,127,139 and 114, 3-15-92 Note 2 (Revision 1) i 2025 CRD valve 138.

2-10-88 9-30-91 2026 DG velves 1DG008A-K.

3-15-92 Note 2 (Re<lsion 1) 2027 Deleted 2028 1C41-F336 Exercise 12-13-88 9-30-91 (Revision 1) l l

2029 Alt. Leak Rate Testing to allow 5 2 9-30-91 pressure drop tests.

2030 Deleted 2031 Deleted l

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2032 Stroke time trending of the air 6-15-92 Note 3 (Revision 2) operated valves listed in Table 2032-1.

I 2033 Test frequency and testing method 11-30-92 Note 5 (Revision 1) for valves 1G33-F051 and 1G33-F052A,8.

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2034 Leak rate testing in grcups.

6-15-92 9-25-92 2035 Relief valve test supervisor 11-30-92 Note 4 requirements.

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Note 2: Augmented testing racpirements which are beyond the scope of 10CFR50.55a as these conponents are not i

ASME Class 1, 2 or 3.

No NRC approvat required.

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Note 3: Acceptable per Generic Letter 89-04, Attachment 1, Positions 5 and 6.

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i Note 4: Pending NRC review.

Note 5: Previously approved by 9-30-91 NRC SER.

1#: APP 3 TAB

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l ILLlHCIS POWER COMPANY CLINTON POWER STATION PUMP RELIEF REQUEST INDEX l

Relief Request Description Date Date Remarks N dier Sdanitted Approved 3001 Arrual measurement of pq bearing 8-20-87 9-30-91 (Revision 1) tenverstures.

3002 Flow rate measurement of pumps 11-30-92 hote 5 (Revision 3) 10001PA, 1DOO1PB and 1D001PC.

3003 Flow rate measurement of pgs 3-09-88 9-30-91 (Revision 1) 1C41-C001A and C0018.

3004 Deleted 3005 Time for pres 1C41-C001A and C001B 6-30-87 9-30-91 to run prior to measuring /observirig psnp parameters.

3006 Ranges for pm p flow rates and 4-23-92 9-25-92 (Revision 1) differential pressure.

1 Note 5: Previously approved by 9-25-92 NRC SER.

WP: APP 3 TAB

r ILLINDIS POWER COMPANY CLINTON POWER STATION NDE RELIEF REQdEST INDEX Relief Request Description Date Date Remarks Ntanber

$dtnitted Approved 4001 Weld examination of Class 2 lines 2-08-93 Note 6 (Revision 2) which are open-ended.

4002 Deleted 4D03 Perform VT-3 examinations per 83WB4 7-29-88 7-9-92 (Revision 1)

Code in lieu of att VT-3 and VT-4 examinations.

4004 Hydraulic and Mechanical Srsteers; 12-28-88 7-9-92 (Revision 1)

Frequency of Inspection, Testing, and Corrective Action I

Note 6: Previously approved ty 7-9-92 NRC SER.

WP: APP 3 FAB

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ILLINOIS POWER COMPANY CLINTON POWER STATION REPAIR / REPLACEMENT RELIEF REQUEST INDEX Retlef Request Description Date Date Remarks htsaber submitted Approved Disapproved 5001 Reptacement botting materia 1 10-20-87 Disapproved 5002 Replacement parts for components 10-20-87 5003 Deleted 5004 Deleted 1

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ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request i

RELIEF REQUEST 1001 (Revision 2)

N All Pumps and valves that are GEC Z 3 U E.iigigMEM M "? y %

required to perform a specific 9

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function in shutting down the reactor or in mitigating the consequences of an accident and are listed in Table I arid Table II of the IST Program except safety and relief valves and valves not tested at three (3) month or shorter intervals.

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y The ASME Code Section XI,

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Subsection IWP-3400 requires u.

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performing an inservice test on pii@ @ @ j each pump nominally every three (3) months.

Subsection IWV-3411 requires that valves be exercised and stroke timed at least once every three (3) months.

Subsection IWV-3521 requires that check valves be exercised at least once every three (3) months.

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The ASME Code Section XI, MJ lESD?gggggggggg7pygggggp MRELIERfREQUES " STIFICATIONiF various subsections mentioned l

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above, specify the test frequency interval but do not l

specify any allowable extension.

Often there are operational 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 the ~ Code testing 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 l

for most Code specified testing and provides an acceptable level of l

quality and safety.

This is consistent with Technical Specification 4.0.5.c.

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Illinois Power Company will 9ALTERNATERTESTINGKPROPOSEDTs W uti1ize CPS:

Technica1 yx 1' ' '~ g p ~ J T D J M Q Rif J 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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SECTION XI RELIEF REQUEST RELIEF REQUEST NO. 2002 (Revision 1)

COMPONENT INFORMATION This Contnsi Rod. Drive (CRD) Water Header. Check Valve (ICll-F122) is a containment isolation' valve and prevents the back flow of reactor water when the CRD Pumps are secured.

It is an ASME Section III Code Class 2.Section XI Category A/C valve.

It is a 2 inch check valve and is highlighted on the attached drawing.

CODE REQUIREMENT The' ASME Code Section XI, Stibarticle IWV-3521 requires that this valve be e.xcrcised every three (3) months.

' RELIEF P'ZQUEST/ JUSTIFICATION

-s Illinois Power Company requests relief frcm the C. ode requirementia for the following reasons:

.This check valve is a containment isolation valve which provides

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. drive water to' tihe hydraulic control units and seal flow to the reactor recirc'ulation pumps.

This is a normally open valve and.

cannot be tested during normal plant operation or cold shutdowns stem be shutdown since testing.this valve requires that the CRD sy'and stopping causing the control rods' motion to be preventied seal flow to the reactor recirculation pumps.

Although the reactor recirculation pumps are not required for safe shutdown of the plant, these pumps are use.d to assure uniform temperatures are maintained in the vessel during cold shutdowns.

Exercising l

this valve would also allow air to enter the CRDs which would require substantial venting of the' system to remove..

hLTERNATE TESTING PROPOSED Illinois Power' Company will exercise this valve during refueling outages.

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i ILLINOIS POWER COMPANY CLINTON POWER S.TATION SECTION XI RELIEF REQUEST RELIEF REQUEST NO. 2004.

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=.6 COMPONENT INFORMATION Th,e Fuel Tool Emergency Makeup. Valves (ISX016A/B) provide emergency makeup water to tihe. Fuel Pools from, the lake.

They are

's ASME Section III Code. Class 3, Sectiion XI Category B valves.

1 They are 2k inch motor operated gate valves and are highlighted on the attached drawings.

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The ASME Code Section II, Subsection IW-3411 requires that these i

- valves be exercised and stroke timed every three.(3) months.

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Illinois Power Company requests relief'from the Code requirem'nts e

for the following reasons:

. Testing these valves will-allow lake water into th'e fuel pools thereby affecting the chemistry of a large quantity of water in l

i the pools.

Cleanup of the fuel pool water will-generate l

additional solid radwaste and delay the plant. st'artup.

Te' sting i

these valves during refueling outages wil-1 ensure that there is

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sufficient time to accomplish these activities.

t ALTERNATE TESTING PROPOSED Illinois Power Company will exercise and stroke time these valves during refueling outages.

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l ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2008 (Revision 3) l w en.a an.=n. g~gggg asm. ergga.n;#,

Valve 1E22-F006 is located emn e.

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?COMPONENTH NFORMATIONWmM %n..

between High Pressure Core Spray g.n dsl0$$MSDNMMDSM$$@@$Mdn$g (HP) water-leg pump and the main Ny HP injection line.

It is a 2-inch stop-check valve, 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 respective injection lines (Residual Heat Removal (RHR) and Low Pressure 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 drawing "B".

l' M E$ggggg g ggggg g gg p y g g The ASME

Code,Section XI, MCDDE% REQUIREMENTS $5h4 M Rg@?

Subarticle-IWV.3520 requires i

NMMhMNEMEN3k$E._.. OME that these valves be full-stroke exercised individually. every three (3) months.

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Illinois Power Company requests SRELTEElREQUEST/ JUSTIFICATION @s relief from the Code

[ $ 3 0f C V 77$ $ M(Eif Mi@jjg5 requirements for the following reasons:

l The above groups of valves; although located in separate systems, have 'similar configurations; they are check valves located in series with other check valves and no test connections provided l

between them to permit individual valve testing.

Each of these valves has a separate check valve in; series.

The two l

check valves in series, although not required by design or safety

analysis, provide an added assurance that the. high pressure Emergency Core Cooling System (ECCS) line will not damage the lower pressure water-leg piping.

Illinois Power Company considers these l

two check valves in series as a single entity and will test them as such.

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Illinois Power Company considers

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these two check valves in series l

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Acceptance criteria will be established' and in the event of not meeting this criteria, appropriate action will be initiated for the entity and the deficiency will be corrected.

The open exercise of these valves will also be performed every three (3) months.

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l ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2009 (Revision 2) was m.m %;m m mmr These Manual Deluge Valves (see ICdMh6N E5NIhbhhiMIdhkrgg 4p ~ n v;yy g y.'

k Table 2009-1) provide shutdown

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service water to the Standby Gas Treatment Charcoal

Beds, the Makeup Air Filter Package, and the Supply Air Filter Package. They are all ASME Section III Code Class 3 valves.

Valves 1SXO71A/B, 073A/B, 074A/B, 076A/B, 105A/B, and 107A/B are ASME Section XI Category B, 3 inch motor operated gate. valves.

These valves are highlighted on the attached drawing.

9-s ermwn The ASME Code Section XI, m@- c.~ ~ ~,..>,..-.A.we _"

1X'ODEQREQUIREMEl! tsp #, m@ey., l Subarticle IWV-3411 and IWV-3521

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exercised.and stroke timed every three (3) months.

$ l % M Q M W $ M M W C. d 5 T E ;m Illinois Power Company requests JUSTIEICAT re1ief from the Code

, g dRELIEF5 REQUEST /gjggggy'IONiW 1

Mygg ggyprygg g, 4 requirements for the following reasons:

Testing these valves will flood the charcoal beds of the Control Room HVAC 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 systems required to be operable in all modes of l

operation.

l Both of the above options are not possible duri,ng 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 HVAC system'to be declared j

inoperable.

The second. option is not possible because the plant must be shut down if the Shutdown Service Water header is drained.

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Illinois Power Company will ALTERNATE?"PESTINGDPROPOSED},

perform the required tests 2

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during refueling outages.

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Valve Number Size 1SXO71A 3

ISXO71B 3

ISXO73A 3

1SXO73B 3

1SXO74A 3-t 1SX074B 3

ISXO76A 3

i ISXO76B 3

1SX105A 3

ISX105B 3

1SX107A 3

1SX107B 3

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.N 1 DELUGE SYSTEM DIV 11 DELUGE SYSTEM O

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LLLINOIS POWER COMPANY CLINTON POWER STATION SECTION XI RELIEF REQUEST

(

RELIEF REQUEST NO. 2011 (Revision 1)

COMT 4 INFORMATION I

All Section XI, Category A and A/C valves which require a leakage test per IWV-3420 as identified in Illinois Power's Pump & Valve Testing Prog' ram Plan.

CODE REQUIREMENT The ASME Code Section XI, Subsection IWV-3420, Valve Leak Rate Testing, requires leak rate 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, Analysis of Leakage Rate, and IWV-3427, Corrective Action, require establishing the maximum permissible leakage rate and. evaluating the test results for individual valves.

RELIEF REQUEST / JUSTIFICATION Illinois Power Company requests relief from the Code requirements for the following reasons:

For all valves except Excess Flow' Check Valves:

A 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.

Therefore, the maximum permissible leakage rate for individual valves cannot be specified.

As the purpose of these valves is to isolate the containment, testing in grpups, i.e., by -containment penetration, l

would verify the integrity of the containment boundary.

Also,Section XI, 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 intervals.

However, l

industry data has shown that the trending'of leak < rates is not a l

meaningful way to predict failure.

For Excess Flow Check Valves Excess Flow Check Valves are not -required.co be individually leak I

l rate tested (Type B or Type C) per Clinton Power Station (CPS),

l Technical Specification or 10CFR50, Appendix J.

However, excess flow check valves are included within the Integrated Leak Rate l 1 l

Test (ILRT) boundaries.

Although the ILRT does not measure individual valve leakage rates, the satisfactory completion of j

'. /

the ILRI verifies the overall function of these valves.

1 Page 1 of 2 Section XI/ISI/18

)

e

ILLINOIS POWER COMPANY CLINTON POWER STATION SECTION XI RELIEF REQUEST RELIEF REQUEST NO. 2011 (Continued) t

~

ALTERNATE TESTING PROPOSED For all valves except Excess Flow Check Valves Illinois' Power Company will utilize 10CFR50, Appendix J and CPS Technical Jpecifications to determine the differential test pressure for these containment isolation valves.

The maximum 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 Rates.

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 IWV-3427, Correctiv'e Action.

The c' rending requirements of IWV-3427(b) will not be Laplemented since meaningful trends cannot be established.

For Excess Flow Check Valves No separate test or evaluation either by: individual valve or by penetration will be performed on excess flow check valves.

These valves are included within the Integrated Leak Rate Test (ILRT) boundaries.

s L

[

Page 2 of 2 Section XI/ISI/19

k.

ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2012 (Ravision 2) s 4

i

' lHMT!!EMMME?BffSF'""fw These Automatic Depressurization MtOMPONENTjaNFORMATIONb $1@g System valves (1B21-F041B/C/D/F,

" gy? J QE@nFMF%fM7MW@yE 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. safety / relief valves.

The ASME.

Code Section XI, 93hfMR.7.4Mh9El$?61F *NW@p dCODEfREQUIREMENTSpih gp?

Subsection IWV-3411 requires

<eggMahsmg3Mg%gggg f age 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.

MijBPi3EJR Illinois Power Company requests I

@p@Ef% REQUEST 2@MMM?E7myg

(

0USTIEICATION relief from the Code M @tg @ h igif$yRe4$$ M@n 3REL1E 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 OwnerN Group Evaluation of NUREG-0737 Item II.K.3.16, Reduction of Challenges and Failures of Relief j

Valves).

j 1

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 valvcs.

b e

Illinois Power Company will

+

4

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O, A15$RN5TE(!'fESTINGINNUP6S5b$5M exercise and stroke time these if ~

eW dp.

Illinois Power Company will 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.

This is in conformance with NRC Generic Letter 89-04,lAttachment 1 Position 6.

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1

ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2013 (Revision 3) s 49 These valves are various rapid M&indu.J$h ', wny3@w JCOMPONENT&INFORMnTIONi d 4Cnge acting valves (see Table 2013-1) rngg qqqqwggmqgp@FOMP 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.

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The ASME

Code,Section XI,

^NOU$.mimy;EhEM$iiTsk : Amf n;t., $TAE6U

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SubarticlecIWV-3417 (a) requires a

sjm 4MF@g5M$d d ' 4 (Mif69 trending the stroke time results-for these valves and taking appropriate corrective action.

asem;msswr wae mm Per Generic Letter 89-04, these eerrey$$kOES$

R d a J'I M V W A M P ' / 8 0 $ $ 5 E $ $ $ I s d N M

$R5$ IEd valves are defined as rapid

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$i@$$$Mif@fMM@@

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 specified change.

The verification that these valves meet a maximum stroke time of a relatively short duration provides l

adequate assurance of operability of these valves.

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Illinois Power Co~mpany 'will m

m_.~. m m.. m _

...m assign a maximum stroke time of-OALTERNATE$@TESTINGRPROPOSEDi T9@ed$

two (2)

. seconds for these id@ *MN Niji ~'ngg,

valves. If this limiting stroke time is exceeded, the valve will be declared inoperable and corrective action will be taken.

4

ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2014 (Revision 3)

These testable check valves 7 COMP'ONENTfINFORMATIONf (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 1E21-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,

. CODE' REQUIREMENTS 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 EREhIEF ' REQ'UEST/JUSUIFICATIOld ^

three month frequency using the emergency core cooling system pumps to inject water into the reactor is not in the interest of plant safety, because this cooler water would create an undesirable power transient.

In addition, l

1 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 l

operator is not designed to perform a full stroke test.

Although the air operator can be removed to perform the ful.1 stroke test, this is a significant maintenance activity and could interfere with l

work which is necessary to restore the plant to service.

This I

would create an unreasonable hardship for Illinois Power Company.

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..- =..

Using pump pressure to exercise these valves during cold shutdown is also not in the interest of plant safety.

Although temperature could be matched fairly closely between the injection source (emergency core cooling systems) and the reactor, a minor thermal mismatch between these temperatures creates an undesirable effect i

on the fatigue life of the reactor nozzles.

i 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 water through this flow path and the potential damage.

to nuclear instrumentation or Juel assemblies which could occur if

?

this flow path were used for other than emergency conditions.

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Illinois Power Company will full j

SALTERNATERTESTINGEPROPOSED;

stroke' exercise the valves n J gh

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during reftieling by measuring l

the torque _ required to lift the disc and then move the disc through a full stroke.

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SECTION II RELIEF REQUEST RELIEF REQUEST NO. 2018 (Revision 1) j COMPONENT INFORMATION s

Reverse flaw check valve lE12-F475 is a containment i' solation l

valve and provides necessary thermal relief foi the Residual Heat Removal System piping between valves -lE12-F008 and lE12-F009.

It

(

is an ASME Section III Code Class 2,Section II Category A/C i

valve.- It is a one inch check valve and is highlighted on the -

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atta'ched drawing.

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' CODE REQUIREMENT Th'e ASME Code Section XI, Subarticle'IWV-3521 requires that this l

valve be exercised every three '(3) months.

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l RELIEF REQUEST / JUSTIFICATION Illindis Power Company'reque'sts relief from the Code requirements

[

for the following reasons:

This valve is installed in the piping of the shutdown cooling ~

mode of operation of the Residual Heat Removal System and.is

/

loca.ted inside the drywell.

During normal operation, this line

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is pressurized;by the reactor recirculation sy.stom.

The valve.is not designed to open-against.this pressure.

Therefore, this 1

valve cannot be exercised quarterly. -

l 3

This valve cannot be exercised during cold shutdowns since the shutdown cooling mode of the Residual Heat Removal System will be j

i 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 l

l this valve.

ALTERNATE TESTING PROPOSED Illinois Power Company will exercise this, valve during refueling outages.

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(

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RsLIEF REQUEST NO. 2022

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COMPONENT INFORMATION Valve 15L175 is a % inch check valve which functions as a

)

containmedt' isolation valve.

The attached P&ID depicts the l

7 configuration of this valve in the systent.

CODE REQUIREMENT The ASME Code Section XI, Subarticle IWV-3521 requires. check

. valves to be. exercised to their safety position every three (3) months.

i RE IEF REQUEST /.IUSTIFICATION I

Illinois Poweir ' Company requests relief from the Code requirements because there is no way to functionally test this valve without-per. forming a-leak rate test.

No direct containment leakage path is available through this valve.

The leakage path through this-,

valve is limited by the pipe cap and the piping connections to the actuator.

As -the probability' for. leakage through these 7

connections.is small, it appears to be excessive to leak test

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this penetration on' a quarterly'or cold shutdown basis.

~

t ALTERNATE TESTING PROPOSED' Illinois Power Company will satisfy the exercise reqdirement for

[

this % inch check valve upon performance.of the leak rate test.

The frequency of the exercise' test will be revised to coincide with the leak rate frequency, i.e., 2 years.

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RELIEF REQUEST 2022 T

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ILLINOIS POWER COMPANY CLINTON. POWER STATION SECTION XI.RELI2F REQUEST s

~

RELIEF REQUEST NO. 2023 COMPONENT INFORMATION tcu Valve,1h (typical of.145 each) is the control rod drive ply check valve; refer to attached drawing.

These accumulator.sup/C %-inch check valves.

These valves allow the are Catej;ory 'A individual accumuLcors to be charged with sufficient pressure to scram the appropriate control rod drive upon loss of CRD header

. ith a loss of header pressure, these valves must W

pressure.

close to maintain enough pressure in the accumulator to insert the.CRDs.

~

CODE REQUIREMEITI Section XI, Subarticle IWV-3521 requires check valves to be exercised to their safety position every three (3) months.

IWV-3420 requires Category A valves to be leak tested every 2

~

years to verify the. component's ability to perform its safety function.

RELIEF IGQUEST/ JUSTIFICATION Illinois Power Company requests relief from the above Code D

.r'equirements'because it is not' feasible tc individually, exercise

~

these valves wi'thout securing the CRD pumps.

The reverse flow exercising and leakage tests.of these check valves will'be satisfied by the performance of an accumulator pressure drop with the pumps secured,.during refueling outages..This

test, test will verity the valve is closed by monitoring the.

accumulator pressure which would indicate any leakage past the check valve.

ALTERNATE TESTING PROPOSED Illinois Power Company will satisfy the leakage and exercise tests,for these valves upon performance of the accumulator pressure drop test on a refueling outage frequency..

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4 De RELIEF REQUEST 2023 O

I ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request r

RELIEF REQUEST 2024 (Revision 1) e 1$$i@E3$N?S$Y$$EIidEE5$NT$E!8I?gg Valves 1C11-126, 127 and 139 jMOR OHgg M MpM EqNg g g g (typical of 145 each) are power

M9MnnsMSNEMifRENWEsi$AME Operated valves wh.tch 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 u lve opens to allow flow to exhaust from the control rod drive to the scram discharge volume.

Valve 139 'is 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 ~,

f category C.

This valve opens to allow flow to the scram discharge

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volume.

I ASME Section XI, Subarticles M5f D @.S $ W @$@M N '

i j;

$(EGODEDIEQUIREMENTSEMg$hNPNd e g !L IWV-3411 'and IWV-3413 require

$5 E N M $l$52 S E E $$$E$$

Power operated valves to be 5$s$$$5$$$$:&SE8?$$E@dS0$$iI$$$E 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.

M h M M MP$ des @~sf @s k.

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.These valves operate

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!! RELIEF 3 REQUEST simultaneously when a

scram M y N $$kh @yn@$1USTh@EM (hjd valve's-are skid mounted with no V

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%sSQ

'l signal is present.

As these 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 power operated 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.

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Me Je ^&p?;:p Rdr;m a::esw Testing of the control rod drive SAL 555d/EN56ES$yINb)h5tdsdsE0ji

@i4S$$5?%M$3MMdh353?$JUjML.[glCd8 per Technical Specification 2%

4.1.3.2 will be performed in i T4d?indgt?$2@Fsys;MylKtssj@Md lieu of the code requirements..

The Technical Specifications -

require all rods to be tested following any core alterations and any prolonged outages (120 days).

Ten percent of the rods'are i

tested on a rotating basis every 120 days and any rod requiring, i

isg ested upon completion of the work.

This is in maintenance t

accordance with NRC Generic Letter 89-04, Attachment 1, Item 7.

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CLINTON POWER STATION SECTION XI RELIEF REQUEST

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RELIEF REQUEST NO. 2025

' COMPONENT INFORMATION i

h lve 1$8 (typical of,145 each) is a %" Category C check valve on the CRD hydraulic control units.

Valve 138 is the CRD cooling water check valve which must close upon reverse flow to allow the Reverse flow through this check valve could CRD-to insert.

impair the function of.the CRD.' See attached drawing.

CODE REQUIREMENT Sectio'n X', Subarticle IWV-3521 reqtiires check valves to be-I exercised to their safety position every three (3) months.

R'ELIEF REQUEST / JUSTIFICATION Failure of these valves to reverse flow exercise vbuld be.

identified by performing a " notch" test.

The notch test is required per -Technical Specificatiion 4.1.3.1.2 which tioves. 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 survdillance.

The CRD would " double-notch" if

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valve 138 did not properly exercise; A "d6uble-notch" is'where th'e CRD would not be 'able to move one notch at a time.

ALTERNATE TESTING

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Exercise valves by performin'g a " notch" test as described above (i.e., coniplying with Technical Specification 4.1.3.1.2).

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RELIEF REQUEST 2025

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ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2026 (Revision 1)

Diesel generator (DG) air start b@ff$$$6IM5i$7f53 RPM, M;cq dOMPDNENT@lNEORMAEi8N$$a i

valves,1DGOO8A-K are 1.5" power

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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.

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.ASME Sectioc XI, Subarticles F~5Isd$wesm e?ya$ M $$ggg sW3M IWV-3411. and Iwv-3413 require Ei$b 6BinGniS EMME@fj@@js@[g@@@X Mrg$@j power operated valves to be 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 relief request does not require'NRC approval.

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~r gg enclosed solenold valves with no ST

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It is not i

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 i

tests are designed to test the diesel generator as a unit, but do not specifically verify actuation.of each individual valve.

MTg$iI$!5$$E$$pMyyyydggggg@g No stroke time testing of these Mfk2 ES$$75fg g g gp g 3; p gjg g g fAERTE ma air start valves will be

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EM$@

3E5hMy4EMUSTi M Performed.

The air gauge 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.

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I ILLINOIS POWER COMPANY CLINTON POWER STATION j

SECTION XI RELIEF REQUEST RELIEF REQUEST NO. 2028 (REVISION 1) l COMPONENT INFORMATION

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Valve 1C41-F336 is a check valve. downstream of the Standby Liquid Control (SC) pump and is physically located inside the drywell.

This is an ASME Shetion III Class 1,Section XI Category A/C, 4-inch check valve.

The valve is circled on the attached drawing.

e CODE REQUIREMENT The ASI1E Code,Section XI, Subarticle IWV-3521 requires that this l check valve be full stroke exercised every three (3) months.

RELIEF REQUEST /JUSTIFICAT' ION Illinois Power Company requests relief from the Code requirement-for the following reasons:

This check valve is 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 i

Illinois Power Company will full stroke exercise this check valve

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every refueling outage.

The open direction exercise will b6 i

verified with. system flow and the closed direction exercise will be verified with a leakage test.

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ILLINOIS POWER COMPANY CLINTON POWER STATION l

SECTION XI RELIEF REQUEST i

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RELIEF REQUEST FO.2029 i

COMPONENT INFC.UATION Various Categcry-A/C check valves whose function is to hold pressure for a specified time in an air accumulator / receiver.

See attached list.,,

L CODE REQUIREMENT The ASME Code Section XI, Subarticle IWV-3424, specifies the methodology to be used for leakage testing.

RELIEF REQUEST / JUSTIFICATION Illino s Pcwer Company requests relief from the Code requirements for the following reasons:

facilitate the.

The design of these piping systems does not measuring of actual leak rate-through these check. valves.

i ALTERNATE TESTING PROPOSED these check valves as Illinois Power Company will leak test l

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follows:

In lieu of monitoring actual leakage rates through each check valve, a pressure drop test over a specified time will be This pressure drop test will not only verify the performed.

check valve has seated but will also~ verify the integrity of the f

piping system.

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ILLINOIS POWER COMPANY l

CLINTON POWER STATION SECTION XI RELIEF REQUEST j

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RELIEF REQUEST NO. 2029 a

IB21-rv9B 1B21-F039C ~

1B21-F039D 1B21-F039E o

IB21-F039H IB21-F039K l

1321-F039S i

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ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 2032 (Revision 2) w^

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m This Relief Request refers to NOMPONEN$,siNpdNNE$i6Sl@$ @

Power (Air) Operated valves with v y z.g: fW

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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 Table 2032-1.

These changes may be implemented prior to submittal of the revised table to the NRC.

The ASME Code Section XI, teas w;m ;

' -we Subarticle IWV-3417 (a) requires

[C$DNI55d5E5MEh..-.5kp%@

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increasing the testing frequency in m

to monthly for a 50% increase from the previous stroke time test.

ee w rr Per Generic Letter 89-04 these

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valves are defined as rapid n

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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 2 seconds), none of these minor increases in stroke time (1 valves were found to have a physical problem and all ~ were subsequently returned to normal frequency.

Illinois Power Company proposes JALTERNATEETESTINGNPROPOSEDR.J. f.m. _ A.JEBMMR M9M@,s to evaluate the test results for e

{, 7 m q u a g g gg q q g;, n 'i s k M 6 the air-operated valves on Table 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 valvo's stroke time increase by more than 50% from the valve's reference value, CPS will consider i

this to be an indication of potential valve degradation and g

increase the valve's testing frequency.

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Should any valve's stroke time increase beyond the valve's limiting stroke time value, the valve will be declared inoperable.

As this position is in accordance with the positions stated in NRC -

Generic Letter 89-04, no further NRC approval is' required.

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Table 2032-1

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EIN:

ORA 026 ORA 027 ORA 028 ORA 029 OVC010A OVC010B OVCO22A OVC022B 1833-F019 1 B33-F020 1C11-F010 1C11-F011 1 E51-F004 1 E51-F005 1E51-F025 5

1 E51-F026

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1FC023 1RE019 1RE020 1RE021 1RE022 1RF019 1RF020 1RF021 1RF022 1SA030 1SA031 1SX010A 1SX010B 1SX010C 1SX023A 1SX023B 1SX027A 1SX027B 1SX027C

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t Table 2032-1 (cont.)

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1SX029BL 1SX029C 1SX033 1SX037 1SXO41 A 1SX0418 1SX181 A 1SX181B 1SX185A 1SX185B -

1SX189 1SX193A 1SX1938 1SX197 1SX209 f,

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1VQ002 1VQ003 1VQ004A 1VOOO4B 1VQ005 1VR001 A 1VR001B 1VR006A 1VR0068 1VR007A 1VR007B

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ILLINOIS POWER COMPANY Clinton Power Station 1

ASME Section XI Relief Request RELIEF REQUEST 2033 (Revision 1)

Valves 1G33-F051 and 1G33-C.O M P O N E N T I N F.O R M A T I O N...

F052A/B are the injection check 3

"alves 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 ar'e 4-inch check valves of identical design and are circled on the attached drawing.

The ASME

Code,Section XI, CODE RElQUIREMENTS Subarticle IWV-3520 requires that these valves be full-stroke exercised individually every three (3) months.

1G33-F052A/B are parallel valves

RELIEFEREQUEST/ JUSTIFICATION.

in the piping system and both of these valves are in series with 1G33-F051.

These valves are located in series with no test connections provided between them to permit individual valve testing.

These valves cannot be individually exercised every three (3) months since they are located in the Steam Tunnel and physical access is restricted during normal plant operation due 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 differential flow signals and may cause containment isolation valves in this system to isolate and subsequently trip the RT pumps, which will likely require filing a Licensee Event Report (LER).

Either method will cause the RT system to be out of service and create potential delay for plant startup.

This will cause unnecessary hardship for Illinois Power Company without any significant gain in safety.

LALTERNATE TESTING PROPOSED.'-

Illinois Power will test these valves on a refueling frequency using either a

sample disassembly and inspection program or a non-intrusive method.

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ASME Section XI Relief Request RELIEF REQUEST 2034 l

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All 'Section XI, Category A

$ COMPONENT 81NpON AYIbNde %,17).

ry containment isolation valves pymg ; s' wpe y]e7 which require a leakage test per IWV-3420 as identified in Illinois Power's Pump & Valve Testing Program Plan.

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The ASME Code Section XI, m..s 1.f A /~ 1, 2 % M SN 95$#j@%.t^

Subsection IWV-3420, Valve Leak

$ CODE $ REQUIREMENTS $ig g$h ^; f r D f*

44% $fid@Ql M Rate Testing, requires leak rate

' 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.

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Illinois Power Company requests

{REUIEE2REDUEST/JUSTIFICA,TIONp re1ief from the Code Ms ~ '

"T ' ' hi Th&

requirements for the following reasons:

i 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.

By e'stablishing conservative acceptance criteria for a valve group (containment penetration) such that none of the valves can be significantly degraded, considerable savings in personnel radiation exposure and scheduling flexibility can be achieved.

This - approach is of benefit to Illinois Power and provides equivalent levels of quality l

and safety to those achieved through individual testing.

As the purpose of these valves is to isolate the containment, testing in

groups, i.e.,

by containment penetration, would verify the i

integrity of the containment boundary.

By establishing conservative acceptance criteria, the condition of the valves I

within reasonable limits can also be established by this method.

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The maximum permissible Icakage ALTERNATE TESTING, PROPOSED ^

rate for a specific containment penetration (inboard and

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outboard isolation valves 1

,1 combined) will be specified utilizing conservative acceptance l

criteria which allows for detection of valve degradation within

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reasonable limits instead of a leakage rate for individual valves

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as required by IWV-3426, Analysis of Leakage Rates.

to this relief request provides a technical basis for the acceptance criteria.

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 bygWV-3427, Corrective Action.

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Relief Request 2034 - Attachment 1

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The following is an idealized model of valve leakage as diagramed in Figure 1.

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The purpose of this model is to demonstrate that leakage, typical of the type of leakage which would be created by abrasive particles being ground across the valve seat, can be measured prior,to component degradation using an acceptance criteria of 20,000 standard cubic centimeters per minute (sccm). Using this acceptance criteria, leakage path size is calculated using a given differential pressure. This is typical of a problem encountered in the field when performing local leak rate testing (LLRT).

For the purpose of this calculation, the leakage path is assumed to be a square edged orifice. This assumption is representative of a scratch across a valve seat made by a abrasive particle or the type of leakage path which an LLRT is designed to measure.

Using the Reactor Coolant System as an example, the normal or average particle size is 18 microns 1, or 7.1 x 10-4 inches. As the calculation will demonstrate, 20,000 sccm is a conservative acceptance criteria which will allow adequate monitoring of component degradation prior to failure. Further, a valve which f "3 to fully seat will produce leakage rates wilich are several orders of magnitude greater than the acceptance criteria used for valve testing.

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FIGURE 1

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Where:

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O = flowrate in standard cubic centimeters per minute (secm)

(for this calculation the flowrate is 20000 secm)

(P -P ) = pressure differential in pounds per square inch (psid) l 3 2 (for this calculation the differential pressure is 9 psid)

X = the density of the medium in pounds mass percubic foot (Ibs IM) m i

( for this calculation the test medium is air with an assumed density of 0.076lbsm /ftN2 D = the full diameter of the test or component body 1

D = the orifice or corrosive particle diameter i

2 t

l Aj = the cross-sectional area of the test or component body A = the cross-sectional area of the orifice j

2 pi = the numerical constant 3.1415927...........

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l Using the Bemoulli obstruction theory 3 or a generalized flow obstruction, which can f

be written as follows:

[

E Q

2(P - P )

t 2

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{_-

4-D X

1-2 D

t t

This theory is based on the assumptions of incompressible, steady, frictionless, flow.

The validity of these simplifying assumptions for the range of test parameters of l

concem for valve testing (small differential pressures and low flow rates) was verified l

via experimentation using an LLRT machine and precisely machined orifices of various sizes. The results of this experimentation are tabulated in Table 1 of this j

discussion and are compared with calculated values using the same flowrates and l

differential pressures.

j Solving for D2 one obtains the following expression:

1 D4 A=4 Q

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2

=

2 2

2(P - P )

P1 P1 i

2 2

X 1-D(

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Because the orifice diameter D is very small in relation to the component diameter l

2 Dj theterm 1D 4

can be considered approximately equal to 1.

D tothefollowing:

This further simplifies the expression for D2 D =g Q

2 2(P -P )

Pt i

2 r

X Inserting numerical values and the appropriate conversion factors yields:

t 1*

3 f 1b cm D=4 min (2.54 cmj 2

2 1

p1 2

f Ibs3 f32.2 fil,f12ini.r60 sec3 h 1 ft j"ti min;

}y 2

3 I

lbs f 1 ft 1 0.076 12 inj l

2 = 2.06 X 10-3 in2 D

D2 = 0.045 in. or slinhtiv under2164 "

An orifice of this size is approximately equal to the size of the maximum leakage path allowed using an acceptance criteria of 20,000 socm. This is equivalent to 100 i

scratches of " normal" 18 micron size, which would represent valve wear over many t

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cycles, or a significant leakage path 100 times the size of a path created by one 18 micron abrasive particle.

Thus, a 20,000 sccm criteria can be utilized to monitor for degradation of several valves in the penetration group and is sensitive enough to identify significant problems.

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Table 1 j

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flow ('secm ) '

diff. press psid) l test'dia.( in)'

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1950 9.48 0.0156 0.0139 11.4 9.45 0.0313 0.0263

_16.0 7000 94000 ~ ~}.

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0.125 0.113 9.76

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this was the highest differential pressure the LLRT stand could maintain at this,large of an orifice size.

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- nitrogen testing medium - density = 0.07307 lbm /ft 2 As Table 1 shows, the error between the calculated data and the experimentally The Bernoulli model used in this calculation may be l

measured data is acceptable.

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..'

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conditions and instrument accuracies.

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. 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 l

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ILLINOIS POWER COMPA11Y Clinton Power Station ASME Section XI Relief Request l

l RELIEF REQUEST 2035 i

This Relief Request pertains to

{D_ISCUSSIOIE the qualification of personnel performing supervision of safety valve and relief valve testing.

The ASME

Code,Section XI, s.

(CODEshEQUIREMENTS.

Subarticle IWV-3512, 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 / JUSTIFICATION-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.

Illinois Power will qualify

. P.R O Pf:0 S:E DS LA.LMERNA.TE safety / relief valve test J

supervisors in accordance with

(REQUIR, MENTS:

E the Illinois Power Quality Assurance Manual.

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i ILLINOIS POWER COMPANY CLINTON POWER STATION SECTION XI RELIEF REQUEST

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m RELIEF REQUEST NO. -3001 (Revision 1) e

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COMPONENT INFORMATION Thesepumps(seeTabk.e3001-1) are to safely shutdown the. reactor or to mitigate the consequences of an accid'ent.

They include all These of'the pumps in the IST Program except the RCIC Pump.

pumps are identified in Table 3001-1 by their Equipment Identification Number, Name, and ASME Section III Code Class.

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' CODE REQUIREMENT The ASME Code Secti.on XI, Subsection IWP-4310 requires tire measurement of these pumps' bearing temperature annuall'y.

RELIEF REQUEST / JUSTIFICATION-~

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' Illinois Power Company requests relief from the Code requirements

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~

~for the following reasons:

The measurement of these pumps' bearing temperature annually does n'ot increase any confidence in the reliability of the pumps-because bearing temperature rises just minutes prior to failurs In order to measure this parameter, bearing of the pump bearing, f

temperature,is required ~to be stabiliz'ed 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. Thererore, deasurement of these pumps' bearing temperatures annually as required by the Code vill not.be performed.

ALTERNATE TESTING PROPOSED None.

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-Section XI/ISI/60

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I Table 3001-1 (Revision 1)

I' Identification Pump ASME Section III Name Code Class Number

2 l

1C41-C001A St'and,by Liquid Control (SL'C)

Pump A.

2 l

IC41-C001B Standby Liquid Condrol Pump-B 3

1D00lPA Diesel Oil Transfer Pump.A 3

l 1D00lPB Diesel Oil Transfer Pump B 3

1D00lPC Diesel 011 Transfer Pump C 2

1E12-C002A Residual Heat Removal (RHR) 1 Pump A 2

1E12-C002B Residual' Heat Rem 6 val Pump B lE12-C002C Residual Heat Removal, Pump-C' 2

IE12-C003 Waterleg Pump-2 1E21-C001 Low Pressure Core Spray-(LPCS,)

2 l

t Pump 2

lE21-C002 Waterleg Pumo 2

{

~ lE22-C001 High Pressur'e Core Spray (HPCS)

Pump' 2

lE22-C003 Waterleg Pump LE51-C003 Waterleg Pump 2

Fuel. Pool Cooling and Clean-Up Pump A 3

i

{;

IFC02PA ITCO2PB Fuel Pool Cooling and Clean-Up Pump B 3

t ISX0lPA Shutdown Service Water Pump A 3

ISX0lPB Shutdown Service Water Pump.B 3

ISX0lPC Shutdown Service Water Pump C 3'

j OVC08PA Control Room HVAC. Chilled Water-3

^

Pump A 3

i OVC08PB Control Room HVAC Chilled Water Pu=p B i

i f

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(

j Section XI. Tables /ISI/5

.... - - _. _ _..._... _ _ j

ILLIdOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST 3002 (Revision 3)

This relief request refers to

-COMPONENT :.lNFORMATION.

three (3) Diesel Fuel Oil (DO) transfer pumps (1DOO1PA, 1DOO1PB, and 1DOO1PC).

.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 differential pressure (DP) of 13 psid, with baseline flow rates ranging from 16.424 to 18.13 gpm.

The ASME

Code,Section XI, LCODEjREQUIREMENTS Subsection IWP-3210 tabulates the allowable ranges of inservice test quantities (flow rate) in relation to 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.

These pumps do not have flow DRELIEFfREQUEST/JUSTIFICATIONT rate instrumentation installed.

A calculation is used to determine a flow rate.

Because the DO 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 rate) 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 equipped 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 IDOO1PA and 1DOO1PB 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 1DOO1PC supplies only 1 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

i requirements of the diesel generator and the baseline flow rate provided by the DO. pumps, compliance with the Code requirements constitute a hardship with no appreciable gain in safety.

Illinois Power will calculate

?ALTERIATEhTESTING: PROPOSED the flow rate (Q) of the Diesel Fuel Oil Transfer Pumps by dividing the change in level of l

the diesel fuel day tank by the time the Diesel Fuel Oil Transfer l

Pump is in operation.

l Illinois Power will utilize the following Allowable, Alert, and Action ranges for Diesel Oil pump flowrates.

l Acceptable Range 2.94 and 5 1.10 of baseline flow Alert Range 2.90 and <.94 of baseline flow Action Range

<.90 of baseline flow

> 1.10 of baseline flow j

1 l

Based upon CPS's operating experience, Illinois Power believes that l

the revised upper ranges will provide good indication of pump l

degradation without the unnecessary burden of requiring the pumps to be tested on an increased frequency or declared inoperable for minor ( < 0.5 gpm ) variations in flowrates.

(SEE GRAPH 2) l i

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PUMP 1DOO1PA

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IWP ALERT RANGE LIMITS

+

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IWP ACTION RANGE LIMITS m;

PUMP 1DOO1PA PERFORMANCE i

to F8 APR JUN SEP DEC MAR APR JUL OCT

( 1991 -1992 )

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PUMP 1DOO1PA

( GRAPH 2) 20 b

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+ RR 3002 ALERT RANGE LIMIT RR 3002 ACTION RANGE LIMITS 12 -

U PUMP 1DOO1PA PERFORMANCE 10 i

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FEB APR JUN SEP DEC MAR APR JUL OCT

( 1991 - 1992 )

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_L ILLINOIS POWER COMPANY j

CLINTON POWER STATION SECTION XI RELIEF REQUEST

(

RELIEF REQUEST NO. 3003 (Revision 1) 1 COMPONENT INFORMATION The StEqdby Liquid Control (SLC) Pumps (1C41-C001A,and C001B) -

supply a neutron absorbing solution into the reactor in sufficient' ' concentration and quantity to overcome the mnr4m They are ASME Section III Code Class 2 positive reactivity.

These are positive displacement pumps which are pumps.

highlighted on the attached drawing.

~

CODE REQUIREMENT _

The ASME Code Section XI, Subarticle IWP-4600 requires measuring the pump's,flok rate. 'Subarticle IWP-4100 specifies the.

requirements for instrument accuracies, ranges, 'ecc.

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

(

installed which meets the above Code requirements.

ALTERNATE' TESTING PROPOSED

~

Illinois Power Company will calculate the flow rate (Q) of the J SLC pump by dividing the chattge in level of the SLC test tank by.

the time the SLC pump is in operation.

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l CLINTON POWER STATION SECTION XI RELIEF REQUEST

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RELIEF REQUEST NO. 3005 COMPONENT INFORMATION.

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~

The Sta'ndby Liquid Control Pumps (1C41-C001A and C001B) supply a neutron ' absorbing solution into the reactor in sufficient concentration and quant-it.f to overcome the mdrimum positive reactivity..These pumps are ASME Section III Code Class 2 and are, highlighted on the attached drawing.

CODE REOITIREMENT

^

The ASME Code Section II, Subsection IWP-3500(a) requires that when n'easurement, of the b. caring. temperature is not requirsd, these pumps shall be run at l' east.five (5) minutes under.

cotiditions as stable as the system permits.

At the end of th'is time, at.least one measurement 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:

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f' Plant demineralized water is utilized to perform the quarterly -

tests for these pumps.

The discharge of these pumps is collected in the Test Tank.. The capacity of the Test Tank does not permit i

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running these pumps for five (5) minutes.

Since these p'mps are positive displacement type pumps and the u

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.

Illinois Power Company will perform the required testing quarterly and all of the required parameters will be observed / measured and recorded after the pumps have been running.

j at least one minute but prior to i unning fo'r five miriutes..

14 h-I Section XI/ISI/64

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ILLINOIS POWER COMPANY

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Clinton Power Station ASME Section XI Relief Request l

RELIEF REQUEST 3006 (Revision 1)

~.n.n.me unagg This relief request pertains to d< u. m B C 3 M %a,.~.sCOg DNEljTEINFORMATION5 %yy y;m:spgf the four (4) water-leg pumps

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MidkrNdg~ < % W [ dygggyi (1E12-C003, 1E21-C002, 1E22-C003, and 1E51-C003) in the CPS IST program.

These pumps are required to maintain the water level in the associated ECCS systems to ensure the prevention of a water-hammer transient in the event of an ECCS initiation.

In addition, these pumps have similar characteristics. All four are Gould model 3196 ST, with the primary difference being impeller diameter. They are tested at flows ranging from 50 to 64.5 gpm with baseline differential pressures (DP) ranging from 44.4 to 48.3 psid for the

~

1E12-COO 3, 1 E 2 1'- C 0 0 2, and 1E22-C003 pumps and 29.4 psid for 1E51-C003. All pumps are ASME Code Class 2.

v tegu m:e>xpwmew wwm The ASME Code Section XI, Np w w$NEOUYR$NNN@$ k M } @ $p d65 Subsection IWP-3210 tabulates I

$$MN$$$dMMS%N#4IEMShM} E the allowable and alert ranges (5

of inservice test quantities (differential pressure (DP))

in relation to the reference, or baseline, values. Table IWP-3100-2 r.equires an acceptable DP range of 0.93 baseline DP to 1.02 baseline DP and an alert range of 0.9 baseline DP to 1.03 baseline DP.

2.

M $32M C E Rggggy Because the water-leg pumps h@%V@g~Q@j.5 E MhW VM~?

REJ EEE~REQUESTfJUSTIE1 CATION W operate at a low DP and the, Code 9fyg specified acceptable ranges are based 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 is operating within design parameters.

Using data for the HPCS water-leg pump (1E22-COO 3) as a

representative example, which has a baseline DP of 48.5. psid, the Code-required acceptable range varies from 45.1 to 49.5 psid, or less than 4.4 psid (SEE GRAPH 1).

Likewise the Code-required alert range for 1E22-C003 varies from 43.7 to 50 psid, for a range of 6.3 psid.

L CPS believes the lower acceptable and alert range boundaries (0.93 1

and 0.9 of baseline DP) are achievable without undue hardship.

However, based upon the Code required upper acceptable and alert i

range boundaries of 1.02 and 1.03 baseline DP) a deviation of only b

1.0 psid above baseline DP is sufficient to force any of the CPS r

waterleg pumps onto increased frequency, and an increase greater

than 1.5 psid above the baseline DP will place the pumps in the

(

action range.

s......c. AM.M?$M L.95% n....... j Illinois Power will utilize the' 4AL,TERNAT.E?TE --. M O

following allowable, alert, and

'M tend /yr, c STIN, G.n"P.,R.n POSE. DWF

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n-9 49W J / ^ - OE ' A action ranges for water-leg pump differential pressure.

Acceptable Range (0.93 to 1.05) x (baseline dp value)

Alert Range (0.90 to 1.10) x (baseline dp value)

Action Range

< (0.90) x (baseline dp value)

> (1.10) x (baseline dp value)

Based upon CPS's operating experience,. CPS feels that the revised upper ranges will provide 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 psid) variations in DP (SEE GRAPH 2).

CPS has evaluated minor fluctuations of this type and has determined that this performance is not an indication of pump degradation, and the pumps are operating within design allowable limits.

(

In addition, as these pumps are normally running, line pressure is continually monitored via pressure transmitters by the Main Control Room and any failure'will be immediately observed by Control Room personnel.

(

9

JUV3 LE22'-C003 (GRAPH 1)

BASEO UPON A. FLOW RATE (Gr).

OF 64.5 gpm e

54 c.

s2 -

51 -

REQU D ALER FIA UPPER BOUND x W

l7i

l

); px

l x

274 'l x

l X

X yx

'j sc:

7 IWP MEGDIFIED 'ACdEPTABCE AANUE UPPB

' BOUND '+

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==

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BASEL.INE =

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DP (psid) n.

45-e_

,.-IWP REQUIRED ACCEPTABLE RANGE LOWER BOUND +

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IhPNEGUIRhDSLEhTRANGEL0lkERBOUNDx 42-41-JL4 FEB XAR M KAY ME JULY M EPT OCT trJV DEC M FEB XAR M KAY M E JULY M. SEPT OCT lOY DEC 1,,

1991

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JUV3

. E22-C 00 3 (GRAPH 2)

BASED UPON A. FLOW RATE (Gr).

OF 64.5 gpm ss RELIEF REQUEST 3006 ALERT RANGE UPPER BOUND x "d

x x

53-u.

RELIEF REGUEST 300 AC QP. TABLE AN p : UPPER BOUND +

51 so e-

=

m a

a a

=

m a

a a

=

m a

a

=

BASELINE =

4 DP (psid) 47 -

e -

e_

RELIEF REQUEST 3006 ACCEP. TABLE RANGE LOWER BOUND +

s yx x

x x

x c_

RELIEF REQUEST 3006 ALERT RANGE LOWER BOUND x 42-41 -

5, FB na W MY JuE JULY AUG SEPT OCT t0Y DEC JAN FE XAA APR XAY JJtE Ja.Y At.G SEPT DCT 10V DEC 1991 19 ' '

ILLINOIS POWER COMPANY Clinton Power Station ASME Section XI Relief Request RELIEF REQUEST NO. 4001 (Revision 2) l l

I l

l Several ASME Class 2 lines are COMPONENT-INFORMATION 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.

~

The ASME Code Section XI,

= CODE REQUIREMENTS 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 supports for those components required to be examined under subsection IWC-2500.

Illinois Power Company requests RELIEF REQUEST / JUSTIFICATION that the lines on page 2 and associated component supports be exempt from the Code requirements for the following reasons:

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 ), allows lines meeting the above conditions to be exempt from 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 and would have no adverse safety impact on the plant.

None ALTERNATE: TESTING PROPOSED Page 1 of 2

i i

l Class 2 Open-Ended Lines

)

The following lines are in open-ended systems and require relief from examination-l 1HG05AA-6" 1HG05AB-6" l

1HG05BA-6" l

1HG05BB-6" i'

1HG05CA-6" 1HG05CB-6" 1HG06AA-10" 1HG06AB-10" 1HG06AC-10" 1HG06AD-10" 1RH30BA-12" i

1RH30BB-12"

{

1RH30CA-12" I

1RH30CB-12"

{

1RH30DA-12" i

1RH30DB-12" i

1RIO8B-12" l

1RIO8C-12" i

l 1

Page 2 of 2

. - ~.....

=

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ILLINOIS POWER COMPANY.

CLINTON POWER STATION SECTION XI RELIEF REQUEST RELIEF REQUEST NO. 4003 (Revision 1) k#

COMPONENT INFORMATION All component supports requiring VT-3 and/or VT-4 examinations.

j i

CODE REQUIREMENT SubarticleINR-2500andTable1WF-2500-1requirethatavisual examination, VT-3 and/or VT-4, be performed each inspection interval for the supports described above.

RELIEF REQUEST / JUSTIFICATION f

Illinois Power Company requests relief from performing any VT,

I examinations-for the following reasons:

1.

The definition of VT-4 examination in the 80W81 Code does not clearly < identify the attributes to be considered in I

developing the inspection criteria.

l 2.

Functional testing of snubbers required by Clinton Power Station (CPS) Technical Specifications is more. stringent j

i than this-Code requirement.

3.

The 83W84 Code has been clarified by combining;the. Visual i

Examinations VT-3 and VT-4.

(

If relief isigranted, Illinois Power will update the applicable-I procedures to not only' delete the' references to VT-4, but to include the revised VT-3 examination requirements from the 83W84 l

. Code in our program.

ALTERNATE TESTING PROPOSED i

Illinois Power will perform VT-3 examinations using the~

i definition'from the-83W84 Code in lieu of performing VT-3 and-VT-4 examinations in accordance with 80W81 requirements.

l Functional testing will be performed in accordance with CPS Technical Specifications.

r l

l 1

-Section XI/ISI/83 i

s m

~. -..-

'S ILLINOIS ?OWER COMPANY CLINTON POWER STATION SECTION X.I RELIEF REQUEST RELIEF REQUEST NO. 4004 (REV. 1) i i

COMPONENT INFORMATION I

Hydraulic and mechanical snubbers associated with the piping lines included in the Clinton Power Station (CPS) Inservice Examination Program Plan.

CODE REQUIREM$NT The ASME Code specifies visual inspection frequencies for the above supports in Table IWF-2500-1 and functional testing frequencies in Subarticle IWF-5400.

In addition, corrective actions with regard to selecting additional supports are specified in IWF-2420, IWF-2430, and IWF-5500.

i l

RELIEF REQUEST / JUSTIFICATION l

Illinois Power Company requests relief from the requirements identifie'd above with regard to frequency of inspection and testing, and corrective action.

This relief request is justified because the CPS Technical Specification 4.7.4 specifies inspection and testing frequencies for these supports which are generally more restrictive than the Code requirements.

Tracking the completion of inspection and i

testing activities with regard to both ASME Code and technical

i specification requirements creates additional administrative work E

without significant benefit in snubber reliability.

l' ALTERNATE TESTING PROPOSED Visual inspection and functional testing frequencies and corrective action for selecting additional or successive supports for testing will be as specified by CPS Technical Specifications.

i Visual inspection of those snubbers initially selected for functional testing during each outage will be performed.in accordance with ASME Code requirements for VT-3 inspection.

All other visual inspections will be performed in accordance with CPS Technical Specification requirements.

l l

i i

/

'i Section XI/ISI/84-

. -.

ML20034E746

Text

==C>

==

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