PY-CEI-NRR-0716, Informs That Testing & Review of Updated Inservice Testing Program for Pumps & Valves Identified Need for New Relief Requests.Listing of New & Revised Relief Requests Encl.Fee Paid

Informs That Testing & Review of Updated Inservice Testing Program for Pumps & Valves Identified Need for New Relief Requests.Listing of New & Revised Relief Requests Encl.Fee Paid

ML20235Z457
Person / Time
Site:	Perry
Issue date:	10/16/1987
From:	Edelman M CLEVELAND ELECTRIC ILLUMINATING CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
PY-CEI-NRR-0716, PY-CEI-NRR-716, NUDOCS 8710210156
Download: ML20235Z457 (106)

Text

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o COMPANY i

f .THE CLEVELAND ELECTR P.O.

Murray R. Edelman DOX 97 e PERRY, OHIO'44081 e TELEPHONE (216) 259-3737 e ADDRESS-Io CENTER ROAD Serving The Best Location in the Nation PERRY NUCLEAR POWER PLANT

$R. VIG PRFJilDENT NUCLEAft

, Octobe r 16, 1987 PY-CE1/NRR-0716 L Document Control Desk

.U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i Ferry Nuclear Power Plant Docket No. 50-440 Pump & Valve Inservice Testing Program Gentlemen:

The Perry Nuclear Power Plant Unit 1 Inservice Testing (IST) Program for Pumps and Valves (document No. 80 A5237 Rev. 1 ) wa s mos t recently updated and reviewed by PY-CEI/NRR-0618 L, dated April 15, 1987.

Subsequent testing and review has identified the need for new relief requests, I and revisions for several previously submitted. A listing of the new and revised relief requests is attached for revision 4 to the IST Program. For j your convenience, a complete set of relief requests is also provided in I I

Attachment 2 to this letter.

Relief request VR-54 is consistent with our recent request (PY-CEI/NRR-0714 L and 715 L) to defer local leak rate testing of high pressure isolation valves.

1 Pur suan t to 10 CFR 170.12, we have included an application fee of $150.00.

Please contact me if you have any questions. f Very truly o s, 8, uy

/ NW 8710210156 871016 PDR P ADOCK 05000440 PDR Mur ray R. Ede man

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Senior Vice President '8 Nuclear Group O g

MRE: cab Attachment cc: T. Colburn 1 O d

R. Connaughton 5 USNRC, Region III I

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REVISIONS!AND ADDITIONS TO PNPP PUMP-AND VALVE IST PROGRAM

' Revision 4 1 Relief R'equest No. .Commente GR-2' New-Requests-relief from ASME$Section-XI requirements.for_ containment' isolation valve seat leakage' testing. Testing vill. l'

'be in accordance with 10CFR50, Appendix J.-

VR-29 Revised-Deleted valve 1P43-F722 and added 1P51-F563. . Revised' testing requirement to take credit for Dryvell. Leak Rate Testing. Valve'1P43-F722 is addressed by_.

VR-55.'

VR-51 Revised-Added Div. 1 and 2 Standby' Diesel Generator Starting Air (1R44) to take credit for valve exercising'during Diesel Engine starts.

VR-53 New-Requests' relief from quarterly exercising'due to an interlock which-prevents valves from opening with Reactor Vessel Pressure above 135 psig.

VR-54' New-Requests' relief from two year seat leakage testing. Testing would be .

performed during refueling outages only.

VR-55 New-Requests relief from quarterly

' exercising. Valve vill be exercised during refueling outages.

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-PUMP AND VALVE. INSERVICE TESTING PROGRAM' .

, FURL PERRY NUCLEAR:POVER PLANT.

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.z- UNIT l' Preparerd By CLEVELAND ELECTRIC ILLUMINATING COMPANY Perry,' Ohic

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Generic Relief Requests >j ,.  ;.. j A-g#} ' . ( (, 1

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M' :2.0 INSERVICE TESTING'PROGRMi F0f! PUMPSt '- (4 . INv ,

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2.1.4 .Allovable. Ranges of' Test Parae h(rs

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2.3 Pump. Testing' System Index and Test Tables f /. 25 i 3 ;i

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2. 3.1 - Pump Testing

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.2.3.2 -Pump Test

• Table Nomenclature 17 '- fj g'

2.3.3 Pump Test *' Table Notes 7

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3.0 INSERVICE TESTING PROGRAM POR VALVES: s 32 t =I

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' 3.2 Relief Requests for Inservice t/s).ve Testing Program 41 3.3 Valve' Testing

• System / Attachment Index 98 I

• Note Pump and Valve test tables omitted from letter PY-CEI/NRR-0716 L l'o  !

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( 9 1.0: INTRODUCTION V) f-t l de The Perry Nuclear Power Plant ASME Inservice Testing Program for Pumps yA s and Valves will be in effect through the first 120 month inspection I ,

,' period and will be updated in accordance with the requirements of 10CFR 50.55a(3),

3 Ns documet.t outlines the inserjice testing (IST) program based on the u q' r ~ir:quirements 6f Section XI of the ASME Boiler & Pressure Vessel Code, Km 1983 Edition through the Summer 1983 Addenda. All references to IWP or h

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IWV; respectively,ofASMESectionXI,reflectthe1983Editionthrough

.the. cmmor 1983 Addenda, unless otherwise noted.

1e i ervice inspection (ISI) classification boundaries are identical to th 'o'esign classificatiory or quality group boundaries shown on the plant pi>Sg god Instrument diagrams (P& ids). Some pumps and valvos within the ISI boundaries are J.dentified as.non-classed (NC). This<IST program was developed tuing the ISI classification boundaries and the following documents: /

Title 10,, Code of Federal Regulations, Part 50, Paragraph 50.55a(g).  !

NRC Regulatory Guides Division 1.

Standard Review Plan 3.9.6, " Inservice Testing of Pumps and Valves.:

cy Division f (draft) Regulatory Guide and Valve / Impact Statement, 1 "IdentificationLof Valves for Inclusion in Inservice Test Programs."

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"NRC htbif Guidance for Prephring Pump and Valve Testing Programs and Assdciated Relief Request," November, 1981.

t Final Safety Analysis Report, Pe:ry Nuclear Power Plant.

r Technical Specifications, Perry Nuclear Power Plant.

'A The inservice tests identified in this program will verify the operation-h . al readiness of pumps and.valver whose functions are required to mitigate 4/ the consequences of an accident or to bring the reactor to a cold shut-down condition or maintain the reactor in a safe shutdown condition.

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GENERIC M . .c RELIEF REQUEST

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COMPONENT: 'All, I y, ..

'As Applicable.

FUNCTION: . i v ,

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' TEST REQUIREMENTS: -ASME Section XI Subsection IWP and IWV., '!

c Throughout the refueling cycle, numerous cold. shutdowns.of.-

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- BASIS FOR' RELIEF:  ;

..relatively sitort durations can occur.Section XI requires  !

.c inservice testing to' corranence' during each shutdown.

Sufficient time is needed to make scheduling arrangements, appropriate valve line-ups, ALARA considerations, and.-

system adjustments prior to testing. Therefore, sometime is required to prepare for inservice. testing.

ALTERNATE TESTINGi Inservice testis; di .;A commence no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />  ;

after cold .% n y u. e.e dition:is-achibved; and will l conting e .i all te.si.ing is completed or the plant is

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n*dF e .. return to power. For planned shutdowns of  !

.g . sc hicient duration, all required testing will be com-

P leted. '

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RELIEF REQUEST GR-2 COMPONENT: All Category A, AC Containment Isolation Valves .

I FUNCTION: As Applicable CLASS: 1 and 2  ;

i TEST REQUIREMENTS: For Sectien XI Category A valves, IWV-3426 requires ths j establishment of individual valvo pu missible leakage -i rates, .Each time leak-rate r.sts are performed the test results are to be compared with the previous test'results and the permissible leakage rates. IWV-3427 establishes j test result rejection criteria and specifies ccrrective actions to 'ae taken.

BASIS FOR RELIEF: IWV-2200(a) defines Category A valves as " valves for which seat leakage is limited to a specified maximum amount in the closed position of fulfillment of their function."

The intent of the Code requirement is to verify that valve leakage is limited to an acceptable value. For containment isolation va?ves an acceptable total allowed leakage rate 6 has been established in compliance with the requirements q~j'. of 10CFR50 Appendix J. Performance of Appendix J, Type C Local Leak Rate testing fulfills the intent of Section XI Category A valve seat leak testing for containment .

1 solation valves. 1 ALTERNATE TESTING: Containment isolation valves will be local leak rate tested to the requirements o'. Appendix J. Type C Local Leak Rate testing in lieu of Section XI Category A individual valve testing.

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PUMP AND VALVE INSERVICE TESTING PROGRAM' FOR PERRY NUCLEAR POWER PLANT UNIT 1 i

SECTION 2

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p. 2.0 INSERVICE TESTING PROGRAM FOR PUMPS k' 2.1l'GeneralInfprmation  !

.2.1.1 Applicable Code .]

This testing program for ISI Class 1, 2 and 3 pumps meets the i requirements of Subsection IWP of Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through the Summer of 1983 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included in Section 2.2.

2.1.2 Pump Program Tables The tables in Section 2.3.4 list all pumps included in the Perry Nuclear Power Plant (PNPP) IST Program. Data contained in these tables identifies those, pumps subject to inservice. testing, the inservice test quantities to be measured, the inservice' testing frequency, and any applicable remarks. The column headings 6te listed and explained below:

PUMP IDENTIFICATION

1. SYSTEM: The system of which the pump is a component.

1 c.s 2. PUMP NUMBER: The pump identification number.

\ ] 3. P&ID NUMBER: The PNPP drawing number for the P&ID referring i '

to the pump.

4. P&ID COORD: The drawing coordinate location of the pump on ,

the P&ID.

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5. ISI CLASS: The ISI classification of the pump.

ISI REQUIREMENTS j i

l PUMP SPEED, INLET (SUCTION) PRESSURE, DIFFERENTIAL PRESSURE 1 (AP), FLOW RATE, VIBRATION, BEARING TEMPERATURE AND LUBRICANT ]

LEVEL OR PRESSURE: When the symbol "X" appears in a particular 1 measured parameter column, that quantity will be measured during inservice testing in accordance with Subsection IWP. If a modified test is planned or a test is being waived, a numer-  !

ical integer, which refers to a Pump Test Table Note (Sec- ,

tion 2.3.3.), shall appear in the measured parameter column.  !

Requests for relief are identified with the letters "PR" under l the measured parameter column in the test tables. The requests j for relief are included in Section 2.2.

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%' SPEED: Per IWP-4400, shaft speed need not be measured for pumps  ;

directly coupled to synchronous or induction type motor drivers. '

For variable speed pumps, the pump speed is set at the. reference .

speed per'IWP-3100. l INLET (SUCTION) PRESSURE: .For submerged pumps, inlet pressure I I

will be calculated (using appropriate correction factors) trom a measured tank or' basin level. All other inlet pressure measurements will be taken using pressure instruments at or near the pump inlet.

'- DIFFERENTIAL PRESSURE: Differential pressure will be calculated i from. inlet and discharge pressure measurements or by direct differ-ential pressure measurement.

FLOW RATE: Flow rate will be measured using a rate or quantity meter installed in the pump test circuit.

VIBRATION: Pumo vibration will be measured as close as possible to the inboard bearing, in a plane approximate perpendicular to rotating shaft, in a horizontal or vertical direction that has the ,

largest deflection for that particular pump. At least one displace-ment and one velocity measurement will be taken with one of the instruments referenced in IWP-45.'0.

q BEARING TEMPERATURE: .

Pump bearing temperature (s) will not be y measured. (Relief Request PR-1.)

LUBRICANT LEVEL OR PRESSURE: Pump lubricant level or pressure will j be observed during each inservice test, when applicable. l l

2.1.4 Allowable Ranges of Test Parameters The allowable ranges specified in Table IWP-3100-2 will be used for differential pressure, flow and vibration measurements except as discussed. Should a measured test quantity fall outside the allow-able range, the possibility of defining an expanded allowable range, i, in accordance with ASME Code interpretation XI-1-79-19, will be l investigated.

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2.1.5 Instrument Accuracy j Allowable instrument accuracies are given in Table IWP-4110-1. If i the accuracies of the station's instruments are not acceptabis, temporary instruments meeting those requirements in Table IWP-4110-1 will be used. q l

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RELIEF REQUESTS FOR INSERVICE PUMP TESTING PROGRAM i

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Pump Relief Request #

PR-1 1

System: As applicable

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tPumps: IC41-C001A 1E22-C003 1P42-C001B 1R45-C002A 1C41-C001B 1E32-C001 1P45-C001A 1R45-C002B C41-C002A' IE32-C002D IP45-C001B 1R45-C002C C41-C002B 1E32-C00?F 1P45-C002 1E12-C002A 1E51-C001 P47-C001A.

1E12-C002B 1E51-C003 P47-C001B 1E12-C002C G41-C003A P49-C002A

.1E12-C003 G41-C003B P49-C002B 1E21-C001 1M51-C001A 1R45-C001A i 1E21-C002 1M51-C001B 1R45-C001B 1E22-C001 1P42-C001A 1R45-C001C Class: ASME Class 2 and 3 l

l Function: As applicable'

. Test Requirement: IWP-4310, Bearings - temperature of all centrifugal pump bearings'outside the main flow path and of the main shaft bearings of reciprocating pumps shall be measured at points selected to be responsive to changes in the

,, -~s temperature of the bearing. Lubricant temperature, when

( ) measured after passing through the bearing, and prior to entering a cooler, shall be considered the bearing temperature.

Basis for Rellof:  !

l (a) Some of the pumps addressed in this relief request are cooled by their respective process fluid, " Main Flow Path." Thus, bearing temperature measurements would be highly dependent on the temperature of the cooling medium.

i (b) Pump bearing temperature is taken at (1) one-year intervals, only, which provides very little data toward determining the incremental degradation of a bearing, nor does it provide any meaningful trend data.

(c) Except for: the Emergency Service Water Pumps IP45-C001A, B and C002; the Residual Heat Removal Pumps 1E12-C002A, l 1E12-C000B and 1E12-C002C; the Low Pressure Core Spray '

Pump 1E21-C001; the High Pressure Core Spray Pump 1E22-C001, the ESW Screen Wash Pumps P49-C002A and P49-C002B which are

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submerged under water, all pumps addressed in this relief request will be subject to vibration measurements per subsection IWP-4500. Vibration measurements (displacement and velocity) are a significantly more reliable indication of pump g-'g bearing degradation than that of temperature measurements.

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Alternate Testing:

Vibration measurements shall be taken on all pumps identified

'above as' required by ASME Section XI Subsection IWP-4500, except as noted in paragraph "c", above. Additionally, vibration measurements using velocity as a measured value shall be taken on each pump in the same locations as the. required displacement measured values.

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,  : Pumps 17 10412 00'0!A' 1E22-C003' J1P42-C001B  ;1R45-C002A

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IC41-C001B s1E32-C001 1P45-C001A 1R45-C002B C41-C002A( 7 1E32-C002B. IP45-C001B .IR45-C002C IP45-C002' C41'-C002E - IE32-C002F

'1E12-C002A > 1E51-C001 P47-C001A:

,7 , '1E12-C002BL 1E51-C0031 3 P47-C001B

-1E12-C002C - 'G41-C003A P49-C002A

~1E12-C003 G41-C003B P49-C002B

.1E21-C001 -1M51-C001A: 1R45-C001A

,, 1E21-C002l _1M51-C001B 1R45-C001B' '

"R-1E22-C001 1P42-C001A' :1R45-C001C ,

' Class: ~ASME Class 2 and.3-

%~ $ Eundt%on:'As~ Applicable .

gs Test' Requirement:- :-IWP-3220.: Time. Allowed for Analysis of Tests .all test .

i: , data shall.be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of a .: t es t .

/ Basis for Relief: . Test.' acceptance criteria is contained within the. test u

. procedures, and the initial approval of equipment opera-

bility is by.on-shift personnel. The analysis of.results for degradation requiring increased testing'or engineering evaluation will then occur when the appropriate personnel:

are available for reviewing the inservice pump test' data The appropriate personnel'are not always readily availabic for this review effort.

Alternate Testing: . Test data shall be reviewed within four (4) work days

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following the test, excluding weekends (Saturday & Sunday) and Holidays, within the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />' time frame.

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!' V PR-3 System: Standby Liquid Control System I

Pumps: 1C41-C001A and IC41-C001B l i

Class: 2 i

Function: Provides a method of shutting down the reactor without use of the  ;

1 control rods.

Test Requirements: IWP-3300; Scope of Test - measurement and observation of l inlet pressure (P1) and differential pressure (Pd) across >

the pumps.

IWP-4520(b); Instruments to Measure Amplitude - The

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frequency response range of the readout s; stem shall be 1 from one-half minimum speed to at least maximum pump shaft l rotational speed. j Basis for Relief: The standby liquid control pumps are required to supply j the necessary flow rate at a given system pressure. The inlet pressure (no installed test equipment) is equivalent to the static head provided by the test tank. Test tank  !

n level is established within the inservice test procedures.

l*) . Also, the measurement of inlet pressure on a positive displacement pump is not a significant test parameter.

The system resistance is varied to establish tFe measured and observed discharge pressure as the ;eference value. l Flow rate is measured, observed and monitored to verify l pump operability and degradation.

The SLC pumps are positive displacement with a shaft j rotational speed of 360 revolutions per minute (RPM). The ]

amplitude frequency response range is 180 RPM which  !

corresponds to a frequency of 3 cycles per second (cps).

The International Research and Development (IRD) vibration instrument is calibrated to 5 cps even though it measures the entire frequency spectrum. The calibrated frequency range adequately covers pump induced inputs. q Alternate Testing: Utilize pump discharge pressure reading in lieu of pump l differential pressure reading and verify test tank level 1 to ensure adequate suction pressure. The IRD equipment shall only require calibration to as low as practical  ;

(approximately 5 cps). 1 TN U .

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PR-4 -

-System: .Waterleg Fill Pumps (RER, LPCS, HPCS, and RCIC) 7 Pumps: 1E12-C003, 1E21-C002, 1E22-C003, and 1E51-C003 Class: 2-Function: Waterleg pumps maintain the discharge piping of safety-related q systems full to expedite flow during initiation, and to minimize the likelihood of system damage due to water hammer, i

Test Requirements: -IWP-3100; Inservice Test Procedure - measure, record, and compare inlet (suction) pressure Pl.

l IWP-3300; Scope of Test - measurement and observation of inlet'(suction) pressure Pi stopped.

IWP-4600; Flow measurement'(Accuracy), IWP-3230 (a) corrective action (alert range), and IWP-3230(b) corrective action (action range).

Basis for Relief: The securing of waterleg pumps (RHR, LPCS, HPCS and RCIC) to measure the suction pressure stopped would serve no

.f~s useful purpose, since an adequate net positive taction

'" ) head (NPSH) is. verified by proper suppression pool or condensate storage tank level. These levels are  ;

maintained per Technical Specification requirements. j Also, securing these pumps will require filling and  ;

venting the safety-related system increasing the duration o

that the sistem ir. In a non-standby readiness mode.

The starting of the waterleg pumps has shown no deviation in running or stopped pressure for RHR, LPCS and HPCS.

The waterleg pumps have a capacity of 40 gpm and a minimum flow design requirement of 10 gpm. Flow rate shall be measured with sutvey flowmeter (approximately iS%  !

accuracy). The pump can meet the design ft.netion with as much as 75% degradation. Therefore, relief from accuracy requirements and alert / action ranges adequately allows assessment of pump operability.

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.PR-4;(Continued) k4.) . o w" 'LAlternate Testing: : The inlet suction pressure shall be measured using.

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, suppression. pool level (RHR and LPCS) and condensate

. storage tank pressure (HPCS), The suction pressure-q 4 stopped shall not be measured or observed. . Measurement of: j

.., flov i sha11Lbe performed with a survey flowmeter 1 (approximately 15% accuracy) and corrective action ranges for. flow shall be: '50%' degradation' alert range and 75%'

degradation' action' range.

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PR-5

' System: MSIV Leakage Control (E32), Combustible Gas Control (M51')=

Pumps: 1E32-C001, IE32-C002B, 1E32-C302F, 1M51-C001A, IM51-C001B-C1.ss s : 2

' Function: The blowers provide.: 1) MSIV LeJkage Control (E32) - a means to control and minimize the' release of fission products which may le'k a through the closed MSIVs after a Loss-of-Coolant Accident (LOCA) and

2) Combustible Gas Control (M51) prevent flammable hydrogen concentrations from forming in the containment vessel or drywell following a Loss-of-Coolant Accident (LOCA).

' Test Requirements: IWP-3300, Scope of Test - measurement and observation of flow (Qf), inlet pressure (P1), and differential pressure ,

I (Pd).

Basis for Relief: Although the blowers may fall within the definition of -i pumps, they do not have hydraulic characteristics-that will show blower degradation; the afore, only the mechan-ical characteristics will be moni:: cared. l I

f se Alternate Testing: Perfarm testing of the mechanical characteristics in J, ) - conjunction with PNPP Unit 1 Technical Specification, f 4

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System: . ' Ercergency Core Cooling Systems- (E12, E21, E22).

Emergency Service Water System (P45) l- ESW Screen Wash (P49)-

Pumps: IE12-C002A, IE12-C002B, 1E12-C002C, 1E21-C001, 1E22-C001^ ,

IP45-C001A, 1P45-C001B, 1P45-C002, P49-C002A, P49-C002B O Class:

2 and 3..

Function: The Emergency Service Water Pumps provide the cooling water to support the safety.-related shutdown systems.

The ESW Screen Wash' Pumps provide clean water to the spray.nor.zles

for cleaning debris'Lfrom'the ESW traveling screens. The~ pumps also supply flushing watei to the ESW screen tray.

The Emergenty Core Cooling Systems-(RHR, LPCS, HPCS) Pumps are used to supply water to the reactor vessel during plant' abnormal

. conditions.

Test Requirement - IWP-4500;. Vibration amplitude-- location shall generally be on.a bearing housing or its structural support, provided it is not separated from the pump by;any

-; resilient mounting. On a pump coupled to the driver,.the

' measurement'shall be taken on the. bearing housing near the coupling;'on close-coupled pumps, the. measurement point shall be as close as possible to the. inboard bearing.

Basis for Relief:~ The Emergency Service Water Pumps, ESW Screen Wash Pumps, and ECCS. Pumps are totally submerged under water making the required vibration testing impractical, however, the motor drivers are shaft connected to the pumps and are accessible.

Alternate Testing: The vibration measurements shall be taken, as scheduled on a quarterly basis, on the lower bearing or its structural.

support, closest to the pump driver motor stuffing box assembly.

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-- Pumps i. IP45-C001A, IP45-C001B,'-1P45-C002, P49-C002A, P49-C002B ,

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Function:!The' Emergency Service Water Pumps provide the cooling water to support'the safety-related shutdown systems.

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The ESW Screen. Wash Pumps provide clean water;to'the spray nozzles for tleaning debris from the ESW, traveling screens. The pumps also' supply flushing water to the ESW screen tray.

<Tokt. Requirements:._ Measure, record, and compare inlet-(suctinn) pressure Pi

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. Per'IWP-3100.

. Basis..for. Relief: 'An' inlet (suction) pressure gauge is not prr 4t

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-Emergency Service Water. Pump 3 or: ESW Screen h.-n Pumps. ~

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The pumps have cul inlet-pressure dependent upon Lake Erie t

Ewater level. Calculation of this static' head between Lake ~

level and pump inlet sha11' adequately ~ provide the necessary inlet pressure.

. Alternate' Testing: .Calbulate the static head between Lake Er'io water level.

- and-the pump suction.for inlet suction pressure. l l

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j?' Pumps:'  : P49-C002A and P49-C002B:

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, , Function: The'ESW Screen. Wash'Ptmps provide clean water to the. spray. nozzles  !

' l for cleaning-aebris from the ESW traveling screens. The: pumps,

( , also,' supply flushing water to the ESW screen ~ tray, n .

' Test Esquirementst. .IWP-4600 Flow Measurement (accuracy), IWP-3230(a) correc--

tive.actionL(alert range), and IWP-3230(b). corrective actionf(action range).

E y -Basia~for~ Relief: Flow rate will-be' measured and observed with a survey: i l flowmeter which has an accuracy of iS%, A low pressure-spray header alarm is provided to warn operators of

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'w, insufficient screen cleaning pressure'and t'o start'the )

traveling. screens. The low pressure alarm setpoint is at

'72 psid1 l

Alternate Testing: 1 Measurement of flow by. survey flowmeter (approximately yjk - iS%) and corri ive action ranges for flow shall be: 15% )j

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. degradation al rt' range and 25% degradation action range- "

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1 PR-9 Y '" System: Standby Diesel Generator Fuel Oil (A"and.B),-HPCS Diesel Generator 3, Fuel 011-(C)

'Pum:3: ~ 11R45-C001A/1R45-C002A, 1R45-C001B/1R45-0002B, 1R45-00010/1R45-C0020

-Class: 3.

' Function': The. fuel. oil transfer pumps maintain a sufficient' operating level in the; fuel oil day tank by transferring: fuel oil from the fuel oil V

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storage tank toithe' fuel oil day tank.

> A[' T Test Requirements: 'LIWP-4600LFlow: measurement (accuracy), IWP-3230(a) correc-tive. action (alert range), and IWP-3230(b) corrective action (action range).-

i Basis for. Relief: Two' fuel oil' transfer pumps supply one' day tank; one pump U ,, is designated"as inservice.and the other pump isfdesig

.c nated as backup. Thefcapacity.of a: fuel transfer-pump.--is90-140 gpm with the required. design capacity of the Diesel' o EngineLbeing 35:gpm.' Flow rate will'be measured with a n survey' flowmeter which has an accuracy of approximately=

iS%. The pump can' meet the design. function-with as'much t 'as 50% degradation; therefore, relief.from accuracy-AiOi requirements and alert / action ranges adequately. allows 1 --

assessment of, pump operability.

' Alternate Testing: Measurement of. flow by survey' flowmeter (approximately.

, 15%) with corrective action ranges for flow shall be: 25%

degradation alert range and 50% degradation action range.

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[. System: Waterleg Fill Pumps (RHR, LPCS, and HPCS)

Pumps: 1E12-C003, 1E21-C002, and 1E22-C003 Class: 2 Function: Waterleg pumps maintain the discharge piping of safety-related systems full to expedite flow during initiation, and to minimire the likelihood of system damage due to waterhammer.

Test Requirements: IWP-3400; Test Frequency - Test pumps at least every three months, quarterly.

Basis for Relief: The waterleg pumps'were designed to be inservice to . ]

maintain functional systems (discharge / suction piping) pressurized. The waterleg pump normal discharge path must be redirected to perform safety-related pump testing.

This would require racking out of scfety-related pump breakers (RHR, LPCS, and HPCS) as to prevent system damage due to waterhammer or cavitation upon receipt of an actuation signal. Racking out of safety-related pump breakers will place the plant in a Limiting Condition of

,, - ~ Operation for testing. The intent of ASHE Code,

(g) Section XI is not to reduce the reliability of

, safety-related systems. Therefore, the listed safety-related waterleg pumps shall be tested during cold shutdown.

Alternate Testing: Test during cold shutdown.

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Pump Relief Request #

PR-11 System: Reactor Core Isolation Cooling Pump and Waterleg Fill Pump Pumps: 1E51-C001 and IE51-C003 Class: 2 Function: The'RCIC Pump ensures sufficient reactor water inventory during a vessel isolation condition and prevents reactor fuel overheating.

The RCIC Waterleg Pump maintains the suction / discharge piping of the reactor core isolation cooling system full .. expedite flow during initiation, and to minimize the likelihood of system damage due to waterhamme-Test Frequency: IWP-3400; Test Frequency - Test pumps at least every three months, quarterly.

Basis for Relief: The Reactor Core Isolation Cooling (E51) System is required to be operable during power operation, start-up and hot shutdown with reactor steam dome pressure greater than 150 psig. The RCIC System pumps sht11 be tested within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is being supplied to the turbine at 1020+25-100 psig. The system

()

operability shall be verified in accordance with IWP-5400 after performance of initial test when reactor steam prescure is adequate (1020625-100 psig).

Alternate Testing: Test frequency in accordance with PNPP Unit 1 Technical Specification.

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PR-12 Syst m: . Standby Liquid' Control Transfer Pumps: C41-C002A and C41-C002B Class: 3 l

Function: The SLC Transfer Pumps provite makeup solution to the Standby Liquid <

Control. Systems (Unit 1/Unft 2) for long term operation.

Test Requirements: IWP-4600 Flow Measurement (accuracy), IWP-3230(a) correc-tive action (alert range), and IWP-3230(b) corrective

-action (action rance), i l

Basis for Relief: Flow rate will be measured and observed with a survey l flowmeter which has-an accuracy of approximately iS%. The j flow path shall be established using the test return line '

to the transfer tank, Differential pressure shall be adjusted to a predetermine value and degradation of the pump hydraulic characteristics shall be trended / monitored i using flowrate.

' Alternate Testing: Measurement of flow by survey floumeter (approximately l j-s , iS%) and corrective action ranges for flow shall be: 15% l

-( ) degradation alert range and 25% degradation action range.

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PR-13 System: As Applicable Pumps: IC41-C001A' 1E22-C003 1P42-C001B 1R45-C002A 1C41-C001B 1E32-C001 1P45-C001A 1R45-C002B C41-C002A 1E32-C002B 1P45-C001B 1R45-C002C C41-C002B 1E32-C002F 1P45-C00 1E12-C002A' 1E51-C001 P47-C001A 1E12-C002B 1E51-C003 P47-C001B 1E12-C002C G41-C003A P49-C002A 1E12-C003 G41-C003B P49-C002B 1E21-C001 1M51-C001A 1R45-C001A 1E21-C002 1M51-C001B 1R45-C001B IE22-C001 1P42-C001A 1R45-C001C Class: ASME Class 2 and 3 Function: As Applicable Test Requirements: IWP-4120; Range - the full-scale range of each instrument shall be three times the reference values or less.

Basis for Relief: The instrumentation (IRD) used to measure vibratier.

amplitude has a range selector with multiples of .03, .1,

~ll .3, 1, 3 and others for full-scale readings. When measuring reference values that fall between 0.031 to 0.033, 0.31 to 0.33, and 3.1 to 3.3, the full-scale range requirement can not be met. The minimal portion of scale usage which does not comply; does not degrade monitoring of pump operational readiness. The scale indication is close enough to meeting three times or less to provide an accurate vibration reading.

Alternate Testing: The small range of reference values identified shall be measured on the appropriate scale.

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s/ PR-14 System: Control Complex Chilled Water Pumps: P47-C001A and P47-C001B 1

Class: 3 Function: The Control Complex Chilled Water Pumps circulate cooling water to  ;

cooling Coils of the heating, ventilating and air conditioning (HVAC) systems which service the Control Room and other areas of the Control Complex.

Test Requirements: IWP-4600 Flow Measurement (accuracy), Table IWP 4110-1 12%

acceptable instrument accuracy.

Basis for Relief: Flow rate will be measured and observed with a plant installed instrument which has an accuracy of 14%. A low chilled water flow alarm is provided to warn operators of .

Insufficient system flow. The low chilled water flow 6 alarm setpoint is at 964 GPM.

Alternate Testing: Measurement of flow with plant installed instrument (approximately i4%) and corrective action ranges for flow f .s shall be the same required by Table IWP-3100-2 allowabic l-( ) ranges of test quantities.

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'l SECTION 2.3 PUMP TESTING SYSTEM INDEX AND' TEST TABLES o

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! 3; 2.3.1 Pump Testing System Index

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System Dwg. No./Rev. No. of Pumps

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/StandbyLiquidControl(C'41) D-302-691/Rev. H 2-L.

- Standby Liquid Control Transfer.

. (C41)< D-302-692/Rev. E.

2.

Residual Heat Removal (E12) D-302-641/Rev. M 1 D-302-643/Rev. M 3

. , Low Pressure Core Spray ~(E21)

D-302-:205/Rev. K' .2 i Ds fg liigh Pressure Core Spray . (E22) D-302-701/Rev.~ N 2 f!

E

.MSIV Leakage Control'(E32)- D-302-341/Rev. E 1 D-302-342/Rev. B 2 ,

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Reactor Core: Isolation Cooling

(E51); D-302-631/Rev. G 2 Fuel Pool Cleaning and Cleanup!

(G41) .

D-302-654/Rev. F 2 ry iy[ Combustible Gas Control (M51)' D-302-831/Rev. L 2

Emergency Closed Cooling' Water D-302-621/Rev. J 2 (P42).

Emergency Service Water.(P45) D-302-791/Rev. L 3 Control' Complex Chilled Water D-913-001/Rev. X 2

.(P47)' i ESW Screen Wash (P49) D-302-214/Rev. J 2

' Standby D.G. Fuel Oil (R45) D-302-352/Rev. L 4 IIPCS D.G. Fuel Oil (R45) D-302-356/Rev. F 2

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=' TInlet. Pressure (Before and after' pump start) )

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. Pd ~= Differential Pressure Across. Pump j Qf =' Flow Rate :

V- =. . Vibration' Amplitude t.;,.

T = . Bearing Temperature b.

. Q = Quarterly,.

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E X' =.

'. Measurement / Observation Per IWP ~!

.L- = iLubricant Leve'l or Pressure-PR =' Rellef. Request, i.

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l 2.3.3 Pump Test Table Notes In the Pump Test Table, the test parameters to be measured or observed and the test frequency are idsntified. Footnotes 1 and 2 refer to amplifications, deviations and exceptions to the Code requirements and are further discussed below:

(1) Pump with constant speed drive, speed is not measured since test will be performed at nominal motor nameplate speed as required by Section XI, IWP-3100.

(2) Lubricant level or pressure not observed because of bearing lubrication design.

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PUMP AND VALVE INSERVICE TESTING PROGRAM for PERRY NUCLEAR POWER PLANT UNIT 1 SECTION 3.0 )

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l VALVE IST PROGRAM l

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i 3.0 INSERVICE TESTING PROGRAM FOR VALVES n ' /'

k- 3.1 General Information 3.1.1 Applicable Code This testing program for ISI Class 1, 2, 3 Valves and Valve Actuators meet the requirements of Subsection IWV of Section XI of j the ASME Boiler and Pressure Vescel Code, 1983 Edition through the Summer 1983 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included.in Section 3.2.

3.1.2 Valve Program Tables The tables in Section 3.3.2 list ISI Class 1, 2, 3 and Nonclass  !

valves that have been assigned valve categories. Valves exempt per '

IWV-1200 are not listed. The following information is included for q

each valve-l VALVE IDENTIFICATION AND IST REQUIREMENTS SYSTEM-P&ID: Located in the top left hand corner of the program table the system and drawing number (DWG. NO.) is i identified. This identifies the valve's associated  !

system and P&ID.

b w/ VALVE NO.: The valve identification number. i J

P&ID C00R., The drawing coordinate location on the P&ID for the j valve. ]

ISI CLASS: The ISI classification of the valve.

ISI CAT.: The category (s) assigned to the valve based on the definitions per IWV-2200. Four (4) separate cat-egories are defined in the Code:  ;

CATEGORY A - Valves for which seat leakage is l limited to a specific maximum amount i in the closed position for fulfillment I of their function. I 1

CATEGORY B - Valves for which seat leakage in the )

closed position is inconsequential for j fulfillment of their function, i CATEGORY C - Valves which are self-actuating in 1 response to some system characteris- 1 tic, such as pressure (relief valves) or flow direction (check valves).

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l CATEGORY D - Valves which are actuated by an energy M U source capable of only one operation, such as rupture disks or explo-sive-actuated valves.

L. - VALVE SIZE: The nominal size of the valve in inches.

VALVE TYPE: The valve body design as indicated by the following abbreviations:

BALL BAV BUTTERFLY BFV CHECK CHV DIAPHRAGM DIV >

GATE GTV {

GLOBE GLV I RELIEF REV l RUPTURE DIAPHRAGM RUD I STOP CHECK SCK THREE WAY TWV ACT. TYPE: The type of valve actuator as indicated by the following abbreviations: l i

MOTOR OPERATOR MOV l AIR OPERATOR POV n- SOLEN 0ID OPERATOR SOV V HYDRAULIC OPERATOR HOV MANUAL. MAN .

SELF ACTUATED SEV NORM. POS.: The position of the valve during normal plant opera- i tion, specified as follows:

1 0 Normally Open C Normally Closed i LO Locked Open i LC Locked Closed l DE Depends on Sys. Condition i

TEST RQMT. i 6 FRES: The test (s) that will be perforced to fulfill the I requirements of Subsection IWV. The test definitions  !

and abbreviations used are identified in Table 3.1-1.

1 The frequency at which the above mentioned tests will I be performed. Test frequencies are defined in Table 3.1-2. i MAX STRK. ,

TIME: The limiting maximum value of full stroke time, in l seconds, for power-operated valves in Category A or B ..

CHECK VLV

(~') -

A/

TEST DIR: The direction in which flow will be applied to check valves during test (s) will be as follows:

F Forward (Normal to allow flow through valve)

R Reverse (Opposite to allow flow through valve)

RELIEF REQUEST: The reference to a relief request in Section 3.2 i for valve testing. Requests for relief are  ;

identified as VR-XX. i REMARKS: Remarks in the Inservice Testing Program are to clarify any special requirement due to design or identify other documents effecting testing requirements. .l 3.1.3 Measurement of Test Quantities STROKE TIME: Stroke time is that time interval from initiation of the actuating signal to the end of the actuating cycle. Stroke time values for each power operated valve is specified in the valve program table.

Stroke time is measured to the nearest second, for times 10 sec. or less or 10% of the specified limit-ing stroke time for times greater than 10 sec.

rs POSITION

(

) .j INDICATION: Valve disk movement is determined by exercising the  ;

valve while observing an appropriate indicator which signals the required change of disk position, or observing indirect evidence, such as changes in system pressure, flow rate, level or temperature, which reflect stem or disk position. ,

l SEAT LEAKAGE: Seat leakage is measured by one of the following methods:  ;

(a) draining the line, closing the valve, bringing one side to test pressure, and measuring leakage through a downstream telltale connection, or (b) by measuring the feed rate required to maintain pressure between two valves or between two seats of a gate valve, provided the total c.pparent leak rate is charged to the valve or gate valve seat being tested, and that the conditions required by IWV-3423 are satisfied.

L

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L p.,7 3.1.4 Allowable Ranges of Test' Quantities I t i STROKE TIME: I (a) If, for power operated valves, an increase in stroke time of 25% or more from the previous  !

test for valves with stroke times greater than )

10 sec. or 50% or more for valves with stroke 1 l

times less than or equal to 10 sec. is observed, corrective action will be taken. For valves l with stroke times less than or equal to i three seconds see Relief Request VR-2.

(b) Valve stroke time shall not exceed its specified limiting stroke time value without corrective action being taken.

l POSITION INDICATION: The valve disk shall move from the fully.open posi- l tion to the fully closed. position or vice versa, s SEAT LEAKAGE: (a) Valve leakage rates shall not exceed either the  :

values specified by Perry Nuclear Power Plant ]

Technical Specifications or the Owner's (CEI) '

established leakage rates.

(b) For' valves 6 in nominal pipe size and larger j the leakage rate shall not exceed Technical

()

, i Specification (Relief Request VR-3). If tests W show a leakage rate increasing with time, and a projection based on three or more tests indicates that the leakage rate of the next scheduled test will exceed the maximum permissible leakage rate by greater than 10%,

corrective action will be taken.

3.1.5 Instrument Accuracy Instruments used to measure stroke times shall be capable of mea-surement to the nearest tenth of a second.

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i TABLE 3.1-1 INSERVICE VALVE TESTS TEST TEST NAME TEST DESCRIPTION LJ Containment Containment isolation valves will be seat leak Isolation Valves tested in accordance with 10 CFR 50, '

Appendix J, Type C Leak test and PNPP Technical Specification requirements. 1 LK Pressure isolation Pressure isolation valves will be seat leak tested valve in accordance with ASME Boiler and Pressure ,

Vessel Code,Section XI, IWV-3420 Valve Leak Rate j Test.

LC Containment and Both a containment and pressure isolation valve pressure isolation will be seat leak tested in accordance with valve 10 CFR 50, Appendix J and'ASME Boiler and Pressure Vessel Code,Section XI.

FE Full-Stroke Exercise testing of Category A or B valvss through exercise one complete cycle of operation.

1) Normally open: Full Stroke s4ercise the valve closed then return to open position.

() 2) Normally closed: Full Stroke exercise the valve open then return to closed position.

ST Stroke Time Stroke time is the measurement of the time required to exercise test a Category A or B valve through an operation. Valve timing shall be to the alternate position to comply with ASME Boiler and Pressure Vessel Code,Section XI.

1) Stroke Direction (c) - Normally open: Full Stroke time close.

2) Stroke Direction (o) - Normally closed: Full Stroke time open.

Motor operated valves shall be stroke timed in only one direction since no deviation should occur.

Additional stroke timing may be required by other documents (i.e., PNPP Technical Specifications and PNPP Final Safety Analysis Report).

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,. TABLE 3.1-1 (Continued) v INSERVICE VALVE TESTS PE Partial Partial stroke exercise testing'will be performed 4 Stroke to confirm partial stroke capability when full Exercise ' stroke exercise is impractical.

FE Check Valve Exercise testing of Category C (i.e., check valves)

Exercise valves-through one complete cycle of operation by system flow or other positive exercise method.

1) Forward Flow Direction (F) - Normally closed:

Flow Stroke open.

2) Reverse Flow Direction (R) - Normally open.

Flow-Stroke close.

PC Partial Partial' check valve flow direction exercise is Check when a Category C valve can only be partially Exercise exercised.

RD Rupture Rupture Test of all Category "D": Non-Testable Detonate valves were performed by the manufacturer or the Test start-up testing program and no additional testing shall be required; Testable valves were performed by the start-up testing program and shall be routinely g scheduled by CEI.

EX Explosive Testing of explosive charges by firing per ASME Test Section XI with at least 20% of the charges in a batch shall be fire every 2 years with no charge exceeding 10 years.

RT Relief Set Relief and safety valve set point will be verified Point in accordance with ASME Boiler and Pressure Vessel Code,Section XI, IWV-3511 ASME PTC 25.3-1976 and PNPP Technical Specifications.

FS Fall Safe Valves with fail safe actuators (e.g., air operated, Test spring loaded, solenoid operated, and hydraulic operated) will be tested to verify proper fail safe i operation upon loss of actuator power. l PI Position Valves with remote position indicators will be Indicator checked to verify that remote valve position Verification indicators accurately reflect valve position.

I

_ - - - - - - -- i

1 1

1 TABLE 3.1-2 1

../~N I U TEST FREQUENCY (3)

TIST OPERATIONAL (1) FREQUENCY FREQUENCY CONDITION OF TESTING j 1

Q. Power Operation At least once per 92 days j i

Cold Shutdown CS See (2) below R0- Refueling Not more than once every two years i

SY No' operational Every five years (see Article condition IWV-3511). Applies to RT test.

l limitations 2Y No operational Every two years (see Article condition IWV-3300). Applies to position limitations indication tests and seat leakage tests.

(1) Operational conditions are defined in PNPP Technical Specifications.

1 (2) Inservice valve testing will commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> when reaching the cold shutdown conditions as defined in Generic Relief Request GR-1.

Testing not completed before start-up may be completed during subsequent

.(3j cold shutdowns. Valve testing need not be performed more often than once every three months. In the case of extended cold shutdowns, the testing need not be started within the hours limitation. However, in these instances, all valve testing must be completed prior to start-up.

NOTE: Completion of all valve testing during cold shutdowns is not required if plant operating conditions do not permit testing of specific valves.

(3) Provisions of PNPP Unit 1 Technical Specification 4.0.2 are applicable to the following required frequencies for performing inservice testing activities. j ASME BOILER AND PRESSURE VESSEL REQUIRED FREQUENCIES FOR CODE AND APPLICABLE ADDENDA PERFORMING INSERVICE TEST TERMIN0 LOGY FOR INSERVICE TESTING ACTIVITIES ACTIVITIES WEEKLY AT LEAST ONCE PER 7 DAYS MONTHLY AT LEAST ONCE PER 31 DA7S  ;

QUARTERLY OR EVERY 3 MONTHS AT LEAST ONCE PER 92 DAYS  !

SEMIANNUALLY OR EVERY 6 MONTHS AT LEAST ONCE PER 184 DAYS EVERY 9 MONTHS AT LEAST ONCE PER 276 DAYS YEARLY OR QUARTERLY AT LEAST ONCE PER 366 DAYS O

b i TABLE'3.1-2 TEST FREQUENCY (3)

(Continued)

NOTE: PNPP Unit 1 Technical Specification 4.0.2 states:

Each Surveillance requirement shall be performed within the specified time interval, with

a. A maximum allowable extension not to exceed 25% of the surveillance interval, but

b. The combined time interval for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified t surveillance interval.

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SECTION 3.2 RELIEF REQUESTS FOR INSERVICE VALVE TESTING PROGRAM -!

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'!H- n . Valve Relief Request #-

VR-1

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Systems: ' All- 'i Valves:- All.

Class:. All' Function: .As' applicable Test. Requirements: ASME.Section XI (IW-3417b .and 'IW-3523) states that when -

icorrective action is required'as.a result of testing,-the condition must be corrected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the valve 1

-shall be declared inoperative. In the event of testing'-

y during cold shutdown, condition shall be corrected prior..-

to start-up.

Basis-for Relief: 'The Perry Nuclear. Power Plant. Technical Specification.

limiting conditions for operations,.and ASME Section XI,.

provide the: controls by which' valves and~ system are

-declared inoperative. PNPP. Technical Specifications also control entry into various operational. conditions,iwhich '

is generally more restrictive, . Failure to meet'Section XI' testing. criteria should not, therefore, preclude plant

,;  ; start-up with that'particular component inoperable, nor

- should the declaration of component or system inoperabil'

' ~

ity:be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Plant safety is assured by,

' adherence to PNPP Technical' Specifications.

Alternate Testing: -The ability to declare' component or system inoperability, and' conduct plant start-up, shall be governed by PNPP Technical Specifications and not by ASME'Section XI, IW-3417b and IW-3523.

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4 Valve' Relief Request #

l _/. VR System: As applicable .,

Valves: All fast-acting valves with short-stroke time less than or equal to 3 seconds.

Category: A, B  ;

Class: As applicable i Function: As applicable Test' Requirements: ASME Section XI IWV-3417(a) requires a comparison of the most recent stroke time measurement with that of the previous test. ,

'l Basis for Relief: Rapid acting' valves have stroke times of such short durations that comparison of measurements with previous data for specified percentage increases is not indicative of degrading valve performance. With measurement of stroke times to the nearest second per IWV-3413(b), a very sma11' increase in stroke time will result in an extremely large percentage cf change. Verification that these

,- valves meet a specified maximum stroke time of a rel-(s) atively short duration', should provide adequate assurance of operability.

Alternate Testing: When stroke times of rapid acting valves are measured, the criterion for determining acceptability will be the specified maximum stroke time of 3 seconds. Actual trending or measurement of rapid acting valve stroke times will not be made other than confirmation that they stroke less than 3 seconds. }

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Valve Relief Request #

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VR-3 l

System: As' applicable l 1

Valves: . Valve Test Tables j Category: A and AC

Class: As applicable Function: .As applicable Test Requirements: IWV-3427(b); corrective action For valves 6 in, nominal pipe size and larger, if a i leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate by 50% or j greater, the test frecuency shall be double.

(IWV-3427(b)).

Basis for Relief: These valves are located inside containment or inside radiation areas during operation and testing on an increased frequency would increase radiation exposure for testing personnel. Testing is now being performed during-7

g s) refueling to minimize exposure. With increased' frequency, operational constraints would be placed upon the plant requiring possible shut down for testing. Therefore, l corrective action per IWV-3427(b) will not be used due to ALARA considerations and operational constraints on the I plant. l l

Alternate Testing: Valves will be replaced or repaired as required when the i leakage rate exceeds that as stated in Perry Nuclear Power l Plant Technical Specifications. i l

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,, Valve Relief Request #

D' VR-4 System: As applicable Valves: All Fast-acting solenoid operated: valves with short-stroke time less ;

than or equal to 3 seconds.  !

Category: A, B Class: As applicable Test Requirements: IWV-3300, Valve Position Indicator Verification - valves with remote position indicators shall be observed at least once every two years to verify that valve operation is accurately indicated.

?

Basis for Relief: These valves require disassembly of the actuator compo- '

nents to verify operation. Additionally, each valve has minimal stroke time (less than 1 second) and stem travel (approximately.0.075 inch). The accurate visual verifica- l tion of valve operation is at possible due to the minimal stem travel and short stroka period. This visual observa-tion would not contribute significantly to the <ssurance of safe and proper valve operation.

.(/~~)

Alternate Testing: The valve open indication / position is verified by normal  !

system parameters during operation. The valve shut indication / position is verified by 10CFR50 Appendix J testing, and ASME Code Section XI Seat Leakage Testing during refueling outages or by normal system operating parameters.

Valves affected by this general exception, see following listing:

1D17-F071A 1D23-F050 1M51-F240A 1P53-F040 1P87-F077 1D17-F071B 1E12-F060A 1M51-F240B 1PS3-F045 1P87-F083 1D17-F079A 1E12-F060B 1M51-F250A IP53-F070 1P87-F264 1D17-F079B 1E12-F075A iM51-F250B 1P53-F075 1D17-F081A 1E12-F075B 1M51-F260A 1P87-F001 1D17-F081B 1G43-F050A 1M51-F260B 1P87-F007 1D17-F089A 1G43-F050B 1M51-F270A 1P87-F025 1D17-F089B 1G43-F060 1M51-F270B 1P87-F028 1D23-F010A 1M17-F055 1PS2-F160 1P87-F037 ,

1D23-F010B iM17-F065 1P52-F170 1P87-F046 i 1D23-F020A iM51-F210A 1P53-F010 1P87-F049 1D23-F020B 1M51-F210B 1P53-F015 1P87-F052 1D23-F030A 1M51-F220A 1P53-F020 1P87-F055 ID23-F030B 1M51-F220B 1P53-F025 1P87-F065 1D23-F040A iM51-F230A 1P53-F030 1P87-F071 es ID23-F040B 1M51-F230B 1P53-F035 1P87-F074

s Valve Relief Request #

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.VR-5 System- Feedwater (N27) i

. Valves: 1B21-F065A, 1B21-F0653 Category: A  !

Class: 2 Test Requirements: IWV-3411; Test Frequency - Exercise at.least once e.very.

three months.

IWV-3413; Power operated valves - full stroke time Basis for Relief: Exercising these valves during normal operation would require a significant reduction in power,and stopping one line of feedwater flow. Isolation of one line of feed-water flow during normal operation introduces undesirable operational transients and could result in a reactor trip.

Partial stroke testing cannot be performed since valves  ;

stroke fully on initiation.  !

Alternate Testing: During cold shutdown, perform full exercise and full-f-q stroke time test on these valves.

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\d VR-6 System: . Nuclear Boiler ADS and Relief / Safety Valves (B21)

Valves: IB21-F041A, B, C, D, E, F, G, K 1B21-F047B, C, D, F, G, H IB21-F051A, B, C, D, G Category: B, C Class: 1 Function: Provide automatic depressurization and/or overpressure protection of i the reactor coolant pressure boundary.

Test Requirements: IWV-3411; Test Frequency - Exercise at least once every three months.

IWV-3413; Power operated valves - full stroke time and IWV-3415; Fail Safe - at least once every three months.

Basis for Relief: If the valves.were to fail to reclose after testing the plant would be placed in a LOCA condition. Stroke time is f~s a function of reactor pressure and, therefore, shall not

() be measured during exercising test. In addition, a recent study (BWR Owners Group Evaluation of NUREG-0737 Item II.K.3.16 Reduction of Challenges and Failures of Relief Valves) recommends that the number of ADS and/or ,

relief / safety valves openings be reduced as much as '

possible. Based on this study and the potential for i causing a possible LOCA condition, exercise testing of the ADS and/or relief / safety valves is delayed to refueling.

Alternate Testing: Exercise valves during refueling (i.e., start-up) i l

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.j  : Valve Relief Request #.

, d: VR I System: Main Steam System (N11) .

Valves: IN11-F020A, IN11-F020B, IN11-F0200, IN11-F020D i

Category: B j Class: 2 j

Function: Main Steam Shutoff Valve

~ Test Requirements: IWV-3411; Test Frequency - Exercise at least once every three months.

IWV-3413; Power operated valves - full stroke time ] !

Basis for Relief: Valves fully stroke on initiation of close signal making partial valve stroke impractical, Full stroke exercise results in loss of steam flow from one main steam line to the turbine creating adverse transients and potential of valve' damage from steam erosion of valve seat.

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. Alternate Testing: Exercise valves during cold shutdown f~g

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(/ VR-8 fi System: Reactor Coolant Pressure Isolation Valves - Motor operated (e.g.;

RHR, LPCS, HPCS, and Feedwater Leakage Control).

Valves: 1E12-F008, 1E12-F009, IE12-F023, 1E12-F042A, 1E12-F042B, 1E12-F042C, 1E12-F053A, 1E12-F053B, 1E21-F005, 1E22-F004, IN27-F737, IN27-F740 Category: A Class: 1, 2 Function: Provide pressure isolation from high pressure coolant systems (e.g.;

Rx. Coolant, Feedwater and other safety-related systems containing low pressure designed components.

Tast Requirements: IWV-3411; Test Frequency - Exercise at 1 cast once every three months and 1

IWV-3413; Power operated valves - full stroke time Basis for Relief: These pressure isolation motor operated valves maintain one of the two high to low pressure barriers during plant operation. To exercise these valves during plant opera-tion would involve a loss of one isolation barrier. There l is a significant increase in the probability of causing an internal loss of coolant accident to exercise these motor operated valves quarterly.

Alternate Testing: Exercise valves during cold shutdown I

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Valve Relief Request #  ;

'N-) VR-9 System: Reactor Core Isolation Cooling (E51)

Valves: 1E51-F013 Category: A Class: 1 Function: Provide primary containment isolation and isolation of the RCIC injection to reactor coolant system Test Requirennts: IWV-3411; Test Frequency - Exercise at least once every three months and IWV-3413; Power operated valves - full stroke time Basis for Relief: The RCIC motor operated injection isolation valve is normally closed and provides additional pressure isolation between a high pressure system (i.e., Rx coolant) and the  ;

low pressure designed RCIC components. Testing of the RCIC injection isolation valve during cold shutdown prevents the likelihood of an internal loss of coolant accident. Quarterly testing of the RCIC pump is performed (g with the motor operated injection isolation valve closed.

Alternate Testing: Exercise valves during c71d shutdown i

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Lr s LV VR-10 System: Nuclear Boiler'(B21)

Valves: IB21 f022A, 1B21-F022B, 1B21-F022C, 1B21-F022D, 1B21-F028A, 1B21-F028B, 1B21-F0280, 1B21-F028D Category: A Class: 1 Funct' ion: Main Steam Icolation Valves Test Requirements: IW-3411; Test Frequency - Exercise at least once every ,

three months and IW-3413; Power operated valves - full stroke time IW-3415; Fall Safe - at least once every three months Basis for Relief: Full. stroke exercising results.in loss.of steam flow from one main steam line to the turbine. Recent industry information indicates that closing these valves with high steam flow in the line may be a large contributing factor

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in observed seat degradation. The valves are designed for l

( . partial stroke exercising with full steam flow during plant operation by bleeding down the accumulator air supply to the operator. The partial stroke test will verify operability of the valve operator's fail safe function.

l Alternate Testing: Partial exercise and fail safe test monthly, full exercise and stroke time test during cold shutdown.

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I V VR-11 System

Control Rod Drive Hydraulic (Cil)

Valves: IC11-F083 Category: A Class:. 2 Function: Condensate Water to Control Rod Drive Outboard Containment Isolation Valve.

Test Requirements: IVV-3411; Test Frequency - Exercise at least once every three months and  !

IWV-3413; Power operated valves - Full stroke time Basis for Relief: Failure of valve in the closed position during plant operation would result in a loss of drive water to the control rods. This would inhibit normal operation of the control rods and could result in a reactor shutdown. This valve fully strokes upon initiation and cannot be partial stroke tested.

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f Alternate Testing: During cold shutdown, perform full exercise and full stroke time test on this valve.

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_ ,__ . ' Valve Relief Request #

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VR-12 System: Control Rod Drive Hydraulic System (C11)

Valves: 1011-114., IC11-126, 1C11-127 (Typical of 177)

Category: B (IC11-126, 1C11-127) ,

C (IC;1-114)

Class: 2 Function: Control Rod Dr!ve Scram Inlet, Exhaust, and Scram Discharge Header Check.

Test Requirements: IWV-3411; Test Frequency - Exercise at least once every three months and IWV-3413; Power operated valves - Full stroke time IWV-3521; Test Frequency - Exercise at least once every three months.

Basis for Relief: These valves operate as an integral part of the hydraulic control unit to rapidly insert control rods. . Valves wil1 be tested in accordance with Technical Specifica-(). tion 4,1.3.2 (i.e., maximum scram insertion time). The technical specification requires testing of all controls rods prior to thermal power exceeding 40% of rated thermal power following core alterations or after a reactor shutdown exceeding 120 days. Testing of 10% of the control rods, on a rotating basis, at least once per 120 days of operation.

Alternate Testing: Scram insertion timing shall be substituted for individual valve testing, j l

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i d VR-13 l System: - Nuclear Closed Cooling 4'at e t bystem (P43)

Valves: 1P43-F055, 1P43-F140, 1P43-F215, 1P43-F355, 1P43-F400, IP43-F410

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Category: A (IP43-F055, 1P43-F140, 1P43-F215)

B (1P43-F355, IP43-F400, 1P43-F410) l 1

Class: 2 Function: Containment (i.e., drywell and primary) isolation valves for cooling water to the reactor recirculation coolant pumps and other safety-related systems.

Test Requirements: IWV-3411; Test Frequency - Exercise at least once every three months and IWV-3413; Power operated valves - Full stroke time Basis for Relief: These valves are the inlet and outlet isolation valves for nuclear closed cooling water. Exercising could result in loss of cooling to the Reactor Coolant Recirculation ,

pumps. The reactor coolant recirculation pumps are d 7

- normally operated during all plant operating conditions

( j- except refueling.

Alternate Testing: Exercise valves during refueling.

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' - ' VR-14 System: Reactor Core Isolation Cooling System (E51)-

Valves: 1E51-F511 Category: B Class: 2 Function: RCIC turbine governing valve Test Requirements: IWV-3300; Valve Position Indicator Verification.

IWV-3411; Test Frequency - Exercise at least once every three months and IWV-3413; Power operated valves - Full stroke time Basis for Relief: The RCIC turbine governing valve is a hydraulically operated valve which is positiened by system parameters.

The hydraulic control unit is sealed and attempting to exercise the valve by external means could damage the control mechanism. During turbine operation the valve f- moves in response to control signals. Valve position is steam pressure and turbine speed dependant with repeated

( j throttling being impossible. Operability is adequately j demonstrated during turoire operation. j Alternate Testing: Proper operation of the RCIC Turbine governing valve shall f be verified by the turbine response during testing. j l

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VR-15 System: Instrument Air System (P52) ,

Valves: -1PS2-F200, 1PS2-F646 Category: A (1PS2-F200)- j B-(1PS2-F646)

-Class: 2 Function: Containment.'(i.e., drywell and primary) isolation valves for air supply to the non-automatic depressurization system and main steam isolation valve accumulators.

Test Requirements: IWV-3411; Test Frequency - Exercise at least once every' three months and IWV-3413; Power operated valves - Full stroke' time Basis for Relief: These isolation valves are within the normal flow path for supply air to the non-automatic depressurization system (ADS) and main steam isolation valve accumulators. This is the normal source of air supply to the non-ADS and MSIV fS accumulators and exercising of the isolation valves tj reduces the operational readiness of the systems.

Alternate Testing: Exercise valves during cold shutdown.

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Valve Relief Request #

U VR-16.

System: Safety-Related Instrument Air System (P57)

Valves: 1P57-F015A, 1P57-F015B, 1P57-F020A, 1P57-F020h Category: A (1P57-F015 A, B)

B (1P57-F020 A, B) .;

Class: 2 Function: Containment (i.e., drywell and primary) isolation valves for air supply to the automatic depressurization system (ADS) accumulators.

Test Requirements: IWV-3411; Test Frequency - Exercise at least once every three months and IWV-3413; Power operated valves - Full stroke time Basis for Relief: These isolation valves are within the normal flow path for supply air to the automatic depressurization system (ADS) accumulators. This is the normal source of air supply to the ADS accumulators and exercising of the isolation valves reduces the operational readiness of the system.

( -Alternate Testing: Exercise valves during cold shutdown. -

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'w) ' VR-17 System: Reactor Core Isolation Cooling (E51)

Valves: ,1E51-F030 Category: C Class: 2 Function: RCIC Pump Suction Check Valve Test Regairements: IW-3521; Test Frequency - Exercise at least once every three months.

Basis for Relief: Normal testing of the RCIC System does not include taking a suction on the suppression pool due to possible con-tamination of the condensate storage tank. This normally closed valve will be exercised to the fully open position q during refueling outages by removing the valve and verify- '

ing disc freedom of movement.

Alternate Testing: During refueling outage, disassemble valve and mechanical-ly exercise the disc.

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- Valve Relief Request #

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i System: Standby Liquid Control (C41)

Valves: 1041-F006, IC41-F007 ,

Category: AC Class: 1 Function: Standby Liquid Control Injection Check Valve Test Requirements: IW-3521; Test Frequency - Exercise at least once every three months, quarterly. l Basis for Relief: To verify forward flow operability during normal operation i would require firing a squib valve and injecting water into the reactor vessel using the SLC pumps. Injecting water during operation.could results in adverse plant conditions such as changes in reactivity, power tran-sients, thermal shock induced cracking and a possible plant trip.

Alternate Testing: Verify forward flow operability during refueling while 7 performing the standby liquid control system injection test, which fires at least one squib valve and pumps demineralized water into the reactor vessel.

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VR-19

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System: .Fehdwater Leakage Control (N27)

I LValves: l1N27-F739A; 1N27-F739B, 1B27-F742A, 1N27-F742B

' Category: L C-Class:' '2

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Function:' These valves allow a flowpath to the feed system during feedwater Lleakage' control operations and provide a pressure isolation from the

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feed system during normal power operations.

Test Requirements: IWV-3521; Test Frequency - Exercise at leastionce every three months, quarterly.

Basis'for Relief: To demonstrate. forward flow operability would require opening upstream Valves IN27-F737 and 1N27-F740. These valves have pressure interlocks to prevent either full or<

partial stroke exercising during normal operation.

Alternate Testing: Exercise valves'during cold shutdown.

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-y; Valve Relief Request #

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\'/ VR-20 i

l System: Nuclear Boiler (B21) l Valves: IB21-F024A, B, C, D 1B21-F029A, B, C, D 1821-F0360, D, G, H, J, K, M, N, R, S, U 1B21-F039A, B, E, F, L, P, T, V Category: C i

Class: 3 Function: Prevent depressurization of air accumulators on a loss of instrument air or safety-related instrument air.

Test Requirements: IWV-3521; Test Frequency - Exercise at least once every three months, quarterly.

Basis for Relief: Exercising these valves would require isolating the air supply to the accumulators. This could prevent the safety-related (i.e., safety reAlef and mainsteam iso-lation valves) valves from performing their design func-tion. An accumulator pressure drop test is performed each 7- refueling outage to verify system integrity. Satisfactory

( j completion of the pressure drop test verifies exercising i of these valves in the reverse direction.

Alternate Testing: Exercise valves during refueling.

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,,. Valve Relief Request #

k.-) VR-21 System: Emergency' Service Water (P45)

Valves: 1P45-F575 Category: C Class: 2 Function: To prevent intersystem Icahage from the residual heat removal system to the emergency service water system.

Test Requirements: IWV-3521;. Test Frequency - Erercise at least once every three months, quarterly.

Basis for Relief: This valve is closed during normal operation. Excrcising in the forward direction would require injecting emergency service water into the RHR system. Injection of this i water is not desirable due to the poor water quality of I the ESW system.

Alternate Testing: During refueling outaget disassemble valve and mechanical-ly exercise the disc or perform a forward flow exercise.

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3 Valve Relief Reeluest #

. ( 'y X- / ya.22 System: Residual Heat Removal Shutdown Cooling (E12)

Valves: .1E12-F050A, 1E12-F050B Category: C Class: 2 Function: Provide a flowpath fer RHR water for shutdown cooling (e.g., using the feedwater nozzles).

Test Requirements: IWV-3521; Test Frequency - Exercise at least once every three months, quarterly.

Basis for Relief: These simple check valves are within the normal flowpath for shutdown cooling (e.g., r,ing the feedwater nozzles).

The valves are normally closed during plant operation and require forward flow exercising. Initiation of shutdown cooling shall be used.to verify the simple check valve forward flow exercising. Both loops of shutdown cooling should not be required during cold shutdown. Therefore, verification of both shutdown cooling loops (e.g.,

-s 1E12-F050A and 1E12-F050B) operability shall be performed

'( during refueling.

Alternate Testing: Exercise valvo during refueling.

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VR-23 e.l. ..

'4 System:

Reactor Coolant Pressure Isolation Check Valves (RHR, LPCS, HPCS, {

L and RCIC) of a testable nature.

Valves:, IE12-F041A, 1E12-F041B, 1E12-F0410,.1E21-F006, IE22-F005, LE51-F065,11E51-F066 l

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. Category:, AC 1

- Class: .1  !

Function: Provide pressure isolation of the reactor coolant pressure boundary.

between the high pressure reactor coolant system and'other safe--

ty-related' systems ,containing low pressure designed corponents, i- ' Test Requirements: ' IWV-3521; Test Frequency'- Exercise at least once every

-)'

- three. months, quarterly.-

Basis'Ior Relief: These pressure' isolation valves maintain one of the two.  !

high to low pressure barriers during plant' operation. To exercise these valves during plant operation would involve

- a loss of one isolation barrier. -There is a.significant increase'in the probability of an internal loss of coolant

-accident to exercise:these valves' quarterly.-

Alternate. Testing: Exercise' valve during cold shutdown.

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Valve Relief Request # .

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%_/ VR-24 System: Residual Heat Removal Head Spray Line (E12) l i

Valves: 1E12-F019  !

4 Category: C l

Class: 1 l i

Function: Provide a flowpath for RHR water for head spray collapsing of the steam in the reactor vessel head.

Test Requirements: IWV-3521; Test Frequency - Exercise at least once every three months, quarterly.

Basis for Relief: The simple check valve is within the normal flowpath for RHR head spray to the reactor vessel head. This valve is normally closed during plant operation.and requires forward flow exercising. The initiation of head spray when shutting down for refueling shall verify forward flow exercising or during the reactor pressure boundary system leakage pressure test.

Alternate Testing: Exercise valve during refueling.

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- -. Valve' Relief Request #

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. %) ' VR-25 '

A iSystem:: 1 High Pressure Core Spray System (E22)

.y . Valves: 1E22-F016-1 LCategory: ,'C, i,g '.

TClass: -2 Function: High Pressure Core Spray Pump Suppression Pool Suction Line Check'

' Valve'

.' Test Requirements: IWV-3521; Test Frequency - Exercise at-least.once every.

-three months, quarterly.

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Basis for Relief: The HPCS suppression pool suction-line check valvt shall

'be partially exercised quarterly during suppression pool cleanup operation. The suppression pool is the alternate supply of water'for the HPCS system and is not used during the HPCS pump operability testing. The design of the HPCS system precludes' ease of valve exercising.

2

'.  : Alternate Tecting: This valve shall be disassembled and manually exercised each' refueling outage.

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Valve Relief Request #

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5 I-VR-26 System: Safety-Related Instrument Air System Valves: 1P57-F555A,.1P57-F555B, IP57-F556A, 1P57-F556B

' Category: C Class: 3 Function: Provide a flowpath for charging air to the ADS safety relief valve

accumulators from the air compressors.

Test Requirements: IWV-3521; Test Frequency - Exercise at least once every three months, quarterly.

Basis for Relief: These simple check valves are within the normal flowpath for supply air to the automatic depressurization system (ADS) accumulators. They are normally open during plant operation and requires reverse flow exercising. This requires depressurization of portions of the safety-related irstrument air system. A reverse flow exercise during refueling outages will ensure operability of the system to perform its design function.

(') Alternate Testing: Exercise valve during refueling.

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l Valve Relief Request #

- VR-27 System: Safety Relief Valve (SRV) Reactor Head Vent and RHR Relief Line to Suppression Pool Discharge Lines Valves: 1E21-F037A, B, C, D, E, F, G, H, J, K, L, M, N, P, R, S, T, U, V.

1B21-F078A, B, C, D, E, F, G, H, J, K, L, M, N, P, R, S, T, U, V

'1B21-F040, 1E12-F605A and F605B i Category: C Class: 2, 3 Function: Vacuum breakers ensure that the steam exhaust discharge lines pressure remains equalized.

Test Requirements: IWV-3521; Test Frequency - Exercise at least once every three months, quarterly.

Basis for Relief: The SRV, reactor head vent, and RHR relief line to suppression pool discharge vacuum breakers are to provide !

a means for releasing a vacuum developed in the discharge ;

line from condensing steam. The vacuum breakers are normally closed during plant operation. The forward flow

.,s exercising of these valves can be verified manually. This

( ) method of exercising would have adverse safety or ALARA

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concerns during power operations. Exercising to be performed during cold shutdown.

Alternate Testing: Exercise valve during cold shutdown.

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VR-28

-System: Primary Containment Isolation Check Valves Valves: 1B21-F032A, 1B21-F032B, 1C11-F122, 1G41-F522, 1N27-F559A, IN27-F559B, 1P22-F577, 1P43-F721, 1P50-F539, 1P52-F550, 1P54-F1098, 1P57-F524A, 1P57-F524B Category: AC Class: 1, 2 Function: System check valves for systems penetrating primary containment.

Test Requirements: IVV-3521; Test Frequency - Exercise at least once every three months, quarterly.

Basis for Relief: These check valves are the inboard primary containment isolation valves for systems considered inservice during plant operation. The normally open check valves required an exercise in the reverse' flow direction which can be verified by leak testing. Primary containment leak testing each refueling (i.e., 10 CFR 50, Appendix J) constitutes proper valve exercising.

/~Tj Alternate Testing: Exercise valves during refueling (at least once every two

(

years).

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Valve Relief Request #

.D.

Al- VR-29 System: .Drywell Containment Isolation Check Valves Valves: 1P22-F593, 1P52-F639, IP51-F653 Categoryi C Class: 2 Function: System check valves for systems penetrating drywell.

Test Requirements: IWV-3521; Test Frequency - Exercise at least once every three months, querterly.

Basis for Relief: These check valves are the inboard drywell containment isolation valves for systems considered inservice during plant' operation. The normally open check valves required an exercise in the reverse flow direction. Leak testing of check valves ensure valve exercising in the close direction. Drywell leak rate test (i.e., Technical Specification 4.6.2.2) will adequately reverse flow test these valves, g Alternate Testing: Exercise valves during refueling.

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VR-30 System: Safety Systems with Thermal Expansion Check Valves ,

Valves: 1E12-F550, 1E12-F552A, 1E12-F552B, IG43-F508A, 1G43-F508B Category: O Class: 1, 2

' Function: To relief pressure from thermal expansion between two normally closed valves Test Requirements: IWV-3521; Test Frequency - Exercise at least once every three months, quarterly and IWV-3522(b) exercising proce-dure - normally closed valves.

Basis for Relief: These valves are installed as a small bypass path around a normally closed valve. During plant and system operations these check valves remain shut. Design of systems using thermal expansion check valves preclude testing in the normal manner and a thermal expansion check valve.is not required to fully open to perform the design function.

Alternate Testing: Verification that these check valves relieve thermal

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,s expansion pressure transients shall be performed during  ;

' refueling outages (at least once every two years).

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l. t/ VR-31 System: Water Leg Fill Pumps

' Valves: ~1E12-F084A, 1E12-F084B, 1E12-F084C, 1E12-F085A, 1E12-F085B, 1E12-F085C, 1E22-F006, 1E22-F007, 1E51-F061, 1E51-F062 i

Category: C Class: 2 Function: The water leg discharge check and stop check valves perform a pressure isolation function during system operation.

Test Requirement: IWV-3522(a); Exercising Procedure - normally open valves.

Basis for Relief: Design of the water leg fill system inhibits individual verification of valve closure during normal operation.

Alternate Testing: These valves shall be exercised shut quarterly during the appropriate system functional test. The water leg discharge check valves shall be verified closed by venting the upstream side of ths valves.

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9s f VR-32 System: Nuclear Boiler (B21)

l. Valves: 1B21-F410A, 1B21-F410B, 1B21-F411A,11B21-F411B,-1B21-F412A,

1B21-F412B, 1B21-F413A, 1B21-F413B, 1B21-F414A,:1B21-F414B, 1B21-F415A,.1B21-F415B, 1B21-F416A, 1B21-F416B, 1B21-F417A,

'1B21-F417B,-1B21-F420A, 1B21-F420B, 1B21-F421A, 1B21-F421B,-.

'IB21-F422A, 1B21-F422B,.1B21-F423A,;1B21-F423B, 1B21-F424A, O -1B21-F424B, 1B21-F425A, 1B21-F425B,.1B21-F440A, 1B21 F440B,

1B21-F441A, 1B21-F441B, 1B21-F442A, 1B21-F442B, 1B21-F443A, 1B21-F443B,.1B21-F444A, 1B21-F444B L

Category: _B Class: 3 Function: Supply air to air operators of the nuclear boiler ADS and Safety / Relief valves.

Test Requirements: IWV-3411; Test Frequency - Exercise at least once every three months.

IWV-3413; Power operated valves - Full stroke time IWV-3415; Fall Safe - at least once every 3 months.

IWV-3300; Valve Position Indicator Verification - at least once every two years.

-Basis for Relief: These solenoid ~ operated valves are proven operable during testing of the Nuclear Boiler ADS and Safety / Relief-valves. Also, in a recent study (BWR Owners Group Evaluation NUREG-0737, Item II.K.3.16).the number of ADS and safety relief valve openings should be reduced as much as possible to minimize LOCA risk. The design of PNPP provides divisional separation of the solenoid valves for each Safety Relief Valve (SRV) such that SRV exercise would only exercise one of the two solenoid valves. Based on this study, and the potential for causing a LOCA condition, exercising these valves is delayed to refueling.

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I Valve Relief Request #.

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b VR-32 (Continued)

Alternate Testing: Exercising, stroke time, fail safe and position indication testing shall be accomplished on an alternating refueling l outage basis as identified in PNPP Technical

l. Specifications.

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f); I kf VR-33 System: Nuclear Boiler (B21) ,

Valves: 1B21-F460, 1B21-F461~, 1B21-F462, 1B21-F463, 1B21-F480, 1B21-F481, 1B21-F482, 1B21-F483 Category: B .

Class: 3 Function: Provide air to air operators of the main steam isolation valves.

Test Requirements: IWV-3411; Test Frequency - Exercise at least once every three m- ths and IWV-3413; Power operated valves - Full stroke time IWV-3415; Fail Safe - at least once every 3 months.

Basis for Relief: These solenoid operated valves are proven operable by testing performed on the main steam isolation valves.

Full stroke exercising of the Main Steam Isolation Valves g shall result in a loss of steam flow from one main steam Q line to the turbine. Recent industry information indicates that closing MSIVs with high steam flow in the line may be a large factor in observed seat degradation.

The MSIVs are designed for partial neroke exercising with  !

full steam flow during plant operation. The partial  !

stroke test will verify operability of the valve and operator.

Alternate Testing: Exercising, full stroke timing, and fail safe timing will-be accredited by the testing of the main steam isolation ' i valves during cold shutdown. Position indication of each j solenoid operated valve will be verified during this'  !

testing at least once every two years.

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i VR-34 System: Suppression Pool Vent.Line (E12, E51)

Valves: 1E12-F103A, 1E12-F103B, 1E12-F104A, 1E12-F104B, 1E51-F079, 1E51-F081 Category: C Class: 2 Function: To provide a vent path to suppression pool for portions of systems in which condensing or cooling of a fluid can cause a negative '

pressure.

Test Requirements: IWV-3251; Test Frequency - Exercise at least once every three months, quarterly.

Basis for Relief: These check valves provide a vent path to the suppression pool during system operation. The valves remain closed during plant operation and shall be forward flow ex-ercised. The test alignment and practicality of testing would require extended system inoperability. Forward flow exercising will be performed during refueling. A refuel-

.ing outage allows access for testing and establishment of

. system nonoperability.

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Alternate Testing: Exercise valves each refueling.

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Valve Relief Request //

VR-35 System: Nuclear Boiler Head Vent Lines Valves: IB21-F001, 1B21-F002, 1B21-F005 Category: B Class: 1 Function: Provide a path for venting noa-condensible gases from the reactor head region.

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' Test Requirements: IW-3411; Test Frequency - Exercise at least once every three months and IW-3413; Power Operated Valve - Full stroke time Basis for Relief: Exercising of the 1B21-F001, 1B21-F002 and 1B21-F005 shall be performed during cold shutdown. Opening of the 1B21-F001 and 1B21-F002 during operation will allow steam to be released into the suppression pool causing a temperature rise and release of non-condensible gas into the primary containment. Testing 1B21-F005 during operation would potentially cause isolation of the head vent path to the main steam lines. Also, the 1B21-F005 valve is not required to operate (i.e., normally open l passive) during plant operation.

Alternate Testing: Exercise valves during cold shutdown.

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Valve Relief Request #

k) VR-36

. System: Nuclear Boiler Safety Reliel Valves (SRVs).

Valves: IB21-F041 A, B, C, D, E, F, G, K 1B21-F047 G, C, D, F, G, H 1B21-F051 A, B, C, D, G Category: BC Class: 1 Functioni To provide a flow path for steam to reduce reactor vessel pressure and heat removal during abnormal plant conditions.

Test Rec,uirements: IWV-3511; Test Frequency - Tested at the end of each time period es defined in Table IWV-3510-1 and IWV-3513 Addi-tional' Tests Requirement.

Basis for Relief: The safety relief valves shall be tested in accordance with PNPP Unit 1 Final Safety Analysis Report which requires a 50% sample of SRVs to be set pressure tested each refueling.and 100% visual inspection every 5 years.

The FSAR sampling requirements are in excess of ASME code,Section XI requirements.

Alternate Testing: Safety relief valves - relief function - shall be. Jn ,

accordance with PNPP Unit 1 Final Safety Analysis Report test requirements.

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., VR-37.

- System': Reactor' Water Cleanup (G33).

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?Valvesi 1G3?-F052A,.1G33-F052B

1. Category: 'C.. .

' Class: 2;

' Function: . Normal return flow path for Reactor Water' Cleanup (RWCU) water to-the-reactor vessel via feedwater.

iTest' Requirements: ;IkV-3521;~ Test Frequency - Exercise at'least once every -

three' months, ouarterly.-

Basis for Relief: Tlie reactor water cleanup system is inservice during plant l operation, maintaining _the above' check valves open.

-Testing requires the RWCU system to be in an inoperative-

' status, s

LAlternate Testing: Reverse- flow exercising shall be performed duririg refueling as plant conditions allow.

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x_'  : Valve.R$11efRequest#

^fN Ji .VR-38

. System: Control Rod Drive Hydraulics:(C11)

- Valvesi :1011-120,'1011-121, 1C11-122,'1C11-123 (Typical of 177).

l. O Category:.B i.

[ . Class: 2r 1

- Function: Dirert Control Rod Drive (CRD) for the insertion and withdrawal of '

control' rods.

J Test Requirements: IW-3413; Power operated valves . - Full. stroke time.

Basis for Relief: The insertion and' withdrawal oficontrol' rods is accom .. ;

plished by the positioning of these valves and'1011-138 (i.e.,.CRD cooling water check valve). 'The CRD Units are integrally attached components and notching of control rods causes~ rapid positioning of these. components. The recording of stroke time (e.g.,:less than tenth of a second) would only be indication of electrical circuitry

a. , delay and human response errors. Proper in-sortion/withdrrwal by notching shall verify proper; valve operability.

' Alternate Testing: , Verify control rod movement-by notching weekly.

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V - VR-39

. System: Standby Liquid Control Transfer System (C41)

Valves: IC41-F520 Category:.AC Class: 2

' Function: To provide inboard containment isolation.

Test Requirements: IWV-3251; Test Frequency - Exercise at least once every three (3) months, quarterly.

Basis for' Relief: This check valve provides containment isolation and allows a flow path from the SBLC transfer tank to the SBLC tank.

The SBLC tank is maintained in a constant state of readi-ness during plant operations. Testing the check valve requires draining borated solution from the SBLC tank while providing demineralized makeup water, thus reducing the system readiness condition.

Alternate Testing: Transferring water during refueling shall provide forward flow exercising when plant operational mode' allows the

(

f-) SBLC system to be inoperable.

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VR-40 3t \L j b System: . Reactor Water Cleanup System (G33) l l

Valves: 1G33-F001, 1G33-F004, 1G33-F039, 1G33-F040, 1G33-F053, 1G33-F054 l 4

Category: A I

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[.- Class: 1

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. 1 Function: To, provide containment isolation of the Reactor Water' Cleanup i

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Wg Test Kequiremente ,IWV-3411; Test Frequency - Exercise at least once every

.4 t'nree months and

.y pg IWV-3413; Power Operated Valves - Full stroke time. I o -

I 'I Basis fm Rolf f: hheReactorWaterCleanupSystemisinserviceduring

'I t normal plant. operation and provides a backup in post

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j t' accident analysis. This system ensures that reactor coolant pli, chlorides, and activity are maintained within c

,ppecified limits. These limits are to prevent the b: ' 'ilikelihood of exceeding 10CFR100 guidelines or allowing 1

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![ stress corrosion cracking of the stainless steel systems.

A closure of any valve during surveillance testing would

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I  ; chuse a loss of the plant's ability to control chemistry. l y, f -.

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t~  ; .i A1N(rnate Testing: The operational readiness of these valves shall be l' s tarified during cold shutdown.

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h *%) VR-41 i

System: Control Rod Drive Hydraulic System (C11)

Valves: 1C11-115 (typical of 177) l l

Category: C )

l Class:- 2 Function: Control Rod Drive Accumulator Supply Check Valve. j Test Requirements: IWV-3521; Test Frequency - Exercise at least once every three months

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Basis for Relief: This valve operates as an integral part of the hydraulic control unit to rapidly insert control rods. To allow proper testing (reverse. flow exercise) of the accumulator supply check valve requires securing of the control rod drive pumps. The control rod drive pumps provide;

1) cooling water to hydraulic control units, 2) reactor vessel level control and 3) reactor coolant recirculation pump seal and purge water.

f-s Alternate Testing: The reverse flow exercising of the check valve shall be

'( ) satisfied by performance of the accumulator pressure decrease test during each refueling.

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Valve Relief Request #

U? , VR-42 System: Residual Heat Removal System (E12) .

Valves: .1E12-F054A, 1E12-F054B Category: C Class: 2 Function: Residual Heat Removal Heat Exchangers Reactor Core Isolation Cooling Check Valves for Steam Condensing Mode.

Test Requirements: IWV-3521; Test Frequency'- Exercise at least once every three months Basis for Relief: These valves are used during steam condensing mode resid-ual heat removal operation. The steam condensing mode is rarely used and requires loss of residual heat removal system safety injection and shutdown cooling modes of operation.

-Alternate Testing: These valves shall be forward flow exercised each refueling outage by removing and manually exercising.

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Ek--) VR-43

' System: Main Steam Isolation Valve Leakage Control (E32)' .

1 Valves: 1E32-F001A, 1E32-F001E, 1E32-F001J, 1E32-F001N, 1E32-F002A, 1E32-F002E, 1E32-F002J. 1E32-F002N, 1E32-F003A, 1E32-F003E, 1E32-F003J, 1E32-F003N, IE32-F006, IE32-F007, IE32-F008, 1E32-F009 Category:.A (1E32-F001A..-F001E, -F001J, -F001N)

B (1E32-F002A, -F002E, -F002J, -F002N), (1E32-F003A, -F003E, -F003J,

-F003N), 1E32-F006, IE32-F007, IE32-F008, 1E32-F009 Class: 1, 2 Function: Provides Leakage Control System pressure isolation from the Main Steam Line Pressure during normal operation.

Test Requirements: IWV 9411; Test Frequency - Exercise at least once every three months'and ,

IWV-3413; Power Operated Valves - Ful! Stroke Time Basis for Relief: These isolation valves receive an is91ation signal when steam line presaure exceeds 20 psig. To exercise these valves during plant operation would involve a loss of one isolation barrier and bypassing the satety interlock.

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Exercieing of these valves will be performed during cold shutdown as to protect the low pressure MS1V Leekage Control System from overpressurization.

Alternate Testing: Exercise during cold shutdown p.

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r~s l k-- VR-44 System:- Containment Vessel & cywell Purge (M14)

Valves: 1M14-F045, 1M14-F055A, IM14-F055B, IM14-F060A, 1M14-F060B, IM14-F065, IM14-F070, IM14-F085 Category: A, B' i

Class: 1, 2 Function: To provide drywell isolation'for the Drywell Purge Supply System and containment isolation for the Drywell and Containment Purge Systems.

Test Requirements: IWV-3411; Test Frequency - Exercise at least once every three months and IWV-3413; Power Operated Valves - Full Stroke Time.

IWV-3415; Fall Safe - At least once every three months.

Basis for Relief: These valves are placed under " sealed closed" administra-tive controls during normal plant operations. The drywell purge supply train isolation valves are maintained closed per Technical Specification 3.6.1.8.c and seal water is injected between these isolation valves. The seal water is used to minimize tho'affects of radiation streaming.

()' The term " sealed closed" as used in this context means that the valves are secured in its close position by deactivating the motor operators. The maintaining of drywell integrity and required draining / filling of these lines ~to perform routine testing would involve extensive maintenance periods. Exercising of these valves shall be deferred to refueling outages and prior to declaring the valves operable.

Alternate Testing: Exercise valve during refuelitc and/or prior to declaring j valves' operable, j i

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LSystem: Fuel Pool Cooling and Cleanup (G41)

~ Valves: -G41-F597A and G41-F597B

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Category: _C Class: 3 Function: The check valves prevent backflow from the Fuel Pool Cooling and Cleanup Surge Tanks (G41-A002A and G41-A002B) to the Fuel Transfer Tube Drain Tank (G41-A003),

i Test Requirements: IWV-3521; Test Frequency - Exercise at least once every '

three months, quarterly. i i

Basis of Relief: These check valves remain closed during reactor operation with the Fuel Transfer Tube Drain Tank secured. The l functional operability of each check valve (i.e., forward flow exercising) shall be required during refueling outages for the purpose of pumping the~ Fuel Transfer Tube Drain Tank to the Surge Tanks. In addition, the Fuel Transfer Tube Drain Tank is isolated by a blank flange (10CFR50, Appendix J. Type C Test) making the system inoperable during reactor operation.  ;

Alternate Testing: Exercising valves during refueling and/or prior to declaring valves operable.

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1 1 n/ VR-46 System: Reactor Coolant Pressure Isolation Testable Check Valves (RHR, LPCS, RCIC and ifPCS).

. Valves: . 1E12-F041A, IE12-F041B, IE12-F041C, 1E21-F006, 1E22-F005, 1E51-F066 Category: AC Class: 1-Function: Provide pressure isolation of the reactor coolant' pressure boundary between the high pressure reactor coolant system and other safe-ty-related systems'containing low pressure designed components.

Test Requirements: IWV-3300 Valve Position Indicator Verification. Valves with remote position indicators shall be observed at least once every two (2) years to verify'that valve operation is accurately indicated.

Basis of Relief: These check valves have no external means of visually verifying actual valve position.

Alternate Testing: Verify actual valve open position by magnetic means and.

closed position during seat leakage. tests. Valve open

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position shall be verified by magnetic means and compared to indicator lights at least every two years.

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(/ VR-47 System: Residual Heat Removal System (1E12)

Valves: 1E12-F026A, 1E12-F026B, 1E12-F052A, 1E12-F052B, IE12-F087A, 1E12-F087B.

Category: B Class: 2 Function: Residual Heat Removal Valves used during steam condensing mode of operation. With the RHR system in standby readiness these valves are normally closed isolating the RHR from Main Steam system pressure.

Test Requirements: IWV-3411; Test Frequency - Exercise at least once every i three months and IWV-3413; Power Operated Valves - full stroke time Basis for Relief: These valves are closed for all modes of system operation except steam condensing mode. The Residual Heat Removal

' System is designed as low pressure and requires isolation s from the reactor coolant pressure boundary. These' valves provide system pressure isolation from Reactor Core

() Isolation Cooling supply steam and RCIC pump supply. To maintain the system pressure isolation these valves shall  ;

be tested during cold shutdown.

Alternate Testing: Exercise valves during cold shutdown.

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() VR-48 L System: Residual Heat Removal (Loop C), Low Pressure Core Spray, High

= Pressure Core Spray Valves: 1E12-F105, 1E21-F001, IE22-F001, 1E22-F013.

Category: A, B Class: 2 Function: These valves provide the action supply for the safety-related pumps. The two (2) sources of water supply are the condensate storage tank and suppression pool.

Test Requirements: IWV-3411; Test Frequency - Exercise at least once every' ,

three months and  !

IWV-3413; Power Operated Valves - full stroke time Basis for Relief: These valves have stroke time durations, such that, should the' pumps receive a sfp al to start during the exercising, pump damage could occur due to loss of suction supply. To prevent pump starts 14old require making the safety system l

. inopetabic which would place the plant in a Limiting Condition of Operation. These valves shall be tested during cold shutdown as not to place the plant in a  !

Limiting Condition of Operation.

Alto uate Testing: Exercise valves during cold shutdown. ,

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e VR-49 Systems: Containment Atmosphere Monitoring System Valtos: 1D23-F010A, ID23-F010B, ID23-F020A, ID23-F020B, 1D23-F030A, ID23-F030B, 1023-F040A, ID23-F040B, 1D23-F050 Category: A Class': 2 t

Function: Provide instrumentation isolation in case of an instrument line l failure to maintain containment integrity.

Test Requirements; IWV-3411; Test Frequency - exercise at.least once every three months and i

IWV-3413; Power Operated Valves - full stroke time IWVe3415; Fail Safe - at least once every three months Basis for Relief: The Containment Atmosphere Monitoring System provides highly reliable instrumentation for detecting abnormal conditions in the containment, drywell and the suppression g pool, and for monitoring of these areas after postulated scidents. Their normal and accident position is open.

Failure of these valves in a closed position during exercising could place the plant in a Limiting Condition for Operation. This would reduce the availability of indications to correct or analyze any abnormal condition.

Alternate Testing: Exercise, stroke time and fail safe testing during cold shutdown.

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Valve Relief Request #

'-- VR-50

. Systems: Combustible Gas Control;. System Valves: 1M51-F531A, 1H5*-F531B, IM51-F532A, IM51-F5316, !.M51-F618A, 1M51-F618B Category: C Class: 2 Function: These sample line check valves allow automatic dr.atning of condensate in sample lines and isolation to pet 1:om a localized sample.

Test Requirements: IW-3521; Test Frequency - exercise at least once every three months.

. Basis for Relief: These simple check valves are locceed inside the drywell -l and primary containment. To reverte fits exercise these l-check valves would require making the sample lines l inoperable for installation of. test equipt:.ent and requires i entry into the drywell.

n Alternate Testing: The reverse flow exercise shall be performed during each (g refueling.

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G.' VR-51 Systems: Division 1 and 2 Standby Diesel Generator Starting Air (1R44) and Division 3 HPCS Standby Diesel Generator Starting Air (1E22)

Valves: 1E22-F543A, 1E22-F543B, 1R44-F010A, 1R44-F010B, 1R44-F015A, 1R44-F015B, 1R44-F020A, 1R44-F020B, 1R44-F025A, 1R44-F025B Category: B Class: 3 Function: Starting Air Valves supply starting air for the Division 1 and 2 Standby Diesel Generators and the HPCS Standby Diesel Generator.

Test Requirements: IWV-3411; Test Frequency - Exercise at least'once every three months and IWV-3413; Power Operated Valves - full stroke time IWV-3415; Fail Safe - At Icast once every three months Basis for Relief: Valve design does not provide valve position indication.

Failure of a valve to perform the required function will result in an increase in the starting time of the diesel

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generator or failure to secure starting air.

Alternate Testing: Valves shall be verified operable during monthly diesel generator technical specification surveillance testing.

The starting time shall be monitored to determine valve operability.

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As .) . .VR-52 Systems: - Control Rod Drive IIydraulic System Scram Discharge Volume Valves: IC11-F010, IC11-F011, IC11-F180, 1C11-F181 Category: A Class: 2 Function: These valves provide pressure isolation of the reactor coolant pressure boundary (RCPB) during a reactor scram condition.

1 Test Requirements: IWV-3424, Seat Leakage measurement a) measuring leakage through a downstream tell tale connection or b) by measuring the. feed rate required to maintain pressure.

IWV-3426, Analysis of Leakage Rates. Leakage rate measurements shall be compared with previous measurements and with the permissible leakage rates specified by the owner for a specific valve.

TWV-3427, Corrective Action. Action for exceeding specified leakage rates, p)

(' Basis for Relief: These valves have been identified as Category "A" valves, to address the concerns of IEN 85-72 involving failures of SDV Vent and Drain valves. The design of the Perry Nuclear Power Plant Unit 1 ensures: 1) integrity of the primary containment by venting to the drywell and draining to the suppression pool and 2) minimizing the potential of inadvertent isolation of the scram discharge volume.

These design considerations prohibit measuring seat leakage in accordance with Subsection IWV.

Alternate Testing: Identify seat leakage by external measurement (e.g., Sonic Flow Detector) at least once every two (2) years to commence during the first refueling outage.

9 f.l jq Valve Relief Request #

\.

XI VR-53

-Systems: Residual Heat Reauoval- (RHR)

Valves: 1E12-F037A, IE12-F037B.

i.

Category: A

Class

2 Functlon:. Provide Reactor Pressure Vessel Isolation.from Upper Containment Pool Test' Requirements: IWV-3411; Test Frequency - Exercise at least once every three. months and IWV-3413; Power operated Valves - full stroke time.

i

-Basis for Relief: These valves (1E12-F037A and 1E12-F037B) provide Isolation between Reactor' Pressure Vessel (RPV) and the Upper '

- Containment Pool (UC) . An 135 psig Interlock is provided to prevent Inadverten Valve misalignment during Shutdown Cooling Oparation, which would allow transfer of RPV water into the UCP.. This : d ition could cause thermal loads on

q the UCP and high UCP bulk temperatures. Also, there could 4j be an increase in contamination to the UCP leading to higher radiation exposures to plant personnel.

Alternatie Testing: Exercise valves during Cold Shutdown.

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VALVE RELIEF REQUEST #. ,

L '\- r VR-54 i System: High Pressure Isolation Valves (RHR, RCIC)

Valves: 1E12-F008, IE12-F009, 1E12-F550, 1E12-F019, 1E12-F023, 1E51-F065, l

.1E51-F066.

Category: A, AC Class: .1, 2 Function: Provides Pressure Isolation for the Reactor Coolant Pressure Boundary System and provides high pressure to low pressure system isolation, Test Requirements: IWV 3422; Test frequency - valves shall be leak tested at least once every two years.

Basis for Relief: During cold shutdowns or refueling, Technical Specifications 3.4.9.2 and 3.5.2 require that two modes of i shutdown cooling and two ECCS systems be maintained

' operable unless the plant is in the refueling with the reactor vessel head removed and the cavity flooded. High

. pressure seat leakage testing of these valves in any mode

, other than refueling with the head removed, renders one or more ECCS and shutdown cooling modes inoperable, in

(#)-

violation of these Technical Specifications. Testing of

.these valves during refueling outages ensures that adequate alternate means of decay heat removal exists and enhances system availability.

Alternate Testing: Leak test valves during refueling outages.

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Valve Relief Request #

\--l' VR-55 Systemi Drywell Containment Isolation Check Valves Valves: 1P43-F722  ;

Category: C Class: 2 Function: System check valve for drywell penetration supplying cooling water to drywell equipment.

Test Requirements: IWV-3521; Test Frequency - Exercise at least once every three months, quarterly.

1 i

Basis for Relief: This check valve is the inboard drywell isolation valve for a system inservice during plant operation and shutdown. The normally open check valve requires an exercise in the reverse flow direction. Individual reverse flow test during refueling verifies proper valve exercising.

Alternate Testing: Exercise valve during refueling.

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'SECTION 3.3

- VALVE TESTING SYSTEM / ATTACHMENT INDEX AND TEST TABLES.

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1 b<:

Valve Testin;; System / Attachment Index

! [_ ')_

Lj System Dwg. No./Rev. . Attachment No. Page Nuclear Boiler (B21) D-302-121/Rev. L 1 III-1-1 D-302-605/Rev. E I

.l 4

Reactor Water Recirculation (B33) D-302-601/Rev. G 2 III-2-1 i D-302-602/Rev. G 1 s Control Rod Drive Hydraulics (Cil) D-302-871/Rev. J 3 III-3-1 D-302-872/Rev. J l

Standby Liquid.

Control (C41) D-302-691/Rev. H 4 III-4-1 D-302-692/Rev. E Plant Radiation Monitoring (D17) D-806-004/Rev. D 5 III-5-1  ;

D-806-007/Rev. E Containment Atmosphere Monitoring (D23) D-302-881/Rev. H 6 III-6-1 rs l ) Residual Heat

.%aoval (E12) D-302-641/Rev. M 7 III-7-1 D-3C2-642/Rev. M D-3.02-643/Rev. M Low Pressure Core Spray (E21) D-302-705/Rev. K 8 III-8-1 High Pressure Core Spray (E22) D-302-701/Rev. N 9 III-9-1 MSIV Leakage Control (E32) D-302-341/Rev. E 10 III-10-1 D-302-342/Rev. B i Reactor Core Isolation Cooling (E51) D-302-631/Rev. G 11 III-11-1 D-302-632/Rev. H Containment Integrated i

' Leak Rate-Testing (E61) D-302-811/Rev. H 12 III-12-1 Reactor Water Cleanup (G33) D-302-671/Rev. H 13 III-13-1 D-302-672/Rev K tO L.-)

<d ., , qiy . -l; .f I F ,

m  ;,w , ,

g -

4 = .6

- System

,

Dwg. No./Rev. Attachment No. Page TFueliPool Cooling' .

, '?and Cleanup (G41)' 'D-302-651/Rev.-R' '14 III-14-1 1 f. , D_-302-654/Rev. F' 3 .; D-302'655/Rev.'J.

/

4- Suppression Pool" .

Cleanupj(G42) LD-302-661/Rev. R- 15 III-15 4 Suppression Pool-

- Makeup . (G43) - D-302-685/Rev.'H' 16 III-16-1 1

I Liquid'Radwastef(G50) D-302-737/Rev, Os 17 III-17~1>

~

, ,.g Liquid Radwaste:

s

• ' Sumps.(G61). D-302-739/Rev.-S 18 III-18-l' D-302-740/Rev. R-

. Containment Vessel-and-

Drywell Purge .(M14) D-912-604/Rev, U 19 III-19-1 Drywell and Containment.

~

L .. y a .

'} Vacuum Relief ~(M17) D-912-606/Rev. M .20; ,

III-20-1

' Combustible Gas Control (MSI): D-302-831/Rev. L 21 III-21-1 D-302-832/Rev. L Main Steam (N11) D-302-011/Rev. Q 22 III-22-1 Main, Reheat,.

Extraction, and Misc., Drains-(N22) 'D-302-121/Rev. L 23 III-23-1

~

Feedwater Leakage

. Control.(N27) D-302-082/Rev. S 24 III-24-1 D-302-971/Rev. D g, . Condensate Transfer l and Storage (P11) D-302-102/Rev. P 25 III-25-1 Mixed Bed Demin, and

-Distribution (P22)- D-302-713/Rev. R 26 III ".e-1 Emergency. Closed Cooling Water (P42) D-302-621/Rev. J 27 III-27-1

.. D-302-622/Rev. F

- 100 -

p b.

A '

7 ,j.- , 3; E' t d'

1

.kr. >

u Valve ~ Testing' System / Attachment Index Continued '

System '

Dwg.' No;/Rev. Attachment No., Page

! Nuclear Closed l LCooling'(P43): D-302-613/Rev.' L 28 'III-28-1 1

iEmergency" Service

' Water (P45) 'D-302-791/Rev..L 29 ~III-29-l' i; . D-302-792/Rev. L ,

% Control Complex

' Chilled Water,(P47)- 'D-913-001/Rev. X- 30' .III-30-1

'D-913-002/Rev. M  :

s i' ESW Screen Wash r 1 '(P49) .D-302-214/Rev.-J. .31 III-31-1

, -Containment'.. Vessel'

Chilled _ Water (P50): E-913-008/Fev. H 32 :111-32-1

,' Service Air, .

Distribution (PSI)'- ,D-302-242/Rev. H '

33 III-33-1' '!

Instru;nent : Air (PS2) D-302-243/Rev. J- -34 III-34-1 W ,

Penetration Pressurization (P53) D-302-761/Rev. C 35 III-35-1

-U Fire 8iervice Water-andC0f(P54)1 D-914-003/Rev. S' 36 III-36 D*914-005/Rev. M Safety-Related:

Instrument' Air(P57) D-302-271/Rev. F 37 III-37-1

. Nitrogen Supply (P86) . D-302-950/Rev. E 38 III-38-1 Post Accident '

~- Sampling : (P87) - D-302-431/Rev. F 39 III-39-1 Standby _ Diesel

, Generator Starting

. Air (R44)-- D-302-351/Rev, K 40 III-40-1

• Staridby. Diesel

' Generator Fuel D-302-352/Rev. L 41 III-41-1 Oil (R45) D-302-356/Rev. C lO1

- 101 -

Valve Testing System / Attachment Index

=,

\ Continued

. v' .

System Dwg. No./Rev. Attachment No. Page Standby Diesel

. Generator Jacket Water (R46) D-302-354/Rev. G 42. III-42-1 Standby Diesel Generator Lube Oil (R47) D-302-353/Rev. E 43 III-43-1 j

.s Q

s DW218/C/107/ew 1

V

- 102 - )

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