ML20079L119

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Rev 5 to Inservice Testing Program for Pumps & Valves
ML20079L119
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 12/23/1983
From: Keith Young
IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML112240710 List:
References
PROC-831223, NUDOCS 8401250296
Download: ML20079L119 (145)


Text

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DUANE ARNOLD ENERGY CENTER Page 1 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 DUANE ARN0LD ENERGY CENTER INSERVICE TESTING PROGRAM APPROVED BY: > u * /Z-Ea-#3 k 'ERFORMANCE SUPE ISOR DATE APPROVED BY: x 12 - l o -5 3 PLANT SUPERINT - NUCL R DATE REVIEWED BY-

& fm ) ;2 -I20 -tG OPERATJdNSC'OMMITTE CHAIRMAN DATE REVIEWED BY: 11_eA [ nir,)u 3E;1t 17 93 ALARA'C00RDINATh. 00 oATE Effective Date: 12/23/83 8401250296 840112 PDR ADOCK 05000331 P PDR

GUANE ARN0LD ENERGY CENTER Page 2 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 List of Effective Pages TITLE: Duane Arncid Energy Center Inservice Testing Program Page Number Revision Date 1 - 66 5 12-23-83 ,

Appendix A 1-3 5 12-23-83 Appendix B 1 - 67 5 12-23-83 Appendix C 1 5 12-23-83

._miw.

DUANE ARNOLD ENERGY CENTER Page 3 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 ,

Iowa Electric Light and Power Company Duane Arnold Energy Center (Docket No. 50-331)

ASME INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES RECORD OF REVISIONS REVISION DATE Original March 1, 1978 Rev. 1 October, 1978

~

Rev. 2 May 1, 1980 Rev. 3 November 1, 1980 Rev. 4 January 1, 1983 Rev. 5- December 23, 1983 i "m a nur i

_ _ _ _ _ _ . _ _ _ _ _ _ . _ _ m _ _

DUANE ARNOLD ENERGY CENTER Page 4 of 66 TITLE: INSERVICE TESTING ?ROGRAM Date 12-23-83 Rev. 5 TABLE OF CONTENTS Page Title Page i List of Effective Pages 2 Record of Revisions 3 Table of Contents 4 List of Tables 5 List of Figures 6

1.0 INTRODUCTION

7 2.0 TESTING PROGRAM FOR PUMPS 8 2.1 General Information 8 2.1.1 Applicable Code 8 2.1.2 Pump Program Tables 8 2.1.3 Measurement of Test Quantities 9 2.1.4 Allowable Ranges of Test Quantities 9 2.1.5 Bearing Lubricant 9 2.1.6 Instrument Accuracy 9 2.1.7 Exempted Pumps 9 2.2 Relief Requests for Pump Testing Program 10 3.0 TESTING PROGRAM FOR VALVES 23 3.1 General Information 23 3.2 Relief Requests for Valve Testing Program 29 Appendix A - Pump Testing Program Appendix B - Valve Testing Progrcm

DUANE ARNOLb ENERGY CENTER Page 5 of 66 TITLE: INSERVICE TESTING PROGRAM Data 12-23-83 Rev. 5 LIST OF TABLES Table Title Page PR-8.1 Allowable Ranges of Vibration 20 Velocity Quantities

,-- 3.1-1 Inservice Valve Test 26 3.1-2 Test Frequency 28 I ' EE ' ' E - -

.- m__. __ __-__ _im_____m.___-.__- _ _ _ _ _ _ _ _ _ _ -

DUANE ARNOLD ENERGY CENTER Page 6 of 66 TITLE: INSERVICE TESTING PROGRAM y

Date 12-23-83 Rev. 5 LIST GF FIGURES Figuie Title Page PR-5.1 Alternate Testing Approach for Determination of Hydraulic Change 16

DUANE ARNOLD ENERGY CENTER Page 7 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5

1.0 INTRODUCTION

Revision 5 of the Duane Arnold Energy Center (Unit 1) ASME Inservice Testinn Program for Pumps and Valves will be in effect through February 1,1985, the end of the first 120-month (10-year) inspection interval. The program will be updated prior to the start of the second inspection interval in accordance with the requirements of 10CFR 50.55a(g).

This document outlines the inservice testing (IST) program for Duane Arnold Energy Center, based on the requirements of Section XI of the ASME Boiler &

Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda. All references to IWP or IWV in this document correspond to Subsections IWP or IWV, respectively, of ASME Section XI,1980 Edition through the Winter 1980 Addenda unless otherwise noted.

The inservice inspection (ISI) classification boundaries for the Duane Arnold Energy Center are identical to the design classification or quality group boundaries shown on the plant piping and instrument diagrams (P& ids). This IST program was developed using 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" Division 1 (Draf t) Regulatory Guide and Value/ Impact Statement,

" Identification of Valves for Inclusion in Inservice Test Programs"

- "NRC Staf f Guidance for Preparing Pump and Valve Testing Programs and Associated Relief Request," January 1978

- Final Safety Analysis Report, Duane Arnold Energy Center

- Technical Specifications, Duane Arnold Energy Center The inservice tests identified in this program will verify the operational readiness of p;mps and velves whose functions are required to mitigate the consequences of an accident or to bring the reactor to a cold shutdown condition. The ISI classification of each pump and valve matches the ISI classification indicated on the P& ids excepting those pumps and valves in the IST boundaries that are identified as non-classed (NC).

FOR INFORMA110H Dlit.Y

DUANE ARNOLD ENERGY CENTER Page 8 of 66 TITLE: INSERVICE TESTING PROGRAM l Date 12-23-83 Rev. b i

2.0 TESTING PROGRAM FOR PUMPS 2.1 General Information 2.1.1 Applicable Code This Inservice Testing Program for ISI Class 1, 2, 3 and NC Pumps meets the requirements of Subsection IWP of Section XI cf the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter of 1980 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 Appendix A list all pumps included in the Duane Arnold Energy Center IST Program. Data contained in these tables identifies those pumps subject to inservice testing, the inservice test quantities, the inservice testing interval, and any applicable remarks. The column headings are listed and explained below:

- PUMP NUMBER: The pump identification number PUMP NAME: The system of which the pump is a component.

CLASS: The ISI classification of the pump

- P&ID: The DAEC drawing number for the P&ID referring to the pump C00R: The drawing coordinate location of the pump on the P&ID

- SPEED, INLET PRES, CIFF PRES, FLOWRATE, VIBRATION AND BLARING ltMP: Inservice test quantities to be measured, keen the character "Y" appears in a particular test quantity column, that quantity will be measured during inservice testing in accordance with Subsection IWP. If a modified test is planned or if the character "N" appears in a particular test quantity column, a request for relief number will be referenced. Requests for relief are identified PR-X. The requests for relief cre included in Section 2.2.

. TEST INTERVAL: The frequency of testing.

- REMARKS: Remarks in the IST Program are coded as Note 001, Note 002, etc.

- DUANE ARNOLD ENERGY CENTER Page 9 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 2.1.3 Measurement of Test Quantities

. SPEED: Per IWP-4400, shaft speed measurements ?re not applicable (NA) for pumps directly coupled to synchronous or indgetion-type drivers. For variable speed pumps, the pump speed is set at the reference , speed per IWP-3100.

. INLET PRESSURE: For pumps taking suction from a tank or the residual heat removal (RHR) service water complex basin, inlet pressure will be calculated (usina appropriate correction factors) from 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 from inlet and discharge pressure measurements or by direct differential pressure measurement.

FLOWRATE: Pump flowrate will be measured.

. VIBRATION: Pump vibration will be measured.

. BEARING TEMPERATURE: Pump bearing temperature (s) will be measured when practical. ,

2.1.4 Allowable Ranges,of Test Quantities

.The allowable ranges specified in Table IWP-3100-2 will be used for differential pressure, flow and vibration measurements except as discussed in PR-8. Should a measured test quantity fall outside the allowable range, the possibility of defining an expanded allowable range, in accordance with ASME Code interpretation XI-1-79-19, will be investigated. In some cases, the performance ~ of a pump may be adequate to fulfill its safety function even though there may be some parameter variation outside of the allowable ranges.

2 .1. 5 - Bearing Lubricant As specified in Table IWP-3100-1, the pump bearing lubricant level or pressure will be observed during inservice testing.

2.1.6. Instrument Accuracy

' A1lowable instrument accuracies are given in Table IWP-4110-1. In some cases, relief.has been requested from the requirements of Table IWP-4110-1. (See Relief Request No. PR-7) ,

2.1.7 Exempted Pumps The reactor recirculation centrifugal pumps have been exempted from the IST program because they do not perform a safety function. The reactor

. recirculation jet pumps have been exempted from the IST program because SJbsection IWP is applicable to centrifugal and positive displacement pumps only. These pumps have been exempted in accordance with IWP-1100.

_ _ _ _ _ _ _ _ - _ - _ - _ _ _ - _ - _ _ - _ . l

0UANE ARNOLD ENERGY CENTER Page 10 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 SECTION 2.2 RELIEF REQUESTS FOR PUMP TESTING PROGRAM k's su

DUANE ARNOLD ENERGY CENTER Page 11 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. PR-1 PUMP NUMBER:

DIESEL FUEL OIL PUMPS iP-44A and 1P-44B SECTION XI REQUIREMENTS 1 Measure pump vibration amplitude quarterly and bearing temperature annually.

(IWP-3100)

BASIS FOR RELIEF:

The diesel fuel oil pumps and motors are inaccessible during operation. Both the pump and motor are submerged inside the diesel fuel oil tank (IT-35).

ALTERNATE TESTING:

No alternate testing is proposed.

y FOR ll1 FORMAT 10!1 DNLY

DUANE ARNOLD ENCRGY CENTER Page 12 of' 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5

) .

RELIEF REQUEST NO. PR-2 PUMP NUMBER:

EMERGENCY SERVICE. WATER (ESW) PUMPS 1P-99A and 1P-99B.

SECTION XI REQUIREMENTS:

Measure bearing temperature annually. (IWP-3100)

BASIS FOR RELIEF:

The ESW pump motors are provided with roller bearings immersed in an integral oil bath reservoir. Discussions with the manufacturer of the motors (General Electric Company) indicate that measuring bearing temperatures would be difficult and of marginal value. Likewise, measuring oil temperature on an annual basis, is also questionable. It is estimated that approximately four hours of pump operation w3uld be required for the oil temperature to stabilize.

Furthermore, in this particular case due to the arrangement of the oil reservoir, oil temperature is more a function of winding and ambient air temperatures than of bearing temperature. It is likely that annual trends of oil temperature in this case would be of little value in determining the condition of pump bearings.

ALTERNATE TESTING:

-No alternata testing is proposed.

DUANE ARNOLD ENERGY CENTER Page 13 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12 23-83 Rev. 5 RELIEF REQUEST NO. PR-3 PUMP NUMBER:

HIGH PRESSURE COOLANT INJECTION (HPCI) booster and main pumps IP-216 REACTOR CORE ISOLATION COOLING (RCIC) pump 1P-226 SECTION XI REQUIREMENTS:

Measure pump vibration amplitude quarterly and bearing temperature annually.

(IWP-3100)

BASIS FOR RELIEF:

These measurements require stationing a man in close proximity .to the pumps in the HPCI and RCIC rooms. Because of the rooms' layout. the man would be in a confined area distant fran the exits. Consequently, should an accident occur such as the rupture of a steam line rupture disc, which has occurred previously (Ref. R0 78-02), the man probably could not exit in time to preveat serious injury. Thus, measurement of HPCI and RCIC pump vibration and bear ing temperatures represents a significant safety hazard.

ALTERNATE TESTING:

Instsilation of permanent sensors for bearing temperature and vibration with renote readouts is under evaluation and is slated for completion in 1985. At chat-time measurements will be taken in accordance with IWP-3100 or request for relief will be submitted.

I

DUANE ARN0LD ENERGY CENTER Page 14 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. PR-4 PUMP NUMBER:

RHR SERVICE. WATER PUMPS 1P-22A, B, C, & D ESW PUMPS IP-99A & B RIVER WATER PUMPS 1P-117A, B, C, & D DIESEL FUEL OIL TRANSFER PUMPS 1P-44A & B STANDBY LIOUID CONTROL PUMPS 1P-230A & B SECTION XI REQUIREMENTS:

Measure pump inlet pressure before starting the pump and during the test.

(Table'IWP-3100-1)

BASIS FOR RELIEF:

Pumps other than IP-230 A & B are submerged and have inlet pressures which correspond to levels of .the wet pit, the river, or diesel oil storage tank.

Because these levels remain relatively constant before and during the test, only one measurcriant per test is necessary.

In the case of the standby liquid control (SBLC) pumps, no gauge is installed at the pump suction and suction pressure .is assumed to be equivalent to the static head corresponding to the average height of test tank level above the pump suction.

ALTERNATE TESTING:

One inlet pressure, based on wet pit, river', or oil tank level, will be calculated per test.

One suction pressure for the SBLC Pumps will be calculated from the average '

' test tank level during the test.

_-_ ___ J

DUANE ARNOLD ENERGY CENTER IPage 15 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. PR-5 PUMP NUMBER: .

RIVER WATER PUMPS 1P-117A, B, C, and D CORE SPRAY PUMPS 1P-211A and B HPCI PUMP 1P-216 RCIC PUMP 1P-226 RHR PUMPS 1P-229A, P C, and D SECTION XI REQUIREMENT:

Reference values shall be at paints of operation readily duplicated during subsequent inservice testing. (IWP-3110)

BASIS FOR RELIEF:

Operating experience has shown that flowrates (independent variables during inservice performance testing) cannot be readily duplicated with the present flow control systems. Efforts to exactly duplicate reference values would require excessive valve manipulation which could ultimately result in damage to ,

valves or operators.

ALTERNATE TESTING:

DAEC will implcment an alternate means of measuring pump performance. ,

Reference values will be established for flowrate (Qr) and differential pressure (dP p ) during the reference value tests. However, in lieu of duplicating Q during subsequent inservice performance tests, a flowrate (Q)),lowertf$anQp, will be obtained and recorded along with the corresponding differential pressure (dPj ). Next, a flowrate (Qh ), higher than Qp , will be obtained and recorded along with its corresponding differential pressure (dP h). These two points, (Q , Pj ) and (Oh , Ph)>

define a small portion of the pump curve which inte)rsects the vertical line defined by Qp (See Figure PR-5.1). Using linear interpolation between the two points, a different.ial pressure (dP) will be computed from the intersection of the pump curve and the vertical line established by Q .rThis computed value for dP will be recorced and compared to the reference differential pressure (dPp ) per table IWP-3100-2.

The alternate testing procedure described above assumes that the pump curve is nearly linear between Q3 and Qh. Procedural limits for Qj and Qh have been established and individual pump curves have been ana.yzed to ensure near linearity between Q1 and Qh -

FOR INFORMATION DNLY I

k DUANE ARNOLD ENERGY CENTER Page 16 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 1

~ PUMP CURVE DURING REFERENCE VALUE TEST.

PUMP CURVE AT TIME OF e N CURRENT TEST WHICH o REFLECTS PUMP DEGREDATION.

e dPr w a dP1

-- - - .U N

,1 dP f a d4 l __. ,\

I s

5 l

i.

i s\

I I I I I I

% Cr Oh Flow Rate Figure PR-5.1 Alternate Testing Approach for Determination of Hydraulic Change

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DUANE ARNOLD ENERGY CENTER Page 17 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5

. RELIEF REQUEST NO. PR-6 PUMP NUMBER:

DIESEL FUEL OIL TRANSFER PUMPS 1P-44A and B

- SECTION-XI REQUIREMENTS:

Each pump shall be run at least five minutes under conditions as stabic as system permits. (IWP-3500)

BASIS FOR RELIEF:

The diesel fuel oil transfer pumps cannot be operated for five minutes because

.the available capacities of the diesel oil day tar.ks are too small. Sufficient volume for both five minutes of operation and flow measurement by increase in tank level is required. Since the tank is filled at the end of each diesel generator operability tett, about two hours of operation of the diesel generator would be needed to reduce the tank level to that required for

. retesting of the fuel oil pumps. The additional hour of operation of the diesel generator, beyond the one hour technicai specification requirement, is unaccept able.

ALTERNATE TESTING:

As soon as.the diesel fuel oil transfer Dumps reach stable operation at the reference conditions, as indicated by a steady reading of the discharge pressure gauges, test data will be recorded.

4 4

1 2

DUANE ARNOLD ENERGY CENTER Page. 18 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. PR-7 PUMP NUMBER:

DIESEL OIL TRANSFER PJMPS 1P-44A and B RIVER WATER PUMPS 1P-117A, B, C and D HPCI PUMP 1P-216 RCIC PUMP 1P-226 SECTION XI REQUIREMENTS:

Instrument accuracy shall be within the limits of Table IWP-4110-1.

BASIS FOR RELIEF Based on engineering judgement, the difference between an instrument with an '

accuracy of + 2.0 percent of full scale and one with an accuracy of + 2.25 percent of-full scale is insignificant. Thc costs due to replacing The existing instrumentation with new devices that meet the 1.imits of Table IWP-4110-1 are not justified since there will be no corresponding improvement in the level of plant safety.

ALTERhATE TESTING:

' Inservice test measurements of pressure, differential pressure, and flowrate will be taken using instruments with instrument accuracies that are less than or equal to + 2.25 percent of full scale.

t

DUANE ARNOLD ENERGY CENTER Page 19 of 66 TITLE: INSERVICE TESTING PROGRAM Date Hv.

t 5 RELIEF REQUEST N0. PR-8 PUMP NUMBER:

All pumps (except Diesel Fuel Oil Transfer Pumps IP-44 A & B).

SECTION XI REQUIREMENTS:

Al least one displaceaent vibration amplitude (pee < to-peak composite) shall be read during inservice testing. (IWP-4510)

BASIS FOR RELIEF:

Measuring vibration in velocity units rather than amplitude is an industry accepted method considered to be more sensitive to small changes that oftentimes are indicative of developing mechanical problems. Velocity measurements detect not only high-amplitude vibration, characteristic of major mechanical problems, but low-amplitude vibrations caused by misalignment, imbalance, or bearing wear.

ALTERNATE TESTING:

Where practical, pump vibration measurements will be taken in velocity units.

In all other cases, displacement measurements will conform to Paragraph IWP 4510. Acceptance criteria for velocity measurements will conform to ASME Publication 78-WA/NE-5 and Table PR-8.1.

_ - . _ _ _ - . --_____,--_-._._.__.__m.. _ _ _ _ _ . _ , ._

TABLE PR-8.1 -

ALLOWABLE RANGES OF TEST QUANTITIES ALERT RANGE REQUIRED ACTION RANGE LOW HIG!1 LOW HIGH [

ACCEPTABLE RANGE VALUES VALUES VALUES VALUES

' QUANTITY G  !

v When 0 < vp< .15 in/sec 0 to .3 in/sec None .3 in/sec to None v > .45 in/sec @5

.45 in/sec 5 E R 8 <

- G i v' When .15 in/sec < v r 0 to .45 in/sec None .40 in/sec to None v > .75 in/sec U g l j

l < .3 in/sec .75 in/sec E 9

S i

'I n j v When .3 in/sec < v r 0 to .9 in/sec None .9 in/sec to None. v > 1.5 in/sec 8

o

.9 w i

< .6 in/sec 1.5 in/sec E 9 l

y When .6 in/sec < v 0 to 1.1 in/sec None 1.1 in/sec to None v > 1.5 in/sec r

< l.0 in/sec 1.5 in/sec 5' 2 hi  %

C L

w E

Where:

v = velocity measured in inches /second, peak. F ui $

vr=. reference velocity measured.

(1) See ASME Technical Paper. 78-WA/NE-5.

DUANE ARNOLD ENERGY CENTER Page 21 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. PR-9 PUMP NUMBER:

SCREEN WASH PUMPS 1P-112A and B  ;

SECTION XI REQUIREMENTS:

An inservice test shall be run on each pump nominally every 3 months during normal plant operation. (IWP-3400)

BASIS FOR RELIEF:

There is currently no permanent instrumentation installed nor are there provisions for the installation of temporary instrumentation. An engineering evaluation is underway to identify instrumentation requirements and initiate necessary system modificatior.s. Modifications will be accomplished during 1985.

ALTERNATE TESTIiG-No alternate testing is proposed until modifications are completed. These pumps are currently test-operated as part of the DAEC surveillance test progr am. ,

DUANE ARNOLD ENERGY CENTER Page 22 of 66 TITLE: IhSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST N0. PR-10 PUMD NUMBER:

DIESEL FUEL OIL PUMPS 1P-44 A & B .

SECTION XI REQUIREMENTS:

Pump test results shall be analyzed per IWP-3200.

BASIS FOR RELIEF:

. The ASME recognizes that the characteristics of systems containing other than steam or water (eg. fuel oil) may not necessarily lend themselves to the type and detailed requirements as specified by Subsection IWP. This is so stated in the ASME response to WPPSS inquiry, File no. BC 77-666/NI 77-371 dated 1/8/79.

(See Appendix C) In cases where test data is erratic or questionable, strict compliance with the Section XI requirements will likely result in unnecessary

- pump maintenance and excessive testing of the fuel oil pumps and the emergency diesel generators.

ALTERNATE TESTING: -

Analysis of the quarterly . test data will be based on IWP-3200. In those cases where the test results are obviously erratic or misleading, alternate acceptance criteria will be developed.

4 Fh-FOR INFORIUTION 01 0 4

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..~,w , , , , , . , , - , n-. . - - . . , , , - - 7 - ~ - - -,- , , p

DUANE ARNOLD ENERGY CENTER Page 23 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 3.0 INSERVICE TESTING PROGRAM FOR VALVES 3.1 General Information This testing program for ISI Class 1, 2, 3, and NC valves meets the requirements of Subsection IWV of Section XI of the ASME Boiler and Pressure Vessel Code,1980 Edition through the Winter 1980 Addenda. Where these

. requirements are deternined to be impractical, specific requests for relief have been written and included in Section 3.2.

The tables in Appendix 3 list all ISI Class 1, 2, 3, and NC valves that have been assigned . valve categories. Valves exempt par IWV-1200 are not listed.

The following information is included for each valve:

2 - VALVE NUMBER: The valve identification number.

- P&ID C0 ORDINATE: The drawing coordinate location on the P&ID for the valve.

CLASS: The ISI Classification of the valve.

VALVE CATEGORY: The category (s) assigned to the valve based on the definitions per IWV-2200. Four (4) Jeparate categories

.are defined in the Code:

CATEGORY A - Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment or their safety function.

CATEGORY B - Valves for which a specific amount of leakage in the closed position is not measured but which require stroke testing to verify their ability to fulfill their safety function, CATEGORY C - Valves which are self-actuating in response to some system ch'aracteristic, such as pressure (relief valves) or flow direction (check valves).

CATEGORY D - Valves which are actuated by an energy source capable of only a single operation (eg. explosively-actuated valves) .

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

DUANE ARNOLD ENERGY CENTER Page~ 24 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 VALVE TYPE: The valve body design as indicated by the following abbreviations:

ANGLE ANG BALL BAL BUTTERFLY BTF CHECK CK EXCESS FLOW CHECK XFC GATE GA GLOBE GL ilEEDLE NDL NOTCHED GLOBE NGL PLUG PLG RELIEF RV RUPTURE DIAPHRAGM RPD SAFETY SV SHEAR SH STOP CHECK SCK 3-WAY 3WY 4-WAY 4WY

- ACTUATOR TYPE: The type of valve actuator as indicated by. the following abbreviations:

MOTOR OPERATOR M0 AIR-PIL0T OPERATOR AP AIR OPERATOR A0 SOLEN 0ID OPERATOR SO HYDRAULIC OPERAT0R H0 EXPL0SIVE ACUTATOR EXP MANUAL M SELF ACTUATED & MANUAL OPERATED MSA SELF ACTUATED SA SELF ACTUATED & MOTOR OPERATED SAM SELF ACTUATED & PILOT OPERATED SAP SELF ACTUATED, TESTABLE CHECK SAT

)

DUANE ARN0LD ENERGY CENTER Page 25 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 NORMAL POSITION: The position of the valve during normal plant operation, specified as follows:

0 Normally Open C Nonnally Closed 0/LO Normally Open/ Locked Open 0/LC Nonnally Open/ Locked Closed 0/KL Normally Open/ Key Locked 0/F0 Normally Open/ Fail Open 0/FC Normally Open/ Fail Closed 0/K0 Normally Open/ Key Locked and Fail _0 pen C/LO Normally Closed / Locked Open C/LC Normally Closed / Locked Closed C/KL Normally Closed / Key Locked C/F0 Normally Closed / Fail Open C/FC Normally Closed / Fail Closed C/KC Normally Closed / Key Locked and Fail Closed NE Normally Energized ND Nonnally De-energized Valves with fail-safe positions are indicated as either FO-fail open or FC-f ail closed.

. TEST: The test (s) that will be performed to fulfill the requirements of Subsection IWV. The test definitions and abbreviations used are identified in Table 3.1-1.

TEST FREQUENCY: The frequency at which the above mentioned tests will be performed. Test frequencies are defined in Table 3.1-2.

- MAXIMUM STR0KE TIME: The limiting maximum value of full stroke time, in seconds, for power-operated valves in Category A or B.

. MAXIMUM LEAKAGE: The maximum leakage allowed during the specified leaktest. The abbreviations for the units of measurement are:

C . Standard cubic centimeters per minute.

P Pressure decay in pounds per square inch per minute G Gallons per minute ,

. RELIEF REQUEST: The reference to a relief request in Section 3.2 for valve testing. Requests for relief are identified as VR-X X.

REMARKS: Remarks in the IST Program are coded as NOTE 001, NOTE 002, etc.

TABLE 3.1-1 INSERVICE VALVE TESTS TEST TEST NAME TEST DESCRIPTION 2

AT-1 Type C leaktest Containment isolation valves will be seat leak tested in #

accordance with DAEC Technical . Specification requirements .

and Appendix J, 10CFR50.

2 E

AT-2 Fxcess flow check Excess flow check valves will be tested in accordance with E valve test DAEC Technical Specifications, Section 4.7.D. g m 3  % \

AT-3 Safety and relief valve Safety and relief valve leakage is continuously monitored . . p g by the safety and relief valva tailpipe. temperature y G monitor. An alarm at 250*F indicates safety or relief 0; m valve leakage. Refer to DAEC Technical Specifications, d g Section 4.6,0. gg -<

AT-4 Vacuum breaker leaktest The suppression chamber-drywell vacuum breaker will be $p leak tested in accordance with DAEC Technical o z Specifications,Section 4.7.4. [@

AT-5 Pressure isolation valve Those- valves so designated will be leak tested in leaktest accordance with IWV-3420 using water as a test medium.

BT0 Full-stroke exercise Exercise testing in the open direction, verified by stroke

, test to the OPEN time measurement,'will be performed to confirm the full I position (IWV-3412 stroke capability of each valve. The stroke direction and 3413) tested and timed (open) is based on the direction the s'  ?

valve disk must travel to fulfill a safety function. Ei  %

~

BTC Full-stroke exercise Exercise testing in the close direction, verified by '? m test to the CLOSE stroke time heasurement, will be performed to confirm the O position (IWV-3412 ft.11 stroke capability of each valve. The stroke 43 and 3413) direction tested and timed (close) is based on the ,,

-direction the valve disk must travel to fulfill a safety $'

l function.  ?

BTD Full-stroke exercise Solenoid valves, which direct control air to main air-test to de-energized operated valves, are shown to stroke to their de-energized position pcsition by the proper operation of the associated main valves.

TABLE 3.1-1 INSERVICE VALVE TESTS _ (continued)

TEST TEST NAME -TEST DESCRIPTION- d BTE Full-stroke exercise Solenoid valves, which direct control air to main air- ".'

test to energized operated valves, are shown to stroke to their energized position position by the proper operation of the respective main - g valves. 5 'g

.m m

( CT-C0 Check valve exercise Check ' valves will be exercised from the fully closed to the. $g test to OPEN fully open positions. Verification of safety basis system p g position (IWV-3412) flow through a check valve shall be an adequate g demonstration that the valve is full open. The stroke m. m direction tested (open) is based on the direction the valve 3 g disk must travel to fulfill a safety function. g g CT-CC Check valve exercise Check valves will be exercised fram the fully open to the 3 n test to CLOSED fully closed positions. The strcke direction tested 8 9 position (IWV-3412) (closed) is based on the direction the valve disk must .g m r travel to fulfill a safety function. "

CT-SP Relief valve set point Relief and safety valve set point will be verified in verification test accordance with IWV-3510.

(IWV-3510)

DT Explosive valve test Explosively-actuated valves will be tested in accordance (IWV-3610 and 3620) with IWV-3610. g g E  %

FST Fall-safe test All velves with fail-safe actuators will be' tested to (IWV-3415) verify proper fail-safe operation upon loss of actuator y y electric power. g N PIT Position indication All valves with positioa indicators will be checked to 8 o checks (IWV-3300) verify that remote valve indicators accurately reflect valve g operation <

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TABLE 3.1-2 TEST FREQUENCY d m

(1) a TEST FREQUENCY OPERATIONAL CONDITION -

FREQUENCY 0F TESTING yy m m OP Power operation At least once per 92 days g o 2 P

i l CS Cold shutdowr. See (2) below y a RR Refueling Not less than once every two years ] y 2 x See appropriate See appropriate relief request Q l SP ;8 relief request n 8 E No operational Every five years (see Article y M SY 3 "

condition limitations IWV-3511). Applies to CT-SP test.

2Y No operational Every two years (see Article condition limitations IWV-3300). Applies to PIT test.

(1) Operational conditions are defined in DAEC Technical Specifications, page 1.0-3.

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 /> of reaching the cold stiutdown g y (2) g g condition as defined in the DAEC Technical Specifications. Testing not completed before startup may be completed during subsequent cold shutdowns. Valve testing need not be -

performed more often than once every three months. In the case of extended cold shutdowns, y y the testing need not be started within the 48-hour limitation. However, in these instances, y o' all valve testing must be completed prior to startup. -

4 LaJ O x

NOTE: It is expected that the required testing will normally be completed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> @

following cold shutdown. However, completion of all valve testing during cold shutdowns is not required if plant operating conditions do not permit testing of specific valves. [ g

DUANE-ARNOLD ENERGY CENTER- Page 29 of 66

- TITLE: . INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5

+

- SECTION 3.2 RELIEF REQUESTS FOR. INSERVICE VALVE TESTING PROGRAM 4

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DUANE ARN0LD ENERGY CENTER Page 30 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 ,

RELIEF REQUEST.NO. VR-1

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t L DUANE ARNOLD ENERGY CENTER Page 31 of 66 I:

l. -TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF EEQUEST NO. VR-2 SYSTEMS:

Various COMPONENTS:

All solenoid and air-pilot operators without individual position indication.

CATEGORY:

A&B FUNCTION:

Solenoid and air-pilot operators are used to control actuators on many valves.

TEST REQUIREMENT:

- Stroke time evaluation per IWV-3413 (b).

BASIS FOR REL!EF1 Solenoid and air-pilot valves which control the air supply to a main valve usually do not have indicator lights. However, the operation of the main valve within its stroke time limit implies that the solenoid and/or air-pilot valve is performing satisfactorily.

ALTERNATE TESTING:

r For solenold-operated and air pilot-operated valves which control the air supply to air-operated valves and have no individual positien' indication, verification that the main valve has stroked to the correct position within its respective time limits will provide adequate evidence that the solenoid or air pilot-operated volve has stroked to its proper position within the required time. When the letters "NA" appear in the stroke time column of the Inservice Testing Program cisting, the valve's stroke time is verified indirectly by the stroke time measurement of its associated main valve.

i

DUANE ARNOLD ENERGY CENTER Page 32 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST fl0. VR-3

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DUANE ARNOLD ENERGY CENTER Page 33 of 66 TITLE: INSERVICE TESTING PROGRAM '

Date 12-23-83 Rev. 5 RELIEF REQUEST N0. VR-4

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DUANE ARNOLD ENERGY CENTER Page 34 3f 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST N0. VR-5

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DUANE ARNOLD ENERGY CENTER Page 35 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST N0. VR-6 SYSTEM:

NUCLEAR BOILER

. COMPONENTS:

Reactor Relief Valves Solenoid Valves PIS No. PIS No.

PSV-4400

  • SV-4400 PSV-4401 SV-4401 PSV-4402
  • SV-4402 PSV-4405
  • SV-4405 PSV-4406
  • SV-4406 PSV-4407 SV-4407

CATEGORY:,

A/C for the reactor relief valves B for solenoid valves ,

FUNCTIONS:

  • s The functions of the relief valves are to: (1) open upon receipt of an ADS signal to blowdown reactor vessel (for the ADS valves only) and (2) act as

-primary system safety valve actuating on high system pressure or capable manual actuation from the control room.

~ The function of the solenoid valves is to energize upon receipt of a manual or ADS relief valve actuation signal and, in so doing, vent the poppet valve assembly causing the associated main valves to open.

TEST REQUIREMENT:

Exercisa and time valves every three months (BTO).

DUANE ARNOLD ENERGY CENTER Page 36 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-6 (continued)

BASIS FOR RELIEF:

Relief -is requested from the Section XI required testing frequency of once

. every three months. Exercising these valves during normal operation would cause primary system pressure spikes and reactor power fluctuations which could lead to a reactor scram. These valves will be exercised once per operating cycle as specified in DAEC Technical Specifications, Section 4.6.0.3.

In addition, relief is requested from the stroke timing requirements of Section XI. It is impractical to measure stroke times for relief and solenoid valves since the stroke times are on the order of 100 milliseconds. An abrupt change in the turbine bypass valve position will verify that the solenoid and relief valves have performed their function.

NOTE: Stroke timing requirements for the solenoid valves are discussed in Relief Request No. VR-2.

ALTERNATE TESTING:

These valves will be exercised at least once per operating cycle. The response of these valves will be verified by observing an abrupt change in the turbine bypass valve position. No stroke times will be measured.

1 i

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DUANE ARNOLD ENERGY CENTER Page 37 of 56 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST N0. VR-7 SYSTEM:

NUCLEAR BOILER COMPONENTS:

PSV-4439A PSV-4439D PSV-44398 PSV-4439E PSV-4439C PSV-4439F CATEGORY:

C FUNCTION:

During a relief valve discharge, thesa valves must be closed to prevent steam release into the drywell. After a relief valve discharge, steam remaining in the relief valve discharge piping will condense and draw a vacuum in the

' discharge line. These relief valves (vacuum breakers) open to admit air to the discharge ~line thus relieving the vacuum condition.

TEST REQUIREMENT:

Exercise in the open and close directions every three months (CT-CC, CT-CO).

BASIS FOR RELIEF: -

These valves have no external means of actuation for exercising. The only practical method for exercising these valves is by manually pushing tne disk from its seat. This requires access to the valves, which are located in the

! drywell.

ALTERNATE TESTING:

These valves will be exercised during each refueling outage concurrently with

. the setpoint verification tests (CT-SP).

DUANE ARNOLD ENERGY CENTER. Page 38 of 66 TITLE: . INSERVICE TESTING PROGRAM .

Date 12-23-83 Rev. 5-RELIEF REQUEST N0. VR-8 ,

- SYSTEMS:

NUCLEAR BOILER, REACTOR RECIRCULATION,' REACTOR CORE ~ ISOLATION C0OLING, CORE

, SPRAY, HIGH PRESSURE COOLANT INJECTION, and REACTOR VESSEL INSTRUMENTATION

COMPONENTS:

Excess flow check valves -

- CATEGORY: FOR INFORMATION

- A/C ONLY FUNCTIONS:

I Excess flow check valves limit leakage from the reactor coolant system in the-event of ~ instrumentation piping failures outside containment by closing at-10 psid and perform a containment isolation function if an instrument line were to 1f ail inside containment concurrent with a similar failure outside containment.

. TEST REQUIREMENTS:

t Exercise'in the closed direction every' three months (CT-CC).

Conduct valve seat. leakage tests once every two (2) years. (AT-1)

- BASIS FOR RELIEF:

Exercising of' these -valves is impractical during normal operation since it
i. . requires isolating instrumentation downstream of the excess flow check valves.

t Additionally,: this . testing involves a. total of 94 valves which would require L excessive cold shutdown time solely to. accomplish this testing and would ~

l greatly increase total personnel radiation . exposure.

?The excess flow ' check valves, designated F:.0-FUSE by the manufacturer (Marietta Valve: Corp, Boonton, New Jersey), have no provision for~1eaktesting nor are there such provisions in the upstream side of the lead-in tubing from the root valves. Thus, there-is no practical, method of conducting leaktests of'these.

E valves. .

It should be noted that.these valves'see little or no: flow and essentially function only.during-the exercise testing described:below. Also, the significant internal components 'are f abricated 'fran corrosion-resistant

, - materials that :are not expected to degrade during the plant lifetime. For these -reasons, general seat degradation is highly unlikely. Gross failure of +

the seat, if.present, will be identified during exercise testing.

ALTERNATE TESTING:

These valves will be exercised during each reactor refueling in accordance with DAEC-Technical Specifications,Section 4.7.0.

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DUANE ARN0LD ENERGY CENTER- Page 39 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST VR-9

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DUANE ARNOLD ENERGY CENTER Page 40 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5-i-

RELIEF REQUEST VR-10

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DUANE~ ARNOLD ENERGY CENTER Page 41 of 66 TITLE:  : INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-11 SYSTEM:

CONTAINMENT ATMOSPHERE CONTROL COMPONENTS:

CV-4327A CV-4327F CV-43278 CV-4327G CV-4327C CV-4327H CV-4327D CATEGORY:

A/C FUNCTION:

These are the pressure suppression chamber to drywell vacuum breaker valves which equalize the pressure between the two volumes when the suppression chamber pressure exceeds that in the drywell.

TEST REQUIREMENT:

Measure valve seat leakage and compare the measured leakage to a specific maximum leakage for each valve (IWV-3426).

BASIS FOR RELIEF:

A specific maximum leakage per valve is not applicable to the vacuum breaker valve testing. As part of the containment _ integrity (Type A) test a pressure decay test is performed on the pressure suppression chamber atmosphere in accordance with DAEC Technical Specifications Section 4.7.A.4.d. This pressure decay test demonstrates the aggregate leak tightness of the vacuum breaker valves.

ALTERNATE TESTING:

The leak tightness of the pressure' suppression chamber to drywell vacuum breakers will be demonstrated during the containment integrity (Type A) test.

This test consists of establishing a drywell to suppression chamber pressure differential of 1.1 psi and then measuring the suppression chamber pressure increase over a ten (10) minute period. If this pressure increase is less than 0.009 psi / min the vacuum breakers have demonstrated adequate leak tightness.

i

-DUANE ARNOLD ENERGY CENTER Page 42 of 66

-TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST N0. VR-12 SYSTEM:

CONTROL R0D DRIVE HYDRAULIC COMPONENTS:

-V-17-83 -

V-17-96 CATEGORY:

A/C FUNCTIONS:

Prevent backflow through the reactor recirculation pumps seal purge line. They also function as primary containment isolation valves.

TEST REQUIREMENT:

Exercise every three (3) months'(CT-CC).

BASIS FOR RELIEF:

These simple check valves cannot be remotely operated. They are located inside primary containment and are not accessible for testing during reactor operation. Additionally, the primary containment is inerted with nitrogen during plant operation. De-inerting and then re-inerting the containment atmosphere each cold shutdown solely for_ the purpose of conducting valve testing would represent .an excessne operational burden. These valves cannot be exercised by utilizing outside drywell test lines because the reactor recirculation pumps would require venting, necessitating containment entry.

These valves can be exercised closed during leakrate testing performed during refueling outages.

ALTERNATE TESTING:

Exercise valve for operability during each refueling outage (RR). Normal

system operation implies that the valves are open. By verifying that the valves close with the leaktest, the valves are indirectly observed to stroke from their open to closed positions.

FOR INFORMATION ONLY y - , , , . - - - . , - - - , , ay._ ~ ,

DUANE ARNOLD ENERGY CENTER Page 43 of 66

' TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF _ REQUEST NO. VR-13 SYSTEM:

CONTROL R0D DRIVE (CRD). HYDRAULIC COMPONENTS:

CV-1849 CV-1850 SV-1855 SV-1856 V-18-118 thru 206 V-18-919 thru 1007 V-18-1453 thru 1541 CATEGOR'/:

CV-1849, CV-1850, SV-1855 and SV-1856 -- Category B V-18-118 thru 206, V-18-919 thru 1007, and V-18-1453 thru 1541-- Category C FUNCTIONS:

CV-1849 - Opens with SCRAM signal to pressurize lower side of CRD pistca from accumulator.

CV-1850 - Opens with SCRAM signal to vent top of CRD piston to scram discharge header.

SV-1855 &

SV-1856 - Pilot valves for CV-1849 & CV-1850, respectively. Open on SCRAM signal to vent air operators.

-V-18-118 thru 206 -- Prevent bypassing drive water to charging water header (if depressurized); open to charge accumulators following SCRAM.

V-18-919 thru 1007 - Prevent backflow into cooling water header during SCRAM; allow cooling water circulation during normal operation.

t

.V-18-1453 thru 1541 - Open to allow flow from top of CRD pistions to the scram discharge header, t

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DUANE ARNOLD ENERGY CENTER Page 44 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 Relief Request No. VR-13 (continued)

TEST REQUIREMENTS:

Exercise and time air-operated and solenoid valves every three months (BT0,BTC).

Exercise check valves every three months (CT-CO, CT-CC).

The corresponding fail-safe test is discussed in VR-17.

BASIS FOR RELIEF:

These valves can only be tested by scramming each individual control rod. Due to extensive effort and operational constraints associated with scram testing, this is impractical to accomplish on'a quarterly basis or even during cold shutdown periods. '

Exercising and measuring the individual stroke times of the air-operated scram valves (CV-1849 and CV-1850) is impractical due to design limitations. There

-is a single position indicating light for both valves that is energized only when both valves are not in the fully-closed position. Thus, in order to accurately measure stroke time, additional individual position indicating circuitry is required. Such a backfit would be costly and could possibly detract from the basic reliability of the present configuration.

Proper operation of the check valves is monitored during plant operation.

Failure of any of tnese manifests itself in abnormal operation of the associated control rod drive which would be noted (and corrected) by the plant staff.

ALTERNATIVE TESTING:

Proper operation of these valves is demonstrated during normal plant operation and scram testing each operating cycle. The testing and acceptance criteria of the DAEC Technical Specifications, Sections 4.3.C and 3.3.C, will be substituted for stroke timing and exercising of individual valves.

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DUANE ARNOLD ENERGY CENTER Page 45 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-14 SYSTEM:

CONTROL R0D DRIVE HYDRAULIC COMPONENTS:

SV-1851 SV-1852 SV-1853 SV-1854 CATEGORY:

B FUNCTIONS:

There are 89 sets of these valves--one for each control rod drive. Normal insertion and withdrawal of the CRD's is accomplished by opening and closing a particular set of valves (only one CRD can be moved at at time). These valves are not required to change position during a scram, but must be niaintained in their normally-closed position.

TEST REQUIREMENT:

Exercise and time valves in the closed direction every three months (BTC).

Fail-safe test (FST) valves every three months.

BASIS FOR RELIEF:

The proper operati.on of these valves is demonstrated frequently during normal operation as discussed in DAEC Technical Specifications, Section 4.3.A.2.

Malfunctioning valves would be evidenced by unusual rod movement (drift).

Therefore, a special exercise and timing test for operability is not required for these valves.

ALTERNATE TESTING:

The control rod drives will be continously monitored for proper operation as required by the DAEC Technical Specifications. Weekly tests and periodic scram testing will demonstrate that the subject valves are in the closed position and operating properly. Stroke times will not be measured for the subject valves.

FORIHf0RMhil0H QNLY j

I: l of DUANE ARNOLD ENERGY. CENTER -Page 46 66 I TITLE: INSERVICE. TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST VR-15

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DUANE ARNOLD ENERGY CENTER Page 47 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELEIF REQUEST VR-16

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DUANE ARNOLD ENERGY CENTER Page 48 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-17 SYSTEM:

ALL SYSTEMS

~

COMPONENTS:

All valves equipped to fail open or closed.

CATEGORY:

A and B FUNCTION:

Upon loss of electrical power, the valve must stroke to its fail-safe position.

TEST REQUIREMENT:

Solenoid valves which control the air supply to air-operated valves and direct solenoid-operated valves must stroke to their fail-safe position upon interruption of their electrical supply. (FST).

BASIS FOR RELIEF:

De-energizing the solenoid valve has the same effect as loss of electrical power. Therefore, stroking the valve from the control room (BTO, BTC) to its f ail-safe position constitutes an FST.

ALTERNATE TESTING:

Normal stroking (BT0, BTC), to the fail-safe position of valves eruipped to fail open or closed constitutes an FST. No additional testing is necessary.

DUANE ARNOLD ENERGY CENTER Page 49 of 66 TITLE: INSERVICE TESTING PROGRAM

.Date 12-23-83 Rev. 5 RELIEF REQUEST N0. VR-18 SYSTEM:

HIGH PRESSURE'C00LANT INJECTION (HPCI)

COMPONENT:

SV-2219 CATEGORY:

B FUNCTION:

This valve functions .as the HPCI turbine drain pot level control valve and is a Class 2 isolation valve.

TEST REQUIREMENT:

Exercise and time valve every three months (BTC).

BASIS FOR RELIEF:

This valve has no individual handswitch, but is operated automatically by a local controller. Also, .it has no position indication lights. As such, the valve cannot be. operated ~to verify operability. However, during HPCI turbine operation, indirect verif.ication of its operability can be made by observing that the HPCI turbine drain pot high level alarm actuates and then resets.

This would mean that the valve is actually opening and closing as required to maintain proper drain pot level. Stroke timing, however, cannot be done.

ALTERNATE TESTING:

No alternate testing is proposed. Valve operability will be verified in the manner described above.

FOR INFORMAT10H DNLY w_ _ _ -

I DUANE ARNOLD ENERGY CENTER Page 50 of 66 l l

' TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 j 4

RELIEF REQUEST N0. VR-19 SYSTEM:

-NUCLEAR B0ILER COMPONENTS:

V-14-9 V-14-32 V-14-112 V-14-14 V-14-100 V-14-116 V-14-15 V-14-104 V-14-120 V-14-16 V-14-108 V-14-124 CATEGORY:

C FUNCTION:

These valves must close upon loss of normal air or nitrogen supply to the automatic depressurization system (ADS) relief valve accumulators and the main steam isolation valve accumulators.

TEST REQUIREMENT:

Exercise valves in the closed direction every three months (CT-CC).

BASIS FOR RELIEF:

The position of these valves cannot- be verified during normal operation since they are simple check valves and have no position indicators. In addition, access to these valves is limited since they are located either inside the drywell or the steam tunnel.

ALTERNATE TESTING:

These valves will be exercised during refueling. More frequent testing is not oractical because a leaktest must be performed to verify that they are closed.

DUANE ARNOLD ENERGY CENTER Page 51 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-20 SYSTEM: ,

i STANDBY LIQUID CONTROL (SLCS)

COMPONENTS:

V-26-08 V-26-09 CATEGORY:

A/C FUNCTIONS:

The safety functions of these check valves are to open during system injection and close for containment ~ isolation.

TEST REQUIREMENT:

Exercise valve in the open and closed directions every three months (CT-CO, CT-CC).

BASIS FOR RELIEF:

These check valves are normally closed. They can only be stroked closed during seat leakage tests performed during reactor refueling. To stroke these valves open, the SLCS pumps must discharge directly into the reactor vessel through the explosivly-actuated isolation valves. This cannot be done during normal operation or cold shutdown since the SLCS system must be drained and flushed to prevent contamination of the reactor coolant with sodium pentaborate. In addition, extensive testing is required to replace the explosive charges of-the isolation valves.

4 ALTERNATE TESTING:

These valves will be exercised open and closed during each reactor refueling.

_ DUANE ARNOLD ENERGY CENTER Page 52 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-21 SYSTEM:

HIGH PRESSURE CCOLANT INJECTION (HPCI)

REACTOR CORE ISOLATION COOLING (RCIC)

COMPONENTS:

V-23-01 V-25-01 CATEGORY:

C FUNCTIONS:

These valves are designed to prevent backflow into the suppression pool in t:.!

event of pump suction shift from the contaminated condensate storage tank (CCST) to the suppression pool. The safety-related function of these valves is to open to provide suction flow to the HPCI and RCIC pumps.

. TEST REQUIREMENT:

Exercise every three months (CT-CO).

BASIS FOR RELIEF:

There is no convenient method for verifying the ability of these valves to swing to the full-open position. The s.ystem test circuits utilize the CCST for pump suction rather than the suppression pool. Taking suction from the suppressian pool during testing is undesirable because, in so Jing, torus i water would be transferred to the condensate storage tank. Since torus water i is not demineralized, the entire condensate storage tank inventory would require processing following each test.

ALTERNATE TESTING:

l In lieu of the Code-required full-stroke test, valve operability will be demonstrated by. disassembling the valves during each refueling outage and verifying that the valve disk swings freely to the open position. Since these valves have no function during normal operation, no internal wear-induced degradation is expected.

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- DUANE ARNOLD ENERGY CENTER Page 53 of 66 TITLE: . INSERVICE TESTING PROGRAM Date 12-23-83 Rev.-5

. RELIEF REQUEST VR-22 void-a ir i

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DUANE ARNOLD ENERGY CENTER Page - 54 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST VR-23

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.DUANE ARNOLD ENERGY CENTER Page 55 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-24 SYSTEM:

CONTAINMENT ATMOSPHERE CONTROL COMPONENT 3:

V-43-82 V-43-84 V-43-86 V-43-88 CATEGORY:

C FUNCTION:

The function of these check valves is to prevent backflow from the containment into the containment atmosphere dilution (CAD) system.

TEST REQUIREMENT:

Exercise valve every three (3) months (CT-C0).

BASIS FOR RELIEF:

These valves are verified open during the CAD system functional test and verified closed during the Type C leak tests on the downstream containment isolation valves. Both of these tests are performed during reactor refueling.

ALTERNA.TE TESTING:

Valves will be exercised during each , refueling outage (RR).

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00ANE ARN0LD ENERGY CENTER Page 56 of 66 TITLE: ' INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-25 SYSTEM:

CONTAINMENT ATMOSPHERE CONTROL COMPONENT:

V-43-214 CATEGORY:

A/C FUNCTIONS:

This valve prevents backflow from the containment into the nitrogen inerting supply line and al;o functions as a primary containment isolation valve.

TEST REQUIREMENT:

Exercise valve every three (3) months (CT-CC).

BASIS FOR RELIEF:

This simple check valve cannot be remotely operated. It is located inside primary containment and is not accessible for testing during reactor operation.

Additionally, the primary containment is inerted with nitrogen during plant operation. De-inerting and then re-inerting the containment atmosphere each cold shutdown solely for the purpose of conducting valve testing would represent an excessivt operational burden. This valve can be exercised closed during leakrate testing performed during refueling outages.

ALTERNATE-TESTING:

This valve will'be exercised during each refueling outage (RR).

FOR INf0RMAll0N ONLY

/

DUANE ARNOLD ENERGY CENTER- Page 57 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST VR-26

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DUANE ARNOLD ENERGY CENTER Page 58 of .66.

TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST VR-27

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DUANE ARNOLD ENERGY CENTER Page 59 of 66 TITLE:

INSERVICE TESTING PROGRAM

? Date 12-23-83 Rev. 5 RELIEF REQUEST VR-28

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DLANE ARNOLD ENERGY CENTER Page 60 of 66

. TITLE: . INSERVICE TESTING PROGRAM n Date 12-23-83.Rev. 5 4

RELIEF REQUEST N0. VR-29 4

ESYSTEMS:

. NUCLEAR BOILER, RESIDUAL HEAT REMOVAL, CORE SPRAY, HIGH PRESSURE COOLANT INJECTION, REACTOR CORE ISOLATION COOLING, RADWASTE SUMP,

: CONDENSATE & DEMINERALIZED WATER COMPONENTS:

CV-2211' M0-1900 V-09-111 n CV-2410- M0-1908

CV-3704 M0-2117.

F-CV-3728 M0-2137-M0-2238 .

M0-2400

  • M0-4423 CATEGORY:

A

-FUNCTIONS:

These valves are subject to 10 CFR 50, Appendix J, Type C leak testing.

7 TEST REQUIREMENT:

I -

Valve seat- leakage tests.shall be made with the pressure differential in the ,

same direction as when the valve is performing its. function. These valves are gate valves and are not exempt from the above requirement (IWV-3423).

, BASIS FOR' RELIEF:

Wedge disk, gate valves have the same sealing characteristics in. either direction. Therefore, testing these valves in the opposite direction to that in which they perform their containment isolation function is equivalent to testing in the accident direction.

f ALTERNATE TESTING:

The piping between the two -isolation valves will be pressurized and the low-pressure side of each valve will be vented. The combined leakage from the two -

containment isolation valves in series will be conservatively attributed to the penetration being tested.

1 9

6 4 ,

r ,- ~. ,--. -e,-,..-.--, . , - - - . . , ..__-,_,__.---.-.-----__.,.,-,,._--.-,--,m.. ....,----..,-a

DUANE ARNOLD ENERGY CENTER Page 61 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-C3 Rev. 5 RELIEF REQUEST NO. VR-30 SYSTEM:

CONTROL R0D DRIVE (CRD) HYDRAULIC

~

COMPONENTS:

-V-17-52 V-17-53 CATEGORY:

A/C FUNCTION:

These valves provide containment isolation tur the control rod drive hydraulic systein.

TEST REQUIREMENT:

Check valves will be exercised from the full-open to the full-closed positions every.three months (CT-CC).

BASIS FOR RELIEF:

These valves are in the CRD return line to the reactor vessel. In accordance

- with NUREG-0619, this system is no longer used. Therefore, these check valves are now passive valves and verifying that they stroke from the open to closed positions'is not necessary.

ALTERNATE TESTING:

The closed position is verified during leaktests performed once each cycle.

DUANE ARNOLD ENERGY CENTER Dage 62 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-31 SYSTEM:

NEUTRON MONITORING COMPONENT:

TIP-CK CATEGORY:

A/C FUNCTION:

This valve provides containment isolation for the nitrogen purge portion of the TIP system.

TEST REQUIREMENT:

Check valves will be exercised from the full-open to the full-closed positions ~

every three months (CT-CC).

BASIS FOR RELIEF:

This valve is a simple check valve and thus the only practical method to verify closure is by performing a leaktest. Conducting such tests every three months is' excessively time-consuming and difficult.

ALTERNATE TESTING:

This valve will be full stroke exercised to the closed position during each refueling outage (RR).

FOR INFORMMION DHl.Y

-r r + w q g gr-- ,

DUANE ARN0LD ENERGY CENTER Page 63 of 66 TITLE: -INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST N0. VR-32 SYSTEM:

CONTAINMENT ATMOSPHERE MONITORING SYSTEM POST ACCIDENT SAMPLING SYSTEM COMPONENTS:

SV-8101A SV-8106A SV-4594A SV-8101B SV-8106B SV-45948 SV-8102A SV-8107A SV-8772A SV-8102B SV-81078 SV-87728 SV-8103A SV-8108A SV-8103B SV-8108B SV-8104A SV-8109A SV-8104B SV-81098 SV-8105A SV-8110A SV-8105B SV-8110B CATEGORY:

A FUNCTION:

These valves provide containment isolation for the containment atmosphere monitoring and post accident sampling systems.

TEST REQUIREMENT:

Exer cise valves in the closed direction every three months (BTC). The stroke time of all power-operated valves shall be measured. (IWV-3413)

BASIS FOR RELIEF:

These valves are not provided with individual position indicators and thus the only reasonable means of verifying the close position is by performing leaktests--tests that are impractical to perform during normal operation.

Also, meaningful stroke time measurements cannot be taken.

' ALTERNATE TESTING:

These valves will be exercised every three months. Verification of the close position will be performed during each reactor refueling. Stroke times will

not be measured.

DUANE ARN0LD ENLRGY CENTER Page 64 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev 5 RELIEF REQUEST NO. VR-33 SYSTEM:

CORE SPRAY.

COMPONENTS:

CV-2118 CV-2138

-CATEGORY:

C FUNCTIONS:

These check valves provide a flowpath for core spray to the reactor vessel and prevent backflow from the reactor vessel to the core spray system.

TEST REQUIREMENT:

Exercise check valves in the open and closed direction every three months (CT-CO, CT-CC).

BASIS FOR RELIEF:

These check valves are normally closed. To open the valves, the core spray pumps are operated at rated flow and disch6rged directly into the reactor vessel. This cannot be done during normal operation as these valves cannot be opened against normal reactor pressure. The air operators on these valves (used for testing only) have proven to be unreliable and a continuing source of nitrogen inleakage in the drywell. Thus, operating nitrogen is normally cut-off to the operator. ' Currently, an engineering evaluation is being conducted to determine if these operators should be replaced or removed.

'In the first case this would allow for testing of these valves during cold shutdown. In the event the operators are removed, these valves can only be tested during refueling.

ALTERNATE TESTING:

These valves will be exercised at each refueling outage by verifying that each division of core spray can deliver rated flow to the reactor vessel.

1

DUANE ARNOLD ENERGY CENTER Page 65 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-34 SYSTEM:

CONTAINMENT ATMOSPHERE DILUTION COMPONENTS:

SV-4331A SV-4333A SV-4331B SV-43338 SV-4332A SV-4334A SV-43328 SV-43348 CATEGORY:

A/B FUNCTIONS:

~

These valves function to provide a flowpath into the containment in the event that containment dilution is required during an accident and serve as containment isolation valves.

TEST REQUIREMENT:

Evaluate stroke times in accordance with IWV-3413 (b).

BASIS FOR RELIEF:

It is impractical to apply the requirements of IWV-3413 (b) to valves with stroke times on the order of 1-2 seconds without installing sophisticated timing devices. Operator reaction times could easily vary by .5 seconds or more ther-ty invalidating the 50% criteria for increasing the surveillance l frequency.

ALTERNATE TESTING:

Stroke times for these valves will be measured; however, the frequency of testing will be increased to once each month if an increase in measured stroke time of 100% or more from the previous test is observed and the stroke time is greater than 2 seconds.

. - = _ . - . . -.

DUANE ARNblD ENERGY CENTER Pag 2 66 of 66 TITLE: INSERVICE TESTING PROGRAM Date 12-23-83 Rev. 5 RELIEF REQUEST NO. VR-35 SYSTEM:

EMERGENCY SERVICE WATER (ESW)

COMPONENTS:

CV-1956 A CV-1956 B

. CATEGORY:

B FUNCTIONS:

These valves open to provide a return path for ESW cooling water from the control building chillers.

TEST REQUIREMENT:

Stroke time shall be measured during exercise testing. (IWV-3413)

BASIS 'FOR RELIEF:

These valves are actuated by the starting logic of the associated emergency service water pump, with no individual control handswitch. Also, there are no position indicators.for these valves. Thus, stroke time measurements are impractical. ,

ALTERNATE TESTING:

These valves will be. exercised every three months. During this testing, valve operation will be observed. Based on visual observation, any erratic operation or excessively long stroke time will be cause for failure.

FOR INFORMATION 0NLY

9 O

O APPENDIX A PUMP TESTING PROGRAM O

A-1

___-------_-- --- -~~

fHSERVICE ILSII M PRIH;RAN 6$16'nl<El HT  !!UI E CH IDWa EI E Clkl0 Lit.Ut

!!I CL ASS 1. 2, 3 AND ffC PilttPS find POWER I'l<Ui.Ritri PRiffM DUANE ARNULD El!E liCf CENTER - - -

. PALE IST PRIN.RAN FLVISIUN 905 12/23/03 E r4SE RVICE ILSI yllANitTIES FUDP PilhP ISI PAID INLET DIF F FLOW BL'AR IESI NtlHirE R NAtiE CLASS P&lb COUR SPEED PRESS ItESS RA1E' VibkA 1EMP INIERVAL f LMAkk!'

.nu m ... ...... ..... ....... .. ....... ....... ....... ....... . - - . ....... ......... . . . . . . . . - .

1 P- 0. ' in RURSW 3 M-146 H-0 NA Y:PR-4 Y f y Y 00 ARIEL 1f a

1PW22H FHRSW 3 M-146 H-81 NA Y:PR-4 Y Y Y Y QUARIERLY 18'-0220 tillRSW 3 H-146 H-U HA Y:PR-4 Y Y f f QUARIEFLY W-9 2.!D RURSW 3 11-146 H-U HA Y:PR-4 Y Y f Y QUARIERL) 1 P-t'4 4 A DF D NC M-132 A-2

  • NA Y:PR-4 f:PR-6 Y:PR-6 N :l le-1 N:PR-l QUARIE RLY NU l f - DO t el'W 449 14 88 NC N-132 n-3 NA Y:PR-4 V:PR-6 1:PR-6 N:PR-1 N:PR-1 QUARIERLY NOIE-Out I P- t*Y Yn ESW 3 #1-146 H-/ NA V:PR-4 y f f N:fk-2 QUARILFLT
  • rWuvH ESW 3 H-846 H-6 NA Y:PR-4 Y Y Y N:PR-2 QUARIERLY ll*-112A SCliE EN NC h-129 I-7 NA Y PR-9 ) PR-9 Y PR-9 Y PR-V Y (*R-9 QUAk1ERLY er-e63H SCbtLN NC N-129 C-5 NA Y PR-9 Y PR-9 Y PR-9 Y PR-9 Y PR-9 QUARIERLY ll-Il7A kW NC H-12V P-7 NA Y;PR-4 Y:PR-S V:PR-5 Y f QllAR1 eft Y s t -i t /** RW HC H-129 .0-4 r4A Y:PR-4 Y:PR-3 Y:PR-5 Y Y QllAR IE RL)

IP-I l /C RW NC N-129 la-6 NA Y :l'R-4 Y:PR-5 Y:PR-5 Y Y QUARillel Y W st/0 liW NC h-129 0-s #4A V:PR-4 f : P R '> + V:PR *i V Y yllAR I E RI.Y IP-26tn CS 2 tt-124 0 .1 NA y Y:PR-S Y:fR-S 1 Y QUARILFl.f e r ' t 4 << CF 2 N-128  :-4 HA T V : Pk *J f : PR *) y t QllAR IE RL) i t' ;*16 11P01 2 M - 12.4 l' .* i Y V.PP-S 1.it-S ti . I't.: .i N :I*-3 4tlAkit.Fl y al' 6 RC II: 2 H 6 25 D-4 1 y 1 :lt-5 Y . i t 'i fi - l * - 5 N:PR-3 uuARit til Y ll'- 2 ?/A lilfli 2 h-120 D 14 NA I V :lt-S V:lt-5 ) Y QilAR li bt f

.-- ------- ..----- ---.. . . . - , - ~ . . - - - - - - - - - - . . . . . . - - . - - - - . - - - - . . . - - - - - - - - - - - - - - - - - - - - - . . - - . . . - - - - - -

n _ _ _ _ . _ _ . -

l'AE PnkEb H( (HSL RVIt'E IEFIING PRHl.RAtt NellE CH IFOGRah PRISIM IDWA ELE C1RIC LII.HI ISI CLAIS 1. 2, .I AND NC PHMPS AND POWER bt)ANE AkNOLD ENEkGy CEN1Ek

____ ___- _____- = _ - -

PALE 2 ISI PROI.RAN REVISION 005 12/2.5/8.I INIFHVICE IEST GUANTIIIES sunP PunP ISI PAID Ntitil'E R INLET DIFF FLDW BEAR TESI NAhE CLASI l'A I D 000k XFEED PREII IFESS san.===..

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fMSERVICE TESTING'PROGRAN FREPARED BY ; NUTECH IOWA ELECIRIC LIGHT ISI CLASK 1, 2, 3 AND NC VALVES AND POWER PROGRAN PRISIN DUANE ARNOLD ENERGY CENTER . - = - = - - - - - - . . . .

PAGE .3 ~

IIT PROGRAN REVISION 005 , 12/23/S3

= ___

PUMP IST PROGRAM REMARKS NOTE 001: Although the diesel fuel oil transfer pumps (IP-44A & B) are included in the program, they do not strictly fall within the jurisdiction of the ASME B & PV Code,Section XI. (Reference ASME res WPPSS inquiry, File no. BC 77-666/NI 77-371 dated 1/8/79)ponse See Relief- to Request No. PR-10 for further discussion of this issue.

W i

i APPENDIX 8 VALVE TESTING PROGRAM i

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M= -

- - . E = .- - -

_ - - R= - .

- - = - . - .

- - I = - - - - - -

- - FS= - - _ - .

8 - - LE= - - -

1

- - l U= - . -

- l

- lQ= - -

- 0 -

- 1 - - EE= - -

- - RR= - - -

- 1R - - - - -

CE - - .

.. E W - - = - _ -

- RO - - = -

- IP 3- = -

- C 8 ME= - -

ED L N

/

3 UG=

MA= -'-

- EA - 2 IK= -

- - / XA= -

- A - 32 AE= -

- W -

31 ML = -

- O =