ML20082H175

Rev 1 to Arkansas Nuclear One Unit 2 ASME Section XI Pump & Valve Test Program Second 10-Yr Program Submittal

ML20082H175
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/31/1991
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20082G587	List: 2CAN089103, Forwards Response to NRC Comments Re 900112 Submittal of Second 10-yr Inservice Testing (IST) Program for Facility & Summary of Changes to Second 10-yr IST Program.Change PC-2 to Rev 27 to HPSI Test Procedure Also Encl ML20082G753 ML20082H175
References
PROC-910831, NUDOCS 9108230216
Download: ML20082H175 (86)

Text

. . . _ _ _ . _ _ . - _ . _ - _ - _ _ - - _ - _ _ _ _ _ - _ _ _ _ . -- - _. __ . _ _ _ _ _ -

AltKANSAS NUCIEAll ONIC 1 UNIT 2 ASSIE SECTION XI l'US11' AND VAINE TEST l'ItOGilAh!

SECOND 10-YEAlt-l>llOGilAhl SUllhllTTAL llEVISION 1 AUGUST,1991 TiR""R88s n 888ho P PDR _

Roy. 1 TABLE OF CQMIENIS Page No.

4 SECTION

1.0 INTRODUCTION

I.1 Relationship with Technical Specifications 2 1.2 Qualification of Test Personnel 2 1.3 ASME Code Relationship with Generic Letter 89-04 2 SECTION 2.0 PUMP INSERVICE TEST PROGRAM 2.1 Pump Bearing Temperature /

Vibration Measurement 3 2.2 Multiple Reference Values 4:

4 SECTION 3.0 VALVE INSERVICE TESTING PROGRAM 3.1 Category A Volves 5 3.2 Pressure Isolation Valves 5 3.3 Thermal Relief Valves 6 3.4 Cold Shutdown Testing 6 3.5 Part-Stroke Testing 7 3.6 Fail-Safe Actuators 8 3.7 Valve Position Indication Verification 8 3.8 Passive Valves 8 3.9 Stroke Times 8 3.10 Relief Valve Testing 9-3.11 Non-Code Component Testing 9 REFERENCES '10 t

APPENDIX A- Drawings Used in Preparation of Program- 111-APPENDIX B Pump Test Program and Pump Relief Requests 14 l

APPENDIX C Explanation of Valve Test Program Symbols- 24.

APPENDIX 0-_ Valve-Inservice Test Program 29 APPENDIX E Valve Relief Requests 69 l

APPENDIX F Cold Shutdown Testing-Justifications- -81 l

l

PAGE 1

Rey, 1 SECTION

1.0 INTRODUCTION

Under the provisions of 10CfR50.55a, inservice testing of safety-related pumps and valves will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code to the extent practical. As specified in 10CfR50.55a(b), the offective edition of Section XI with regard to this program is the 1986 Edition. This program identifies the pump and valve inservice testing that will be performed at ANO-2 to comply with - the requirements of 10CFR50.55a. This program applies to the Second Ten Year Inservice inspection Interval beginning March 26, 1990, and ending March 25, 2000.

1.1 R_elationshio with Technical Soecifuations Based on Technical Specification requirements, in - the event of any conflicts between ASME Section XI reqeirements and the reqJirements of Technical Specifications, the plant Technical Specifications _shall ge .

ANO-2 will meet all requirements of both : ASME Section XI and plant Technical Specifications unless there is a specific conflict between the two. -

If any requirements of ASME Section XI cannot be met due to lechnical Specifications, guidance will be identified in appropriate Relief Requests.

1.2 Qualification of Test. Personnti Personnel performicg pump and valve testing per ASME Section XI Subsections IWp and IWV will be qualified in accordance with the ANO-2 Quality Assurance Program. This is in keeping with the requirements of ASME Section XI, as clarified by ASME Code Interpretation XI-1-82-06R, 1.3 ASME Code Relationshjo with Generic Letter 89-04 Paragraph 50.55s(g) of 10 CFR Part 50,." Domestic Licensing of Production and Utilization Faci.ities," requires that certain ASME Code Class 1, 2, and 3 pumps and valves be designed to enable inservice testing and that testing be performed to assess operational readiness in accordance with the Section XI-requirements of- the ASME Boiler and Pressure = Vessel Code. The inservice testing of ASME Code Class 1, 2, and 3 pumps and valves;should be viewed as one part of a broad effort to ensure operational readiness of equipment rather than viewed in the narrow sense as compliance with 10 CFR 50.55a(g). The intent of the testing is to-detect degradation affecting operation and assess whether adequate margins are_ maintained. 'While ..GL-89-04 has been written toi provide guidance relative to meeting-the requirements of 10 CFR 50.55a(g), it is only one'part of other ongoing industry and regulatory-activities.-_Recent efforts have been undertaken by the nuclear _ industry and = NRC.. sponsored

.research to provide information and techniques for' enhanced : assurance of equipment operability. ANO-2 may incorporate the results of - this research,-

supported by appropriate relief request, as final input to the IST program.

4 PAGE 2

Rev. I 2.0 PUMP INSERVICE TESTING PROGRAM 1he pump test program shall be conducted in accordance with Subsection IWP of Section XI of the 1986 Edition of the ASME Boiler and Pressure Vessel Code, except for relief requested under the provisions of 10CFR50.55a(g) (5)

(iii). Appendix B details the inservice testing program for all safety related pumps at ANO 2. These tables list each pump required to be tested in accordance with IWP-1100 of Section XI of the Code. Each parameter to be measured, as well as specific relief requests concerning non-conformance, are also listed.

2.1 l' ump _Bearina Temocrature/ Vibration Measurement Subsection IWp-3300 requires pump bearing temperatures be measured at least once each year. Industry experience demonstrates that bearing temperatures typically rise only minutes prior to failure. Any bearing failure predicted by a yearly recording of bearirg temperature would be a random event and thus, yearly measurement of- bearing temperatures does- not increat the level of confidence in component reliability. The expense of adding J additiona? testing both in component degradation and man-hours expended is, therefore, not justif ed.

Further, IWP 3500(b) specifies that pumps be run until bearing temperatures stabillze as determined by three measurements-- at 10 minute intervals. Clearly the. pump would have to be run in excess of one-half hour to obtain these readings. The pump degradation caused by this requirement does not justify the very limited assurance it might provide. In-addition, the ASME-approved OM-6 standard on pump inservice testing does not require bearing temperatures to be taken. This request for relief should apply for all bearings presently required to be temperature tested.

Quarterly vibration measurements will provide meaningful- indication of bearing reliability. Vibration data taken on at least a quarterly basis will be utilized to define pump mechanical condition. In addition, a frequency spectrum analyzer will be used when appropriate to more fully define bearing condition.

Due to improvements in vibration measurement and analysis -since Section XI was developed, ANO has utilized measurement of vibration . velocity to more fully define bearing mechanical condition,. In keeping with the interim approval gained in _the previous revision to the test program, as well ias the approved OH-6 inservice testing standard for pumps,- ANO will utilize measurement of vibration velocity for all _ bearings presently requiring vibration measurement per _0M-6. ' The acceptance criteria for_ this - parameter-will be in accordance with guidance provided in OM-6.

-pAGE 3.

Rov. 1 2.2 billiple Reference Vglygg Based on plant operating conditions and the pump testing hydraulic circuit, ANO-2 may choose to generate multiple sets of reference values (per IWP 3112) in order to more fully describe pump hydraulic condition. Each set of pump reference values will meet all appropriate requirements of IWP-3000.

i f

I l

l l

PAGE 4

Rev. 1 3.0 VALVE INSERVICE TESTING PROGRAM The valve test program for AND 2 shall be conducted in accordance with Subsection IWV of Section XI of the 1986 Edition of the ASME Boiler and pressure Vessel Code, except for relief requested under the provisions of 10CfR50.55a(g) (L)(iii). The valve test program is included as Appendix D.

The codes and symbols used to abbreviate the tables in Appendix 0 are explained in Appendix C.

3.1 {ttsgory A Valyn Valves for which seat leakage is important may generally be classified as pressure isolation valves (plV), containment isolation valves (CIV), or both pressure and containment isolation valves. Containment isolation valves falling within the scope of ASME Section XI are tested in accordance with the Section XI requirements of IWV-3400, Category A, with the exception of the seat leakage tests (lWV 3420). The seat leakage testing performed on these valves meets the intent of Section XI, but the actual test procedures shall be conducted in accordance with the 10CfR50, Appendix J, Type C, CIV test program. For valves performing a containment isolation function, individual valve leak rates are not in themselves significant. The only pertinent leak rate criteria for CIVs is that the total leak rate for all penetrations and valves be less than 0.60 LA. ANO-2 was designed to perform the Appendix J.

Type C tests, not the individual Category A leak test (i.e., some penetration test connections test more than one valve at a time). Accordingly, all CIV seat leakage testing shall be perf ormed in accordance with the requirements of 10CfR50, Appendix J Type C, in lieu of the Category A requirements of Section XI. The requirements of Section XI IWV-3426 and IWV-3427(a) will be maintained for all CIVs. See Generic Relief Request GR-2 in Appendix E.

All CIVs have been categorized as A-Active or A-passive, and will, as a minimum, be leak tested per 10CFR50 Appendix J. passive valves will in general have no other testing performed.

3.2 Er. enure .lsolation Valyn The purpose of the plant pressure Isolation Valves (PlV's) is to reduce the possibility of an inter-system LOCA which would pressurize ice presrure systems to pressures exceeding their design limits. Such valves will be fully tested per IWV-3420, with the exception of relief requested under GR-2 (see Appendix E).

Several safety systems connected to the reactor coolant system have design pressures less than the reactor coolant system operating pressure.

Redundant isolation valves within the Class 1 boundary forming the interface between these high and low pressure systems protect the low pressure systems from exceeding their design limits. The redundant isolation provided by these valves assures that_ system integrity will be maintained in the event of a single valve failure. The following is a listing of valves that perform a safety-related pressure isolation function:

PAGE 5

Rev. I hlygj k Valve Desionation 2CV-5084-1 Low pressure safety injection loop suction 2CV-5086-2 Low pressure safety injection loop suction 251-13A High pressure injection check valve 251-130 High pressure injection check valve 251-13C High pressure injection check valve 251-130 High pressure injection check valve 251-14A low pressure injection check valve 251-140 Low pressure injection check valve 251-14C Low pressure injection check valve 251-140 Low pressure injection check valve 2SI-15A Safety injection combined discharge check valve 251-150 Safety injection combined discharge check valve 251-150 Safety injection combined dischar0> check valve 251-150 Safety injection combined discharga check valve 2SI-16A Safety injection tank outlet check valve 251-160 Safety injection tank outlet check valve 251 160 Safety injection tank outlet check valve 251-160 Safety injection tank outlet check valve 2SI-27A High pressure injection check valve-251-270 High pressure injection check valve 2SI-28A High pressure injection check valve 251 280 High pressure injection check valve for the loop inlet check valves, there is a pressure indicator that alarms on high pressure between adjacent loop inlet and safety injection tank outlet valves displayed in the control room. Using this indication, it is possible to determine the pressure -between the valves. Should the reactor coolant loop inlet check valves fail, the pressure increase would be noted in the control room. The operators will take appropriate measures following the recelot of an alarm.

3.3 1hermal Relief Valves Many safety related systems. - particularly those with heat. exchangers, have been provided with relief valves. These relief valves are thermal relief-valves '(TRV) of small- capacity intended to reli6ve pressure due to' theraal expansion of fluid in a " bottled-up" condition, which is considered. a self-limiting transient. Experience has shown that failure of these: valves will not result in failure of a system to fulfill-its safety related function.

Thus, thermal relief valves are not considered to perform a function important-to safety and such valves have not been included in the program.

3.4 Cold Shutdown Testing Where the test frequency in_ Appendices C and D is specified as: " Cold:

Shutdown" the following definition for cold shutdown testing applies:-

For unplanned or forced outages, testing will commence not- later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after Cold Shutdown is achieved.- Completion of.all-valve testing ;is not a prerequisite to- subsequent startup. Any PAGE 6.

Rev. 1 testing not completed at one Cold Shutdown will be performed during subsequent Cold Shutdowns (excluding refuelings) to meet as close as practical the specified Section XI testing frequency. For planned outages, including refueling, where all required testing can be completed, exception to the above start time may be taken.

However, during these planned outages all testing must be completed consistent with Section XI requirements prior to heatup.

Appendix F specifically identifies those valves tested during Cold Shutdowns, with operational justifications for each. Valves tested on a Cold

$hutdown frequency may be tested during outage recovery, plant heatup etc.

3.5 Enl:. Stroke Testina The goal of the ANO-2 Inservice Test Program is to perform full-stroke tests of all appropriat9 valves. With the exception of those valves for-which specific relief has been requeu ad all valves will be full stroke tested.

part-stroke testing of power-operated valves is of ten not possible, due-to valve logic circuitry which only allows full-open or fall-closed- valve movement. Moreover, the intent of Section XI is to assess valve operability through inservice testing; while a part-stroke exercise does provide some measure of confidence in valve operability, it does not provide assurance of valve safety-related function.- In addition, a part-stroke of a power-operated valve has the possibility, through human or mechanical error, to cause adverse plant consequences (isolation of cooling water, plant transients, etc.).

Based on the above, ANO-2 will full-stroke _ test power-operated valves in accordance with the Valve Test program (with associated relief requests as appropriate). $pecific part-stroking of power-operated valves to meet Section XI will not be performed. However, some valves used in specific plant evolutions may undergo par t-stroking to meet Manufacturers recommendations or-specific maintenance requirements. An example _of valves in this category would be the Main Steam isolation Valves which are designed to.be part-stroked monthly to comply with Technical Specifications. The cold shutdown justifications provided in Appendix F also include. a ' basis for not part-stroking -spect fic valves.

Check valves .whose safety function is to open will' be full-stroked exercised. Since disk position is' not always observable, the NRC staff has stated that " verification of the plant's safety analysis' flow rate through the check valve would: be an- adequate demonstration of full-stroke . requirement.

Any flow rate less' than design- will be considered part-stroke exercising unless it can be-shown that the check valve's disk position at the lower flow rate would be equivalent lto the position of the disk at the design flow. rate-through the valve." Based on this-position, check valves-within the-scope of this test program will be at least part-stroko enercised whenever any flow is passed - through the valve. Check - valves are considered to be full-stroke tested on at least the Code-required frequency, > unless identified by Relief.

Request.. It inay be possible -to . qualify other techniques to confirm that the valve :is - exercised to the position required to ' perform its safety. function.

Valve- disassembly and - inspection-.can. be. used' as a~ positive means ofu detemining that a valve's disk will' full-stroke exorciseiopen or will close under reverse pressure. . Check valves for'which a full-stroke exercise cannot

~PAGE 7

-t

Rev. 1 be confirmed, therefore, will be identified by an appropriate relief request.

ANO-2 feels that this position meets the intent of IWV-3522(b) and Generic L*tter 89-04 regarding exercising of check valves.

6 3.6 Fail-Safg_Attuators All those valves which have a fail-safe actuator are exercised normally using that actuator. Thus, the fail-safe actuator is regularly tested when the valve is tested.

3.7 Valve Position Indication Verification Verification of valve position indicator accuracy will be performed in accordance with Section XI IWV-3300 with the exception of those valves for which specific relief has been requested.

3.8 Passive Va'yn Valves whit? ere in safety-related systems that are not required to change position and to not receive an isolation or actuation signal in order to perform their safety-related function are classified as passive valves.

ANO-2 has also categorized valves which are administratively locked-open or locked-closed in their safety-related position as passive valves. The position of these valves will be verified and controlled by AND operations procedures and plant , administrative control. Due to the lack of operability testing requirements, these valves have been excluded from Appendix 0, 3.9 Stroke Times The valve stroke times identified in Appendix D are nominal values only and may thange due to modification, maintenance, etc. over plant lifetime.

AN0-2 will change these stroke times as necessary, incorporating the requirements of ASME Section XI, without further notification.

Valves with extremely short stroke times (less than 2 seconds) have stroke times of such short duration 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 small increase in stroke time will result in an extremely large percentage change. Verification that valves meet a specified maximum stroke time of short duration provides adequate assurance of operability. Therefore, ANO-2 will verify that only the maximum stroke time is not exceeded for these valves with nominal stroke times less than 2 seconds, as noted in the " Stroke Time" column of Appendix D. The trending requirements of 1WV-3417(a) will not apply. This is also in keeping with the ASME-approved OM-10 standard for valve inservice testing. See also relief requested under GR-4.

ANO-2 also feels that comparison of valve stroke times to the previous test results, without any evaluation of overall change in stroke time from PAGE 8

Rev. 1 initial tes data, is not the optimum method of gauging valve performance.

Therefore, Ar40-2 will, as an alternative, evaluate current valvi stroke time data with a reference valve stroke time taken when the valve is known to be in good condition. This philosophy is in keeping with the intent of both pump testing under ASME Section XI and the current methods identified in the ASME-approved OM-10 inservice testing standard and NRC Generic Letter 89-04 for valves.

Valve stroke times will be compared to reference values derived from initial testing and testing following maintenance pursuant to IWV-3200 using the average of three stroke times. If the reference value is less than 10 seconds, the reference value is multiplied by 1.5 for a limiting value for operability. If the valve stroke time fails this limit, it is inoperable. If the valve stroke time is greater than 10 seconds, it is multiplied by 1.25 for the normal limit and 1.5 for the operability limit. If the valve fails the normal limit, the test f requency is int.reased from quarterly to monthly.

3.10 Relief Valve Testina ANC-2 will perform all Relief Valve Testing using app *oved procedures to ,

meet the requirements of ANSI /ASME OM-1-1981. This level of administrative control, including the requirements for Quality Assurance / Control per 10CFR50 Appendir B, ensures the overall test quaiity is maintained. Therefort, ANO-2 feels that the intent of OM-1 for relief valve testing regarding test personnel qualifications and test group makeup are met.

3.11 Han-Code Component Testina ANO-2 includes several non-code components in the IST Program. All applicable code testing is applied to these components where possible. Where deviations occur, the deviations are not documented as relief sequests.

Instead, deviations for non-code components are documented by internal correspondence. The non-code testing is accomplished in many cases by the same implementing procedures that accomplish code testing.

(

PAGE 9 )

1

Rev. 1 REFERENCES

. 10CFR50.55a(g); Inservice Inspection

. 1986 Edition ASME Boiler and Pressure Vessel Code - Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components

. AND-2; Piping and Instrument Diagrams (See Appendix A)

. AND-2; Technical Specifications

. Regulatory Guide 1.26 ANSI /ASME OM Standards OM-1 Relief Valve Inservice Testing OM-6 Pump Inservice Testing OM-10 Valve Inservice Testing

. ANO-2 Safety Analysis Report Section 6, Engineered Safety Features Section 6.24, Containment Isolation Systems Section 9, Auxiliary Systems Section 15, Accident Analysis e NRC Generic Letter No. 89-04, " Guidance on Developing Acceptable Inservice Testing programs" PAGE 10

Rev. 1 i

APPENDIX A DRAWINGS USED IN PREPARATION OF ASME SECTION XI TEST PROGRAM PAGE 11 i

Rev. 1 DRAWINGS USED IN PREPARATION OF ASME SECTION XI TEST PROGRAM Dn dna_flh Iltle M-2202, SH. 4 Lube Oil, Lube Oil ecoling. Electro / Hydraulic Controls and Main Steam l

M-2204, SH. 4 Emergency feedwater M-2206, SH. 1 Steam Generator Secondary M-2206, SH 2 Steam Generator Secondary M-2210, 511. 1 Service Water M-2210, SH. 2 Service Water M-2210, Sil. 3 Service Water M-2213, SH 1 Liquid Radioactive Waste M-2213, SH 10 Liquid Radwaste Containment Building M-2214, SH. 1 Boron Management M-2215 Gaseous Radioactive Waste M-2217, SH. 1 Emergency Olesel Generator Fuel Oil M-2217, SH. 2 Emergency Olesel Generator Starting Air-1 M-2218, SH. 1 Service Air M-2218, SH. 2 Instrument Air M-2218, SH. 5 Breathing Air M-2219, SH. 2 Fire Water-M-2220, SH. 1 Plant Heating M-2222, SH. 1 Chilled Water - Containment, Turbine and Auxiliary Buildings M-2230, SH. 1 -Reactor Coolant M-2230, SH. 2 Reactor Coolant M-2231, SH. 1 Chemical,and Volume Control M-2231, SH. 2 Chemical and Volume Control PAGE 12

Rev. 1 DRAWINGS USED IN PREPARATION OF ASME SECTION XI TEST PROGRAM Drawino X L lills M-2232 Safety Injection M-2234, SH 1 Component Cooling Water M-2235 Fuel Pool System M-2236, SH. 1 Containment Spray M-2236, SH. 2 Containment Spray M-2237, SH. 1 Sampling M-2239, SH. 1 Nitrogen Addition M-2261, SH. 1 Air Flow and Control PAGE 13

Rev. 1 APPENDIX 11 ASME SECTION XI PUMP TEST PROGRAM AND PUMP RELIEF REQUESTS

/

+

g

.PAGE 14-

Rcmision 1  ;

ASME SECTION XI PUMP TEST REQUIREMENTS i Parameter to be Measured ASME Delta Inlet Lubricant Bearing  ;

Puen No. Pumo Name Class 1 Speed Press. Press. Vibration Flow Level / Press. Temo. Remarks

. :2P4A- Service Water 3 N/A X X PR-5 X PR-2 PR-1

c. .

2P48 Service Water 3 N/A X X PR-5 X PR-2 PR-1

, :2P4C. Service Water 3 N/A X: X .PR-5 X .PR-2 PR-1 l

-.2P7A Emergency Feedwater 3 X X X PR-5 X X PR-1

2P78 Emergency Feedwater. 3 N/A X X PR-5 X X PR-1  !

-2P16A- Emergency Diesel' Fuel. NN f:*/A X' X PR-5 X X PR-1 .

! Transfer.  !

i

'2P168. Emargency Diesel Fuel ! .NN N/A- X- l X PR-5. X X PR-l'  ;

j. - -Transfer -  !

1- ,

2P35A 4 Containment' Spray 2 N/A' X- X PR-5 X. X PR-1

.. 2P35B( Containment Spray 1 2.. N/A X X PR-5 X X PR-1  ;

i-  !

2P36A. Charging 2 N/A .X- X- PR-5 PR-4 X PR-1 i

'2P368 Charging- 2 N/A X X PR-5 PR-4 X PR 1

, i L-2P36C . Charging ~2' :N/A '

'X' X PR PR-4 X .PR-1 i i

2P39A 7 Boric Acid. Makeup 21 N/A- X X 'PR-5 X X _ PR-1

.L2P39B- Boric Acid Makeup 2 .. N/A .X X. PR-5 X X PR-1 I

a l

i  !

PAGE 15  ;

i  :

f I

Revision 1 ASME SECTION XI PUMD TEST REQUIREMENTS Parameter to be Measured ASME Delta Inlet Lubricant Bearing LP =a No. Pumo Name Classi Speed Press. Press. Vibration Eln level / Press. Temo. Remarks

'2P60A- Low Pressure Safety 2 N/A X X PR-5 X X PR-1 Injection

.2P608- Low Pressure' Safety ' 2. - N/A X X PR-5 X X PR-1

Injection 2P89A; _High' Pressure Safety.

2 N/A PR-3 X PR-5 X X PR-1

' Injection ~-

2P898. High. Pressure Safety 2 N/A PR-3' X. PR-5 X X PR-1 Injection High' Pressure

Safety

'2P89C- 2 N/A PR-3 X PR-5. X X PR-1 Injection .

2P136At . NaOH Addition: 2 N/A' :X X- PR-5 X- X PR-1 2P136B NaOH' Addition. 2 N/A. X X PR-5 X X PR-1 NOTES:

1. ,NN - Symbol for.a non-ASME Code' Class component (other than Class 1,.2 or 3).

PAGE 16

- .- -. . . - . . . . ~ . . - - - - -.--. - .. - .- .- .. -- . . - --

Rev. 1 RELIEF REQUEST NUMBER PR-1 System: As applicable P&lD: As applicable Pumps: All pumps in program Class: 2, 3 and NN Function: As applicable Impractical Test Requirements:

IWp-4310; Temperature of all centrifugal pump _ bearings .outside the main flowpath and of the main shaf t bearing of reciprocating pumps shall be measured at points selected to be. responsive- to changes in the temperature of the bearing. Lubricant temperature, when measured af ter passing through the bearing, and prior to entering- a cooler. - shall be considered the bearing temperature.

Basis for Relief:

(a) Some of the _ pumps addressed in this relief request are coo' led :by their respective process - fluid, in. the main flow path. Thus, bearing temperature measurements would be . highly. dependent on the temperature of the cooling medium (see (c) below).

(b) Pump bearing temperature -is _taken at_ one-year intervals only,: which provides very- -little data = toward determining. the !ncremental.

degradation- of a_ bearing, nor does it provide any meaningful trend data.

~

Industry- experience demonstrates 'that_ bearing temperatures typically rise only minutes prior to failure.. Any bearing failure predicted by a' yearly. recording of- bearing : temperature -would- be a random event? and- thus, yearly me'asurement .of bearingf temperatures does not increase the level of confidence in ~ component reliability.

The expense of adding the additiona_l' testbg both in ' component -

degradation and man-hours expended is, _ therefore, not. justified.-

(c)' Except for the Service Water Pumps (2P4A,'2P48,c2P4C),.alliof which are submerged --under Lwater, all-' pumps addressed in!. this -relief request will be subject to . vibration ' measurements per subsection OM- 6. - Vibration measurements . (displacement and ivelocity) - are a:

significantly more reliable . indications of _ pump- bearing degradation::

than are' temperature measurements. . Vibration data taken on'at_least a quarterly --- basis will be utilized to1 define pump mechanical-condition.-

i l

[-

PAGE17f 'N j

Rev. 1 RELIEF REQUEST NUMBER PR-1 (Cont'd)

Alternative 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. Vibration measurements using velocity as a measured value shall be taken on each pump in lieu of bearing temperature measurements.

PAGE 18

Rev. 1 RELIEF REQUEST " UMBER PR-2 System: Service Water P&ID: M-2210, Sh. 1 Pumps: 2P4A, 2P48, 2P4C Class: 3 Function: Service Water pumps provide the cooling water to support the safety-related shutdown systems.

Impractical Test Requirements:

IWP-3100; Observe lubricant level or pressure.

Basis for Relief:

The Service Water pumps are vertical shaft pumps with no external lubricant indication. All of the pump bearings with the exception of the suction bowl bearings are lubricated by the fluid pumped (water). The suction bowl bearing is grease packed. Hence, due to the inaccessability and design of these bearings, it is impossible to observe lubricant level or pressure.

Alternative Testing:

Pump bearing lubrication is assured by quarterly flow testing the service water pumps. Also, three orthogonal velocity readings are taken on the-motor inboard and outboard bearings. These vibration readings should detect pump bearing degradation.

PAGE 19

Rev. 1 RELIEF REQUEST NUMBER PR-3 System: High Pressure Safety Injection i P&lD: M-2232 Pumps: 2P89A, 2P898, and 2P89C d Class: 2 /

Function: To provide borated water to the reactor during a loss of coolant accident.

Impractical Test Requirements:

IWP-4230; pressure taps shall be in a section of the flow path.

Basis for Relief:

-The discharge pressure gauges available .for use in testing The. high '

pressure safety injection pumps are downstream'of the pump disenatge atop- -

check valves. .The test flow path, through .the mini-recirc li,wi, does not pass through these-discharge stop-check valves. 1Therefore, the gauge.

used for measuring pump discharge pressure is not in the test flow path but is pressurized by' pump discharge pressure through_ the normally-open pump discharge stop-check valves. This arrangement meets the intent of IWP-4230.

Alternati~e Testing:

2 As stated in the Basis for Relief, the alternative testing involves the use of a discharge pressure- gauage' not in the test flow path. The proposed testing arrangement although appearing not to meet the letter of the code, does - meet the - intent of the E code - in - the acquisition of accurate, repeatable data--for use in. assessing pump performance.- .

NOTE: In order to alleviate concerns aat the initial pressure. wave:

created when the pump-is started might cause a press'ure higher than-steady state _ discharge pressure to be trapped downstream of the.-pump-

-discharge stop-check valve,; downstream valves are cycled after pump-start per the test procedure to relieve.that condition.

-l PAGE-20

_j

Rev. 1 RELIEF REQUEST NUMBER PR-4 System: Chemical and Volume Centrol P&lD: M-2231, Sh. 1 Pumps: 2P36A, 2P36B, 2p36C Class: 2 Function: Deliver normal makeup to the Reactor Coolant System (RCS) and provide emergency boration upon safety injection actuation.

Impractical Test Requirements:

IWP-4120; Full-scale range of each instrument shall be three times the reference value or less.

Basis for Relief:

The normal charging pump flow for a single pump is 44 gpm. The flow instrumentation for the charging pumps is in an injection header that all three pumps tie into. The range for this instrumentation is 0-150 gpm.

The full-range for this instrumentation is slightly more than the three times reference value.

In an emergency boration condition, all three pumps would be operating concurrently, injecting 132 gpm through this common header. Thus, the flow instrumentation is sized correctly for the intended safety function of the charging pumps. The installed instrumentation provides accurate, repeatable data and has detected pump degradation. To install flow instrumentation in each charging pump header would constitute a backfit.

Altcrnative Testing:

None.

PAGE 21

Rev. 1 RELIEF REQUEST NUMBER PR-5 System: As applicable P&lD: As applicable Pumps: All pumps in program Class: 2, 3 and NN Function: As applicable.

Impractical Test Requirements:

IWP-4500; Vibration amplitude -

At least one displacement vibration amplitude shall be read during each in-service test.

Basis for Relief:

Due to improvements in vibration measurement and analysis since Section XI was developed, ANO has utilized measurement of vibration velocity to more fully define the pump mechanical condition. In keeping with the interim approval gained in the previous revision to the test program, as well as the ASME approved OM-6 inservice testing standard for pumps, ANO will utilize measurement of vibration velocity for all bearings presently requiring vibration measurement per Section XI. The acceptance criteria for this parameter will be in accordance with guidance provided in OH-6.

Alternative Testing:

The vibration measurements shall be taken in accordance with OM-6 utilizing velocity in lieu of displacement.

PAGE-22

Rev. I f

APPENDIX C EXPLANATION OF CODES AND SYMllOLS USED IN Tile ARKANSAS NUCLEAR ONE. UNIT II VALVE INSERVICE TESTING PROGRAM e

\

b PAGE'23-p g, ' - + ' 4 , W e

Rev. 1 TABLE C-1 SYMBOLS USED TO DESIGNATE VALVE TYPE lypAql Meanina CK Check Valve BF Butterfly Valve G Gate Valve GL Globe Valve RV Pressure Relief Valve SC Stop Check BA Ball Valve DIA Diaphragm SG Sluice Gate TABLE C-2 SYMBOLS USED TO DESIGNATE VALVE ACTUATOR TYPE Symbol Meanina M Motor A0 Air Operated S Solenoid H Hand (manual)

SA Self_ Actuating PAGE 24

Rev. 1 TABLE C-3 SYMBOLS USED TO DESIGNATE VALVE POSITION lymbols Meanina 0 Open C Closed NOTE: AN0 may revise, without notice, the identified positions listed in

" Normal Position" and " Safety Position" based on changes in valve function / system configuration. In the event changes in valve position change the designation of valves from "Parsive" to

" Active", ANO Unit II will make appropriate changes to test commitments and submit those changes as necessary.

4 PAGE 25

.. _i___--__--------------_----

Rev. I 1ABLE C-4 SYMBOLS USED TO DESIGNATE TESTING REQUIREMENT lymb21 tituting FE Stroke Test (with time measurement, as appropriate) per IWV-3400, on a quarterly frequency; or stroke test of check valves per IWV-3520 FC Stroke Test per IWV-3400, on a Cold Shutdown frequency supported by Justification FR Stroke Test per IWV-3400, on a Refueling frequency supported by Relief Request FS Fail Safe Test (see Section 3,6)

PI Position Indicator Test (see Section 3.7)

LJ Leak Test per 10CFR50, App. J.

LK Leak Test per IWV-3420 SP Set Point Test per IWV-3510 01 Disassembly and Inspect RR See Relief Request for testing details PAGE 26

Rev. 1 TABLE C45 SYMBOLS USED TO DESIGNATE SECTION XI VALVE CATEGORY heb91 litanina A Valves' with specified maximum leakage rate (pressure isolation valves and containment isolation valves).

B Valves with no specified maximum leakage rate.

C Self-actuating (check, relief valves) 0 Actuated by energy source capable of only one operation.

TABLE C-6 SYMBOLS USED TO DESIGNATE ACTIVE AND PASSIVE VALVES Symbol Meanina 1 Active - valves which are required to change position to accomplish a safety-related function.

2 Passive -

valves which are not required to change position to accomplish a safety-related function.

TABLE C-7 SYMBOLS USED TO DESIGNATE SYSTEM CODE CLASSES Symbols Meanina NN A- non-ASME Code Class component (other than Class I, 2 or3).

l PAGE 27-l

Rev. 1 APPENDIX D-ARKANSAS NUCLEAR ONE UNIT 11 VALVE INSERVICE TEST PROGRAM E

PAGE 28 1: _. _ -

i

Recision 1 SYSTEM: Main' Steam P&ID NO.: M-2202, SH. 4 ASME P&ID- Sec. XI Size Valve Act Strcke Normal Safety Required Relief Tests -

Valve No. Class Coord. Cateaory (In.) Type Tvoe Time Position Position Tests Recuest No. Performed 2CV-0340-2 3' B-4 B-1 4 G M 42 C 0 FE,PI FE,PI

2SV-0205 3 3-4 B-1 1 GL 5 <2 C 0 FE,PI GR-1,GR-4 FE,PI 2SV-0317-2 3 C-0 B-1 1 GL 5 <2 C 0 FE,FS,PI GR-1,GR-4 FE,FS,PI i

PAGE 29

Revision 1 i

P&ID NO.: M-2204, SH. 4 SYSTEM: Emergency Feedwater ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Class .C_qgrd. Cateaory (In.) Type Tyce Time Position Position Tests Reauest No. Performed Valve No.

D-3 B-1 6 G M 28 C 0 FE, PI FE, PI 2CV-0711-2 3 2CV-0714-1 3 G-6 B-1 4 G A0 18 C C FE, PI, FS FE, PI, FS F-3 B-1 6 G M 32 C 0 FE, PI FE, PI 2CV-0716-1 3 E-4 B-1 8' G M 49 0 C FE, PI FE, PI l 2CV-0789-1 3 E-4 B-1 8 .G M 42 0 C FE, PI FE, PI l

2CV-0795-2 -3 4 AD 18 C C FE, PI, FS FE, PI, FS 2CV-0798-1 3 G-6 B-1 G  ;

3 F-6 B-1 4 GL M 20 C 0/C FE, PI FE, PI 2CV-1025-1 D-6 B-1 4 G M 20 C O/C FE, PI FE, PI 2CV-1026-2 3 F-7 B-1 4 G M 18 0 0/C FE, PI FE, PI 2CV-1036-2 2 D-7 B-1 4 G M 13 0 0/C FE, PI FE, PI 2CV-1037-1 2 F-7. B-1 4 M 16 0 0/C FE, PI FE, PI 2CV-102 9 2 G D-7 B-1 4 G M 13 0 0/C FE, PI FE, PI 2CV-1039-1 2 F-6 B-1 4 GL M 20 C 0/C FE, PI FE, PI i 2CV-1075-1 3 3 D-6 B-1 4 G 'M 18 C O/C FE, PI FE, PI 2CV-1976-2 2EFW-1 3 E-3 C-1 8 CK SA N/A C 0 Fc FE DI, RR 3 D-4 C 6 CK SA N/A C O/C FE EFV-1 2EFW-2A F-4 C-1 6 CK .SA N/A C O/C FE EFV-1 DI, RR 2EFW-2B 3 PAGE 30 l

L _

Revision 1 P&ID NO.: M-2204, SH. ? (Cont'd)

SYSTEM: Emergency Feedwater Sec. XI Size Valve Act Stroke Norraal Safety Required Relief Tests ASME .. P&ID Class Copr L Cateaory (In.) TVDe Type Tirne Position Position Tests Recuest No. Performed Valve No.

4 SA N/A C 0 FE FE 2EW-4A 3 D-5 C-1 SC N/A C 0 FE FE

! 2EW-48 3 E-5 C-1 4 SC SA 8 SA N/A C 0 FE FE 2EW-801- 3 E-3 C-1 CK 8 SA N/A C 0 FE FE 2EW-16 NN E-2 C-1 CK i.

I l

l l

l l

PAGE 31 l

l

Revision 2 SYSTEM: Steam Generator Secondary P&ID NO.: M-2206, SH. I ASME- P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Class Coord. Catecorv (In.) Type Typa Time Position Position Tests Recuest No. Performed 2CV-1000-1 2 H-5 B-1 4 G M 20 0 0/C FE, PI FE, PI 2CV-1001 2 ' H-6 B-1 10 GL A0 20 C O/C FE, FS, PI FE, FS, PI 2CV-1002 2 G-6 B-1 10 G M 30 C 0/C FE, PI FE, PI 2CV-1010-1 2 H-5 B-1 36 GL A0 3 0 C FE, FS, PI FC, FS, PI 2CV-1023-2 NN C-7 B-1 24 G M 20 0 C FE, PI FC, PI 2CV-1024-1 2 C-1 B-1 24' G M 20 0 C FE, PI FC, PI 2CV-1050-2 2 H-4 ~B-1 4 G. M 20 0 0/C FE, PI FE, PI 2CV-1051 2 G-3 B-1 10 GL AD 20 C 0/C FE, FS, PI FE, FS, PI 2CV-1052 2 G-3 B-1 10 G M 30 C 0/C FE, PI FE, PI 2CV-1060-2 2 H-4 B-1 36 GL 'A0 3 0 C FE, FS, PI FC.FS,PIl 2CV-1073-2 NN C-2 B-1 24 G M 20 0 C FE, PI FC, P1 2CV-1074-1 2- C-2 B-1 24 G M 20 0 C FE, PI FC, PI 2FW-5A 2 D-7 C-1 24 CK SA N/A 0 C FE FC 2FW-5B 2 D-2 C-1 24 CK SA N/A 0 C FE FC 2EFW-7A 2 C-8  : C-1 4 SC SA N/A C O/C FE FE 2EFW-7B 2 C-8 C-1 4 SC SA N/A C O/C FE FE 2EFW-8A '2 D-1 C-1 4 SC SA N/A C O/C FE FE 4

PAGE 32

Revision 1 SYSTEM: Steam Generator Secondary P&ID NO.: M-2206, SH. 1 (Cont'd)

ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Class Coord. Cateoory (In.) Type Typ_g Time Position Position Tests Reauest No. Performed Valve No.

N/A O/C FE FE 2EFW-8B 2 0-1 C-1 4 SC SA C C-1 4 SA N/A C 0/C FE FE 2EFW-9A 2 D-8 CK C-1 4 SA N/A C O/C FE FE 2EFW-98 2 D-2 CK 2MS-39A 3 H-5 C-1 4 CK SA N/A C 0/C FE SGS-1 FE(0), DI, RR j 2MS-39B 3 H-4 C-1 4 CK SA N/A C O/C FE SGS-1 FE(0), DI, RR 2PSV-1002 2 G-7 C-1 8 RV SA N/A C 0 SP SP 2PSV-1003 2 G-6. C-1 8 RV SA N/A C 0 SP SP 2PSV-1004 2 G-6 C-1 8 RV SA N/A C 0 SP SP 2PSV-1005 2 G-6 C-1 8 RV SA N/A C 0 SP SP 2PSV-1006 2 G-5 C-1 8 RV SA. N/A C 0 SP SP 2PSV-1052 2 G-3 -C-1 8 RV SA N/A C 0 SP SP 2PSV-1053 2 G-3 C-1 8 RV SA N/A C 0 SP SP 2PSV-1054 2 G-3 C-1 8 RV SA N/A C 0 SP SP C-1 8 SA N/A C 0 SP SP 2PSV-1055 2 G-3 RV

-2PSV-1056 2 G-4 C-1 8 RV SA N/A C 0 SP SP PAGE 33 l

l L___ _

Ravision 1 SYSTEM: Steam Generator Secondary P&ID NO.: M-2206, SH. 2 ASME P&ID Sec. XI Si7a Valve Act Stroke Normal Safety Required Relief Tests Class Coord. Cateoory fin.) Type Type Time Position Position Tests Recuest No. Performed Valve No.

4 AD 20 0 C FE, PI, FS FE, PI, FS 2CV-1016-1 2 G-8 B-1 G G B-1 4 G A0 20 0 C FE, PI, FS .?E, PI, FS

' 2CV-1066-1 2 l  !

(

PAGE 34 i

m__ _.m

Revision 1 P&ID NC.: M-2210, SH. 1 SYSTEM: Service Water Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests ASME P&lD Catecorv (In,) Tvoe TyJ2g Time Position Position Tests Recuest No. Perfon ud Valve No. Class Coord.

150 0 C FE, PI FC, PI 2CV-1425-1 3 F-5 B-1 20 BF M M 150 0 C FE, PI FC, PI i 2CV-1427-2 3 F-5 B-1 2.0 BF 2CV-1470-1 3 B-6 A-1 42 SG M 300 0/C O/C FE, PI, LK GR-2 FE,PI,LKl  ;

3 B-6 B-1 42 -SG M 300 0/C O/C FE, PI FE, PI 2CV-1471^--I 2CV-1472 3 B-4 A-1 42 SG M 300 0/C O/C FE, PI, LK GR-2 FE,PI,LKl B-1 42 M 300 0/C O/C FE, PI FE, PI 2CV-1473-5 3 B-5 SG 4 1

2CV-1474-2 3 B-3 A-1 SG M 300 0/C O/C FE, PI, LK GR-2 FE,PI,LKl

.B-3 B-1 42 SG M 300 0/C O/C FE, PI FE, PI

~2CV-1475-2 3 G-6 B-1 8 BF M 60 C 0 FE, PI FE, PI 2CV-1503-1 3 8 BF M 60 C 0 FE, PI FE, PI 2CV-1504-2 3 G-3 B-1 20 SA N/A 0/C O/C FE FE 252-2A- '3 D-6 C-1 CK SA N/A O/C O/C FE FE 2SV-28 3 D-5 C-1 20 CK 20 SA N/A O/C O/C FE FE t 25W-2C 3 D-3 C-1 CK l

t I PAGE 35

Revision 1 SYSTEM: Service Vater P&ID NO.: M-2210, SH. 2  :

ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Class roord. Cateaory (In.) Type Iygg Time Position Position Tests Recuest No. Perfomed 2CV-1400-1 3 H-7 B-1 16 BF M 60 0/C 0 FE, PI FE, PI 2CV-1406-2 3 H-8 B-1 16 BF M 60 O/C 0 FE, Pi FE. PI 2CV-1453 3 E-1 B-1 14 BF M 60 C 0 FE, PI FE, PI i

2CV-1456-2 3 D-1 B-1 14 BF M 60 C 0 FE, PI FE, PI 2CV-1480-2 3 B-6 B-1 18 BF M 60 0/C C FE, PI FE, PI 2CV-1481-1 3 A-6 B-1 IS BF M 60 0/C C FE, PI FE, PI 2CV-1486-2 3 E-8 B-1 2 G M 20 O/C 0 FE, PI FE, PI 2CV-1487-2 3 D-8 B-1 2 G M 20 0/C 0 FE, PI FE, PI 2CV-1488-1 3 0-8 B-1 2 G M 20 0/C 0 FE, PI FE, PI 2CV-1489-1 3 C-8 B-1 2 G M 20 0/C 0 FE, PI FE. PI

'25W-12A 3 A-5 C-1 . CK SA N/A O/C 0 FE SV-1 DI, RR 2SV-12B 3 B-5 C-1 16 CK SA N/A O/C 0 FE SV-1 DI, RR L

(

I i

PAGE 36

4 r j _ ,

Revision 1 j.

l SYSTEM:- Service Water PEilD NO.: 5-22.10, SH. 3  !

i; . ASME -P&ID Sec. XI Size' ' Valve Act Stroke Normal Safety Required Relief Tests 4

. Valve No. Class Coord. Cateoory ~ (In.) Type Iype Tima Position Position Tests Recuest No. Perforsed

3. f 4 2CV-1500 3- G-8 8-1 2 G M 30. 0/C 0 FE, PI FE, PI 2CV-1501-5 3 G-7 B-1 2 G M 30 O/C 0 FE, PI FE, PI 2CV-1502-2 3 G-6 B 2 G M 30 0/C 0 FE, PI FE, PI

2CV-1510-2. '2 ... G-6 A- 1.. '12 BF M 25 O/C O/C FE, PI, LJ GR-2 FE, PI, LJ

'2CV-1511 2- E-6 A-1. 12 BF .- M 25 0/C- 0/C FE, PI, LJ GR-2 FE, PI., LJ

. t 2CV-1513-2' 2 E-4 ~ A-l' 12 BF M 25 C O/C' FE, PI, LJ GR-2 FE, PI, LJ l2CV-1519-1 '2 :B-4 A-l' 12 BF M 25 C O/C FE, PI, LJ GR-2 FE, PI, LJ  !

2CV-1525-4 '3 ' .G-5 'B-1 .12 BF' M 60 0 C FE, PI FE, PI 2CV-1526-2' 3 G-4~ B-1 12 BF- M- 60 C C FE, PI FE, PI j

" 2CV-1529-2 3: G-4 B- 1. . 2 G M 90 0/C 0 FE, PI FE. PI

i 2CV i l530-1: 3 G-3 B-1 18 BF- M 90 0 0/C FE, PI FE, PI 3 G-2 '- B-1 18 BF M 90 C O/C FE, PI FE, PI f2CV-1531-2

, 2CV-1532 3 F- 4 ~ - - B-l' 2- G M 30 0/C 0 FE, PI FE, PI 2CV-1541-1 '3 ,

B-2. .B-l', 18' BF .M 90 C 0 FE, PI FE, PI h2CV-1542-2 ~ 3

'C-2 B 16' BF M' 90  : 0. 0/C FE, PI FE, PI I

2CV-1543-1 3. C-2. B-1 -16 BF M '90 0 0/C FE, PI FE, PI 2CV-I F . 3- C-2. B-1. 18 BF. M. ~90 C 0 'FE, PI FE, PI g--

1 PAGE 37

, - , . . . , - . , . . , - -. . .- ....--..:e,. ..- ., . - . , . - - - . - .-. - - - . . ,- ..-- -- -. .-

Revision 1

-SYSTEM: Service Water P&ID NO.: M-2210. SH. 3 (Cont'd)

ASME P&ID Sec. XI Size Valve Act Stroke Nore:a1 Safety Required Relief Tests Valve No. Cla;s Coord. Catecory (In,) Type Type Time Position Desition Tests Recuest No. Fe -femM 2CV-1561-1 3 H-1 B-1 2.5 G M 30 0/C 0 FE, PI FE, PI 2CV-1562-2 3 C-5 B-1 1.5 G M 30 0/C 0 FE, PI FE, PI 2CV-1563-1 3 F-3 B-1 1.5 G M 30 0/C 0 FE, PI FE, PI 2CV-1564-2 '3 C-5 B-1 1.5 G M 30 0/C 0 FE, PI FE, PI DAGE 38

a a ._ .-m ,-,- - -- - A t.4 C"

.,o e y e lh

r Si m e)

W e0 LA.

.e.

, O L. s lab

>

• OO M O O t7 48 & (L 4 gg eg H 6-. + Ob N 0 L1J N CL LA.

se e a O Wv

(") .e e M r== 0 65 G D CL cr g ec 3

N M LA.

.e a s D N e=4 U 08 (L WF e Er LAJ LA.

c:

AO p e-D

% .N e- U fp m MO CL c

& O

.e-

.ed e Q O +

Z O (L

W a ci O

O 6- .e-li N eJ F m

Gs W Q U p# aC el &

W

> 0) m o <<

l 4 > d t >F l

i N C r.

se t.< et M %e 06 >

l # M L l

e X O 80 C7 e.4 1 3E e 0 e ;I I U# *aC '

i o e so

> WU

.c Y

U .

80 'O O OL N

• e MO e V e5 O (.D to CL U CC V Lij m e t'

. e=

3 E 80 N tr m-

• r= *C O J

N es O re g K

Lu Z W O

>= 0 N M > 0

>= m > i M 80 W '

> N

Rovision 1 SYSTEM: Liquid Radwaste Containtnent Building P&ID ND.: M-2213. SH. 10 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Requi ed Relief Tests Valve No. Class Coord. fatecorv (In.) TYD? IYre Tire Position Position Ttsts Recuest No. Performed 2CV-2060-1 2 B-3 A-1 4 G M 20 C C FE, PI, LJ FE, PI, LJ l

t i

\

PAGE 40

Revision 1

' SYSTEM: Boron Management P&ID NO.: M-2214, ..H . I ASME P&ID Sec. XI Size Valve Act Stroke Nomal Safety Pequired Relief Te1 ,

Valve No. Class Coord. Catecorv (In,) Type Type Time Position Position Tests Recuest N a Perfomed 2CV-2201-2 2 F-7 A-1 4 BA AD 20 0 C FE,PI,FS,LJ FE,PI,FS.LJ 2CV-2202-1 2 F-7 A-1 4 G M 20 0 C FE, PI, LJ FE, PI, LJ 1

l PAGE 41 t

Rovision 1 SYSTEM: Gaseous Radioactive Waste P&ID NO.: M-2215 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Class Coord. Catecory (In.) Type Type Time Position Position Tests Recuest No. Performed i

2CV-2400-2 2 d-7 A-1 2 G A0 20 C C FE,PI,FS,LJ FE,F:, %,LJ i 2CV-2401-1 2 0-7 A-1 2 G M 20 C C FE, PI, LJ FE, PI, LJ i

~~

PAGE 42

Rovision 1 .

SYSTEM: Emergency Diesel Generator Fuel 01.1 P&ID NO.: M-2217, SH. 1 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Class Coord. Cateoorv (In.) Type TYDe IiU* E9.1jtion Position Tests Recuest No. Perforred 2ED-3A 'NN B-5 C-1 2 CK SA N/A O/C 0 FE DI 2ED-38 NN B-4 C-l ' 2 CK SA N/A 0/C 0 FE DI 2PSV-2938 NN E-5 -C-1 .75 RV SA N/A C 0 SP SP 2PSV-2988 NN E-4 C-1 .75 RP SA N/A C 0 SP SP 2SV-2802-1 NN E-8 B-1 N/A DIA 5 N/A C 0 FE FE 2SV-2822-2 NN E-1 B-1 N/A DIA S N/A C 0 FE FE 1

k PAGE 43 l

Recision 1

-SYSTEM:' Emergency Diesel Generator Starting Air P&ID NO.: E-2217, SH. 2 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Class Coord. Catecory (In ) Type Type Tire Position Position Tests Recuest No. Perfe m d 2ED-12A NN- E C-1 1.5 CK SA N/A 0/C O/C FE FE

'2ED-12B NN E-5 C-1 1.5 CK SA N/A- O/C O/C FE FE 2ED-20A NN E-a C-1 1.5 CK SA N/A O/C O/C FE FE ZED-20B NN E-3 C 1.5 CK SA 'N/A O/C O/C FE FE 2PSV-2803 f;N C-7 C-1 .75 RV SA N/A C 0 SP SP 2PSV-2805 NN C-7 - C- 1 .5 RV SA N/A C 0 SP SP 2PSV-2806 KN C-5 C-1 .75 RV SA N/A C 0 SP SP 2PSV-2808 NN C-5 C-1 .5 RV SA N/A C 0 SP SP 2PSV-2823 NN C-4 C-1 .75 RV SA N/A C 0 SP SP

-2PSV-2825 NN C-4 C-1 .5 RV SA N/A C 0 SP SD 2PSV-2826 NN C-3' C-1 .75 RV SA N/A C 0 SP SP -

'2PSV-2828 NN C-2 C-1 .5 RV SA N/A C 0 SP SP 2SV-2809-1 NN- E-6 B-1 1.5 G S N/A C 0 FE FE 2S7-2810-1 NN E-6 B-1 1.5 G S N/A C 0 FE FE 2SV-2811 NN E-6 B-1 1.5 G S N/A 0 C FE FE

-2SV-2829-2 NN 'E-3 B-1 1.5 G S N/A C 0 FE FE PAGE 44 i

Revision 1 !

SYSTDf: Emergency Diesel Generator Starting Air NID NO.: M-2217, SH. 2 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Class Coord. Cateocry (Ip ) Type Type Time Position Pesition Tests Recuest No. Perfortnad 2SV-2830-2 NN E-3 B-1 1.5 G S N/A C 0 FE FE 2SV-2831 NN E-3' B-1 1.5 G S N/A 0 C FE FE i

1 i

1 PAGE 45

Revision 1 SYSTEM: Service Air P&ID NO.: M-2218, SH. 1 ASME P&ID Sec. XI Size Vtive Act Stroke Normal Safety Required Relief Tests Valve No. Class Coord. Catecory (In.) Tvoe T.ype Time Position Position Tests Recuest No. Performed 2SA-68 2 G-5 A-2 3 G H N/A C C LJ LJ 2SA-69 2 G-5 AC-2 3 CK SA N/A C C LJ LJ PAGE 46

Ravision 1 SYSTEM: Breathing Air P&ID NO.: M-2218, SH. 5 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valvt No. Class Coord. Cateoory (In.) Type Type Time Position Position Tests Recuest No. Perfomed 2BA-216 2 F-4 AC-2 2 CK SA N/A C C LJ LJ 2BA-217 2 F-3 A-2 2 G H N/A C C LJ LJ PAGE 47

Revision 1 SYSTEM: Fire Water P&ID NO.: M-2219, SH. 2 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests

' Valve No. Class Coord. Cateoorv (In.) Type Type Time Position Position Tests Recuest No. Perfomed

,2CV-3200-2 2 D-5 A-1 3 G M 20 0 C FE, PI, LJ FE, PI, LJ 2FS-37 2 E-6 AC-1 3 CK SA N/A C C LJ LJ PAGE 48

Rovision 1 SYSTEM: Plant Heating P&ID NO.: M-2220, SH. 1 ASME P&ID Sec. XI Size Valve Act St oke Normal Safety Required Relief Tests Valve No. Cl a s_s Coord. Catecory (In.) hg_ bg Time Position Position Tests Recuest No. Performed 2PH-22 2 E-4 A-2 3 G H N/A C C LJ LJ 2PH-45 2 E-4 A-2 3 G H N/A C C LJ LJ PAGE 49

Revisien 1 t

.- t

[. SYSTEM: Chilled Water - Containment, Turbine, and Auxiliary Buildings .

P&ID NO.: M-2222, SH. 1 l 4

ASME: P&ID' Sec. XI. Size ,Yalve Act Stroke Normal Sa fety '- Required Relief Tests Valve No. Class Coord. CateoorY (ID.) IVDe .. Type Time' Fosition Position Tests Reauest No. Performed i ,

2CV-3850 . 2 G-3' A 6 G M 20 0 C FE, PI, LJ GR-2 FC, PI, LJ j2CV-3851 ~ 2- G-3 A-1 6' G' A0 20 0 C .- FE,FS,PI,LJ GR-2 FC,FS PI,L1 2CV-3852-1 -2 H-3 A 6' G A0 20 0 C. FE,FS,PI,LJ GR-2 FC,FS,PI,LJ f

$2AC 4 .

2 H AC-1 6 CK SA N/A 0 C- LJ GR-2 LJ 3-i '

l s .

! r f

d-.

2

, l i- _

[

t 4

'PAGE 50

= ' l' ,

Pevision 1 SYSTEM: Reactor Coolant P&ID NO.: M-2230, SH. I ASME P&lD Sec. XI Size Valve Act Stroke Nor::a1 Safety Required Relief Tests Valve No. Class ,oord. Category j_In.) Tyr.e Tygg Tima Position Position Tests Request No. Ferforw d 1' D-3 3 CK SA N/A C O/C FE, LK CC-1 FR, ER 2SI-27A AC-1 C-3 AC-1 3 CK SA N/A C GIC !E, ~ K RC- 1 FR, 4R 251-27B 1 0-3 AC-1 3 CK SA N/A C O/C IE, LK RC-1 FR, RR 2SI-28A 1 AC-1 3 CK SA N/A C O/C FE, LK RC-1 FR, RR 251-288 1 C-3 l

PAGE 51

k Revision 1 i

SYSTEM: Reactor Coolant P&lD NO.: M-2230, SH. 2 i l

ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Class Coo rd. Catecorv (In ) Tvoe Type Time Position Position Tests Recuest No. Pe-fo- ed 2CV-4690-2 2 A-5 A-1 2 G M 20 C C FE, PI, LJ FE, PI, LJ 2CV-4698-1 1 H-3 B-1 3 G M 20 C O/C FE, PI FC, PI 2CV-4730-1 1 G-4 B-1 4 G M 20 C O/C FE, PI FC, PI 2CV-4731-2 1 H-4 B-1 4 G M 20 C O/C FE, PI FC, PI 2CV-4740-2 1 G-4 B-1 4 G M 20 C O/C FE, PI FC. "I 2CV-4741-1 1 .G-3 B-1 4 G M 20 C O/C FE, PI FC, 2CVC-78 2 A-4 AC-1 2 CK SA N/A C C LJ LJ 2PSV-4633 1 F-5 .C-1 6 RV SA N/A C 0 SP SP

'2PSV-4634 1 F-5 C-1 6 RV SA N/A C 0 SP 50

~

2PSV-4732 2 G-4 'C-1 4' RV SA N/A C 0 SP SP 2PSV-4742 2 H-3 C-1 4 RV SA N/A C 0 SP 50 2SV-4636-1 1 G-2 B-1 1 GL 5 5 C O/C FE, PI, FS FC, PI, FS 2SV-4636-2 1 H-2 B-1 1 GL 5 5 C O/C' FE, PI, FS FC. PI, FS 2SV-4668-1 1 G-2 B-1 1 _GL 5 5 C O/C FE, PI. FS FC. PI, FS 2SV-4668-2 1 F-2 B-1 l' GL 5 5 C O/C FE, PI, FS FC, DI, FS 2SV-4669-1 2 H-2 B-1 GL 5 5 FE, PI, FS FC, PI, FS '

1 C O/C 2SV-4570-2 2 G-1 B-1 1 GL S 5 C O/C FE, PI, FS CC, PI, FS PAGE 52

Revision 1 ,

SYSTEM: Chemical and Volume Control P&ID NO.: M-2231 SH. 1 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests

-Valve No. Class Coord. Catecory (In.) Type TYDe Time Positio9 Position Tests Reevest No. Performed 2CV-4820-2 1 E-8 B-1 2 GL M 20 0 C FE, PI FC, PI f 2CV-4821-1 1 E-7 A-1 2 GL M 20 0 C FE, PI, LJ FC, PI, LJ 2CV-4823-2 2 E-6 A-1 2 G A0 20 0 C FE PI,LJ,FS FC,PI,LJ.FS I 2CV-4824-2 1 D-7 B-1 2. GL M 20 C 0 FE, PI FC, PI 2CV-4827-2 I C-7 B-1 2 GL M 20 0 0/C FE, PI FE, PI 2CV-4831-2 1 D-7 B-1 2 GL M 20 0 0/C FE, PI FE, PI 2CV-4846 2 B-3 A-1 .75 G M 20 0 C FE, PI, LJ FC, PI, LJ 2CV-4847-2 2 B-3 A-1 .75 GL AD 20 0 C FE,FS,PI,LJ FC,FS PI,LJ 2CV-4873-1 2 A-2 B-1 4 G M 20 0 C FE, PI FC, PI 2CV-4950-2 2 A-3 B-1 3 G M 10 C 0 FE, PI FC, PI 2CVC-22A 2 D-5 C-1 3 CK SA N/A 0 0/C FE FE 2CVC-22B 2 B-6 C-1 3 CK SA N/A 0 0/C FE FE 2CVC-22C 2 C-6 C-1 3 CK SA N/A 0 O/C FE FE 2CVC-28A 1 D-8 C-1 2 CK SA N/A C 0 FE FC 2CVC-288 1 C-7 C-1 2 CK SA N/A 0 0 FE FC 2CVC-28C 1 D-7 C-1 2 CK SA N/A 0 0 FE FC 2CVC-70 2 A-3 C-1 3 CK SA N/A C 0 FE FC PAGE 53

l Revisico 1 SYSTEM: Chemical and Volume Control P&ID NO.: M-2231, SH. 1 (Cont'd)

ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valvo No.' Class Coord. Catecory (In.) Type Type Time _ Position Desition Tests _ Revest No. Perferred i

2PSV-4835 2 D-5 C-1 1.5 RV SA N/A C 0 SP SP 2 B-5 C-1 1.5 RV SA N/A C 0 SP SP l 2PSV-4845 i'

2 C-5 C-1 1.5 RV SA N/A C 0 SP SP

(.ZPSV-4855 l

l I

l l

~

PAGE 54

Revision 1 P&ID NO.: M-2231, SH. 2 SYSTEM: Chemical and Volume Control ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests )

Valve No. Class Coord. Qtecory (In.) Type Tvpg Tire Position Position Tests Recuest No. Performed F-8 B-1 GL AD 10 0 C FE, FS, PI FE, FS, PI 2CV-4903-2 2 1 F-4 B-1 GL AD 10 0 C FE, FS, PI FE, FS, PI 2CV-4915-2 2 1 2CV-4916-2 2 F-4 B-1 3 G M 20 C 0 FE, PI FE, PI 2CV-4920-1 2 D-7 B-1 3 G M 20 C 0 FE, PI FE, PI 2CV-4921-1 2 D-7 B-1 3 G M 20 C 0 FE, PI FE, PI 2CV-4941-2 3 G-4 B-1 3 GL AD 20 0 C FE, FS, PI FE, FS, PI C-4 C-1 3 CK SA N/A C O/C FE FC 2CVC-41A 2 D-4 C-1 3 CK SA N/A C O/C FE FC 2CVC-41B 2 2CVC-49 2 G-6 C-1 3 CK SA N/A C 0 FE FC 2CVC-58 2 F-4 C-1 3 CK SA N/A C 0 FE FC I'

l PAGE 55 e _ ,

l Reeision 1 l

SYSTEM: Safety Injection P&ID NO.- 4 2232 i ASME P&ID Sec. XI Size Valve Act Stroke Nomal Safety Required Relief Tests Valve No. Class Coord. Catecory (In.) Tyre lyp= Time Position Position Tests Recuest Nc. Pe-fomed 2CV-5015-1 2 F-5 B-1 2 GL M 20 C 0 FE, PI FE, PI 2CV-5016-2 2 E-5 B-1 2 GL M 20- C 0 FE, PI FE, PI 2CV-5017-1 2 E-5 B-1 6 GL M 30 C O/C FE, PI FE, PI 2CV-5035-1 2 H-5 B-1 2 GL M 20 C 0 FE, PI FE, PI 2CV-5036-2 2 G-5 B-1 2 GL M 20 C 0 FE, PI FE, PI ,

2CV-5037-1 2 G-5 B-1 6 GL M 30 C O/C FE, PI FE, PI 2CV-5038-1 2 F-5 B-1 14 G M 30 C O/C FE, PI FE, PI 2CV-5055-1 2 B-5 B-1 2 GL M 20 C 0 FE, PI FE, PI i 2CV-5056-2 2. B-5 B-1 2 GL M 20 C 0 FE, PI FE, PI 2CV-5057-2 2 A-5 B-1 6 GL M 30 C O/C FE, PI FE, PI 2CV-5075-1 2 D-5 B-1 2 GL M 20 C 0 FE, PI FE, PI 2CV-5076-2 2 D-5 B-1 2 GL M 20 C 0 FE, PI FE, PI 2CV-5077-2 2 C-5 B-1 6 GL M 30 C O/C FE, PI FE, PI 2CV-5082 2 B-8 A-2 2 G M 20 C C FE, PI, 1J FE, PI, LJ 2CV-5084-1 1 F-7 A-1 14 G M 30 C O/C FE, PI, LK GR-2 FC, PI, LK 2CV-5086-2 1 F-6 A-1 14 G M 30 C O/C FE, PI, LK GR-2 FC, PI, l_K 2CV-5101-1 2 E-4 B-1 3 GL M 60 C O/C FE, PI FE, PI PAGE 56

Revision I t

SYSTEM: Safety Injection P&ID NO.: M-2232 (Cont'd)

ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests  !

Valve No. Class Coord. Cateaory (In.) Tvoe Iyps Time Position Position Test L Reauest No. Performed 2CV-5102-2 2 B-4 B-1 3 GL M 60 C O/C FE, PI FE, PI  !

2CV-5103-1 2 D-4 B-1 4 G M 60 0 0/C FE, PI PE, PI l 2CV-5104-2 2 C-4 B-1 4 G M 63 0 0/C FE, PI FE, PI

, 2CV-5123-1 2 G-3 B-1 2 O H 20 0 C FE, PI FE, PI

.2CV-5124-1 2 F-3 B-1 2 G M 20 0 C FE, PI FE, PI 2CV-5126-1 2 E-3 B-1 2 G M 20 0 C FE, PI FE, PI

.2CV-5127-1 2- D-3 B-1 2 G M 20 0 C FE, PI FE, PI 2CV-5128-1 2 C-3 B-1 2 G M 20 0 C FE, PI FE, PI 2SI-3A 2 G-3 C-1 12 SC SA N/A C O/C FE FC 2SI-38 2 F-3 C-1 12 SC SA N/A C O/C FE FC 2SI-7A 2 D-1 C-1 8 CK SA N/A C 0 FE SI-1 FR, RR 25I-78 2 C-1 C-1 8 CK SA N/A C 0 FE SI-1 FR, RR 2SI-10A 2 D-3 C-1 4 SC SA N/A C O/C FE SI-1 FR, RR 2SI-10B 2 C-3 C-1 4 SC SA N/A C O/C FE SI-I FR, RR 2SI-10C 2 D-3 C-1 4 SC SA N/A C O/C FE SI-1 FR, RR 2SI-12 2 D-3 C-1 4 CK SA N/A C 0 FE SI-1 FR, RR .

2SI-13A 1 E-5 AC-1 3 CK SA N/A C O/C FE, LK SI-1 FR, RR, LK PAGE 57 i

i Revision 1 SYSitM: Safety Injection P&ID NO.: M-2232 (Cont'd)

AS'4E P&lD Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Class Coord. Cateaory (In.) Type hpa Time Position Position Tests Recuest No. Feeformed 251-138 1 G-5 AC-1 3 CK SA N/A C O/C FE, LK SI-1 FR, RR, LK 2SI-13C 1 A-5 AC-1 3 CK SA N/A C G/C FE, LK SI-I FR, RR, LK 251-13D 1 C-5 AC-1 3 CK SA N/A C O/C FE, LK SI-1 FR, RR, LK 2SI-14A 1 E-5 AC-1 6 CK SA N/A C O/C FE, LK GR-2 FC, LK ,

2SI-14B 1 G-5 AC-1 6 CK SA N/A C O/C FE, LK GR-2 FC, LK 2SI-14C 1 A-5 AC-1 6 CK SA N/A C O/C FE, LK GR-2 FC, LK 2SI-14D 1 C-5 AC-1 6 CK SA N/A C O/C FE, LK GR-2 FC, LK 2ST-15A 1 E-8 AC-1 12 CK SA N/A C O/C FE, LK SI-2,GR-2 DI, RR, LK 251-158 1 G-8 AC-1 12 CK SA N/A C O/C FE, LK SI-2,GR-2 DI, RR, LK 2SI-15C 1 A-7 AC-1 12 CK SA N/A C 0/C FE, LK SI-2,GR-2 DI, RR, LK 251-15? 1 C-8 AC-1 12 CK SA N/A C O/C FE, LK SI-2,GR-2 DI, RR, LK 2SI-16A 1 E-7 AC-1 12 CK SA N/A C O/C FE, LK SI-2,GR-2 DI, RR, LK 2SI-16B 1 G-7 AC-1 12 CK SA N/A C O/C FE, LK SI-2,GR-2 DI RR, LK 2SI-16C 1 A-7 AC-1 12 CK SA N/A C O/C FE, LK SI-2,GR-2 DI. RR, LK 251-16D 1 C-7 AC-1 12 CK SA N/A C O/C FE, LK SI-2,GR-2 DI, RR, LK 2SI-17 2 A-8 A-2 2 G H N/A C C LJ LJ

" 2SI-22A.- 2 G-3 C-1 2 CK SA N/A C 0 FE FE PAGE 58

Revision 1 SYSTEM: Safety Injection P&ID NO.: M-2232 (Cont'd) i ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. fi m Coord. Catecorv (In.) Type Iypg Tire Positien Position Tests Recuest No. terfomed 2SI-22B 2 F-3 C-1 2 CK SA N/A C 0 FE FE 2SI-23A 2 E-3 C-1 2 CK SA N/A C 0 FE .

251-238 2 C-3 C-1 2 CK SA N/A C 0 FE FE 2SI-23C 2 0-3 C-1 2 CK SA N/A C 0 FE FE 2SI-26A 2 E-4 C-1 3 CK SA N/A C 0 FE SI-I FR, RR 2SI-26B 2 B-4 C-1 3 CK SA N/A C 0 FE SI-I FR, RR l

2SV-5001-1 1 E-7 B-1 1 GL S <2 C C FE, FS, PI GR-1, GR-4 FE,FS,PI 2SV-5021-1 1 G-7 B-1 1 GL S <2 C C FE, FS, PI GR-1, GR-4 FE,FS,PI 1 A-7 B-1 1 GL 5 <2 C C FE, FS, PI GR-1, GR-4 FE,FS,PI l 2SV-5041-2 2SV-5061-2 1 C-7 B-1 1 GL S <2 C C FE, FS, PI GR-1, GR-4 FE,FS,PI

'~ PAGE 59

Revision 1  ;

i SYSTEM: Component Cooling Water P&ID NO.: M-2234, SHT. I  ;

l ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Glass Coord. Cateaory (In.) Type lypa Time Position Position Tes*.s Recuest No. Perfomed 2CV-5236-1 2 B-4 A-1 10 BF M 20 0 C FE, FI, LJ GR-2 FC, PI, LJ 2CV-5254-2 2 G-4 A-1 10 BF M 20 0 C FE, PI, LJ GR-2 FC, PI, LJ 2CV-5255-1 2 G-4 A-1 10 BF M 20 0 C FE, PI, LJ GR-2 FC, PI, LJ 2CCW-38 2 B-4 AC-1 10 CK SA N/A 0 C LJ GR-2 LJ 2PSV-5249 2 B-4 A-1 .75 RV SA N/A C C LJ LJ 2PSV-5256 2 G-4 A-1 .75 RV SA N/A C C LJ LJ .

i J

PAGE 60

Revistor. 1 SYSTEM: Fuel Pool System P&ID NO.: M-2235 ASME P&ID Sec. XI Size Valve Act Strok.e Nomal Safety Required Relief Tests Valve No. Class Coord. Catecotv (In.) Type lyn Time Position Position Tests Recuest No. Perforr:ad 2FP-34 2 B-6 A-2 3 G H N/A C C LJ LJ PAGE 61

Revision 1 SYSTEM: Containment Spray P&ID NO.: M-2236, SHT. 1 ASME P&ID Sec. XI Size Valve Act Stroke Nors:al Safety Required Relief Tests Valve No. Class Coord. Catecory (In.) Type Type Tire Position Position Tests Recuest Nom Pe rf o-ed 2CV-5612-1 2 D-7 B-1 10 G M 20 C 0 FE, PI FE, PI 2CV-5613-2 2 C-7 B-1 10 G M 20 C 0 FE, PI FE, PI 2CV-5628-2 2 G-3 B-1 4 G M 20 0 C FE, PI FE, PI i 2CV-5630-1 2 E-2 B-1 20 G M 140 0 0/C FE, PI FE, PI 2CV-5631-2 2 F-1 B-1 20 G M 140 0 0/C FE, PI FE, PI 2CV-5647-1 2 B-5 B-1 24 G M 30 0 0 FE, PI FE, PI 2CV-5648-2 2 A-5 B-1 24 G M 30 0 0 FE, PI FE, PI 2CV-5649-1 2 B-4 B-1 24 3 M 30 C 0 FE, PI FE, PI 2CV-5650-2 2 A-4 B-1 24 G M 30 C 0 FE, PI FE, DI 2CV-5672-1 2 E-4 B-1 2 G M 20 0 C FE, PI FE, PI l 2CV-5673-1 2 G-4 E-1 2 G M 20 0 C FE, PI FE, DI 2BS-IA 2 E-2 C-1 20 CK SA N/A C 0 FE CS-1 DI, RR 285-18 2 E-1 C-1 20 CK SA N/A C 0 FE CS-1 DI, ER 2BS-3A 2 E-3 C-1 la CK SA N/A C 0 FE FE 2B5-38 2 C-3 C-1 14 CK SA N/A C 0 FE FE 2BS-4A 2 E-5 C-1 12 SC SA N/A C O/C FE FE 2B5-4B 2 D-5 C-1 12 SC SA N/A C O/C FE FE j PAGE 62

l i :- Revision 1 SYSTEM: Containment Spray P&ID NO.: M-2236, SET. 1 (Cont'd) i ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests

' Valve No. Class' Coord. Catecorv- (In.) Type Type Time Position Pesition Tests Recuest No. Perfo med 2BS-5A 2 F-8 C-1 10 CK SA N/A C O/C FE CS-2 DI, RR 285-58 2 F-8 .C-1 10 CK SA N/A C O/C FE C3-2 DI, RR i 4-  ;

285-6 2 F-1 C-1 3 SC- SA N/A C 0 FE FC i

p 2SV-5633-1 2- B-4 A-1 1 GL S- <2 C C. FE,91.LJ,FS GR-1, GR-4 FE,PI,LJ,FS  !

3 i l 2SV-5633-2 2 B-4 A-1 1- GL S <2 C C FE,PI,LJ FS GR-1, GR-4 FE.PI,LJ.FS 2SV-5634-1 2 A-4 A-1 1 GL S <2 C C FE,PI,LJ,FS GR-1, GR-4 FE.PI,LJ,FS j 2SV-5634-2 2 A-3 A-1 1 GL S <2 C C FE,PI,LJ,FS GR-1, GR-4 FE,PI,LJ,FS r

} I l

i s

- i 1

PAGE 63 ,

t

~ _ . .

Revision 1 SYSTEM: Containment Spray P&ID NO.: M-2236, SHT. 2 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Cateoorv- (In.) Tvoe lypa Tirne Position Position Tests Recuest No. Performed Class Coord.

2CV-5657-1 2 F-5 B-1 4 G M 25 C O/C FE, PI FE, PI 2CV-5667-2 2 D-4 B-1 4 G M 25 C O/C FE, PI FE, PI 2BS-10A 2 E-5 C-1 4 CK SA N/A C 0 FE FE 285-108 2 C-4 C-1 4 CK SA N/A C 0 FE FE 2BS-12A 2. E-8 C-1 2 CK SA N/A C 0 FE FC 285-128 2 C-8 C-1 2 CK SA N/A C 0 FE FC l

r l

1 l

I PAGE 64 L.__ r .-r -..I r .

Revision 1 4

SYSTEM: Sampling P&ID NO.: M-2237, SHT. 1 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Class "Coord. Cateoory (In,) Tvoe J_ype Time Position Position Tests Reauest No. Performed 2CV-5652-2 2 F-2 A-1 .5 G H 20 0 C FE, PI, LJ FE, PI, LJ 2CV-5859-2 2 F-2 A-1 .5 G M 20 0 C FE, PI, LJ FE, PI, LJ 2SV-5833-1 2 G-2 A-1 .5 GL S <2 C C FE,PI,LJ,FS GR-1, GR-4 FE,PI.LJ,FS 2SV-5843-2 2 G-2 .' A- 1 .375 GL S <2 C C FE,PI,LJ,FS GR-1, GR-4 FE,PI,LJ,FS 2SV-5871-2 2 C-4 .A-1 .5 GL S <2 C C FE,PI,LJ,FS GR-1, GR-4 FE,PI,LJ,FS i 2SV-5872 2 B-3 B-1 .5 GL S <2 C C FE.PI,FS GR-1, GR-4 FE,PI,FS 2SV-5873 2 B-3 B-1 5 GL S <2 C C FE,PI,FS GR-1, GR-4 FE,PI,FS 2SV-5874 2 A-3 B-1 .5 GL S <2 C C FE,PI,FS GR-1, GR-4 FE.PI,FS 2SV-5875 2 A-3 B-1 .5 GL S <2 C C FE,PI,FS GR-1, GR-4 FE,PI,FS 2SV-5876-2 2 B-3 A-1 .375 GL S <2 C C FE,PI,LJ,FS GR-1, GR-4 FE, PI , LJ , FS 2SV-5878 2 C-3 A-1 .75 G S <2 C C FE,PI,LJ FS GR-1, GR-4 FE PI,LJ,FS PAGE 65

Revision 1 SYSTEM: Nitrogen Addition P&ID NO,: M-2239, SHT. I ASME P&IO Sec. XI Size Valve Act Stroke Nornal Safety Required Relief Tests Valve No. Class Coord. Cateaory (In.) hp3_ hpa Time Position Position Tests Reauest No. Performed 2CV-6207-2 2 G-5 A-1 1 .GL- A0 20, C ,

C FE,FS,PI,LJ FE,FS,PI,LJ 2CV-6213-2 2 C A-1 l' GL A0. 20 C C FE,FS,PI,LJ FE,FS,PI,LJ 2N2-1 2 C-5 -AC-1 1 SC SA N/A C C LJ LJ 2N2-18 2 G-5. AC-1 1 SC SA N/A C C LJ LJ ,

PAGE 66

Revision 1 SYSTEM: Air Flow and Control HVAC Containment Building P&ID NO.: M-2261, SHT. 1 ASME P&ID Sec. XI Size Valve Act Stroke Normal Safety Required Relief Tests Valve No. Clast Coord. Cateacry (In.) Type Tyr; Time Position Position Testi__ Recuest No. Performed 2CV-8233-1 2 G-6 A-1 2 G M 20 C C FE, PI, LJ FE, PI, LJ E-7 B-1 54 BF A0 5 C C FE,FS PI FC,FS,PI 2CV-8283-1 2 2CV-8284-2 2 E-7 A-1 54 BF A0 5 C C FE,FS,PI,LJ GR-2 FC,FS,PI,LJ 2CV-8285-1 2 D-7 B-1 54 BF A0 5 C C FE,FS,PI FC,FS,PI 2CV-8286-2 2 D-7 A-1 54 BF A0- 5 C C FE,FS,PI,LJ GR-2 FC,FS,PI,LJ 2CV-8289-1 2 E-7 A-1 54 BF M 5 C C FE, PI, LJ GR-2 FC, PI, LJ 2CV-8291-1 2 D-7 A-1 54 BF M 5 C C FE, PI, LJ GR-2 FC, PI, LJ l 2SV-8231-7 2 G-7 A-1 2 GL S <2 0 C FE,FS,PI,LJ GR-1, GR-4 FE,FS,PI,LJ 2SV-8259-1 2 F-6 A -I 2 GL A0 <2 C C FE,FS,PI,LJ GR-1, GR-4 FE, FS , PI, LJ 2SV-8261-2 2 F-7 A-1 2 GL S <2 C C FE,FS,PI,LJ GR-1, GR-4 FE,FS,PI,LJ 2SV-8263-2 2 .E-7 A-1 2 GL 5 <2 C C FE,FS PI,LJ GR-1, GR-4 FE,FS,PI.LJ l

E-6' A-1 2 GL S <2 C C FE,FS,PI,LJ GR-1, GR-4 FE,FS,PI,LJ I 2SV-8265-1 2 2SV-8271-2 2 F-7 A-1 2 GL 5 <2 0 C FE,FS,PI,LJ GR-1, GR-4 FE,FS,PI,LJ 2SV-8273-1 2 F-6 A-1 2 GL S <2 0 C FE,FS,PI.LJ GR-1, GR-4 FE,FS,PI.LJ 5

PAGE 67

Rev. 1-s I

I l

i 1

i l APPENDIX E 4'

VALVE INSERVICE TEST PROGRAM-j RELIEF REQUESTS i

i i

4

~;

i 3

i I .i

+

1 PAGE 68-i

Rev. 1 RELIEF REQUEST NUMBER EFW-1 System: Emergency Feedwater Valves: 2EFW-2A and 2EFW-2B Category: C-1 Class: 3 Function: Allows service water as emergency supply to steam generaters.

Impractical Test Requirements:

IWV-3521; Test Frequency-exercise at least once every three months.

Basis for Relief:

There is no means available to verify the disc in valves 2EFW-2A and 2EFW-2B moves promptly away from the seat when the closing differential is removed and flow through the valve is initiated. Furthermore, partial or full stroke exercising of these v61ves during power operation or cold shutdown would introduce water of unacceptable chemical quality into the secondary coolant.

Alternative Testing:

The alternative testing performed on these valves meet GL 89-04, Position 2 requirements. Valves 2EFW-2A and 2EFW-2B have been disassembled and manually exercised with no discernable degradation. When the valve is disassembled, the valve internals are visually inspected for worn or corroded parts. One of these valves will be inspected each refueling outage, alternating between the valves. If problems are found, repairs will be made and the other valve shall also be inspected unless a common-mode failure mechanism can be dismissed.

PAGE 69

l 1

Rev. 1 RELIEF REQUEST NUMBER SGS-1 System: Steam Generator Secondary Valves: 2MS-39A and 2MS-39B Category: C-1 Class: 3 Function: Steam supply to the Emergency Feedwater Pump Turbine and prevent reverse flow back to steam generator.

Impractical Test Requirements:

IWV-3521; Test Frequency-exercise at least every three months.

Basis for Relief:

Valves 2MS-39A and 2MS-39B are full stroke exercised open at least every l three months during testing of the emergency feedwater pump turbine, but there is no means available to verify the disc in these valves travels promptly to the seat or, cessation or reversal of flow.

Alternative Testing:

The alternative testing performed on these valves meets GL 89-04, Position 2 requirements. Valves 2MS-39A and _2MS-398 have been disassembled and manually exercised with no discernable _ degradation.

When the valve is disassembled, the valve internals are visually-inspected for worn or corroded parts. The closed safety position of these valves is verified by this inspection. One of these valves will be inspected each refueling outage, alternating between the valves. If problems are found repairs will be made and the other valve shall also be inspected unless a common-mode failure mechanism can_be dismissed.

PAGE 70

Rev. 1 RELIEF REPORT NUMBER SW-1 System: Service Water Valves: 25W-12A and 25W-128 Category: C-1 Class: 3 Function: Allow service water flow from the shutdown cooling heat exchangers.

Impractical Test f.aquirements:

IWV-3521; Test Frequency-exercise at least every three months. <

Basis for Relief:

There is no means available to verify the disc in ' valves 25W-12A' and 25W-128 moves promptly _away from the _ seat to the_ full open position.when the closing- differential is removed--and flow through; the valve .is - '

initiated.

Alternative Testing:

The alternative testing performed < oni:these valves meets GL 89-04, Position 2 requirements. Valves-25W-12A and 25W-12B will be. disassembled and manually exercised. When the valve:'is .- disassembled,- the-- valve in_ternals:- are visually -inspected for worn or corroded . parts. One of

. these valves will be' inspected _each refueli.ng outage, alternating between-l the valves. If problemsiare found repairs'wil'.~be made and_-the remaining valve be shall.also dismissed. These.be inspected valves-areunless:a common-mode also quarterly failure par _tial'~ stroke tested.- mechanism-can -

=l

(-

i l'

P GE 4

= . ~.-:..-. .- . - - - -- -.. - - - _

Rev. 1 RELIEF REQUEST NUMBER RC-1 System: Reactor Coolant Valve: 251-27A, 251-278, 2SI-28A and 251-288 Category: AC-1 Class: 1 function: Prevent, reversal of reactor coolant flow into a lower pressure system and allows flow during long-term core cooling to prevent boron precipitation.

Impractical Test Requirement:

lWV-3422; Test Frequency -

Category A valves shall be leak tested at least once every two years.

IWV-3521; Test frequency - exercise at least once every three months.

Basis for Relief:

The absence of isolation valves on the downstream side does not allow individual leak rate testing of these valves. The low pressure side of these valves are monitored for back leakage. Furthermore these valves cannot be full-stroke exercised durir.g power operation because the high pressure injection pumps' maximum discharge pressure is less than the reactor coolant system pressure during normal operation. Full stroke exercising during cold shutdown is impractical because the reactor coolant system lacks expansion volume to accomodate this large volume of water, tlso the reactor vessel pressure-temperature limitations may be exceeded.

Alternative Testing:

The alternative flow testing meets the requirements of GL 89-04, Position

1. ANO will monitor the low pressure side of these valves for indication of back leakage by observing press _ure indicators 2PI-5105 and 2PI-5106 on a frequency of at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Furthermore, these valves - l will be full-stroke exercised during refueling outages with- the reactor vessel head removed.

l PAGE 72 E -

Rev. 1 RELIEF REQUEST NUMBER S1-1 System: Safety Injection Valves: 2SI-7A, 251-78, 2SI-10A, 251-108, 251-100, 251-12, 2SI-13A, 251-138, 2S1-13C, 251-130, 2SI-26A, and 251-26B Category: C-1 and AC-1 Class: I and 2 Function: Various Impractical Test Requirement:

IWV-3521; Test Frequency - exercise at least once every three months.

Basis for Relief:

These valves cannot be full-stroke exercised during power operation because the high pressure safety injection pumps maximum discharge pressure is less than the reactor coolant system pressure during nermal operation. Full-stroke exercising during cold chutdown is impractical because the reactor coolant system lacks adequate- expansion voluma to accommodate this large volume of water, also the reactor vessel pressure-tempera +.ure limitations may be exceeded.

Alternative Testing:

The alternative flow testing performed' on these valves meets the requirements of GL 89-04, Position 1. These valves will be full-stroke exercised during refueling outages with the reactor vessel head removed.

PAGE 73 4

Rev. 1 RELIEF REQUEST NUMBER SI-2 System: Safety Injection Valves: 2SI .15A, 251-158, 251-150, 251-150, 2SI-16A, 251-16B, 251-16C, and 251-160 Category: 1 Function: Various Impratical Test Requirement:

IWV-3521; Test frequency - exercise at least once every three months.

Basis for Relief:

These valves cannot be full stroke tested during power operation because the high pressure safety injection pumps and safety injection tanks maximum discharge pressure is less than the reactor coolant system pressure during normal operation. Due to the time it takes the safety injection tank MOV's to oper, there is no way to establish maximum accident flow through these valves. 2SI-15A, 251-158, 251-150, and 251-150 cannot be partial stroke tested during cold shutdowns due to low termperature over pressurization concerns.

Alternative Testing:

These valves will te disassembled and stroke tested during refueling.

outages i r, accordanue with the requirements of GL 89-04, Position 2.

Alternating pairs of these valves will be disassembled during each refueling outage. 2SI-16A, 251-16B, 2SI-16C, and 2SI-16D ' are quarterly partial stroke tested.

l PAGE 74 l

Rev. 1 RELIEF REQUEST NUMBER CS-1 System: Containment Spray l

Valves: 2BS-1A, 285-1B Category: C-1 Class: 2 Function: Provides a flow path from refueling water tank to containment spray pumps and prevents reversal of flow f rom . a higher pressure system, j Impractical Test Requirement:

l IW-3521; Test Frequency - exercise at least once every three months.  !

j Basis for Relief:

1-

' Full-stroke exercising these val _ ve s during power. operation or cold shutdown would require the simultaneous operation of; one high: pressure' l safety injection pump, one low prescure safety injection pump - and: one j containment spray pump at design accident flow rates. During power operation, th_e discharge pressure of the> High Pressure Safety- Injection pump and Low Pressure . Safety Injection- pump is less than1RCS pressure.  !

During cold shutdowns, -there is insufficient RCS : volume- to allow'

concurrent - operation of the - High t- Pressure

and z Low ' Pressure - -Safety _

j

[ Injection pumps.  !

L Alternative Testing:

[

E .The alternative testing- performed.- on- these valves 'me'ets ~ GL' 89-04,-

Position 2 requirements.- .Th_e se valves have:.been disassembled- and manually exercised with no L decernable degradation.. When . the valve is- -j

disassembled, . the valve internals are : visually-: inspected _ for worn or.

[ corroded parts. . One of -these valves -will: be_ inspected -each refueling 1 outage, alternating between the. valves. If problems :are- found, repairs -

! will be made and -the other valve shall 'also bed inspected l unless a l_ common-mode failure can be -dismissed.- These valves are . partial /strokei

tested quarterly.-

{

a

!' {

r

.m 1

l t A

.PAGEc75:

o

Rev. 1 RELIEF REQUEST NUMBER CS-2 System: Containment Spray Valves: 2BS-SA and 2BS-5B Category: C-1 Class: 2 Function: Containment spray discharge header check valves and maintain the. spray headers-full of spray water..

Impractical Test Requirement:

IWV-3521; Test Frequency - exercise at least once every three months.

Basis for Relief:

Full'or partial-stroke exercising of these valve during power

-operation-or cold shutdown would result in spraying the containment, with possible. damage to plant equipment.-

Alternative Testing:

The alternative _ testing performed on these valves meets GL 89-04,.

Position 2 requirements.1 Valves 2BS-5A and 285-5B-have been i disasser. led and manually exercised with no' discernable degradation.

- When the valve is disassembled,~the valve internals are visually inspected for-worn oricorrodediparts. -One of-these valves will be' inspected each refueling outage, alternating between the. valves. LI f-problems are found, repairs will belmade and theeremaining' valve shall also be inspected unless a-common-mode-failure mechanism can be dismissed.

l -.

e -

l o

I:

l f

l-

, . PAGE'76-I" '

P1 S 4 T y*tPew F W  ??#$1@ '

'MN" T*"-"y""-+9" $-*-T T 9"" @T 9- " V '"I"F'4 T & Y *P4'^9di W* -W M E'W-IO-#--"#"- ***

Rev.-1 RELIEF REQUEST NUMBER GR-1 System: As Applicable Valves: As applicable Category: A, B Class: As Applicable Impractical Test Requirement:

IWV-3300; Valve Position Indicator Verification-valves with remote position indicators shal' .5 served at least once every two years to verify that valve operatior curately indicated.

Basis for Relief:

These enclosed solenoid valves would require disassembly of the actuator components to verify operation.

Alternative Testing:

ANO will monitor system parameters to verify an enclosed solenoid valve's-safety function. This monitoring will be performed at least once every two years.

j PAGE 77 l

l

Rev. 1 RELIEF REQUEST NUMBER GR-2 System: As Applicable Valves: Valve Test Tables Category: A and AC Class: As Applicable l Function: As Applicable Impractical Test Requirements:

IWV-3427(b); Corrective Action - for valves 6 in, nomical pipe size and larger, if a leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin between measured leakage ratt and the maximum permissible rate by 50% ar greater, the test frequency shall be double.

Basis for Relief:

Based on historical data, it is our position that the leakage rates for l valves 6 in, and largar do not show enough consistency in the level of degradation prior to reaching the maximum leakage limit to justify maintaining these additional corrective action and trending requirements.

This is in keeping with ASME-approved OM-10 philosophy on Inservice Testing of Valves, which does not require trending of leakage rates.

Generic Letter 89-04, Position 10, concurs with this basis.

Alternative Testing:

Valves will be replaced or repaired as required when the- leakage rate

, exceeds that stated in AN0 Technical Specifications, or as identified by the Owner (once evaluation is performed) for those valves without AND Technical Specification leakage limits.

l PAGE 78

Rev. 1 RELIEF REQUEST NUMBER GR-3 System: All Valves: All Class: All Function: As Applicable Impractical Test Requirements:

ASME Section (IWV-3417b and IWV-3523) states that when corrective 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 shall be declared inoperative. In the event of testing during cold shutdown, the condition shall be corrected prior to startup.

Basis for Relief:

The ANO lechnical Specification ' limiting conditions for operations, and ASME Sectior. XI, provide the controls by which valves and system are declared inoperative. AND Technical Specifications also control entry into various operational conditions, which is generally more restrictive.

Failure to meet Section XI testing criteria should not, therefore, preclude plant startup with the particular component inoperable, nor should the declaration of component or system inoperability 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 ANO Technical Specifications.

Alternative Testing:

If the valve can be repaired and retested during startup, then startup will continua provided that LCOs of the Tech Specs allow startup with the valve inoperable. If a valve requires corrective action and cannot be repaired and retested during plant startup, then it shall be repaired and retested prior to plant startup.

PAGE 79 1

_ __._ a

Rev. 1 RELIEF REQUEST NUMBER GR-4 System: As Applicable Valves: All fast-acting valves with a stroke time less than or equal tc two seconds.

Category: A, B Class: As Applicable Function: As Applicable Impractical Test Requirements:

ASME Section XI IWV-3417(a) requires a comparison of the most recent stroke time measurement with that of the previous test.

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 small increase in stroke time will result in an extremely large percentage of change. Verification that these valves meet a specified maximum stroke time of a relatively short duration, should provide adequate assurance of operability.

Alternative Testing:

When stroke times of rapid acting valves are measured, the criterion'for determining acceptability will be the specified maximum stroke time of

-two seconds. LActual trending or measurement of rapid acting valve stroke times will not be made other than confirmation that they stroke less than two seconds.

i l

l l

l PAGE 80

Rey, 1 APPENDIX F COLD SilUTDOWN TESTING

. JUSTIFICATIONS ,

PAGE 81

Rev. 1 VALVES TESTED AT COLD SHUTDOWN System Valves Justification Steam Generator 2CV-1010-1 Cycling these valves during power Secondary (Main Steam) 2CV-1060-2 operations would result in loss of steam flow to the main turbine- causing plant transients leading to reactor trip. In addition, recent evidence indicates that stroking these valves with high steam flow greatly contributes to seat damage and resulting containment isolation

, failures. These ' valves do receive monthly partial stroke testing, which verifies operator condition.

Steam Generator 2CV-1023-2 Cycling these valves- during -power Secondary (Feed Water) 2CV-1024-1 operations would interrupt normal flow 2CV-1073-2 to the-steam generator resulting in loss 2CV-1074-1 of level and reactor-trip.

2FW-5A 2FW-5B 4 i

Service Water 2CV-1425-1 Cycling _ these valves during power 2CV-1427-2 operation would -interrupt the cooling flow to the turbine generator support system resulting- in. a turbine generator and reactor trip.

Chilled Water 2CV-3850-2 Cycling the3e valves:during power 2CV-3851-1 operation would: interrupt - thei cooling-2CV-3852 water flow 'to- the Control Element Drive Mechanisms. The Control . Element Drive Mechanisms would have to be_de-energized-to prevent - --_ damage ' f rom. overheating _

during _ periods- wi_ thout -_ cooling -- and-  !

de-energization i of ;the - Control . Element .

Drive Mechanisms-would result-in. reactor--

shutdown'.

i i

-PAGE 82'

= -

- _-_n

Rev.-1 VALVES TESTED AT COLD SHUTDOWN System Yalru Justification Reactor Coolant System 2CV-4698-1 Cycling of these valves during power 2CV-4730-1 operation could cause a potential 2CV-4731-2 loss of a RCS pressure boundary and a 2CV-4740-2 subsequent loss of integrity. 4 2CV-4741-1 2SV-4636-1 2SV-4636-2 2SV-4668-1 2SV-4668-2 2SV-4669-1 2SV-4670-2 Chamical and Volume 2CV-4820-2 Cycling of-- these valves during power Control 2CV-4821-1 operation would necessitate that-letdown 1 2CV-4823-2 and charging be secured. Reestablishing-

, 2CV-4873-1 charging and'Lletdown causes unnecessary pressure an_d temperature transients.-

Chemical and Volume 2CV-4824-2 These valves cannot be-exercised opened Control 2CVC-28A during power operation because such action would subject the spray line nozzles to- thermal shock at- the-

-pressurizer.. Also, this would cause-unne<:es sary temperature and; pressure transients as well. as an! undesirable cooling-of the pressurizer.

Chemical and Volume- 2CV-4950-2-- These valves cannot be. exercised-.during-.

Control 285-6= power - operation without over - borating--

2CVC-41A- the reactor 1 coolant system resulting -in-2CVC-41B reactor shutdown.--

2CVC-49--

2CVC-58 2CVC-70 k

PAGE 83:

I w _A

Rov. 1 VALVES TESTED AT COLD SHUTDOWN System Valves Justification Chemical and Volume 2CV-4846-1 These valves-cannot be exercised during Control 2CV-4847-2 power. operation _without interrupting reactor coolant pump seal bleed-off flow reducing RCP seal reliability.

Safety In.iection Cycling these valves during power 2CV-5084-1 2CV-5086-2 operations is not possible because they are interlocked snut with RCS pressure above 300 psia.

Safety Injectica 2SI-3A Cycling.these valves during power 2SI-3B ' operation is impractical because the- ,

-2SI-14A HPSI pumps wil? not overcome - reactor 251-148_ coolant system pressure.

2SI-14C 2SI-14D Component Cooling 2CV-5236-1 _ Cycling these valves during power.

Water 2CV-5254-2 operation would interrupt _ cooling water 2CV-5255-1 to the reactor coolant' pumps.- Operating-procedures prohibit. operation of. the RCps without Ecooling _ water- flow. , A reactor ' trio will occur--if any RCP is:

secured..

Air Flow and Control =2CV-8283-1. The :plantlTechnical! Specification, HVAC Containment '2CV-8284-2 3.6.1.6, requires _ these valves =-toDbe=

Building -2CV-8285 closed'in modes 1, 2; 3 and14.-

2CV-8286-2 2CV-8289-1 ,

2CV-8291 s

. Chemical'and-Volume 2CVC-28B- Opening these valves with- fu11Eflow..to

-Control 2CVC-28C the RCS.during power operation would,

, result in a significant increase :in l pressurizer level. JThe resu~1tingL upset:

of the pressurizer. Level _ Contro11 System-would cause-- excessive . temperature; and pressure? transients Jin J Letdown ~ Sy tem -

piping.. -

i-PAGE:841

.1

t Rev. 1 VALVES TESTED AT COLD SHUTDOWN Lulem Valves Justification Containment Spray 2BS-12A Opening these valves with full flow to 285-128 the Containment Spray System would contaminate water used for safety injection and shutdown cooling with Sodium Hydroxide. This would lead to significant corrosion of reactor intet-nal components.

PAGE 85

\ 3