ML20065D002

Rev 6 to SO23-V-3.4, Inservice Testing of Pumps Program

ML20065D002
Person / Time
Site:	San Onofre
Issue date:	04/01/1994
From:	SOUTHERN CALIFORNIA EDISON CO.
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Shared Package
ML20065C993	List: ML20065C990 ML20065D002 ML20065D005
References
SO23-V-3.4, NUDOCS 9404060160
Download: ML20065D002 (46)

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ENCLOSURE 1 PROCEDURE S023-V-3.4, INSERVICE TESTING OF PUMPS i

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• 28a s 32888 P pg 6

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4' UNITS 2 AND 3- .

REVISION 6 PAGE I 0F 45 COMFi.ETE REVISION APR 0 f 19K EFF".CTIVE DATE W(Tly(9 q,,

. 'U 1 1994 INSERVICE TESTING OF PUMPS PROGRAM ' <//t yLL vo;n TABLE OF CONTENTS SECTION PAGE 1.0 OBJECTIVES AND SCOPE 2

2.0 REFERENCES

3 3.0 PREREQUISITES 6 4.0 PRECAUTIONS 7 7

5.0 CHECKLIST (S) 6.0 PROCEDURE 8 6.1 ferminology 8

6. '; Reference Information 9 63 Design Requirements 9 6.4 Test Requirements 9 6.5 Testing Methods 14 6.6 Analysis and Evaluation 18 7.0 RECORDS AND REPORTS 20 7.1 Pump Records 20 7.2 Inservice Test Plans 20 7.3 Records of Tests 21 7.4 Record of Corrective Action 22 7.5 Program Calendar and Test. Status 22 ATTACHMENTS I Acceptable Instrument Accuracy 23 2 Inservice Test Parameters 24 3 Ranges For Test Parameters 25 4 Pumps Tested Within The Inservice Testing Program 27 5 Pumps Requiring Response Time Measurement 30 6 EG(123) 53, Inservice Pump Test Record Key Points 31 7 Summary of Current Test Status 37 8 Pump Relief Request No.12 as Submitted To The NRC 38 9 Pump IST Evaluation Flow Diagram 40 10 Minimum Pump Performance to Achieve Safety Analysis Compliance 44 9

9 23V34R6.W51 QA PROGRAM AFFECTING

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 2 0F 45 INSERVICE TESTING OF PUMPS PROGRAM 1.0 OBJECTIVES AND SCOPE 1.1 This Program Procedure establishes the requirements for San Onofre preservice and inservice testing to assess the operational readiness of certain centrifugal and positive displacement pumps used in Units 2 and 3 in accordance with.the requirements of Reference 2.1.2.

[Ref. 2.1.7, Para. 1.1]

1.1.1 Test results are used ir, assessing operational readiness of pumps during their service life to perform a specific function in shutting down the reactor, bringing it-to cold shutdown or in mitigating the consequences of an accident.

1.2 This Program Procedure identifies the pumps, establishes test -

intervals, parameters to be measured and evaluated, acceptance criteria, corrective action, and records requirements. This guidance is used in the implementing procedures, References 2.3.1 through 2.3.11. These procedures shall be used for the various pump. inservice tests. [Ref. 2.1.7, Para. 7.2]

1.3 This Program Procedure provides the requirements for response time testing of pumps in the IST Program. This testing is required by the Technical Specifications, Section 3.3.2, ENGINEERED SAFE 7Y FEATURE ACTUATION SYSTEM INSTRUMENTATION. Specific acceptance criteria are identified from Reference 2.3.16.

1.4 Scope l.4.1 The pumps covered in this piogre are those, provided with an emergency power source, which are required in shutting i down a reactor to the cold shutdown condition, maintaining l the cold shutdown condition', or in mitigating the consequences of an accident. [Ref. 2.1.7, Para. 1.1] l l

1.4.2 Components-subject to the Inservice Testing Program for  ;

Pumps in accordance with reference 2.1.7 are identified in Attachment 4. Attachment 4 also identifies the parameters to be measured for each pump and the test frequency (additional information is provided by means of notes in Attachment 4 also). Pump Relief Request No. 12 is provided in Attachment 8.~ This is the only pump relief request currently issued for this program. Parameters required to be measured during the Inservice Tests are i identified in Attachment 2.

1.4.3 This Procedure may include the testing of components in addition to those listed in accordance with References 2.5.1 and 2.1.6 (Paragraph IWA-1200), but shall, as a minimum, require testing of at least all of the components (meeting the above scope description) in those references.

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVlSION 6 PAGE 3 0F 45 1.0 OBJECTIVES AND SCOPE (Continued) 1.4.4 ~0ur strategy for determining the pump IST program scope and implementation of the recommendation of the NRC in Reference 2.1.5, Attachment 1, Position 11 includes-planned and systematic reviews of design changes by the Nuclear Engineering Design organization (NEDO) System Design Engineers (SDE) with a backup review by the IST Coordinator, see Reference 2.3.18.

.1 Additional information and criteria used for determining IST Program scope is included in References 2.5.1, 2.1.7, 2.1.5,-2.5.2 and Regulatory Guide 1.26. Engineering judgement and prudence are applied when reference criteria are not directly applicable.

1.5 Exclusions' l.5.1 The following are excluded from the scope of this program provided that the pumps are not required to perform a specific function as discussed above (Ref. 2.1.7, Para. 1.2):

.1 drivers, except where the, pump and driver form an integral unit and the pump bearings are in the driver;

.2 pumps that are supplied with emergency power solely for operating convenience.

1.6 The Inservice Testing of Pumps Program delineated herein covers a ten (10) year interval commencing on August 18, 1993, implemented on approximately April 1, 1994, and terminating on August 17, 2003.

, 1.7 Resoonsibilities for the Procram 1.7.1 In accordance with Reference 2.2.1, The Manager, Station Technical Division is responsible for this program and its implementation at the San Onofre Site.

2.0 REFERENCES

2.1 NRC Commitment (s) 2.1.1 10CFR50, 9 50.55a, Codes and Standards 2.1.2 Units 2 and 3 Technical Specification 4.0.5, (

Subject:

Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components) 2.1.3 Technical Specifications, Units 2 and 3, Section 1.0 DEFINITIONS.

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 4 0F 45

2.0 REFERENCES

(Continued) 2.1.4 Topical Quality Assurance Manual (TQAM), Chapter 7, ASME Code Program Scope, Responsibilities and Program Controls, Rev. 7, September 24, 1992 2.1.5 NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing programs, April 3,1989.

2.1.6 ASME Boiler and Pressure Vessel Code,Section XI,1989 Edition (July 1,1989), Rules for Inservice Inspection of Nuclear Power Plant Components 2.1.7 ASME/ ANSI OH-1987, Operation and Maintenance of Nuclear Power Plants, Part 6, Inservice Testing of. Pumps in Light-Water Reactor Power Plants (including ASME/ ANSI OMa-1988 ADDENDA to ASME/ ANSI OM-1987, C9eration and.

Maintenance of Nuclear Power Plants, and, ASME/ ANSI-OMb-1989 ADDENDA to ASME/ ANSI OM-1987, Operation and Maintenance of Nuclear Power Plants) 2.1.8 Draft NUREG 1482, Guidelines for Inservice Testing at Nuclear Power Plants, November 1993 2.2 Order (s) ,

2.2.1 S0123-IN-1, Inservice Inspection Program 2.3 Procedure (s) 2.3.1 5023-V-3.4.1, Auxiliary Feedwater Inservice Pump Test 2.3.2 S023-V-3.4.2, Component Cooling Water Inservice' Pump Test 2.3.3 S023-V-3.4.3, Diesel fuel Transfer Inservice Pump Test 2.3.4 S023-V-3.4.4, High Pressure Safety. Injection Inservice Pump Test 2.3.5 S023-V-3.4.5, Low Pressure Safety Injection Inservice Pump Test 2.3.6 S023-V-3.4.6, Containment Spray Inservice Pump Test 2.3.7 S023-V-3.4.8, Saltwater Cooling Inservice Pump Test 2.3.8 5023-V-3.4.9, Emergency Chill Water Inservice Pump Test 2.3.9 S023-V-3.4.10, Boric Acid Makeup Inservice Pump Test 2.3.10 S023-V-3.4.ll, Reactor Charging Inservice Pump Test 2.3.11 5023-V-3.4.13, Component Cooling Water Makeup Pump Inservice Pump Test

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 5 0F 45

2.0 REFERENCES

(Continued) 2.3.12 50123-V-5.21,~ VISION PC Based Pump Inservice Test Monitoring .

2.3.13 S0123-V-5.15, Inservice Testing (IST) Coordination,and Trending 2.3.14 S0123-VI-1.0.3, Methods of llandling -Invalid Steps / Sections 2.3.15 S0123-XV-5, Nonconforming Material, parts or Components 2.3.16 S023-XV-6, Technical Specification Response Time Surveillance Implementing Procedure Master List 2.3.17 50123-XXI-1.11 11, Engineering Training and Qualification Program Description -

2.3.18 S0123-XXIV-10.15, Preparation Review and Approval of Facility Change Evaluations (FCE's) for SONGS 1, 2 and 3 (including the Site Procedures Impact Assessment. Form .26-404) 2.4 Operatina Instructions 2.4.1 S0123-0-20, Use of Procedures 2.4.2 S0123-0-23, Control of System Alignments 2.5 Other 2.5.1 Inservice . Testing Topical Report, Design Bases Document, DBD-5023-TR-IS2, Rev. 0, August 21,.1993 2.5.2 Letter, J. G. Partlow, NRC, to All Licensees, etc, Minutes I of the Public meetings on Generic Letter 89-04, October 25, 1989.  !

1 2.5.3 Meno, P. Croy to Cognizant Supervisors and Cognizant Engineers, Vibration Velocity Measurement and Evaluations During inservice Testing of Pumps, February 3,1992 2.5.4 EG(123)53,InservicePumpTestRecord' 2.5.5 Letter, W. C. March to USNRC, ASME Code ~ Update for the Second Ten-Year Interval, Inservice Testing Program, August 17, 1993

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1 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6- PAGE 6 0F 45

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3.0 PRERE0VISITLS  ;

NOTE: Reference to SDMS, ON-LINE, with a PC is the preferred method to verify which version of the Procedure and TCN's are current.

I CAUTION COM-SONGS Controlled copies are updated as soon as their  :

resources permit, however, this might sometimes mean that  !

controlled copies in the Technical Library, for example, are-several days late getting updated. This is not the case with the on-line SDMS system.

I 3.1 Prior to use of a user-controlled copy of this document, it is the user's responsibility to verify the revision and any TCNs are current by using one of the following methods: I 3.1.1 Access the San Onofre Document Management System (SDMS)

[ San Onofre local area network (SLAN) or online system]-

(preferred methods).

3.1.2 Check it against a Corporate Documentation l Management-SONGS (CDM-SONGS) controlled copy and any TCNs. l 3.1.3 Contact CDM SONGS by telephone or through counter inquiry.

3.1.4 Obtain a user-controlled copy of this procedure from CDM-SONGS or SOMS SLAN.  !

l 3.2 'The implementing procedures (References 2.3.1 through 2.3.11) should be updated, as necessary, prior to the next test involving the changed information in the program. The Managers of Operations, and Maintenance shall receive a copy of the revision from the IST Coordinator to serve as notification of a revision.

3.3 Instrumentation used for Inservice Testing shall meet the requirements of ASME Code,Section XI and OM-6. See Section 6.4.6, Below.

3.3.1 Prior to commencing an Inservice Test, the Engineer conducting the test shall ensure that required

instrumentation, both installed plant instrumentation and Measuring and Test Equipment, is available, calibrated and calibration date not expired.

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NUCLEAR ORGAN!ZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 7 0F 45 3.0 PRERE0UISITES (Continued)

NOTE: The Maintenance Division procedures allow a 25 %

calibration interval extension to be applied to the calibration due date. Where instruments used for IST are in this "25 % grace period" these instruments are acceptable for IST.

3.3.2 The Engineer conducting the test shall verify that instrumentation meets the range and accuracy requirements of ASME Code,Section XI, OM-6, and Pump Relief Request No.'12 (see Attachment 8). See Paragraph 6.4.6, below.

This is required for each new instrument or loop (CFMS, temporary instruments, etc.) used if not done and documented previously.

3.4 Reference Data: It is recommended that reference data on the pump under test be available in.the field during the performance of the .IST to facilitate initial evaluation of test results.

4.0 PRECAUTIONS 4.1 Testing required in this program procedure shall not be conducted in Modes or under circumstances that place the Plant in an unsafe condition. Likewise, care shall be exercised that no test will be conducted so a failure of the test would put the plant in an unsafe condition.

l l 4.2 Special care must be exercised to ensure that the allowed test

! interval is not exceeded. For pumps routinely tested at one or three month intervals, a test interval extension is allowed. .This extension shall not exceed twenty-five percent of the test interval.

4.2.1 The twenty-five percent (25%) interval extension is allowed to accommodate plant conditions that may not be suitable for conducting a surveillance.(such as transient conditions or other surveillance in progress). It also provides flexibility for refueling interval surveillance.

Consequently, the twenty-five percent extension is not to be viewed as a routine scheduling tool. It is for exceptional situations only.

5.0 CHECKLIST (S) 5.1 None l

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NUCLEAR ORGANIZATION ENG1NEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 8 0F 45 6.0 PROCEDURE 6.1 Terminoloav NOTE: Terms defined in this section correspond to Reference 2.1.7, Para. 1.3. The consistency with this Reference provides a common basis for understanding among ourselves, as the owner, the ASME documents with which we must comply and the individuals who audit our program, such as the NRC, ANII, etc.

6.1.1 Inservice Test - a test to determine the operational readiness of a pump.

6.1.2 Instrument Accuracy - the allowable ' inaccuracy of an instrument loop based on the square root of the sum of the squares of the inaccuracies of each instrument or component in the loop.

6.1.3 Instrument Loop - two or more instruments or components working together to provide a single output (e.g., a vibration probe and its associated signal conditioning and readout devices).

6.1.4 Operational readiness - the ability of a pump to perform its intended function.

6.1.5 Preservice test period - the period of time following completion of construction activities related to the pump, and prior to first electrical generation by nuclear heat in which component and system testing takes place.

6.1.6 pump - a mechanical device used to move liquid.

6.1.7 reference values - one or more values of test pare. meters measured or determined when the equipment is known to be operating acceptably.

6.1.8 routine servicing - the performance of planned, preventive maintenance (e.g., replacing or adjusting valves in a reciprocating pumps, changing oil, flushing the cooling system, adjusting packing, adding packing rings or mechanical seal maintenance or replacement).

6.1.9 system resistance - the hydraulic resistance to flow in a system.

6.1.10 SRO Operations Supervisor - Any Operations individual holding an SR0 license (active or inactive) who has qualified to the position of Shift Superintendent or Control Room Supervisor [See 2.4.1, Attachment 1, Definitions].

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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE' S023-V-3.4 -l UNITS 2 AND 3 REVISION 6 PAGE 9 0F 45 l I

6.0 PROCEDURE (Continued) l 6.1.11 Test Interval - This program uses the same test interval definitions as those used in the Technical Specifications, namely, one month is defined as 31 days and one quarter is i defined as 92 days.[Ref. 2.1.3].

6.2 Reference Information 6.2.1 Cetection of Change: The hydraulic and mechanical condition of a pump relative to a previous condition can be determined by attempting to duplicate by test a set of reference values. Deviations detected are symptoms of changes and, depending upon the degree of deviation, indicate need for further. tests or corrective action. 1

[Ref. 2.1.7, Para. 2.1] j 6.3 Desian Reouirements 6.3.1 Owner's Responsibility. -

.1 Design changes shall include in both the puap and plant design all necessary valves, instrumentation test loop, required fluid inventory, or other provisions which are required to fully comply with the rules' of this program procedure. [Ref. 2.1.7, Para. 3.1(a)]

.2 Each pump to be tested in' accordance with the rules of I this program procedure is identified in Attachment 4.

[Ref. 2.1.7, Paras. 3.l(b) and 7]

6.3.2 Bypass Loops

.1 Bypass test loops (sometimes called miniflow lines or miniflow recirculation lines) are used on certain pump tests identified in the program procedure, see Attachment 4. Pump bypass loops shall be designed to accommodate the pump manufacturer's operating conditions for minimum flow operation. [Ref. 2.1.7, Para. 3.2]

6.4 Test Reouirements NOTE: Since this is the second IST interval (second 120 months),

preservice testing applies to newly added design changes.

6.4.1 Preservice Testing: Each pump shall be tested during the preservice test period. This testing shall be conducted under conditions as near as practicable to those expected during subsequent inservice testing. Only one preservice test of each pump is required, except that the requirements of 6.4.4, below shall be met. [Ref. 2.1.7, Para. 4.1]

NUCLEAR ORGAfdZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PftGE 10 0F 45 6.0 PROCEDURE (Continued) 6.4.2 Inservice Testing: Inservice Testing in accordance with this program procedure shall commence when the pump (s) is required to be operable. [Ref. 2.1.7, Para. 4.2]

6.4.3 Reference Values: Reference values shall be determined from (1) theresultsofpreservicetesting,(2) from the results of the first inservice test (following initiation of this program), or alternatively, (3) from the results of the previous reference inservice or preservice test (conducted prior to implementation of the second 120 month IST interval, provided the correct parameters and acceptance criteria were applied to comply with the currentprogramprocedure). [Ref.2.1.7, Para.4.3]

.1 Reference values shall be at points of operation readily duplicated during subsequent tests.

.2 All subsequent test results shall be compared to these initial reference values or to new reference values established in accordance with 6.4.4, below, or, 6.4.5, below.[Ref.2.1.7, Para.4.3]

.3 Reference values shall only be established when the pump is known to be operating acceptably.

.4 If the particular parameter being measured or determined can be significantly influenced by other related conditions, then these conditions shall be analyzed.

.5 To doc'iment the new reference in the VISION software program, use the " Comments" field during the upload section of the test. See Reference 2.3.12 for more information.

.6 Prior to establishing an additional set of reference values, the Cognizant Engineer shall inform the IST Coordinator. This notification is necessary so that the VISION software program, Reference 2.3.12, is updated with a new route specifically designed for the new (additional) reference condition.

NOTE: Vibration measurements of pumps may be foundation, driver, and piping dependent.

Therefore, if initial vibration readings are high and have no obvious relationship to the pump, then vibration measurements should be taken at the driver, at the foundation, and on the piping and analyzed to ensure that the reference vibration measurements are representative of the pump and that the measured vibration levels will not prevent the pump from fulfilling its function.

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l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 11 0F 45 l

I 6.0 PROCEDURE (Continued) 6.4.4 Effect of Pump Replacement, Repair, and Maintenance on l Reference Values i

.1 When a Reference value or set of values may have been ,

affected by repair, replacement, or routine servicing of a l pump, a new reference value or set of values shall be I detemined or the previous value reconfimed by an inservice test run prior to declaring the pump operable.  !

[Ref. 2.1.7, Para. 4.4]

.2 Deviations between the previous and new set of Reference values shall be identified. ,

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.2.1 Whenever an additional set of reference values is established, the reasons shall be fully explained and  ;

1 documented.

.2.2 The Cognizant Engineer conducting the test shall verify that the new values represent acceptable pump operation and shall document this in the IST files for that pump.

.1 Use the " Documentation of New Reference" provided in l

each Pump 2.3.11). Ref.[ 2.1.7, Test Procedure Paras 4.4 (References and 7] 2.3.1 through

{ 6.4.5 To Establish an Additional Set of Reference Values

! .1 If it is necessary or desirable, for some reason other than stated above to establish an additional set of Reference values, an inservice test shall first be run at the conditions of an existing set of reference values and ,

the results analyzed. If operation satisfies the i applicable acceptance criteria, a second test run at the new reference conditions shall follow as soon as practicabic. The results of this second test constitute as acceptable additional set of Reference values.

l NOTE: If an additional set of Reference values is being established under this section, the previous quarterly test (when the satisfactorily) pump may was known be used as to thebefirst operating of the pair of ,

tests when establishing a new reference jf the Engineer provides an analysis showing that the pump performance trends indicate continued satisfactory pump condition.

l l .2 Paragraphs 6.4.4.2,6.4.4.2.1and6.4.4.2.2 apply.[Ref.

l 2.1.7, Para. 4.5]

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NVCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVIS10N 6 PAGE 12 0F 45 6.0 PROCEDURE (Continued) 6.4.6 Instrumentation

.1 General

.l.1 Quality: Instrument accuracy shall be within the limits of Attachment 1. Station instruments meeting these requirements are acceptable. [Ref. 2.1.7,- Para.~ 4.6.1.1)

.l.2 Range:

NOTE: Vibration instruments are excluded from the following two range requirements. [Ref. 2.1.7, Para. 4.6.1.2(c)]

.l.2.1 The full-scale range. of each analog instrument shall be not greater than three times the reference value.

[Ref. 2.1.7, Para. 4.6.1.2(a))

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.l.2.2 Digital instruments shall be selected such that the >

Reference value shall not exceed 70 % of the calibrated range of the instrument. [Ref. 2.1.7, Para. 4.6.1.2(b)]

.l.3 Instrument Location:

.l.3.1 The sensor location shall be established by the Owner, documented in the plant records, see Section 7.0, and shall be appropriate for the parameter being measured.

[Ref. 2.1.7, Para. 4.6.1.3]

.1.3.2 The same. sensor location shall be used for subsequent tests.

.l.3.3 Instruments that are position sensitive shall be either permanently mounted or provision-shall be made to

' duplicate their position during each test. [Ref. 2.1.7, Para. 4.6.1.3).

.l.4 Calibration: Instruments and instrument loops shall be calibrated in accordance with the program existing here at the SONGS station [ Responsibility: Maintenar.ce Division).

New or repaired instruments shall be calibrated prior to use in an inservice test. [Ref. 2.1.7, Para. 4.6.1.4)

.1.5 fluctuations: Symmetrical damping devices or averaging techniques may be used to reduce instrument fluctuations.

Hydraulic instruments may be damped by using gauge snubbers or by throttling small valves in instrument lines. [Ref. 2.1.7, Para. 4.6.1 5]-

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i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 l UNITS 2 AND 3 REVISION 6 PAGE 13 0F 45 1

6.0 PROCEDURE (Continued) 6.4.6.1.6 Frequency Response Range: The frequency response range of the vibration measuring transducers and their readout system shall be from one-third minimum pump shaft  ;

rotational speed to at least 1000 Hz. [Ref. 2.1.7, l j

Para. 4.6.1.6]..

.2 Pressure Measurement i

.2.1 Gage Lines: If the presence or absence of liquid in a i gage line could produce a difference of more than 0.25 % 4 in the indicated value of'the measured pressure, means l shall be provided to assure or determine the presence or i absence of liquid'as required for the static correction used. [Ref. 2.1.7, Para. 4.6.2.1] i

.2.2 Differential Pressure: When determining differential pressure across a pump, a differential pressure gauge, a  ;

differential pressure transmitter that provides direct measurement of pressure difference or the difference i between the pressure at a point in the' inlet pipe and the pressure at the point in the discharge pipe, may be used.

[Ref. 2.1.7, Para. '4.6.2.2)'  !

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.3 Rotational Speed Measurements: Rotational speed J measurements of variable speed pumps shall be taken by a I method which meets the requirements of Paragraph 6.4.6 and Attachment 1. [Ref. 2.1.7, Para. 4.6.3]

.4 Vibration Measurements 1 NOTE: All of the San Onofre Pumps in the Inservice Testing Program fall into three groups:

Centrifugal Pumps All pumps except those identified i

below Reciprocating Pumps Charging Pumps S2(3)1208MP190, 191 and 192 Vertical Line Shaft Salt Water Cooling Pumps Pumps S2(3)1413MP112, 113, 114 and 307, Diesel Fuel Oil Transfer Pumps 52(3)2421MP092, 093, 094, and 095,

, Containment Spray Pumps

! S2(3)1206MP012 and 013, and LPSI l Pumps S2(3)1204MP015 and 016 I

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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVIS10N 6 PAGE 14 0F 45 6.0 PROCEDURE (Continued) 6.4.6.4.1 On centrifugal pumps, measurements shall be taken in a plane approximately perpendicular to the rotating shaft in two orthogonal directions on each accessible pump bearing housing. Measurement also shall be taken in the axial direction on each sccessible pump thrust bearing housing.

[Ref. 2.1.7, Para. 4.6.4(a)]

.4.2 On vertical line shaft pumps, measurements shall be taken on the upper motor bearing housing in the three orthogonal directions, one of which is the axial direction.

[Ref. 2.1.7,-Para. 4.6.4(b)]

.4.3 On reciprocating pumps, the location shall be on the bearing housing of the crankshaft, approximately perpendicular to both the crankshaft and the line of plunger travel. [Ref. 2.1.7, Para. 4.6.4(c)]

.4.4 If a portable vibration indicator is used, the reference points must be clearly identified on the pump to permit subsequent duplication in both location and plane.

[Ref. 2.1.7, Para. 4.6.4(d)]

.4.5 The location of test points for individual pumps are shown in references 2.3.1 through 2.3.11. I NOTE: See Attachment 3 for Acceptance Ranges for l Vibration Parameters. I

.5 Flow Rate Measurement: When measuring flow rate, use a I rate or quantity meter installed in the pump test circuit. 1 If a meter does not indicate the flow rate directly, the record shall include the method used to reduce the data.

[Ref. 2.1.7, Para. 4.6.5]

6.5 Testina Methods I 6.5.1 Frequency of Inservice Tests:

.1 An inservice test shall be run on each pump, nominally every 1 or 3 months, except as provided in Paragraph 6.5.3, and 6.5.4 below. See Attachment-4 for details of pump testing frequency. (Ref. 2.1.7, Para. 5.1)

.2 Attachment 5 identifies certain pumps for which the response time must be measured at least every 24 months.

This measurement is part of the individual implementing procedures for affected pumps, references 2.3.1 through 2.3.11.

6.0 PROCEDURE (Continued)

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 15 Of 45 6.0 PROCEDURE (Continued) i l

6.5.1.3 This program uses the same test interval definitions as i those used in the Technical Specifications, namely, one i month is defined as 31 days and one quarter is defined as l 92 days. j NOTE: (1) Operability of a redundant pump must often be assured prior to testing the second pump. It is suggested that testing be done on a staggered basis, where possible.

(2) Compliance with Paragraph 4.2 is mandatory.

6.5.2 Test Procedure'

.1 The preferred method of data collection is using MICR0 LOG data collectors as outlined in Reference 2.3.12.

.2 The alternate method of obtaining measurements is to use an IRD instrument or equivalent with a hard copy of Form EG (123) 53, Inservice Pump Test Record.

.3 An inservice Test shall be conducted with the pump operating at specified test reference conditions. The test parameters shown in Attachment 4 shall be determined and recorded as directed in this section. The test shall be conducted as follows:

.3.1 The pomp shall be operated at nominal motor speed for constant speed drives and at a speed adjusted to the reference speed for variable speed drives. [Ref. 2.1.7, Para. 5.2(a)]

.3.2 The .te.sistance of the system shall be varied until the flow rate equals the reference value. The pressure shall then be determined and compared to its reference value.

Alternatively. the flow rate can be varied until the pressure equals the reference value and the flow rate shall be determined and compared to the reference flow .

rate value. [Ref. 2.1.7, Para. 5.2(b)]  !

.3.2.7 Flow should be established as near to the reference flow value as is practical for the test and in no case should it vary more than i 2 %. (Ref. 2.1.8)

.3.3 Where system resistance cannot be varied, flow rate and pressure shall be determined and compared to their respective reference values. [ Pef. 2.1.7, Para. 5.2(c)]

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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 ,

UNITS 2 AND 3 REVISION 6 PAGE 16 0F 45 j 6.0 PROCEDURE (Continued) 6.5.2.3.4 Changes in the pump test alignment described in the I individual pump test procedures, References 2.3.1 )

through 2.3.10, changes in the pump test j instrumentation and changes in the "As left" valve alignment following the test may be made, provided:

.3.4.1 The changes are documented on the Pump Test Procedure (the remarks section may be used).

.3.4.2 The Engineer conducting the test and the SRO Operations Supervisor, or designee, signify approval by signing j the pump test procedure, and shall be responsible for i ensuring that exceptions and/or changes do not f invalidate the test or violate the Technical Specifications and other operational constraints.

.3.4.2.1 Any changes in the test flow path shall be reviewed and approved by the Engineer conducting the test to assure that the pump test remains valid.

.3.4.2.2 Any changes in the valve lineup shall be documented and approved by Operations using procedures available for this such as Reference 2.4.2.

.3.5 Pressure, flow rate, and vibration (displacement or velocity) shall be determined and compared with corresponding reference values. All deviations from the reference values shall be compared with the limits given in Attachment 3, RANGES FOR TEST PARAMETERS and Attachment 10, MINIMUM PUMP PERFORMANCE TO ACHIEVE SAFETY ANALYSIS COMPLIANCE corrective action taken as specified in 6.6.1, below. [Ref. 2.1.7, Para. 5.2(d)]

.4 Vibration measurements are to be broad band (unfiltered). If velocity measurements are used, they shall be peak. If displacement amplitudes are used, they shall be peak-to-peak. [Ref. 2.1.7, Para. 5.2]

6.5.3 Pumps in Regular Use: Pumps that are operated more frequently than every 3 months need not be run or stopped especially for inservice testing provided the  ;

plant records show each such pump was operated at least '

once every 3 months at the reference conditions, and the quantities specified were determined, recorded, and analyzed as discussed in 6.6, below. [Ref. 2.1.7, Para. 5.3]

6.0 PROCEDURE (Continued)

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.4 I

UNITS 2 AND 3 REVISION 6 PAGE 17 0F 45 6.0 PROCEDURE-(Continued) ,

.6.5.4 Pumps in Systems Out of Service: '

1 l

l .1 For a pump in a system declared inoperable or not required i to be operable, the test schedule need not be .followed.

NOTE: Maintaining the test interval is recommended, ,

however, as this facilitates scheduling the '

testing on a staggered basis as previously addressed, r

l

.2 If not tested during plant' shutdowns, the pump shall be tested prior to entering the Mode in which it.is required to perform a safety function. Within 3 months prior to >

placing the system in an' operable status, the pump shall be tested and the test schedule followed in accordance with the requirements of this program procedure.

l .3 Pumps which can only be tested during plant operation shall be tested within I week following plant startup.

! [Ref. 2.1.7, Para. 5.4]~

l

! 6.5.5 Duration of Tests: After pump conditions are as stable as l

the system permits, each pump shall be run.at least 2 l minutes. At the end of this time at least one measurement l

or observation of each of the quantities required shall be

! made and recorded. [Ref. 2.1.7, Para. 5.6]  ;

6.5.6 Test Control l

.1 Control. direction and scheduling of the Test shall be the  :

responsib.lity of the Cognizant Engineer conducting the  !

test.

.2 Collection of data may be delegated to any individual  ;

approved by the Cognizant Supervising Engineer, provided j this individual meets the training and qualification requirements of References 2.1.4 and 2.3.17.

j .3 Inservice Testing of pumps shall be coordinated with other operational testing, when possible.

.4 Operator responsibilities, including independent verification, are addressed in the individual pump IST-implementing procedures, References 2.3.1.through 2.3.10  ;

and 2.4.1. .

l

, - 6.0 PROCEDURE (Continued)-

NUCLEAR ORGANIZATION ENGINEERfNG PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE IB 0F 45' 6.0 PROCEDURE (Continued) 6.5.7 Inservice Pump Test Record

.1 The Inservice Pump Test Record (Attachment 6) shall be completed by the Cognizant Engineer conducting the test.

Other documentation required to be completed is identified in the individual Pump Test Procedures, References 2.3.1 through 2.3.10.

.2 If the preferred method of data collection is available, refer to Reference 2.3.12, otherwise, complete the Inservice Pump Test Record using available instrumentation in accordance with the Key Points listed on Attachment 6  ;

and Reference 2.3.14. l

.3 A record shall'be completed and provided to the IST Coordinator, even when the pump is not tested during a given pump test interval. In this case it shall identify the reason for omitting the test.

.3.1 The reason for this " dummy" record is to provide an audit trail in the Pump IST records to show why a pump test interval was exceeded. Typical reasons are:

.3.1.1 Pump and system cleared for maintenance or modifications

.3.1.2 Pump not required to be operable in this mode (plant in Mode 5 or refueling).

.3.2 Complete as much of the Pump Test Record, as possible.

Mark the mechanical and hydraulic data "Not Used" and note the reason for skipping the test.

6.6 Analysis and Evaluation NOTES: 1. The requirements to initiate an NCR apply to the IST Program. See Reference 2.3.15 for NCR initiation criteria and Attachment 9 for guidance on use of the NCR as a documentation and notification tool.

2. The VISION software program, is used together with a MICROLOG Data Collector in obtaining and analyzing IST Data. VISION prints out (upon request) a hard copy inservice Pump Test Record for documentation. Additional data collected is processed by VISION for tracking and trending for engineering information only. Additional information is available in Reference 2.3.12.

6.6.1 Acceptance Criteria

.1 When evaluating pump performance, verify that the pump meets the minimum requirements of the Safety Analyses as discussed in Attachments 3 and 10 of this procedure and related references discussed therein.

i i

l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 19 0F 45 j l

6.0 PROCEDURE (Continued) 6.6.1.2 Acceptance Ranges

.2.1 The ranges of test quantities for each pump tested shall j be specified in the Inservice Pump Test Record used for the test. See Attachment 6.

j .2.2 The allowable ranges of inservice test quantities which

! are based on reference va' s are shown on Attachment 3.

[Ref. 2.1.7, Table 3]

! NOTE: Measured test quantities must also meet or exceed the values discussed in Attachment 10, MINIMUM PUMP PERFORMANCE TO ACHIEVE SAFETY ANALYSIS COMPLIANCE.

.2.3 If the allowable ranges for test quantities are more restrictive in the Technical Specifications, or other similar governing document, the more restrictive ranges shall be used and the source of the more restrictive requirements shall be referenced in the record of tests.

.3 See Attachment 9 for guidance on analysis of tests and time allowed for review.

NOTE: If during a test it is obvious that a test instrument is malfunctioning, the test may be l halted and the instruments promptly recalibrated or replaced.

.4 During a test, anomalous data with no clear indication of the cause must be attributed to the pump under test. For this occurrence, a prompt determination of operability is appropriate with follow-on corrective action as necessary.

[See NRC Generic Letter 91-18, "Information to Licensees l Regarding .. 0perability"]

.5 If deviations fall within the ALERT RANGE of Attachment 3, Ranges of Test Parameters, the frequency of testing specified in Attachment 4, shall be doubled until the cause of the deviation is determined and the condition corrected. [Ref. 2.1.7, Para. 6.1] l

.5.1 The test frequency may be returned to normal after the requirements of this section (6.6) have been met and a l successful retest is completed demonstrating operation in the acceptable range.

. -- - - . - . = - . .- .

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 FAGE 20 0F 45 6.0 PROCEDURE (Continued)  ;

6.6.1.6 If deviations fall within the' REOUIRED ACTION RANGE of Attachment 3, and/or do not meet or exceed the values  :

discussed in Attachment 10, the g shall be declared i ingperable until the cause of the a viation has been ,

determined and the condition corrected. (Ref. 2.1.7, Para. i 6.1]

.6.1 When L test shows deviations outside of the acceptable range of Attachments 3 and/or 10, following_the' inoperability declaration, the instruments involved may be i recalibrated and the test. rerun.

6.6.2 Limits may not be modified without a Pump Relief Request, even though when operating normally a pump does not .

perform consistently within the ranges identified in

~

Attachment 3. [Ref. 2.1.7, Para. 6.1] ,

NOTE: Measured test quantities must also meet or exceed the values discussed in Attachment 10, MINIMUM PUMP PERFORMANCE TO ACHIEVE SAFETY ANALYSIS COMPLIANCE.

6.6.3 Time Allowed for Analysis of Tests is discussed in Attachment 9.

7.0 RECORDS AND REPORTS 7.1 PumD Records: Records shall be maintained in CDM and shall include the following for each pump covered by this Program Procedure:

7.1.1 The manufacturer and the manufacturer's model; serial and/or other identification number; 7.1.2 A copy or summary of the manufacturer's acceptance test report if available; 7.1.3 A copy of the pump manufacturer's operating limits.

7.2 Inservice Test Plans: Inservice Testing Plans are issued as pump test procedures, References 2.3.1 through 2.3.10. The Inservice Testing Records for the Pumps in the Program shall be maintained and shall include:  ;

7.2.1 The hydraulic circuit used; 7.2.2 The measurement location and type of measurement for the required test parameters;

- ~ _

i - NUCLEAR ORGANIZATION ENGINEERING PROCEDURE ~ S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 21 0F 45 *

.P

! 7.0 RECORDS AND REPORTS (Continued) 7.2.3 The reference values; i .1 Reference values of test parameters are recorded on the preservice tests, or other reference test records and are

. transcribed to the current test each time a test is conducted.

l

.2 Only one reference test shall be used for a given pump test, that is, a single pump test may not use reference l

numbers from more than a single reference test.

[ NOTE: In evaluating a single pump IST, this eliminates the poor' practice.of using one reference test

, for hydraulic limits and another reference test  !

i. for the mechanical or vibration limits.

7.2.4 The method of determining reference values which are.not directly measured by instrumentation (such as

j. calculations).

7.3 Records of Testi: There shall be one Inservice Pump Test Record, Attachment 6, for each pump test. The Inservice Pump Test Record shows the test results for each. test and, along with its attachments

' or referenced documents, such as NCR's, indicates corrective action needed. This record of shall be maintained in CDM and shall include

7.3.1 Pump identification (the Equipment Identification Number' i from PEDMS);  !

7.3.2 Date of test; 7.3.3 reason for test (e.g., post-maintenance, routine inservice test, establishing reference values); i 7.3.4 values of measured parameters; 7.3.5 Identification of instruments used; 7.3.6 Comparisons with allowable ranges of test values and analysis of deviations;.

7.3.7 requirements for corrective action;  ;

7.3.8 evaluation and justification for changes to reference values; 7.3.9 signature of the person or persors responsible for conducting and analyzing the test.

I

1 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4

. UNITS 2 AND 3 REVISION 6 PAGE 22 Of 65 7.0 RECORDS AND REPORTS (Continued) 7.4 Record of Corrective Action 7.4.1 Records of corrective action shall be maintained and shall include a summary of the corrections made, the subsequent inservice tests and confirmation of operational adequacy (see Para. 6.4.4, above), and the signature of the individual responsible for corrective action and verification of results.

7.4.2 Corrective action performed on a pump in the Inservice-Testing Program shall be documented on Maintenance Orders-(either hard copy or SOMMS), NCRs and/or memoranda for file to provide a record of corrective action. Records of corrective action shall be filed in CDM-SONGS when completed. If on electronic media, such as NCRS or 50 MMS, they may be retained in that format.

7.5 Proaram Calendar and Test Sigtui 7.5.1 Attachment 7, Summary of Current Test Status, shall be.

maintained to provide a current record of the test dates and current test status of each pump. In addition, a schedule of tests, the IST Calendar, shall be maintained and distributed as appropriate by the IST Coordinator in accordance with Reference.2.3.13.

NOTE: This hard copy of.the "IST Log" is maintained in addition to the Computer records to provide a method of determining the test status of IST pumps even if the host or network server should become temporarily' inoperative.

23V34R6.wS1

NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE.- S023-V-3.4 UNITS 2 AND 3 REVISION 6- PAGE.23 0F 45 l '

' ATTACHMENT 1 1

INSERVICE TESTING OF PUMPS PROG M ACCEPTABLE INSTRUMENT ACCURACY'

'(From Reference 2.1.7, Table 1)

Quantity Percent .;

(Percent of full scale for individual analog instruments, percent of total loop accuracy for a combination of instruments,' or over the calibrated range for. digital  ;

instruments.)

Pressure i2 Flow Rate i2' i Speed i2 Vibration i5 Differential Pressure i2 ,

E i

i F

i f

.l j

l 23V34R6.w51 ATTACHMENT 1 PAGE 1 0F 1.

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 24 0F 45 ATTACHMENT 2 INSERVICE TESTING OF PUMPS PROGRAM lt4 SERVICE TEST PARAMETERS (From Reference 2.1.7, Table 2)

The parameters identified in this table shall be determined for each pump identified in Attachment 4 and recorded as directed in paragraph 6.5.2.3 of this procedure.

Quantity Remarks Speed: N If variable Speed Differential Pressure: aP Centrifugal Pumps, including vertical line shaft pumps Discharge Pressure: P Positive Displacement Pumps Flow Rate: Q Each Pump (exceptions in Att. 4)

Vibration: See Ref's 2.3.1 through 2.3.11 for test point locations Displacement, V a Peak-to-Peak Velocity, V. Peak l

23V34R6.wS1 ATTACHMENT 2 PAGE 1 0F 1  !

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4

UNITS 2 AND 3 REVISION 6 PAGE 25 0F 45 i

ATTACHMENT 3 l

LNSERVICE TESTING 0F PUMPS PROGRAM l RANGES FOR TEST PARAMETERS l (From Reference 2.1.7, Table 3 and 3b) l Part 1 Pump Piasp Test Acceptable Alert Required Type Speed Parameter Range Range Action Range Certrifsgal and a 600 rpe Vd of I v 5 2.5V p > 2.5 Vr to 6 v r >6V or r

• 22 mils Vertical lire shaft or l

j > 10.5 mills l

' a 600 rpm Vy or Vd s 2.5V r > 2.5 Vr to 6 v r >6V or p

or > 0.70 In./sec

! > 0.325 in./see Reci erc<a t 4g Vd or V g s 2.5Ve > 2.5 Vr to 6 v r >6V r Part 2 Alert Range Esquired Action Range Test Parameter Acceptable Range Low Nigh Low High P (Positive 0.93 to 1.10 P r 0.90 to . < 0.90 P r > 1.10 P r displacement pumps) < 0.93pr 6P (Vertical lire 0.95 to 1.10 AP r 0.93 to < 0.93 aP r > 1.10 6P p staft pumps) < 0.95 aPr Q (Posttive 0.85 to 1.10 Qr 0.93 to . < 0.93 Or > 1.10 Qr displacement vertical < 0.95 Qr line shaft pumps) aP (Centrifugal Pumps) 0.90 to 1.10 aP r . < 0.93 aP r > 1.10 aP p Q (Centrift. gal Pumps) 5 0.90 Or > 1.10 Q,.

0.90 to 1.10 Or ..

NOTES: a) CENERAL NOT[i ine sutscript r denotes reference value. The subscript d denotes displacement vibration. The subscript v denotes Velocity vibration.

b) Refer to Figsre 1 of this attachment to establish displacement limits for pumps with speeds e 500 rpm or velocity limits for pumps with speeds < 600 rpm.

ATTACHMENT 3 PAGE 1 0F 2

.a-

i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 26 0F 45 ATTACHMENT 3 ELGEREl LANGES FOR TEST PARAMETERS 105 J

5

/

/< _

10 4

- l

-ff l 5 f

$ j i

h,;'dW I '

I s" a c l '

5 2

102 102 5 2 101 6 2 100 5 2 10-1 V d, enHs, peak tofeek 23V34RS.wSI ATTACHMENT 3 PAGE 2 0F 2

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 27 0F 45 ATTACHMENT 4 l PUMPS TESTED WITHIN THE INSEPNICE TESTING PROGRAM I INTRODUCTION: i Components subject to the Inservice Testing Program for Pumps in accordance i with Reference 2.1.7 and 2.5.1 are identified herein. This attachment also identifies the parameters to be measured, test frequency and notes. Pump ,

Relief Request No. 12 is provided in Attachment 8.

GENERAL NOTES: l I

1. All testing is done on a quarterly interval unless otherwise noted. i

2. All parameters listed in Attachment 2 are required to be measured during each pump test.

PUMP NAME AND P&lO/ Test Parametere NOTES EQUIPMENT TAG Coordinates NUMBER Speed .P Disch - Flow Vibre6on Press. Rate Containment Spray Pumpe S2(3)1206MP012 40114A/C 5 N/A Yee Yes Yes Yes These pumps are tested quarterly on minLflow recirculation without flow l measurement and with full flow at cold

$2@)1206MP013 40114A/G-4 N/A Yee Yes Yee Yee shutdown intervals.'

' t.ow Pressure Safety injection Pumpe S2(3)1204MP015 401128/G4 N/A Yee Yee Yes Yee' '.hese Pumps are tested quarterly on minkflow recirculation. without flow measurement and with full flow (using ,

the shutdown cooling system flow path) l S2(3)1204MP016 401128/E-4 N/A Yes Yes Yes Yes each cold shutdown intervals.' Testing  !

ehall be in accordance with T-S 4.5.2.

High Pressure Safety injection Pumpe S2f311204MP017 40112A/G-4 N/A Yes Yes Yes Yes Teetbg shia be in accordance with T.S

-- I 4.5.2.

S2(3)1204MP018 40112NE4 N/A Yes Yn Yo.: Yee S2(3)t204MP019 40112A/C-4 N/A Yes Yes Yes Yee I This testing is in compliance with Reference 2.1.5. Attachment 1 Position 9.

ATTACHMENT 4 PAGE 1 0F 3

. _ . - .. =_ - --. . _ - - - .._ . . . - .

r NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 28 0F 45 ATTACHMENT 4 PUMPS TESTED WITHIN THE INSERVICE TESTING PROGRAM (Continued)

PUMP NAME AND P&lD/ Test Parameters NOTES EQUIPMENT T AG Coordinates Speed 6P D;sch Flow mation NUMBER Press. Rate Component Cooling Weter Pumps 40127A/G-4 N/A Yes Yee Yes Yee None S2(3)1203MP024 S2(3)1203MP025 40127AOS N/A Yes Yes Yes Yes S2(3)1203MP026 40127A/B-5 N/A Yes Yes Yes Yes Diesel Fuel O'J Transfer Pumpe 40116A.S7 N/A Yes Yes Yes Yes These are verticalline sha*I pumps and S2(3)2421MP093 40116A/B 4 N/A Yes Yes Yes Yes S2(3)2421 MP094 R e A f s m S2(3)2421 MP095 40116A/B-3 N/A Yes Yes Yes Yes 40116A/B-6 N/A Yes Yes Yes Yes S2(3)2421MP096 Salt Water Cooling Pumps 40126A/F-5 N/A Yes Yee Yes Yes These ere verticalline shstt pumps and S2(3)1413MP112 S2(3)1413MP113 40126A/D-5 N/A Yes Yes Yes Yes , ,

S2(3)1413MP114 40126B/D-5 N/A Yes Yes Yes Yes S2(3:1413MP307 40126B/G 5 N;'A Yes Yes Yes Yes Auxillary Fee:fwater Pumps S2(3)1305MP140 40100A/E-5 Yes Yes Yes Yes Yes These Pumps are tested MONTHLY en mini-flow rectrculation without flow measurement and with full (or

• **'9*""Y S2(3)1305MP141 40160AS5 N/A Yes Yes Yes Yes

["* ,

Generators) each cold shutdown if it has been more than one quarter sinca S2(3)130SMP504 4016M/G-5 N/A Yes Yes Yes Yes the last fu!! flow test.' Testing shall be in accordance w:th T-S 4 71.21.1 e

! I I

I Aux. Building Emergency Chill Water Pumps SA1513MP160 40100A/D-8 N/A Yes Yes Yes Yes These pumps are common to both Units 2 and 3 and are groaped under

- 'Untt 2 and Common

• for tracking SA1513MP1E2 40179A/E.5 N/A Yes Yes Yes Yes purposes.

Boric Acid Makeup (BAMU) Pumps S2(3)1218MP174 40125B/D-7 N/A Yes Yes Yes Yes None.

S2(3)1218hD175 40125B/B-7 N/A Yes Yes Yes Yes l

' This tes* , is in compliance wah Reference 2.1.5. Attachment 1, Position 9.

ATTACHMENT 4 PAGE 2 0F 3 l

--' " 1=48 1 v'un v w +- -i,- --

9 - g y ppy-+, p.. g.r

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 29 0F 45 ATTACHMENT 4 PUMPS TESTED WITHIN THE INSERVICE TESTING PROGRJA (Continued) j l

PUMP NAME AND P&lD/ Test Parameters NOTES I EQUIPMENT TAG Coordinates NUMBER Speed aP Disch Flow Vibration Prest. Rate Reactor Charging Pumps i l

S2(3)1208MP190 40124EVG 3 N/A No Yes Yes Yes These are reciprocatmg pumps and are j tuted in accordance w1h Reference  :

I S2(3)1208MP191 40124B/E-3 N/A No Yes Yes Yo* 2.1.7 for this style of pump Testing S2(3)1208MP192 40124B/C 5 N/A No Yes Yes Yes Component Coohng Water Makeup Pumps S2(3)1203MP1018 40127J/E4 N/A Yes Yes Yes Yes None S2(3)1203MP1019 40127J/C-4 N/A Yes Yes Yes- Yes I

i l

1 1

23V34R6.W51 ATTACHMENT 4 PAGE 3 0F 3

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 30 0F 45 ATTACHMENT 5 PUMPS REQUIRING RESPONSE TIME MEASUREMJNI 1 Response time are measured in accordance with the requirements of Reference 2.3.16.

Pump Equipment Nimber Response Time Requirement Auxiliary Feedwater Pump S2(3)l305MP140 39.0 see Auxiliary Feedwater Pumps S2(3)l305MP141 and 11.0 sec S2(3)l305MP504 Component Cooling Water Pumps S2(3)1203MP024, . 4.5 sec S2(3)1203MP025 and S2(3)1203MP026 High Pressure Safety Injection Pumps _

20.0 sec S2(3)1204MP017, S2(3)1204MP018 and S2(3)1204MP019 Low Pressure Safety Injection Pumps 52(3)1204MP015 24.5 sec and S2(3)1204MP016 Containment Spray Pumps 52(3)1206MP012 and 3.9 see S2(3)1206MP013 Reactor Charging Pumps S2(3)1208MP190, 20.0 sec S2(3)1208MP191, and S2(3)1208MP192 23V34R6.W51 ATTACHMENT 5 PAGE 1 0F 1

l 1

ENGINEERING PROCEDURE S023-V-3.4 N0 CLEAR ORGsiNIZATION UNITS 2 AND 3 REVISION 6 PAGE 31 0F 45 l ATTACHMENT 6  ;

l EGt123) 53 NSERV CE PUMP TEST RECORD AND KEY POINTS Q(1231 $3. INSERVICE PUMP TEST RECORD i

COM Encode No.

Test Procedure Used Record No.

Unit Test Date dEMMPLE $1<lCW4130. et12o3MrW1 CTCn E.XAMPd:COMPOWNT COOUNG WATER PUMP, ETC.)

1 Plent Tea No 2 Pumo Name ISvetem)

WHIN, PDSr MAIN 4W DC.l j 3 Tested By 4 Reason for Test 5 Plant Power 6 Reference IST Record No/Date ,

1 7 Test Frecuency 8 Date Last Tested 9 Run Time Before Test g,sT et anEAv s u Ni INSTRUMENT C BET NFERENCE TEST ACCE PI Al4 E ENTER MOR cALCo VALm CAUBRATION DUE DATE UNrr$ REF. VALUE VALVE MNGE HYDRAUUC DATA 10 Prestart suction Pressure (Pe) 11 Speed (N) 12 o<senarg.

Pressure (Po) 13 Running Suction Pressure (P4 14 Danmntie Proesure (Po-Pi) 15 Motor Current (AJ 16 Flow Rete (G)

Calculatione MECHAN 6 CAL DATA New weinsww o camwwon oue one on pur.o.ent me) voice 4 pPs)

• • • A'* REFFAFW VALUF TFST VA UE ACCEPTABLE FANGE RErLRENCE VALUE TEST VALUE ACCEP:AbLt RANGE 17 "a" # D*8 8 18 Oi wa amt*o) 19 **

20 ""* 8' D*8 >

21 2",' v** ac D*s t 22 A=>

sw unse 23 wee l *** ' - ""*"'**"*'- em, l

24 BEARING TEMPERATURES pow No t PontNo 2 TIME TEMP  % CHANGE TIME TEMP  % CHAN3F

• .ai o i Cat Due Date l

Date Last Taken 2 I r Reference Dam Record No I

Reference Tempe s'we Was Alowable Tempo,asu o ,

CORRECTIVE ACTIO4 REVIEW RESULTS N QUMD ACTsON hCR NO. ANCbOR M O NO 25 26 ENGINEER PERFORMING OPERAAllITY ANALYSfg ouPERvlSWG ENWNLER OR DFSONEE DAIE 27 28 SCE EGO 23) S3 Rtv i ostaa FACSIMILE t ATTACHMENT 6 PAGE 1 0F 6 l

I l

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 32 0F 45 ATTACHMENT 6 EG(123) 53. INSERVICE PUMP TEST RECORD AND KEY POINTS (Continued)

Key Points NOTE: All blocks must be completed or marked "NOT USED" per

?eference 2.3.14. For clarity, it is recommended that a diagonal line be drawn through the Block (s) not used and "NOT USED" be written on the diagonal.

Elank Instructions "CDM Encode Number" Leave blank.

" Test Procedure Used" Record the procedure used to conduct the Inservice Test on the Pump being tested.

" Test Date" Record the date the test was conducted.

" Unit" Sel f-Expl anatory.

" Record Number" Determine the record number as follows:

1) Pump Number

2) Month Tested

3) Year Tested Example: 2P096-5 93 '

NOTE: If more than one test is run on a given pump in the same month, add a letter following the test number to separate it i from the preceding test (s).

Example:

2P096-5-93 (First Test) 2P096-5-93A (Second Test) l 2P096-5-93B (Third Test) etc.

1 Plant Tag No. Use the plant tag number as it appears in the PEDMS (Example provided on the form).

2 Pump Name (System) Use the pump name and system name as they appear in the PEDMS (Example provided on the form).

3 Tested By Put the name of the Engineer who conducted the Inservice Test.

ATTACHMENT 6 PAGE 2 0F 6

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 33 0F 45 ATTACHMENT 6 j EGf123) 53. INSERVICE PUMP TEST RECORD AND KEY POINTS (Continued)

Bla_!1k Instructions (Continued) 4 Reason for Test Indicate the cause for initiating the test (Examples provided on the form).

5 Plant Power Enter the Plant power in Percent (preferred), by plant Mode (M-4, M-1, etc.), or iny other way to ]

differentiate this test from other tests that might have different results depending in plant mode.

6 Reference IST Record the record number and date of the reference Record No./Date test from which the values recorded under " Reference Value" in the body of this form are *.aken.

7 Test Frequency Record the frequency that the pump is currently undergoing Inservice Tests. This is normally monthly or quarterly, but if the pump is in ALERT, it may be on a 15 day interval or 46 day interval.

8 Date Last Tested Sel f-Expl anatory.

9 Run Time Before Test Record the time the pump is running before data is taken. .This is usually required to be at least 2 minutes. If the pump has been running before the test started (the pump is in service, for example),

write "> 2 Min.", or equivalent, in this block.

HYDRAULIC DATA Columns:

Instrument ID - Put the control number used for control and calibration of the instrument in this block. If the data' recorded in this row are calculated put "C" in this block.

Calibration Due Date - Put the date the instrument calibration will expire, or the recall date in this block.

Units - Record the units of measurement for the values recorded in this row (Examples: Feet, PSI, PSID, GPM, lbs/hr, etc.).

Set Ref. - If this row is the reference to which the system is adjusted to achieve the reference conditions, put a check mark in this column. For example, if the test is run such that the flow rate is set on a constant value and the differential pressure is measured to verify the condition of the pump, put a check mark in this column next to " Flow Rate".

ATTACHMENT 6 PAGE 3 0F 6 i

l

NUCLEAR ORGANf2ATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 34 0F 45 ATTACHMENT 6 EGf123) 53. INSERVICE PUMP TEST RECORD AND KEY POINTS (Continued)

HYDRAULIC DATA Columns: (Continued)

Reference Value - Record the value for~this parameter from the reference test identified in Block 6. If this is a referance test leave this column blank and put the test results in the " Test Value" column.

Test Value - Record the value for this parameter from the measurement made during the test currently being run.

Acceptable Range - Calculate the acceptance range from Attachment 3 to this procedure and record the result here.

NOTE: Measured test quantities must also meet or exceed the values discussed in Attachment 10, NININUN PUNP PERFORMANCE TO ACHIEVE SAFETY ANALYSIS COMPLIANCE.

If the acceptance range is more restrictive than that indicated on Attachment 3 (for example, due to Technical Specification limits), indicate the correct acceptance range here and do not use Attachment 3 (this should be explained on the reference test record to facilitate future review).

10 Prestart Suction Record the pressure at the pump suction before the Pressure (Pa) pump is started and verify that sufficient NPSH is available to safely run the pump. If the pump is already running, or this value is normally unavailable, mark "NOT USED" in this row.

11 Speed (N) Record the component speed if this is required. If pump speed is not required, mark "NOT USED" in this row.

12 Discharge Pressure Record the pressure at the pump discharge in (Po) accordance with the test procedure. If this value is normally unavailable or not recorded, mark "NOT USED" ,

in this row. )

13 Running Suction Record the pressure at the pump suction in accordance Pressure (Pi) with the test procedure. If this value is normally.

unavailable or not recorded, mark "NOT USED" in this row.

14 Differential This is normally a calculated value. Record the Pressure (Po-Pi) results of this calculation or measurement in the " Test Value" column. If this value is normally unavailable or not recorded, mark "NOT USED" in this row.

ATTACHMENT 6 PAGE 4 0F 6 I

on

l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 35 0F 45 ATTACHMENT 6 EG(123) 53. INSERVICE PUMP TEST RECORD AND KEY POINTS (Continued)

HYDRAULIC DATA Columns: (Continued) 15 Motor Current (A) Record the motor current as read per the test ,

procedure. If this value is normally unavailable or -l not recorded, mark "NOT USED" in this row. l l

16 Flow Rate (Q) Record the test loop flow rate per the test procedure. If this value is normally unavailable or ,

not recorded, mark "NOT USED" in this row. I CALCULATIONS If a calculation (such as for differential pressure) is required, it may be made here, if not otherwise required to be elsewhere by the test procedure. In addition, significant Maintenance Orders should be recorded here.

MECHANICAL DAIA Adjacent to the " Mechanical Data" title, is a place to record the vibration instrument ID, its attachment (s) (such as probe) ID and their_

calibration due dates. This information shall be recorded here.

CAUTION When vibration readings are taken on 4KV motors, use an accelerometer vibration detector to avoid erroneous readings due to electrical fields.

Columns:

Vibration Axis - These are defined in the test j procedure. Exercise care to place the vibration i transducer at the same position for each test. Also, l make every effort to keep the vibration probe perpendicular (Rule of Thumb: Within 15 degrees of normal to the surface) to the surface from which the readings are being taken.

Reference Value, Test Value and Acceptable Range -

For both Displacement and Velocity, these columns mean the same as that described under " Hydraulic Data", above.

17, 18, 19, 20, 21 l 22 Point Numbers 1 and 2 Horizontal, Vertical and Axial - This data is i measured as described in the Test Procedure for the  !

specific pump.

ATTACHMENI 6 PAGE 5 0F 6

. _ _ _ - . _ - _ _ _ . . _ . . _. . . . _ . _ . ~ - _ _ ._

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 36 Of 45 ATTACHMENT 6 EGfl23) 53. INSERVICE PUMP TEST RECORD AND KEY POINTS (Continued)

MECHANICAL DATA (Continued) i 23 Lubrication Identify the type of lubrication device on the Level / Pressure bearing (s) of concern and whether the lubrication level and pressure, as applicable, are satisfactory. >

24 Bearing Temperatures Draw a diagonal line through this section and write, "Not Used" above the line. .

CORRECTIVE ACTIDN/ REVIEW RESULTS 25 Required Action If the pump is evaluated as satisfactory, indicate the result by recording "N/A - Pump is Sat.", or equivalent. If the pump fails the IST or is in ALERT, indicate this and explain the required action (Example: " Pump in ALERT - Test interval 46 days").

26 NCR No, and/or If there is an NCR and/or M.0. resulting from this IST, record its number, otherwise write "N/A" in this block. .

27 Engineer Performing The Engineer evaluating the test results shall sign Operability Analysis in this block.

28 Supervising Engineer The Supervising Engineer approving the test and or Designee results shall sign this block, t

l i

i 23V34R6.W51 ATTACHMENT 6 PAGE 6 0F 6

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 37 0F 45 ATTACHMENT 7

SUMMARY

OF CURRENT TEST STATUS YEAR UNIT:

Instructions: 1. Record the year - one sheet per year.

2. As tests are completed, record the date under the appropriate month.

3. Review agamst past dates to assure test intervals are not exceeded.

DATE PUMP PUMP NAME JAN FEB MAR APR MAY JUN JULY AUG SEP OCT NOV DEC NO.

P-012 CONTAINMENT SPRAY PUMP P-013 CONTAINMENT SPRAY PUMP P-015 LP.S L PUMP P-016 LP.S.I. PUMP P-017 H P.S L PUMP P-018 H.P.S.L PUMP P-019 H.P.S L PUMP P-024 COMPONENT COOLING WATER PUMP P-025 COMPONENT COOUNG WATER PUMP P-026 COMPONENT COOUNG WATER PUMP P-093 DIESEL FUEL TRANSFER PUMP P-094 DIESEL FUEL TRANSFER PUMP P-095 DtESEL FUEL TRANSFER PUMP P-096 DIESEL FUEL TRANSFER PUMP P-112 SALTWATER COOUNG PUMP P-113 SALTWATER COOUNG PUMP P-114 SALTWATER COOUNG PUMP P-307 SALTWATER COOUNG PUMP P-140 AUXILIARY FEEDWATER PUMP (STEAM)

P-141 AUXILIARY FEEDWATER PUMP (STEAM)

~'

P-504 AUXILIARY FEEDWATER PUMP MOTOR P-160 AUXILIARY BUILDING EMERGENCY Chit 1ED WATER PUMP P 162 AUXILLARY BUILDING EMERGENCY CHILLED WATER PUMP P-174 BORIC ACID MAKEUP PUMP P-175 BORIC ACID MAKEUP PUMP

~

P 190 CHARGING PUMP P-191 CHARGING PUMP P-191 CHARGING PUMP P 1018 CCW MAKE-UP PUMP P-1019 CCW MAKE-UP PUM3 23V34R6.W51 ATTACHMENT 7 PAGE 1 0F 1

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 38 0F 45 ATTACHMENT 8 PUMP REllEF RE0 VEST NO. 12 AS SUBMITTED TO THE NRC PUMP RELIEF REQUEST No. 12 l

SYSTEM Units 2 & 3 Saltwater Cooling (SWC), Reactor Charging COMPONENTS Saltwater Cooling: Pil2, Pil3, Pil4, P307; Reactor Charging: P190, P191, and P192.

CLASS 2 AND 3 FUNCTION To provide flow to safety systems.

TEST REQUIREMMI Fer OM-6 4.6.1.2, the full-scale range of each analog instrument shall not be greater than three times the reference l

, value.

Bf'5 l FOR RELIEF Relief is requested from the full scale range requirements of OM-6 for SWC pump discharge pressure, and Charging pump suction pressure and flow.

Though the existing installed station instruments do not meet the code range requirement, their accuracy is significantly better than the code requirements. Thus the combination of range and accuracy of the installed equipment provides for the acquisition of repeatable data that meets the intent of the code.

l The instruments listed in the attached table do not meet the

OH-6 requirement (e.g., the full-scale range of each instrument shall not be greater than three times the reference val ue) . However, the manufacturer's stated accuracy for each

, pressure instrument listed in the attached table exceeds the OM-6 4.6.1.1 required accuracy (plus or minus two percent) for pressure instruments by a factor of four. Similarly, although the range for charging pump flow instrument FI-0212 is approximately 3.5 times the reference value, the combined loop accuracy of 1.28% exceeds the OM-6 required accuracy (plus or minus two percent) for flow instruments.

Even Accuracy determination based on the square root of the sum of the squares of the inaccuracles of each component in the loop per OMa 1988 Part 6, Section 1.3, instrument accuracy.

ATTACHMENT 8 PAGE 1 0F 2

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4

, UNITS 2 AND 3 REVISION 6 PAGE 39 0F 45 ATTACHMENT 8 PUMP RELIEF RE0 VEST NO. 12 AS SUBMITTED TO THE NRC (Continued)

PUMP RELIEF REQUEST No. 12 (Continued)

Maximum Asinstated Accuracy inaccuracy at Full Scale Instrument Range Reference Permitted by (error at full scale)

Pump Parameter Instrument (Range + Ref) Value Code

• Saltwater Cooling System Pumps Disch. Press. Pi-8230 0 160 32.4 ps'O 194 Psig 0.5% (0 8 psig)

P112 (5.1)

P113 Disch. Press. PI-6231 0-160 31 psig 1.86 psig 0.5% (0 8 poig) 4 (52)

P114 Disch Press. Pl6233 0 160 27 psig 1.62 paig 0 5% (0 8 psig) .

(5.9)

P307 Disch. Press. PI-8232 0w160 29 psig 1.74 psig 0.5% (0 8 psig)

(5.5)

Reactor Charging Pumpe P190 Suction Press. PI-9284 0-160 48.0 psig 2.78 ps!g 0.5% (0.8 psig)

(3.5)

P191 Suction Press. Pl-9285 0-160 44.0 psig 2.64 psig 0.5% (0.8 psig)

(3.6)

P192 Suction Press PI-9286 0-160 50.0 psig 3 ps!O O 5% (0.8 psig)

(3.2)

P190. Flow F1-0212 0-150 44.9 gpm 2.69 psig 128% (1.92 ps'0)

(3.3)

P191, & 0 150 44 gpm 2.64 psig 128% (1,92 psig)

(3 4)

P192 0-150 45 gpm 2.7 psig 128% (1.92 psig)

(3.3)

Submittal: This Pump Relief Request was submitted by Reference 2.5.5, letter, W. C. March to USNRC, ASME Code Update for the Second Ten-Year Interval, inservice Testing Program, August 17, 1993.

Approval : Not yet received.

• The information in this column represents the gauge error permitted by the code (3 times reference value X code required accursey of 2%)

23V34R6.W51 ATTACHMENT 8 PAGE 2 0F 2

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 40 0F 45 l ATTACHMENT 9 PUMP IST_1 VALUATION FLOW DIAGRAM Cog. Enginew Protest Wakdown (Note 1) 4* -

Cog. Engineer Perform Test

+

Cog.cneae-m Yes gg Problem? > Terminate Test (Note 2)

No i V y Cog. Engineer Cog. Engineer

• • y, T*st Inveldste Test I

'Y Cog. Enginew No Aveastet . _ _ _

Correct Deficionoles l

i V Yw l

" Supervising Engineer

• • ' "P Evda'te vendete end Approve w,c, IST Results (Note 6)

Results Valid?

Yes (Note 6) ,

I No Yes Y

Cog. Engineer Steervising Er@eer NW ,

w f,y y " rnent i e and Vandete en NCR N Necessaryinfeste an NCR l .. Yes .. .

Y Y Cog. Engineer ces c ;- - -- ',Enp.n Noufy the SRO Operanons No#fy the SRO Operations 4 g 7, g g g) s e sor supervisor ATTACHMENT 9 PAGE 1 0F 4

NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 41 0F 45 ATTACHMENT 9 PUMP IST EVALUATION FLOW DIAGRAM (Continued)

NOTES:

1. During the pretest walkdown, the Engineer conducting the test (usually the  !

Cog. Engineer) (a) walks down the system and component alignment to the extent necessary to assure himself that the test flow path is as required '

4 to begin the test described herein and instrumentation is ready, (b) reviews the last test, (c) If applicable, performs a cross comparison of instrumentation as a rough validation of calibration, (d) a " pre-test" is i not allowed.

2. During a test, anomalous data with no clear indication of the cause must be attributed to the pump under test. For this occurrence, a prompt determination of operability is appropriate with follow-on corrective action as necessary. Recalibrating test instruments and then repeating pump or valve tests is an acceptable alternative to the corrective action of repair or re, placement, but is not an action that can be taken before declaring the pump or valve inoperable. However, if during a test it is obvious that a test instrument is malfunctioning, the test may be halted and the instruments promptly recalibrated or replaced. [See NRC Generic Letter 91-18, "Information to Licensees Regarding ... Operability"]

3. SAFETY ANALYSIS LIMITS: When evaluating pump performance, verify that the pump meets the minimum requirements of the Safety Analyses as discussed in Attachments 3 and 10 of the Pump IST Procedure and related references discussed therein. For Units 2 and 3, this is Engineering Procedure S023-V-3.4.

4. NOTIFICATION OF SUPERVISOR: The Engineer conducting the test shall immediately notify his supervisor when the data acquired are in the

" Alert", or, " Required Action Range".t,2

' Required Action Range is defined in Reference 2.1.7, para. 6.1: "If deviations fall within the Required Action Range ... the pump shall be declared inoperable until the cause of the deviation has been determined and the condition corrected." Alert Range is also defined in the Reference 2.1.7, para.

6.1: "If deviations fall within the Alert Range ... the frequency of testing

... shall be doubled until the cause of the deviation has been determined and the condition corrected."

2 Although the Reference 2.1.7, para. 6.2 says completion of the test report (analysis) shall be within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />, including supervisor signature, this is overridden by the NRC Generic Letter 89-04. The 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> remains the mandatory code requirement, however, the SONGS IST Program requires the evaluation be completed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, as a maximum, if the pump is in the ALERT or Reouired Action Rance.

ATTACHMENT 9 PAGE 2 0F 4 i

l l

l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 i UNITS 2 AND 3 REVISION 6 PAGE 42 0F 45 ATTACHMENT 9 i PUMP IST EVALUATION FLOW DIAGRAM (Continued) l NOTES: (Continued) 1

5. It is appropriate to validate the data prior to the inoperability declaration.3 Validation (verifying the test was conducted using the i required system lineup, instruments were not obviously out-of-calibration, a second check of calculations, etc.) must be completed as soon as

possible and in no case later than eight hours following completion of j data gathering phase of the test if it is suspected that the pump is in j the " Alert" or " Required ~ Action" ranges.. The validation period is

provided to obtain management concurrence that the IST test results are

valid and entry into an applicable action statement is required. A retest i using recalibrated instrumentation is not allowed as a validation step.

J 6. If the Cognizant Supervising Engineer and the Engineer conducting the test i conclude that the test is invalid, the test may be ignored and the test I records not used. IN THIS CASE. A VALID TEST SHOULD BE COMPLETED ON THE I- PUMP IN OUESTION AS 500N AS POSSIBLE TO CONFIRM PUMP OPERABILITY.

i Performing an invalid test in no way absolves those responsible from

compliance with the surveillance requirements and schedules of the

Technical Specifications (e.g., IST requirements) as they apply to the

components under test.

f 7. NRC POSITION: The NRC guidance on T-S Clock Policy states that when j performance data fall in the Required Action Range, regardless of whether j the limit is equal to or more conservative than the TS limit,.the pump or

valve must be declared inoperable immediately and the TS action statement

for the associated system must be entered. In cases where the required i action range limit is more conservative than its corresponding TS limit,

! the corrective action may not be limited to replacement or repair; it may be an analysis to demonstrate that the specific performance degradation i does not impair operability and that the pump or valve will still fulfill its function, such as delivering the required flow. A new required action j range may be established after such analysis which would then allow a new

determination of operability.

l 1

1 3

An incident in January, 1992, involving the Unit 1 Main Feed pumps is a circumstance where this policy of validation could have been applied. Declaring a main Feedwater pump inoperable put Unit 1 in Technical Specification 3.0.3.

The pump data were only slightly into the Required Action Range, and, as it turned out, resulted from an inaccurate discharge pressure gauge. it would have been appropriate and consistent with the intent of the NRC Generic Letter 89-04, Att.1, Position 8 to consider this test to be non-valid. A valid IST could then be promptly completed to verify pump operability.

ATTACHMENT 9 PAGE 3 0F 4

i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 43 0F 4S-ATTACHMENT 9 PUMP IST EVALUATION FLOW DIAGRAM (Continued)

NOTES: (Continued)

"The durations specified by the Code for analyzing test results have not been accepted by the NRC for postponing entering a TS action statement. As soon as the data are recognized as being within the required action range for pumps or as exceeding the limiting value of full-stroke time for valves, the associated component must be declared inoperable and, if subject to the TS, the Allowed Outage Time (A0T) specified in the action.

.statementmuftbestartedatthetimethecomponentwasdeclared inoperable."  :

8. If the Engineering Supervisor determines that the test was valid and the data are in the Alert or Reauired Action Ranae (Refer to Footnote No. 1. ,

above), the Supervising Engineer shall immediately initiate and validate an NCR (including an operability assessment) and notify the SR0 Operations Supervisor.

9. The NCR shall containht'e date and time of the pump test. In all cases, ,

the Technical Soecification clock shall be started and controlled by the .

.SR0 Operations S'toervisor.

l l

This is a quote from the NRC Generic letter 91-18, Information ... on Resolution- of Degraded and Nonconforming Conditions and Operability, November 7, 1991.

23V34R6.W51 ATTACHMENT 9 PAGE 4 0F 4

+1G-

_. . _ . ~ _ -. .

NUCLEAR ORGANIZATION ENGINEERfNG PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 44 0F 45 ATTACHMENT 10 tilNIMUM PUMP PERFORMANCE TO ACHIEVE SAFETY ANALYSIS COMPLIANCE 1.0 RE0VIREMENTS 1.1 Pump performance parameters identified in the following reference drawings from NEDO shall be met as a minimum during IST. If these values are not met, the pump is considered to not meet the Safety Analysis assumptions for the performance of the safety systems.

1.2 The Code requirements in Attachment 3 to this procedure shall be met in cases where the Safety analysis requiremer,ts of this Attachment are less restrictive.

1.3 Accordingly, when evaluating a Pump IST, the Cog. Engineer identifies the Code limits as shown on Attachment 3 and then reviews the safety analysis limits form the below references. The most restrictive limits shall be recorded on the pump test record and used for evaluation of the pump performance.

2.0 PUMP PERFORMANCE REFERENCES l

PUMP REFERENGI CONTAINMENT SPRAY PUMPS S2(3)1206MP012 Drawing 41063 S2(3)1206MP013 LOW PRESSURE SAFETY INJECTION PUMPS S2(3)1204MP015 Drawing 41065, and T-S 4.5.2.g S2(3)1204MP016 HIGH PRESSURE SAFETY INJECTION PUMPS S2(3)1204MP017 Drawing 41064, and T-S 4.5.2.g I S2(3)1204MP018 S2(3)1204MP019 COMPONENT COOLING WATER PUMPS l S2(3)1203MP024 Drawing 41066 S2(3)1203MP025 S2(3)1203MP026 COMPONENT COOLING WATER NAKEUP PUMPS S2(3)1203MP1018 Under Development 52(3)1203MP1019 ATTACHMENT 10 PAGE 1 0F 2

i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.4 UNITS 2 AND 3 REVISION 6 PAGE 45 0F 45 ATTACHMENT 10 MINIMUM PUMP PERFORMANCE TO ACHIEVE SAFETY ANALYSIS COMPLIANCE (Continued) 2.0 PUMP PERFORMANCE REFERENCES (Continued)

EU_MP REFERENCE DIESEL FUEL OIL TRANSFER PUMPS S2(3)2421MP093 Drawing 41068 S2(3)2421MP094 S2(3)2421MP095

, S2(3)2421MP096 l

l SALT WATER COOLING PUMPS S2(3)12CMPil2 Drawing 41067 S2(3)120MPil3 52(3)120MPll4 S2(3)120MP307 AUXILIARY FEEDWATER PUMPS S2(3)l305MP140 Drawing 41061 S2(3)l305MPl41 S2(3)l305MP504 AUX. BUILDING EMERGENCY CHILL WATER PUMPS i

l SA1513MP160 Drawing 41075 SA1513MP162 BORIC ACID MAKEUP (BAMU) PUMPS S2(3)1218HP174 Drawing 41069 S2(3)1218MPl75 REACTOR CMARGING PUMPS 52(3)1208MP190 Drawing 41062, and T-S 4.5.2.g S2(3)1208MP191 S2(3)1208MP192 23V34R6.W51 ATTACHMENT 10 PAGE 2 0F 2

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