ML030800142

Temporary Change Review and Approval, IT 10A, Test of Electric-Driven Auxiliary Feed Pumps and Valves with Flow to Unit 1 Steam Generators (Quarterly)

ML030800142
Person / Time
Site:	Point Beach
Issue date:	11/01/2002
From:	Groehler R, Harper R, Krail J, Sokol K Nuclear Management Co
To:	Office of Nuclear Reactor Regulation
References
2002-0850, FOIA/PA-2003-0094, IT 10A, Rev 13 PBF-0026c, Rev 13
Download: ML030800142 (64)

Text

Nuclear Power Business Unit . 'T- W TEMPORARY CHANGE REVIEW AND APPROVAL VP 1.2.3. TemporaryProcedureChanges,for requirements. Page I of I - INITIATION I . nber IT IOA Current Rev 13 Unit PBI Temp Change No. 2002-0850 Z,.tentHue(quarterly)

.iment Title Test of Electric-Driven e Auxiliary Feed Pumps and Valves with flow to Unit I Steam Generators isting Effective Temporary Changes riefDescription Add P&L and Cautions associated with AFW minimum Flow (Identify specific changes on Form PBF-0026c, Document Review and Approval Continuation, and include with the package) 0 Initiate PBF-0026h and include with the change.

Other documents required to be effective concurrently with the temporary change:

Changes pre-screened according to NP 5.1.8? 0 NO El YES (Provid documentation according to NP 5.1.9)

Screening completed according to NP 5.1.8? El NA 0 YES (Atach copy)

Safety Evaluation Required? ZNO El YES (ifYma rmeision maybe proccued or final reviews and appmvls shan be obtained before i,.

Determine if the change constitutes a Change Of Intent to the procedure by evaluating the following questions. S........ 'IF' (If any answers are YES, a revision may be processed or final reviews and approvals shall be obtained before implementing)

Will the proposed change: YES NO

1. Require a change to, affect or invalidate a requirement, commitment, evaluation or description in the Current or ISFSI Licensing Basis (as defined in NP 5.1.8 and NP 5.1.7)? 0]

2. Cause an increase in magnitude, significance or impact such that it should be processed as a revision? 0]

3. Delete or modify a prerequisite, initial condition, precaution, limitation or other steps that could have safety significance or affect the procedure's margin of safety? 0]

4. Delete QC hold points, Independent Verification or Concurrent Check steps without the related step(s) that require the performance also being deleted? 0]

5. Change Tech Spec or other regulatory acceptance criteria other than for re-baselining purposes? []

6. Require a change to the procedure Purpose or change the procedure classifieati n?9 El 0 Initiated By (print/sign) Ross Groehler A. . . ate 11/01/2002 H - INITIAL APPROVAL This change is correct and complete, can be performed as written,,oes not adversely affect personnel or nuclear safety, or Plant operatin .ond(tiog. --,,. /t Group Supervisor (print/sign) ;z. o) 4,oI I/ r? a lDate ///1 /0 (Cannot be the Initiator) ' /

This change does not adverselfe t P Utopera g ondi fety R I ed procedures only)

Senior Reactor Operator (print/sign) *o\ tr .et _ Date ] ' _

(Cannot be the Initiator or Group Supervisor)

HI - PROCEDURE OWNER REVIEW 0D Permanent El One-time Use El Expiration Date, Event or Condition:

El Hold change until procedure completed (final review and approval stI ýre d within 14 days of initial approval)

El QR/MSS Review NOT Required (Admin/iNNSR9-

• 0 QR Review ReIj- MS!R" view Required (Rtrce P15)_

Procedure Owner (print/sign) IL. *._- - ) / Datee t//b4 J ,

This Chanze and suooortine reouirements correctly comoleted and orocessed. / I IV - FINAL REVIEW AND AcPROQVAL ustbe comoleted within 14 daysofinitiah aorov1") (The Initiator. OR and A' rolAutjm1Vv ahall beindenendent from eIchAther)

.Q1yMSS (print/sign) ]L.. , .. / 1L941I" Date ////

Indicates 50.59n72.4S applicability assessed, any necessary screenings/evaluations performed, determination made as to whethe/addiwonal cross-disciplinary review required, and ifrequired, performed.

MSS Meeting No.

Approval Authority (orint/sin) X1 "Ie ,tat/ .... _..- .

V - REVISION INFORMATION FOR PERMANENT CHANGES Post Typing Review (print/sign) / Date Indicates temporary change(s) incorporated exactly as approved and no other changes made to document.

Incorporated into Revision Number Effectivee Date __t_-_

PBF-0026c

References:

NP 1.2.3 Revision 13 01/16/02

Point Beach Nuclear Plant DOCUMENT REVIEW AND APPROVAL CONTINUATION Page _ of Doc Number IT 10A Revision 13 Unit PBI Title Test Of Electrically-Driven Auxiliary Feed Pumps and Valves with flow to Unit I Steam Generators (Quarterly)

Temporary Change Number 2002-0850 Description of Changes:

Step

• Change/Reason Add new P&L associated with maintaining AFW minimum flow requirements./ See SCR 2002-0458, and 3.10 also CAP029908 and CAP029952.

Add new caution associated with maintaining AFW minimum flow requirements. Caution added at a Caution before point where flow is being adjusted and minimum recirt flow is established I See SCR 2002-0458, and step 5.15 also CAP029908 and CAP029952.

Add new caution associated with maintaining AFW minimum flow requirements. Caution added at a Caution before point where flow is being adjusted and minimum recirc flow is established I See SCR 2002-0458, and step 5.20.7 also CAP029908 and CAP029952.

Add new caution associated with maintaining AFW minimum flow requirements. Caution added at a Caution before point where flow is being adjusted and minimum recirc flow is established / See SCR 2002-0458, and step 5.48 also CAP029908 and CAP029952.

Add new caution associatea wiun maintaining AFW minimum flow requirements. Caution added at a Caution before point where flow is being adjusted and minimum recirc flow is established / See SCR 2002-0458, and step 5.53.7 also CAP029908 and CAP029952.

0 Note: Recording of Step Number(s) is not required for multiple occurrences of identical information or when not beneficial to reviewers PBF-0026c Revision 6 0411&101 References NP 1.13, NP 1.23

Point Beach Nuclear Plant TEMPORARY CHANGE AFFECTED MANUAL LOCATION Page of Procedure Number IT 10A Revision 13 Unit PB1 Test Of Electrically-Driven Auxiliary Feed Pumps and Valves with flow to Unit I Steam Generators Title (Quarterly)

Temporary Change Number 2002-0850 I - IMMEDIATELY AFTER INITIAL APPROVAL ON PBF-0026e (Non-intent changes)

(after Final Approval if change of intent involved)

Date This procedure change has been processed as follows: (Manual/Location) Performed E] Copy included in work package for field implementation. (WO No. )

W* Copy filed in Control Room temp change binder (Operations only). / - c Z

[ Original change package provided to k . C,, to obtain Procedure Owner Review (e.g, Owner review may be coordinated by In-Group OA IL Procedure Writer, Procedure Supervisor, etc.). / - (

El El Performed By (print and sign) Q ( J ~ - i Date /(-./-oZ II - PROCEDURE OWNER REVIEW ON PBF-0026e (may be performed by OA 1l, Procedure Writer, etc.)

Date This procedure change has been processed as follows: (Manual/Location) Performed

[I] Copy sent to Document Control Distribution Lead for Master File.

(Not required for one-time use change)

El Copy filed in Group satellite file. (Not required for one-time use rcages.)

El Copy filed in Group one-time use file.

[] Original Temp Change provided to .""- t, to obtain Final Approvals (e.g., final approval may be coordinated by In-Croup OA ILProcedure Writer, Procedure Supervisor, etc.) ____-___..

rl Pe Performed By (print and sign) ¢ C - LC -* r_ *,

• Date *(- * *--

PBF-0026h Revision 5 06/13101

Reference:

NP 1.2.3

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59172.48 SCREENING (NEW RULE) Venfy SCR number on all pagcs Page 1 Title of Proposed Activity: AFW minimum flow requirement change to AOP, EOP, CSP, ECA, SEP, 01-62 A/B procedures Associated Reference(s) #. Removal of internals from AF- 17 and upgrade open function of AFW pumps minirecirc vlaves to safety -related (MR 02-029); SCR 2002-005-01 EOP/ARP actions for AFW mini-recirc requirement ; 2002-0055, P-38A/B mini recirc flow orifice replacment (MR 99-029 *A, *B);

Flowserve Corporation Pump Division letter dated March 2, 20012; CAP 29908; CAP 29952 Prepared by: Eric A. Schmidt I John P. Schroeder  : /o ,,2, Name (Print) infr Reviewed by: ]_,_ _,,___ _ _ _ _ _Date:

Nam-(Print) Signature PART I (50.59/72.48) - DESCRIBE THE PROPOSED ACTIVITY AND SEARCH THE PLANT AND ISFSI LICENSING BASIS (Resource Manual 5.3.1)

NOTE: The "NMC 10 CFR 50.59 Resource Manual" (Resource Manual) and NET 96-07, Appendix B, Guidelines for 10 CFR 72.48 Implementation should be used for guidance to determine the proper responses for 10 CFR 50.59 and 10 CFR 72.48 screenings.

Describe the proposed activity and the scope of the activity being covered by this screening. (The 10 CFR 50.59 / 72.48 review of other portions of the proposed activity may be documented via the applicability and pre-screening process requirements inNP 5.1.8.) Appropriate descriptive material may be attached.

This screening supports procedural uprgrades to address the Auxiliary Feedwater (AFW) System issue as identified in CAP 29908 and CAP 29952. Procedural guidance for operation of AFW System will be changed such that the operator must ensure that discharge flow for P-3 8 A/B must be greater than 50 gpm and 1/2 P-29 discharge flow must be greater than 75 gprm If pump flow cannot be maintained within these requirements, the pump must be secured.

1.2 Search the PBNP Current Licensing Basis (CLB) as follows: Final Safety Analysis Report (FSAR), FSAR Change Requests (FCRs) with assigned numbers, the Fire Protection Evaluation Report (FPER), the CLB (Regulatory) Commitment Database, the Technical Specifications, the Technical Specifications Bases, and the Technical Requirements Manual. Search the ISFSI licensing basis as follows: VSC-24 Safety Analysis Report, the VSC-24 Certificate of Compliance, the CLB (Regulatory)

Commitment Database, and the VSC-24 10 CFR 72.212 Site Evaluation Report. Describe the pertinent design function(s),

performance requirements, and methods of evaluation for both the plant and for the cask/ISFSI as appropriate. Identify where the pertinent information is described in the above documents (by document section number and title). (Resource Manual 5.3.1 and NEI 96-07, App. B, B.2)

FSAR 10.2 Auxiliary Feedwater System (AF) - The AFW system shall automatically start and deliver adequate AFW flow to maintain adequate steam generator levels during accidents which may result in main steam safety valve opening, such as: Loss of normal feedwater (LONF) and Loss of all AC power to the station auxiliaries (LOAC). AFW system shall also deliver sufficient flow to the steam generators supporting rapid cooldown during such accidents as: steam generator tube rupture (SGTR) and main steam line break (MSLB).

Each pump has an AOV controlled recirculation line back to the condensate storage tanks to ensure minimum flow to prevent hydraulic instabilities and dissipate pump heat.

TS 3.7.5 Auxiliary Feedwater (AFW) System TS Bases B 3.7.5 Auxiliary Feedwater (AFW) System FSAR 7.3.3.4 Manual AFW Flow Control During Plant Shutdown Manual control of steam generator water level using the AF pumps to remove reactor decay and sensible heat.

FPER 6.6.4 Auxiliary Feedwater System The Auxiliary Feedwater Pumps are provided with a mini-recirc line to ensure a minimum amount of flow is established to keep the pumps from dead heading.

PBF-1515c

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Vcnfy SCR number on all pages Page 2 FSAR 10.2 Auxiliary Feedwater System (AF)

TS 3.7.5 Auxiliary Feedwater (AFW) System TS Bases B 3.7.5 Auxiliary Feedwater (AFW) System FSAR 7.3.3.4 Manual AFW Flow Control During Plant Shutd6wn FPER 6.6.4 Auxiliary Feedwater System 1.3 Does the proposed activity involve a change to any Technical Specification? Changes to Technical Specifications require a License Amendment Request (Resource Manual Section 5.3.1.2).

Technical Specification Change : El Yes Z No If a Technical Specification change is required, explain what the change should be and why it is required.

1.4 Does the proposed activity involve a change to the terms, conditions or specifications incorporated in any VSC-24 cask Certificate of Compliance (CoC)? Changes to a VSC-24 cask Certificate of Compliance require a CoC amendment request.

D Yes 0No If a storage cask Certificate of Compliance change is required, explain what the change should be and why it is required.

10 CFR 50.59 SCREENING PART fl (50.59) - DETERMINE IF THE CHANGE INVOLVES A DESIGN FUNCTION (Resource Manual 5.3.2)

Compare the proposed activity to the relevant CLB descriptions, and answer the following questions:

YES NO QUESTION Z El Does the proposed activity involve Safety Analyses or structures, systems and components (SSCs) credited in the Safety Analyses?

E3 0 Does the proposed activity involve SSCs that support SSC(s) credited in the Safety Analyses?

0] El Does the proposed activity involve SSCs whose failure could initiate a transient (e.g., reactor trip, loss of feedwater, etc.) or accident, OR whose failure could impact SSC(s) credited in the Safety Analyses?

0] El Does the proposed activity involve CLB-described SSCs or procedural controls that perform functions that are required by, or otherwise necessary to comply with, regulations, license conditions, orders or technical specifications?

El 0] Does the activity involve a method of evaluation described in the FSAR?

El 0] Is the activity a test or experiment? (i.e., a non-passive activity which gathers data)

El 0 Does the activity exceed or potentially affect a design basis limitfor afission product barrier(DBLFPB)?

(NOTE: If THIS questions is answered YES, a 10 CFR 50.59 Evaluation is required.)

T f the answers to ALL of these questions are NO, mark Part III as not applicable, document the 10 CFR 50.59 screening in the nclusion section (Part IV), then proceed directly to Part V - 10 CFR 72.48 Pre-screening Questions.

If any of the above questions are marked YES, identify below the specific design function(s), method of evaluation(s) or DBLFPB(s) involved.

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verfy SCR number on all pages Page 3 AR-02-029 upgraded the open function of the AFW pumps mini-recirc AOV to safety-related. The safety-related boundary includes the recirc orifice and all associated upstream components and piping. It is postulated that a failure of the piping downstream of the recirc orifice will not have any adverse affects on the AFW system. The availability of the recirculation flowpath provides an additional flowpath to support minimum flow requirements. This procedure change will improve the reliability of the AFW pumps by not relying upon the recirc flow path for operability as it has been concluded that the restrictions in the recirc orifice may not be adequate for use. Whereas current guidance mandates that the operator verify the position of the recirc AOV and the status of the Instrument Air system, these procedural changes will only require the operator to monitor pump discharge flow.

PART 111 (50.59) - DETERMINE WHETHER THE ACTIVITY INVOLVES ADVERSE EFFECTS (Resource Manual 5.3J)

If ALL the questions in Part II are answered NO. then Part III is E3 NOT APPLICABLE.

Answer the following questions to determine if the activity has an adverse effect on a design function. Any YES answer means that a 10 CFR 50.59 Evaluation is required; EXCEPT where noted in Part 111.3.

III.I CHANGES TO THE FACILITY OR PROCEDURES YES NO QUESTION El 0 Does the activity adversely affect the designfunction of an SSC credited in safety analyses?

El 0] Does the activity adversely affect the method of performing or controlling the designfunction of an SSC credited in the safety analyses?

If any answer is YES, a 10 CFR 50.59 Evaluation is required. If both answers are NO. describe the basis for the conclusion (attach additional discussion as necessary):

Minimum flow requirements will be maintained within recommendations from the vendor by monitoring pump discharge flow and securing the pump as required. Starting and stopping of the AFW pumps has been previously evaluated in 50.59 Evaluation 2002-005, which addressed procedural changes to reduce the potential of pump damage as a result of the loss of the recirculation flow path.

111.2 CHANGES TO A METHOD OF EVALUATION (If the activity does not involve a method of evaluation, these questions are Z NOT APPLICABLE.)

YES NO QUESTION

[3 ED Does the activity use a revised or different method of evaluation for performing safety analyses than that described in the CLB?

[] E] Does the activity use a revised or different method of evaluation for evaluating SSCs credited in safety analyses than that described in the CLB?

If any answer is YES, a 10 CFR 50.59 Evaluation is required. If both answers are NO. describe the basis for the conclusion (attach additional discussion, as necessary).

111.3 TESTS OR EXPERIMENTS If the activity is not a test or experiment, the questions in III.3.a and III.3.b are [D NOT APPLICABLE.

a. Answer these two questions first:

YES NO QUESTION El El Is the proposed test or experiment bounded by other tests or experiments that are described in the CLB?

[D [I Are the SSCs affected by the proposed test or experiment isolated from the facility?

n,r

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Venfy SCR numbr on al pa.-es Page 4 If the answer to BOTH questions in V.3.a is NO continue to III.3.b. If the answer to EITHER question is YES, then describe the basis.

b. Answer these additional questions ONLY for tests or experiments which do NOT meet the criteria given in 111.3 a above.

If the answer to either question in III.3.a is YES, then these three questions are [] NOT APPLICABLE.

YES NO QUESTION

[I E] Does the activity utilize or control an SSC in a manner that is outside the reference bounds 'f the design bases as described in the CLB?

D [E] Does the activity utilize or control an SSC in a manner that is inconsistent with the analyses or descriptions in the CLB?

E] [3 Does the activity place the facility in a condition not previously evaluated or that could affect the capability of an SSC to perform its intended functions?

If any answer in III.3.b is YES, a 10 CFR 50.59 Evaluation is required. If the answers in fII.3.b are ALL NO descr'be the basis for the conclusion (attach additional discussion as necessary):

Part IV - 10 CFR 50.59 SCREENING CONCLUSION (Resource Manual 5.3.4).

Check all that apply:

A 10 CFR 50.59 Evaluation is [] required or Z NOT required.

A Point Beach FSAR change is [I required or 0 NOT required. If an FSAR change is required, then initiate an FSAR Change Request (FCR) per NP 5.2.6.

A Regulatory Commitment (CLB Commitment Database) change is El required or 0 NOT required. If a Regulatory Commitment Change is required, initiate a commitment change per NP 5.1.7.

A Technical Specification Bases change is El required or 0 NOT required. If a change to the Technical Specification Bases is required, then initiate a Technical Specification Bases change per NP 5.2.15.

A Technical Requirements Manual change is El required or 0 NOT required. If a change to the Technical Requirements Manual is required, then initiate a Technical Requirements Manual change per NP 5.2.15.

10 CFR 72.48 SCREENING NOTE: NEI 96-07, Appendix B. Guidelines for 10 CFR 72.48 Implementation should be used for guidance to determine the proper responses for 72.48 scrernings.

PART V (72.48) - 10 CFR 72.48 INITIAL SCREENING QUESTIONS Part V determines if a full 10 CFR 72.48 screening is required to be completed (Parts VI and VII) for the proposed activity.

ES NO QUESTION El 0 Does the proposed activity involve IN ANY MANNER the dry fuel storage cask(s), the cask transfer/transport equipment, any ISFSI facility SSC(s), or any ISFSI facility monitoring as follows: Multi-Assembly Sealed Basket (MSB), MSB Transfer Cask (MTC), MTC Lifting Yoke, Ventilated Concrete Cask (VCC), Ventilated Storage Cask (VSC), VSC Transporter (VCST), ISFSI Storage Pad Facility, ISFSI Storage Pad Data!Communication Links, or PPCS/ISFSI Continuous Temperature Monitoring System?

P1l11F7-1 1 5C

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Venfy SCR number on all pages Page 5 El [] Does the proposed activity involve IN ANY MANNER SSC(s) installed in the plant specifically added to support cask loading/unloading activities, as follows: Cask Dewatering System (CDW), Cask Reflood System (CRF), or Hydrogen Monitoring System?

El 0 Does the proposed activity involve IN ANY MANNER SSC(s) needed for plant operation which are also used to support cask loading/unloading activities, as follows: Spent Fuel Pool (SFP), SFP Cooling and Filtration (SF),

Primary Auxiliary Building Ventilation System (VNPAB), Drumming Area Ventilation System (VNDRM),

RE-105 (SFP Low Range Monitor), RE-135 (SFP High Range Monitor), RE-221 (Drumming Area Vent Gas Monitor), RE-325 (Drumming Area Exhaust Low-Range Gas Monitor), PAB Crane, SFP Platform Bridge, Truck Access Area, or Decon Area?

El 0] Does the proposed activity involve a change to Point Beach CLB design criteria for external events such as earthquakes, tornadoes, high winds, flooding, etc.?

El 0] Does the activity involve plant heavy load requirements or procedures for areas of the plant used to support cask loading/unloading activities?

El 0] Does the activity involve any potential for fire or explosion where casks are loaded, unloaded, transported or stored?

If ANY of the Part V questions are answered YES, then a full 10 CFR 72.48 screening is required and answers to the questions in Part VI and Part VII are to be provided. If ALL the questions in Part V are answered NO, then check Parts VI and VII as not applicable. Complete Part VIII to document the conclusion that no 10 CFR 72.48 evaluation is required.

PART VI (72.48) - DETERMINE IF THE CHANGE INVOLVES A ISFSI LICENSING BASIS DESIGN FUNCTION (If ALL the questions in Part V are NO then Part VI is El NOT APPLICABLE.)

Jompare the proposed activity to the relevant portions of the ISFSI licensing basis and answer the following questions:

YES NO QUESTION El 0] Does the proposed activity involve caskIISFSI Safety Analyses or plant/cask/ISFSI structures, systems and components (SSCs) credited in the Safety Analyses?

El 0] Does the proposed activity involve plant, cask or ISFSI SSCs that support SSC(s) credited in the Safety Analyses?

El 0 Does the proposed activity involve plant, cask or ISFSI SSCs wh6se function is relied upon for prevention of a radioactive release, OR whose failure could impact SSC(s) credited in the Safety Analyses?

El 0] Does the proposed activity involve cask/ISFSI described SSCs or procedural controls that perform functions that are required by, or otherwise necessary to comply with, regulations, license conditions, CoC conditions, or orders?

E] 0 Does the activity involve a method of evaluation described in the ISFSI licensing basis?

E] [0 Is the activity a test or experiment? (i.e., a non-passive activity which gathers data)

El [0 Does the activity exceed or potentially affect a cask design basis limitfor afission product barrier(DBLFPB)?

(NOTE: If THIS questions is answered YES a 10 CFR 72.48 Evaluation is required.)

If the answers to ALL of these questions are NO, mark Parts VII as not applicable, and document the 10 CFR 72.48 screeriing in the conclusion section (Part VIII).

If any of the above questions are marked YES, identify below the specific design function(s), method of evaluation(s) or DBLFPB(s) involved.

PART VII (72.48) - DETERMINE WHETHER THE ACTIVITY INVOLVES ADVERSE EFFECTS (NEI 96-07, Appendix B, Section B.4.2.1)

(If ALL the questions in Part V or Part VI are answered NO, then Part VII is Z NOT APPLICABLE) pnrF-. I ir

Point Beach Nuclear Plant SCR 2002-0458 Verify SCR number on all pages 10 CFR 50.59/72.48 SCREENING (NEW RULE)

Page 6 Answer the following questions to determine if the activity has an adverse effect on a design function. Any YES answer means that a 10 CFR 72.48 Evaluation is required; EXCEPT where noted in Part VII 3.

VII.1 Changes to the Facility or Procedures YES NO QUESTION El El Does the activity adversely affect the designfuncthon of a plant, cask, or ISFSI SSC credited in safety analyses?

El [] Does the activity adversely affect the method of performing or controlling the designfunction of a plant, cask, or ISFSI SSC credited in the safety analyses?

If any answer is YES, a 10 CFR 72.48 Evaluation is required. If both answers are NO describe the basis for the conclusion (attach additional discussion, as necessary):

VII.2 Changes to a Method of Evaluation (If the activity does not involve a method of evaluation, these questions are [] NOT APPLICABLE.)

YES NO QUESTION El E] Does the activity use a revised or different method of evaluation for performing safety analyses than that described in a cask SAR?

E0 El Does the activity use a revised or different method of evaluation for evaluating SSCs credited in safety analyses than that described in a cask SAR?

If any answer is YES, a 10 CFR 72.48 Evaluation is required. If both answers are NO describe the basis for the conclusion (attach additional discussion, as necessary):

VII.3 Tests or Experiments (If the activity is not a test or experiment, the questions in VII.3.a and VII.3.b are [] NOT APPLICABLE.)

a. Answer these two questions first:

YES NO QUESTION El El Is the proposed test or experiment bounded by other tests or experiments that are described in the cask ISFSI licensing basis?

El El Are the SSCs affected by the proposed test or experiment isolated from the cask(s) or ISFSI facility?

If the answer to both questions is { continue to VII.3.b. If the answer to EITHER question is YES then briefly describe the basis.

b. Answer these additional questions ONLY for tests or experiments which do not meet the criteria given in VII.3.a above.

If the answer to either question in VII.3.a is YES, then these three questions are [E NOT APPLICABLE:

PnF-1 Il ,c

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Venfy SCR number on all pages Page 7 YES NO QUESTION "El El Does the activity utilize or control an SSC in a manner that is outside the reference bounds of the design bases as described in the ISFSI licensing basis?

"El El Does the activity utilize or control a plant, cask or ISFSI facility SSC in a manner that is inconsistent with the analyses or descriptions in the ISFSI licensing basis?

[E El Does the activity place the cask or ISFSI facility in a condition not previously evaluated or that could affect the capability of a plant, cask, or ISFSI SSC to perform its intended functions?

If any answer in VII.3.b is YES a 10 CFR 72.48 Evaluation is required. If the answers are all NO, describe the basis for the conclusion (attach additional discussion as necessary):

PART VIII - DOCUMENT THE CONCLUSION OF THE 10 CFR 72.48 SCREENING Check all that apply:

A 10 CFR 72.48 Evaluation is E] required or Z NOT required. Obtain a screening number and provide the original to Records Management regardless of the conclusion of the 50.59 or 72.48 screening.

A VSC-24 cask Safety Analysis Report change is E] required or E] NOT required. If a VSC-24 cask SAP. change is required, then contact the Point Beach Dry Fuel Storage group supervisor.

A Regulatory Commitment (CLB Commitment Database) change is E] required or Z NOT required. If a Regulatory Commitment Change is required, initiate a commitment change per NP 5.1.7.

A change to the VSC-24 10 CFR 72.212 Site Evaluation Report is [E required or 0 NOT required. If a VSC-24 10 CIR 72.212 Site Evaluation Report change is required, then contact the Point Beach Dry Fuel Storage group supervisor.

r)nrw.i r i -c-

IT-1OA TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 13 EFFECTIVE DATE: September 9, 2002 "REVIEWER: Qualified Reviewer APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Operations Verified Current Copy:

Signature Date Time List pages used for Partial Performance Controlling Work-Document Numbers

. I POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

NOTE: This procedure does NOT satisfy the following IT-10, "Test of Electrically-Driven Auxiliary Feed Pumps and Valves Quarterly" surveillance tests; AF-4020, AF-4022, 2AF-103, and 2AF-105 Inservice Testing Program tests.

1.0 PURPOSE 1.1 This procedure partially satisfies Technical Specification 5.5.7 by conducting the following PBNP Inservice Testing Program tests in accordance with the ASME OM Code 95 Ed./96A. Successful performance of this test will satisfy Technical Specification SR 3.7.5.2.(B.i) 1.1.1 Comprehensive functional test of the Electric-Driven Auxiliary Feed Pumps as required by Technical Specification SR 3.7.5.2 and the ASME, OM Code.

1.1.2 Quarterly full-stroke open and shut, timing and position indication test of the following Auxiliary Feed Pump discharge valves as required by the ASME OM Code:

AF-4021, P-38B AFP Discharge to 1HX-1B Steam Generator AF-4023, P-38A AFP Discharge to 1HX-1A Steam Generator 1.1.3 Quarterly stroke open, timing, and position indication test of the following valves as required by the ASME OM Code:

AF-4012, P-38A AFP Discharge Control AF-4019, P-38B AFP Discharge Control 1.1.4 Quarterly stroke open and shut, timing, position indication, and fail-safe test of the following valves as required by the ASME OM Code:

AF-4007, P-38A AFP Mini-Recirc Control AF-4014, P-38B AFP Mini-Recirc Control Page 2 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY) 1.1.5 Quarterly full stroke open exercise tests for the following check valves, as required by the ASME OM Code:

1AF-102, P-38A AFP Discharge to 1HX-IA SG Check 1AF-104, P-38B AFP Discharge to 1HX-1B SG Check AF-109, P-38A AFP Discharge Check AF-1 10, P-38B AFP Discharge Check AF-1 12, P38A Suction Check from CSTs AF-1 13, P38B Suction Check from CSTs AF-1 15, P-38A, Minimum Flow Check AF-1 16, P-38B, Minimum Flow Check 1.1.6 Quarterly open and shut exercise tests for the following check valves, as required by the ASME OM Code:

AF-142, AF-4012 Backup N2 Check AF-145, AF-4012 Backup N2 Check AF-162, AF-4019 Backup N2 Check AF-165, AF-4019 Backup N2 Check 1.1.7 Quarterly open and shut exercise tests for the following nitrogen backup first-off check valves as required by the ASME OM Code:

AF-133, P-38A AFP AF-4012 N2 Backup First-off Isol AF-153, P-38B AFP AF-4019 N 2 Backup First-off Isol 1.2 Verify auxiliary feedwater flow path operable to each steam generator following each cold shutdown of greater than 30 days and prior to exceeding 2% RTP, as required by Technical Specification SR 3.7.5.5.

2.0 PREREQUISITES 2.1 Assemble the following portable test instruments and log their ID numbers, as required.

2.1.1 Stop watch (2 required)

Control Room ID No.

Cal Due Date:

Local ID No.

Cal Due Date:

2.1.2 Vibration monitor, if required. ID No.

Cal Due Date:

Page 3 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY) 2.2 IF it is desired to consider the equipment Available per the Maintenance Rule, THEN two Level 4 Dedicated Operators will be required, one for the Control Room and the second locally per OM 3.26, Use of Dedicated Operators, during the performance of this procedure.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 If there is any problem in performing this test, then immediately notify the -duty shift superintendent. Operation of this equipment is a technical specification requirement.

3.2 Injection of auxiliary feed to steam generators at power will cause an increase in reactor power. RTO calculation does NOT account for auxiliary flow and is therefore unreliable. Use of DTP and Nuclear Instruments is mandatory during that time. (B-3) 3.3 Do NOT perform more than one portion of this test at a time.

3.4 Low suction pressure causes a common suction pressure alarm and a low suction pressure trip with an attendant alarm and-a trip-enabled light. This trip is reset by placing the control switch to PULLOUT and then to the desired position. Reset is verified by the trip-enabled light being'exiinguished.

3.5 For the purpose of valve stroke testing, the stroke time is the time it takes the valve to go from full open to full shut or full shut to full open, by control board indication. Timing of valve operation will be from the moment of control switch actuation until the desired position is indicated. Local Position Indication Testing (PIT) requires at-valve observation.

3.6 The operability determination of a valve shall only be made in the direction which is required for the valve to perform its safety related functions. Valve stroking in a direction NOT required by the IST program is identified by "For Information Only" within the body of the step.

3.7 To test a given trairror component of the train, the opposite trains normail off-site power is operable and standby emergency power is capable of supplying power.

3.8 If, at any time, pump suction pressure is less than the NPSH required (4.8 psig), then discontinue this test until the problem is corrected.

P 3.9 Fire rounds are NOT required during testing.

3.10 To prevent damage to P-38A and P-38B monitor and maintain AFW discharge and I or recirc flow greater than 50 GPM OR Stop respective AFW pump.

Page 4 of 54 CONTINUOUS USE

SPOINT BEACH NUCLEAR PLANT IT 10A INS ERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 4.0 INITIAL CONDITIONS 4.1 This test is being done to satisfy:

The normally scheduled callup. Task sheet No.

NOTE: If this test is being performed to satisfy PMT or off-normal frequ'ency requirements, Shift Management may N/A those portions of the procedure that are NOT applicable for the performance of the PMT. The use of N/A is NOT__ acceptable for Initial Conditions, Precautions and Limitations, or procedure steps that pertain to the equipment requiring PMT, nor is it acceptable for restoration of equipment/components unless the component has been declared inoperable.

-Post maintenance operability test Equipment ID WO No(s).

Task Sheet No.(s)

Special test - no numbers. Explain:

4.2 Auxiliary feed system lined up for critical operation per CL 13E Part 2, Auxiliary Feedwater Valve Lineup Motor-Driven.

4.3 Standby emergency power shall be available to the 4160 V safeguards buses 1A05, 1A06, 2A05, 2A06, or the component(s) to be tested is/are in the same train that is out of service.

4.4 Chemistry notified about auxiliary feed injection.

4.5 Reactor power reduced a minimum of 2% OR to a power level directed by DSS. (Mark step N/A if in Modes 3, 4, 5, 6, or defueled) 4.6 The IST Coordinator is available for PMT data review if the MDAFW pumps have been replaced, disassembled, realigned to the motor (motor replacement included) or the coupling has been disassembled. This review will establish new reference values and is performed prior to declaring the pump operable. (Mark N/A for oil changes and other minor maintenance which does NOT affect pump vibration or hydraulic performance).

4.7 The IST Coordinator is available for power ot5erated valve reference value data review prior to declaring the valve operable. This step is not applicable if PBF-2114, "Return to Service Testing Reviews" does NOT specify performance of a reference value test.

Page 5 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 4.8 Permission to Perform Test The conditions required by this test are consistent with required plant conditions, including equipment operability. Permission is granted to perform this test.

DSS TIME_ _ DATE NOTE: Attachment L shall be used to document performance of multiple step performance and to record data. A separate copy of Attachment L shall be prepared for each step series requiring multiple performance and all copies shall be attached to this procedure when the procedure is complete.

5.0 PROCEDURE 5.1 IF in Mode 5, 6, or defueled, THEN verify the following:

I (Otherwise mark this step as N/A)

"* The Steam Generators are drained to a level sufficient to accept AFW flows.

"* The RCS is NOT solid.

Page 6 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: When operability testing of Train A is NOT required, then N/A Steps 5.2 through 5.34.

5.2 TRAIN A TEST 5.2.1 IF performing Section 5.2, THEN the following Auxiliary Feedwater Pumps with their associated flow paths are operable, as applicable.

(N/A the step that is NOT applicable.)

a. For two-unit operation:

P-38B, IP-29, and 2P-29 are operable

b. For single-unit operation:

P-38B and IP-29 are operable for Unit 1 OR P-38B and 2P-29 are operable for Unit 2 5.2.2 IF sufficient qualified operators are NOT available on shift to support Step 5.2.3, THEN consider the equipment unavailable per Maintenance Rule AND N/A Step 5.2.3.

5.2.3 Assign a Level 4 Dedicated Operator in the Control Room AND a Level 4 Dedicated Operator in the field per OM 3.26, Use of Dedicated Operators, to perform the restoration steps of Attachment J, if required. (Otherwise mark this step as N/A) 5.3 IF required, THEN enter the appropriate TS Action Condition for P-38A per Technical Specification 3.7.5.

TIME DATE 5.4 IF an Auxiliary Feedwater Initiation is required during the performance of this test, THEN immediately perform Attachment J to recover Train A.

(N/A this step if not required.)

Page 7 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: When performing operability checks of the pump only, then N/A Subsections of 5.5 through 5.8 and Steps 5.21 through 5.28.

NOTE: To prevent preconditioning a valve, the applicable Section steps shall be performed out of sequence to provide a recordable action for each valve manipulation. (i.e., If the mnitial position of the valve is shut and the first step is to shut and time the valve, then the opening stroke evolution shall be performed first.)

5.5 Perform Quarterly Full Stroke Open and Shut, Timing, and Position Indication Test of AF-4023, P-38A AFP Discharge to IHX-IA Steam Generator as follows:

5.5.1 Open AND time AF-4023, P-38A AFP Discharge to 1HX-1A Steam Generator:

a. Record time to open on Attachment A.

b. Check local valve position indication and record on Attachment A.

5.5.2 Shut AND time AF-4023, P-38A AFP Discharge to 1HX-1A Steam Generator:

a. Record time to shut on Attachment A.

6. Check local valve position indication and record on Attachment A.

Page 8 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: The ability for AF-4012 to demonstrate acceptable stroke times to the open position also satisfies the exercise requirements in the open direction for AF-133, P-38A AFP AF-4012 N2 Backup First-off Isol, as required by the ASME OM Code.

5.6 Perform Quarterly Stroke Open. Timing and Position Indication Test of AF-4012, P-38A AFP Discharge Control, and Open Exercise Test of AF-133, P-38A AFP AF-4012 N, Backup First-off Isol. as follows:

5.6.1 Place PC-4012, P-38A AFP Discharge Pressure Controller, in MANUAL.

5.6.2 Shut AF-135, P-38A AFP AF-4012 Nitrogen Backup Second Off Isolation.

5.6.3 Open AND time AF-4012, P-38A AFP Discharge Control:

a. Record time to open on Attachment A.

b. Check local valve position indication and record on Attachment A.

5.6.4 Shut AND time AF-4012, P-38A AFP Discharge Control:

(for information only)

a. Record time to shut on Attachment A.

b. Check local valve position indication and record on Attachment A.

5.6.5 Open AF-135, P-38A AFP AF-4012 Nitrogen Backup Second Off Isolaition.

5.6.6 IF NOT continuing with the balance of this procedure, THEN contiihue with Step 5.27.

(Otherwise mark this step as N/A)

NOTE: C01A 2-8 and 2-10, Auxiliary Feedwater System Disabled, annunciators will alarm when P-38A is placed in PULLOUT.

5.7 Place P-38A Motor Driven Aux Feed Pump control switch in PULLOUT.

Page 9 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: Use local indication for timing AF-4007, P-38A AFP Mini-Recirc Control. Stroke time to closed satisfies Fail Safe Test requirements.

5.8 Perform Quarterly Stroke Open and Shut, Timing. and Position Indication, and Fail-Safe Test of AF-4007, P-38A AFP Mini-Recirc Control as follows:

5.8.1 Unlock AND shut AF-123A, P-38A AFP Mini Recirc AF-4007-S Outlet Isolation.

5.8.2 Unlock AF-123B, P-38A AFP Mini Recirc AF-4007-S Bypass Isolation.

5.8.3 Open AND time AF-4007, P-38A AFP Mini-Recirc Control, by opening AF-123B, P-38A AFP Mini Recirc AF-4007-S Bypass Isolation:

a. Record time to open on Attachment A.

b. Check local position indication and record on Attachment A.

5.8.4. Shut AF-123B, P-38A AFP Mini Recirc AF-4007-S Bypass Isolation.

5.8.5 Shut AF-4007, P-38A AFP Mini-Recirc Control, by opening AF-123A, P-38A AFP Mini Recirc AF-4007-S Outlet Isolation:

a. Record time to shut on Attachment A.

b. Check local position indication and record on Attachment A.

5.8.6 Red lock OPEN AF-123A, P-38A AFP Mini Recirc AF-4007-S Outlet Isolation.

IV 5.8.7 Red lock SHUT AF-123B, P-38A AFP Mini Recirc AF-4007-S Bypass Isolation.

IV 5.8.8 Ensure P-38A LO suction pressure trip has reset.

Page 10 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.9 Ensure P-38A AFP Discharge valves shut:

AF-4022, P-38A AFP Discharge to 2HX-1A Steam Generator AF-4023, P-38A AFP Discharge to lHX-1A Steam Generator.

5.10 Check P-38A pump bearing oil level between the red lines on the glass.

Inboard Outboard 5.11 Place PI-4010A, P-38A AFP Suction Pressure Indicator in service:

5.11.1 Shut AF-36D, PI-4010A vent valve.

5.11.2 Open AF-36C, PI-4010A isolation valve.

5.11.3 Record suction pressure on Attachment B.

5.12 Ensure PC-4012, P-38A AFP Discharge Pressure Controller is in MANUAL AND SHUT.

CAUTION If, at any time, equipment operation appears abnormal, secure the pump.

NOTE: C01A 2-8 and 2-10, Auxiliary Feedwater System Disabled, annunciator will clear when P-38A is removed from PULLOUT.

5.13 Start P-38A. Time Start NOTE: P-38A suction pressure trip is set at 6.5 psig (with a 20 second delay).

5.14 Ensure P-38A suction pressure as read on PI-4010A is greater than the 7.0 psig low suction pressure alarm setpoint. Record on Attachment B.

Page I11 of 54 CONTINUOUS USE

- POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.15 Check AF-4007, P-38A AFP Mini-Recirc Control, mini-recirculation valve open.

NOTE: The following step satisfies full stroke exercising of AF-115, P-38A (I Minimum Flow Check Valve.

5.16 Check mini-recirculation is equal to or greater than 70 gpm, (expected I range is 70 to 85 gpm) on FIT-4050A AND record on Attachment B.

5.17 Check the packing glands for excessive leakage or overheating.

5.18 Check pump and motor for unusual noise or overheating.

5.19 WHEN P-38A has run for two-minutes, THEN record the following on Attachment B.

"* PI-4011, Pump Discharge Pressure

", PI-4010A, Pump Suction Pressure

"* Recirculation Flow Vibration Data To prevent damage to P-38A monitor and maintain AFW discharge and I or recirc flow greater than 50 GPM OR STOP P-38,A.

Page 12 of 54 CONTINUOUS USE

POLNT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: Injection of auxiliary feedwater to steam generators at power will cause an increase in reactor power. RTO calculation does NOT account for auxiliary feedwater flow and is therefore unreliable.

Use of DTP and Nuclear Instruments is mandatory during that time. (B-3) 5.20 Perform Quarterly Full Stroke Open Exercise Test of Check Valves lAF-102, AF-109, AF-1 12. and Full Flow Test of P-38A as follows:

5.20.1 Open AF-4023, P-38A AFP Discharge to 1HX-1A Steam Generator.

NOTE: Rapid Flow adjustments may cause Steam Generator Level deviation alarms to be generated.

5.20.2 Adjust PC-4012, P-38A AFP Discharge Pressure Controller, to establish approximately 115 gpm as read locally on DPIS-4007.

5.20.3 After at least 45 seconds of operation above 95 gpm, check AF-4007, P-38A AFP Mini-Recirc Control, SHUT.

NOTE: Rapid Flow adjustments may cause Steam Generator Level deviation alarms to be generated.

5.20.4 Adjust PC-4012, P-38A AFP Discharge Pressure Controller, to establish greater than or equal to 200 gpm as read locally on DPIS-4007.

5.20.5 WHEN P-38A has run for two-minutes with stable flow at equal to or greater than 200 gpm, THEN record data on 'Attachment C and the IST required vibration points listed on Attachment C.

5.20.6 Shut PC-4012, P-38A AFP Discharge Pressure Controller.

"5.20.7 Check AF-4007, P-38A AFP Mini-Recirc Control, open. "

5.20.8 Shut AF-4023, P-38A AFP Discharge to IHX-1A Steam

~~~~Generator.

0 tCAUTION 0 To prevent damage to P-38A monitor and maintain AFW discharge and / or recirc flow greater than 50 GPM OR STOP P-38A.

3 of 5CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.20.9 Perform the following to remove PI-4010A from service:

a. Shut AF-36C, PI-4010A.

b. Open AF-36D, PI-4010A Vent Valve.

NOTE: C01A 2-8 and 2-10, Auxiliary Feedwater System Disabled, annunciators will alarm when P-38A is placed in PULLOUT.

5.20.10 Place P-38A control switch in STOP, THEN PULLOUT.

Observe pump during coastdown for unusual noises, vibrations, or other abnormal conditions. Record results on Attachment C.

Time stop 5.20.11 Set PC-4012, P-38A AFP Discharge Pressure Controller, setpoint at 1200 psig.

5.20.12 Place PC-4012, P-38A AFP Discharge Pressure Controller, in AUTO.

I 5.21 Perform Quarterly Shut Exercise Test of AF-133, P-38A AFP AF-4012 N2 Backup First-off Isol, as follows:

5.21.1 Make an entry into the SOMs log stating that P-38A is unavailable per IT I0A.

5.21.2 Shut AF-130, AF-4012 AFP Discharge Control Pneumatic, valve. ^.

5.21.3 Shut AF-184, P-38A AFP AF-4063 Upstream Isolation.

5.21.4 Shut IA-354, I/P-4012 AFP Discharge Control Air Inlet.

5.21.5 Uncap AND open the following:

• AF-132, Intermediate Vent 0 IA-355, Instrument Air Vent Page 14 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

INITIALS 5.21.6 Record PI-4051, AF-4012 AFP Disch Ctl AF-4053 N2 Backup Reg Outlet PI, pressure on Attachment D.

NOTE: The Normal Alignment is one Nitrogen bottle valved in with its bottle stop open and one Nitrogen bottle isolated with its bottle stop shut. Pressure must be greater than 1850 psig as indicated on PI-4054.

5.21.7 Shut the isolation valve for the in-service N2 bottle, AF-146 or AF-143, AND begin timing. (Circle the valve isolated because it will be returned to service later in the procedure).

AF-146 \ AF-143 NOTE: It is permissible to use 'snoop' to check for and tighten fittings within the test boundary if leakage appears to be excessive.

5.21.8 WFIEN 15 minutes have elapsed, THEN record PI-4051, AFP Disch Ctl AF-4053 N2 Backup Reg Outlet PI, pressure and elapsed time on Attachment D.

5.21.9 Shut AND cap the following:

• AF-132, Intermediate Vent IV

• IA-355, Instrument Air Vent IV 5.21.10 Open AF-130, AF-4012 AFP Discharge Control Pneumatic.

IV 5.21.11 Open AF-184, P-38A AFP AF-4063 Upstream Isolation.

IV Page 15 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: The ability of AF-4012 to exercise by the South nitrogen bottle within the required acceptance criteria time limitations satisfies the-stroke open test of check valve AF-145 and stroke shut test of AF-142.

5.22 Perform Quarterly Open Exercise Test of AF-145, P-38A AFP N, Backup South Bottle, Check Valve and Shut Exercise Test of AF-142, P-38A AFP N, backup North Bottle, Nitrogen Backup Check Valve as follows:

5.22.1 Open AF-146, P-38A AFPAF-4012 N2 Backup South Bottle Outlet Isolation Valve.

5.22.2 Open the south N2 Bottle Stop Isolation Valve.

5.22.3 Ensure the north N 2 Bottle Stop Isolation Valve is SHUT.

5.22.4 Open AF-143, P-38A AFP AF-4012 N2 Backup North Bottle Outlet Isolation Valve.

5.22.5 Ensure AF-144, P-38A AFP AF-4012 N2 Backup North Bottle Outlet Vent is SHUT.

5.22.6 Remove vent cap downstream of AF-144 AND slowly Open AF-144.

5.22.7 Ensure PC-4012, P-38A AFP Discharge Pressure Controller, in MANIUAL.

5.22.8 Open AND time AF-4012, P-38A AFP Discharge Control.

5.22.9 Record time to open on Attachment D.

5.22.10 Shut AND time AF-4012, P-38A AFP Discharge Control.

(for information only) 5.22.11 Record time to shut on Attachment D.

5.22.12 Shut AF-144, P-38A AFP AF-4012 N2 Backup North Bottle Outlet Vent AND install downstream vent cap.

5.22.13 Shut AF-146, P-38A AFP AF-4012 N2 Backup South Bottle Outlet Isolation Valve.

Page 16 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.22.14 Shut AF-143, P-38A AFP AF-4012 N2 Backup North Bottle Outlet Isolation Valve.

5.22.15 Shut the south N2 Bottle Stop Isolation Valve.

NOTE: The ability of AF-4012 to exercise by the North nitrogen bottle within the required acceptance criteria time limitations satisfies the-stroke open test of check valve AF-142 and stroke shut test of AF-145.

5.23 Perform Quarterly Open Exercise Test of AF-142, P-38A AFP N, Backup North Bottle, Nitrogen Backup Check Valve, and Shut Exercise Test of AF-145, P-38A AFP N2 Backup South Bottle Check Valve as follows:

5.23.1 Open AF-143, P-38A AFP AF-4012 N2 Backup North Bottle Isolation Valve.

5.23.2 Open the north N 2 Bottle Stop Isolation Valve.

5.23.3 Ensure the south N2 Bottle Stop Isolation Valve is SHUT.

5.23.4 Open AF-146, P-38A AFP AF-4012 N2 Backup South Bottle Outlet Isolation Valve.

5.23.5 Ensure AF-147, P-38A AFP AF-4012 N2 Backup South Bottle Outlet Vent is SHUT 5.23.6 Remove vent cap downstream of AF-147 AND slowly Open AF-147.

5.23.7 Ensure P.C-4012, P-38A AFP Discharge Pressure Controller, in MANUAL.

5.23.8 Open AND time AF-4012, P-38A AFP Discharge Control.

5.23.9 Record time to open on Attachment D.

5.23.10 Shut AND time AF-4012, P-38A AFP Discharge Control.

(for information only) 5.23.11 Record time to shut on Attachment D.

Page 17 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.23.12 Shut AF-147, P-38A AFP AF-4012 N2 Backup South Bottle Outlet Vent AND install downstream vent cap.

5.23.13 Shut AF-143, P-38A AFP AF-4012 N2 Backup North Bottle Isolation Valve.

5.23.14 - Shut AF-146, P-38A AFP AF-4012 N2 Backup South Bottle Outlet Isolation Valve.

5.23.15 Shut the north N 2 Bottle Stop Isolation Valve.

5.24 Open IA-354, I/P-4012 AFP Discharge Control Air Inlet.

IV 5.25 Open Nitrogen bottle isolation valve closed in Step 5.21.7. AF-146 or AF-143.

IV 5.26 Ensure the associated north/south N 2 Bottle Stop Isolation Valve is OPEN.

IV 5.27 Set PC-4012, P-38A AFP Discharge Pressure Controller, controller setpoint, at 1200 psig.

5.28 Ensure PC-4012, P-38A AFP Discharge Pressure Controller, in AUTO.

NOTE: C01A 2-'8 and 2-10, Auxiliary Feedwater System Disabled, annunciators will clear when P-38A is placed in AUTO.

5.29 Place P-38A control switch in AUTO.

5.30 Make an entry into fhe SOMs log stating that P-38A is available per IT 10A.

Pagle IS of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.31 Perform Independent Operator Verification.

VALVE DESCRIPTION POSITION PC-4012 P-38A AFP Discharge Pressure Controller Auto 1200 AF-4022 P-38A AFP Discharge to 2HX-1A Steam SHUT*

Generator AF-4023 P-38A AFP Discharge to 1HX-1A Steam SHUT*

Generator AF-4007 P-38A Mini Recirc Control UG/LH N/A P-38A control switch AUTO

• The pump discharge valve control switch for an operating unit must be in AUTO 1 5.32 IF test is being performed as a post-maintenance operability pump test, THEN contact an IST Engineer or representative to verify measured I ASME OM Code data is acceptable prior to declaring the pump operable.

5.33 Check operability by comparing the test data with pump and valve acceptance criteria in Attachments A, B, C, and D and sign the last page of each Attachment.

5.34 IF test was satisfactory, THEN exit the TS Action Condition for P-38A. Otherwise, N/A this step and start fire rounds.

Time Date 5.34.1 IF Level 4 Dedicated Operators were assigned to positions in Step 5.2.3, THEN release them from their duties.

(N/A if continuing with Train B) 5.34.2 IF Train B has already been tested OR is NOT planned on being tested, THEN proceed to Step 5.69, Recovery.

Page 19 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: DSS permission is required to proceed with Step 5.35.

NOTE: When operability testing of Train B is NOT required, then N/A Steps 5.35 through 5.68.

5.35 TRAIN B TEST 5.35.1 IF performing Section 5.35, THEN the following auxiliary feedwater pumps with their associated flow paths, are operable as applicable.

(N/A the step that is NOT applicable.)

a. For two-unit operation:

P-38A, 1P-29, and 2P-29 are operable

b. For single-unit operation:

P-38A and 1P-29 are operable for Unit I OR P-38A and 2P-29 are operable for Unit 2 5.35.2 IF sufficient qualified operators are NOT available on shift to support step 5.35.3, THEN consider the equipment unavailable per Maintenance Rule AND N/A step 5.35.3.

5.35.3 Assign a Level 4 Dedicated Operator in the Control Room AND a Level 4 Dedicated Operator in the field per OM 3.26, Use of Dedicated Operators, to perform the restoration steps of Attachment K, if required. (Otherwise mark this step as N/A) 5.36 IF required, THEN enter the appropriate TS Action Condition for P-38B per Technical Specification 3.7.5.

TIME DATE 5.37 IF an Auxiliary Feedwater Initiation is required during the performance of this test, THEN immediately perform Attachment K to recover Train B. (N/A this step if not required.)

Page 20 of 54 CONTINUOUS USE

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INITIALS NOTE: When performing operability checks of the pump only, then N/A all Steps of 5.38 through 5.41 and Steps 5.55 through 5.62.

NOTE: To prevent preconditioning a valve, the applicable Section steps shall be performed out of sequence to provide a recordable action for each valve manipulation. (i.e., If the initial position of the valve is shut and the first step is to shut and time the valve, then the opening stroke evolution shall be performed first.)

5.38 Perform Quarterly Full Stroke Open and Shut, Timing, and Position Indication Test of AF-4021, P-38B AFP Discharge to 1HX-IB Steam Generator as follows:

5.38.1 Open AND time AF-4021, P-38B AEP Discharge to 1HX-1B Steam Generator.

a. Record time to open on Attachment E.

b. Check local valve position indication and record on Attachment E.

5.38.2 Shut AND time AF-4021, P-38B AFP Discharge to 1HX-1B Steam Generator, AND perform the following:

a. Record time to shut on Attachment E.

b. Check local valve position indication and record on Attachment E.

Page 21 of 54 CONTINýUOUS USE

• POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: The ability for AF-4019 to demonstrate'acceptable stroke times to the open position also satisfies the exercise requirements in the open direction for AF-153, P-38B AFP AF-4019 N2 Backup First-off Isol, as required by the ASME OM Code.

5.39 Perform Quarterly Stroke Open. Timing, and Position Indication Test of AF-4019, P-38B AFP Discharge Control. and Open Exercise Test of AF-153, P-38B AFP AF-4019 N) Backup First-off Isol, as follows:

5.39.1 Place PC-4019, P-38B AFP Discharge Control, in MANUAL.

5.39.2 Shut AF-155, P-38B AFP AF-4019 Nitrogen Backup Second Off Isolation.

5.39.3 Open AND time AF-4019, P-38B AFP Discharge Control:

a. Record time to open on Attachment E.

b. Check local valve position indication and record on Attachment E.

5.39.4 Shut AND time AF-4019, P-38B AFP Discharge Control.

(For information only)

a. Record time to shut on Attachment E.

b. Check local valve position indication and record on Attachment E.

5.39.5 Open AF-155, P-38B AFP AF-4019 Nitrogen Backup Second Off Isolation.

5.39.6 IF NOT continuing with the balance of this procedure, THEN continue with Step 5.61.

(Otherwise mark this step as N/A)

NOTE: C01A 2-8 and 2-10, Auxiliary Feedwater System Disabled, annunciators will alarm when P-38B is placed in PULLOUT.

5.40 Place P-38B Motor Driven Aux Feed Pump control switch in PULLOUT.

Page 22 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: Use local indication for timing of AF-4014, P-38B AFP Mini-Recirc Control. Stroke time to closed satisfies Fail Safe Test requirements.

5.41 Perform Quarterly Stroke Open and Shut, Timing, Position Indication, and Fail-Safe Test of AF-4014, P-38B AFP Mini-Recirc Control as follows:

5.41.1 Unlock AND shut AF-124A, P-38B AFP Mini Recirc AF-4014-S Outlet Isolation.

5.41.2 Unlock AF-124B, P-38B AFP Mini Recirc AF-4014-S Bypass Isolation.

5.41.3 Open AND time AF-4014, P-38B AFP Mini-Recirc Control, by opening AF-124B, P-38B AFP Mini Recirc AF-4014-S Bypass Isolation:

a. Record time to open o~n Attachment E.

b. Check local valve position indication and record on Attachment E.

5.41.4 Shut AF-124B, P-38B AFP Mini Recirc AF-4014-S Bypass Isolation.

5.41.5 Shut AND time AF-4014, P-38B AFP Mini-Recirc Control, by opening AF-124A:

a. Record time to shut on Attachment E.

b. Check local valve position indication and record on Attacliment E.

5.41.6 Red lock OPEN AF-124A, P-38B AFP Mini-Recirc AF-4014-S Outlet Isolation.

IV 5.41.7 Red lock SHUT AF-124B, P-38B AFP Mini Recirc AF-4014-S Bypass Isolation.

IV 5.41.8 Ensure P-38B LO Suction Pressure Trip has reset.

Page 23 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.42 Ensure P-38B AFP Discharge valves shut:

AF-4020, P-38B AFP Discharge to 2HX-1B Steam Generator.

AF-4021, P-38B Discharge to 1HX-lB Steam Generator.

5.43 Check P-38B pump bearing oil level between the red line on the glass:

Inboard Outboard 5.44 Place PI-4017A, P-38B AFP Suction Pressure Indicator in service as follows:

5.44.1 Shut AF-49D, PI-4017A vent valve.

5.44.2 Open AF-49C, PI-4017A isolation valve.

5.44.3 Record suction pressure on Attachment F.

5.45 Ensure PC-4019, P-38B AFP Discharge Control is in MANUAL AND SHUT.

CAUTION If, at any time, equipment operation appears abnormal, secure the pump.

NOTE: C01A 2-8 and 2-10, Auxiliary Feedwater System Disabled, annunciator will clear when P-38B is removed from PULLOUT.

56 Start P-38B. Time Sta-rt NOTE: P-38B suction pressure trip is set at 6.5 psig (with a 20 second delay).

5.47 Ensure P-38B suction pressure as read on PI-4017A is greater than the 7.0 psig low suction pressure alarm setpoint. Record on Attachment F.

Paee 24, of 54 CONTTNT TOTt TT q.

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.48 Check AF-4014, P-38B AFP Mini-Recirc Control, mini-recirculation valve open.

NOTE: The following step satisfies full stroke exercising of AF-116, P-38B Minimum Flow Check Valve.

5.49 Check mini-recirculation is equal to or greater than 70 gpm, (expected I range is 70 to 85 gpm) on FIT-4050B AND record on Attachment F.

5.50 Check packing glands for excessive leakage or overheating.

5.51 Check the pump and motor for unusual noise or overheating.

5.52 WHEN P-38B has run for two-minutes, THEN record the following data on Attachment F:

PI-4018, Pump Discharge Pressure S* PI-4017A, Pump Suction Pressure

• Recirculation Flow Vibration Data 0

0 0

Y26 A Paze 25 of 541 P 5 5('CTh3TT r)TTqTTTT*T

POINT BEACH NUCLEAR PLANT IT 10A INS ERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: Injection of auxiliary feedwater to steam generators at power will cause an increase in reactor power. RTO calculation does NOT account for auxiliary feedwater flow and is therefore unreliable.

Use of DTP and Nuclear Instruments is mandatory during that time. (B-3)

Perform Full Stroke Oen Exercise Test of Check Valves IAF-104 I I 5.53 AF-110, AF-113, and Full Flow Test of P-38B as follows:

.53.1 Open AF-4021, P-38B Aux Feedwater Pump Disch to 1HX-1B Steam generator.

OTE: Rapid Flow adjustments may cause Steam Generator Level deviation alarms to be generated.

0Cn .53.2 Adjust PC-4019, P-38B AFP Discharge Control, to establish v: approximately 115 gpm as read locally on DPIS-4014.

.53.3 After at least 45 seconids of operation above 95 gpm, check AF-4014, P-38B AFP Mini-Recirc Control, SHUT.

U)

NOTE: Rapid Flow adjustments may cause Steam Generator Level deviation alarms to be generated.

~C4 00 5.53A Adjust PC-4019, P-38B AFP Discharge Control, to establish.

greater than or equal to 200 gpm as read locally on DPIS-4014.

5.53.5 WHEN P-38B has run for two-minutes with stable flow at q greater than or equal to 200 gpm, THEN record data on Attachment G and the IST required vibration points listed on Attachment G*

L 5.53.6 Shut PC-4019, P-38B AFP Discharge Control.

F-l cOP 5.53.7 Check AF-4014, P-38B AFP Mini-Recirc Control, open.

5.53.8 Shut AF-4021, P-38B AFP Disch to Unit I SG B CV.

5.53.9 Perform the following to remove PI-4017A from service:

a. Shut AF-49C, PI-4017A.

b. Open AF-49D, PI-4017A vent valve.

Pasze 26 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT I1A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: CO1A 2-8 and 2-10, Auxiliary Feedwater System Disabled, annunciators will alarm when P-38B is placed in PULLOUT.

5.53.10 Place P-38B control switch in STOP, THEN PULLOUT.

Observe pump during coastdown for unusual noises, vibrations, or any other abnormal conditions. Record results on Attachment G.

Time Stop 5.53.11 Set PC-4019, P-38B AFP Discharge Control, controller setpoint, at 1200 psig.

5.53.12 Place PC-4019, P-38B AFP Discharge Control, in AUTO.

5.54 IF Unit 1 Reactor Power was reduced to perform this test, THEN power increase may be commenced as directed by the DSS.

(Mark as N/A if desired) _

5.55 Perform Shut Exercise Test of AF-153, P-38B AFP AF-4019 N2 Backup First-off Isol, as follows:

5.55.1 Make an entry into the SOMs log stating that P-38B is unavailable per IT 1OA.

5.55.2 Shut AF-150, AF-4019 AFP Discharge Control Pneumatic.

5.55.3 Shut AFý185, P-38B AFP AF-4064 Upstream Iholation.

5.55A Shut IA-356, Instrument Air Isolation valve.

5.55.5 Uncap AND open the following:

0 AF-152, Intermediate Vent

• IA-357, Instrument Air Vent

-4I 5.55.6 Record PI-4056, downstream pressure indicator, pressure on Attachment H.

Page 27 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: The Normal Alignment is one Nitrogen bottle valved in with its bottle stop open and one Nitrogen bottle isolated with its bottle stop shut. Pressure must be greater than 1850_psig as indicated on P1-4059, AF-4019 AFP Disch Ctl AF-4058 N2 Backup Reg Inlet PI.

5.55.7 Shut the isolation valve for the in-service N2 bottle, AF-163 or AF-166, AND begin timing. (Circle the valve isolated because it will be returned to service later in the procedure).

AF-163 \ AF-166 NOTE: It is permissible to use 'snoop' to check for and tighten fittings within the test boundary if leakage appears to be excessive.

5.55.8 WHEN 15 minutes have elapsed, THEN record PI-4056 pressure and elapsed time on Attachment H.

5.55.9 Shut AND cap the following:

• AF-152, Intermediate Vent IV

• IA-357, Instrument Air Vent IV 5.55.10 Open AF-150, AF-4019 AFP Discharge Control Pneumatic.

IV 5.55.11 Open AF-185, P-38B AFP AF-4064 Upstream Isolation.

IV Pagye 28 of 54 CONTINUOUS USE

POLNT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: The ability of AF-4019 to exercise by the North nitrogen bottle within the required acceptance criteria time limitations satisfies the-stroke open test of check valve AF-165 and stroke shut test of AF-162.

5.56 Perform Quarterly Open Exercise Test of AF-165, P-38B AFP AF-4019 N, Backup North Bottle, Check Valve, and Shut Exercise Test of AF-162, P-38B AFP AF-4019 N, Backup South Bottle, Check Valve as follows:

5.56.1 Open AF-166, P-38B AFP AF-4"019 Backup North Bottle Outlet Isolation Valve.

5.56.2 Open the north N 2 Bottle Stop Isolation Valve.

5.56.3 Ensure the south N 2 Bottle Stop Isolation Valve is SHUT.

5.56.4 Open AF-163 P-38B AFP AF-4019 N2 Backup South Bottle Outlet Isolation Valve.

5.56.5 Ensure AF-164, P-38B AFP AF-4019 N2 Backup South Bottle Outlet Vent is SHUT.

5.56.6 Remove vent cap downstream of AF-164 AND slowly Open AF-164.

5.56.7 Ensure PC-4019, P-38B AFP Discharge Pressure Controller, in MANUAL.

5.56.8 Open AND time AF-4019, P-38B AFP Discharge Control.

5.56.9 Record time to open on Attachment H.

5.56.10 Shut AND time AF-4019, P-38B AFP Discharge Control.

(for information only) 5.56.11 Record time to shut on Attachment H.

5.56.12 Shut AF-164, P-38B AFP AF-4019 N2 Backup South Bottle Outlet Vent AND install downstream vent cap. _

5.56.13 Shut AF-166, P-38B AFP AF-4019 Backup North Bottle Outlet Isolation Valve.

Page 29 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.56.14 Shut AF-163 P-38B AFP AF-4019 N2 Backup South Bottle Outlet Isolation Valve.

5.56.15 Shut the north N2 Bottle Stop Isolation Valve.

NOTE: The ability of AF-4019 to exercise by the South nitrogen bottle within the required acceptance criteria time limitations satisfies the-stroke open test of check valve AF-162 and stroke shut test of AF-165.

5.57 Perform Quarterly Open Exercise Test of AF-162, P-38B AFP AF-4019 N, Backup South Bottle, Check Valve, and Shut Exercise Test of AF-165, P-38B AFP AF-4019 N, Backup North Bottle, Check Valve as follows:

5.57.1 Open AF-163, P-38B AFP AF-4019 Backup South Bottle Outlet Isolation Valve.

5.57.2 Ensure the south N 2 Bottle Stop Isolation Valve is OPEN.

5.57.3 Ensure the north N 2 Bottle Stop Isolation Valve is SHUT.

5.57.4 Open AF-166 P-38B AFP AF-4019 N2 Backup North Bottle Outlet Isolation Valve.

5.57.5 Ensure AF-167, P-38B AFP AF-4019 N2 Backup North Bottle Outlet Vent is SHUT.

5.57.6 Remove vent cap downstream of AF-167 AND slowly Open AF-167.

5.57.7 Ensure P.C-4019, P-38B AFP Discharge Pressure Controller, in MANUAL.

5.57.8 Open AND time AF-4019, P-38B AFP Discharge Control.

5.57.9 Record time to open on Attachment H.

5.57.10 Shut AND time AF-4019, P-38B AFP Discharge Control.

(for information only) 5.57.11 Record time to shut on Attachment H.

Page 30 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.57.12 Shut AF-167, P-38B AFP AF-4019 N2 Backup North Bottle Outlet Vent AND install downstream vent cap.

5.57.13 Shut AF-166, P-38B AFP AF-4019 Backup North Bottle Outlet Isolation Valve.

5.57.14 Shut AF-163, P-38B AFP AF-4019 Backup South Bottle Outlet Isolation Valve.

5.57.15 Shut the south N 2 Bottle Stop Isolation Valve.

5.58 Open IA-356, Instrument Air Isolation valve.

IV 5.59 Open Nitrogen bottle isolation valve closed in Step 5.55.7.

AF 163 or AF-166.

IV 5.60 Ensure the associated north/south N 2 Bottle Stop Isolation Valve is OPEN.

IV 5.61 Set PC-4019, P-38B AFP Discharge Pressure Controller, controller setpoint, at 1200 psig.

5.62 Ensure PC-4019, P-38B AFP Discharge Pressure Controller, in AUTO.

NOTE: COlA 2-8 and 2-10, Auxiliary Feedwater System Disabled, annunciators will clear when P-38B is placed in AUTO.

5.63 Place P-38B control switch in AUTO.

5.64 Make an entry into the SOMs log stating that P-38B is available per IT 10A.

Page 31 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

INITIALS 5.65 Perform Independent Operator Verification.

VALVE DESCRIPTION POSITION PC-4019 P-38B AFP Discharge Control Auto- 1200 AF-4020 P-38B AFP Discharge to 2HX-IB Steam SHUT*

Generator AF-4021 P-38B AFP Discharge to 2HX-1A Steam SHUT*

Generator AF-4014 P-38B Mini-Recirc Control UG/LH P-38B control switch AUTO

• The pump discharge valve control switch for an operating unit must be in AUTO I 1 _ _

5.66 IF test is being performed as a post-maintenance operability pump test, THEN contact an IST Engineer or representative to verify measured ASME OM Code data is acceptable prior to declaring the pump operable.

5.67 Check operability by comparing the test data with pump and Valve acceptance criteria in Attachments E, F, G, and H and sign the last page of the Attachment.

5.68 IF test was satisfactory, I THEN exit TS Action Condition for P-38B. Otherwise, N/A this step and start fire rounds.

Time Date 5.68.1 IF Level 4 Dedicated Operators were assigned to positions in Step 5.35.3.

THEN release them from their duties.

(N/A if 6ontinuing with Train A) 5.68.2 IF Train A has already been tested OR is NOT planned on being tested, THEN proceed to Step 5.69, Recovery.

Page 32 of 54 CONTINUOUS USE

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INITIALS 5.69 RECOVERY IF NOT already performed, AND reactor power was reduced to perform this test, THEN power increase may be commenced as directed by the DSS.

5.70 The SRO to perform Step 6.1 of Section 6.0, Analysis.

Paze 33 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

INITIALS 6.0 ANALYSIS 6.1 Operations 6.1.1 Comparisons with allowable ranges of Acceptance Criteria test I values complete.

SRO Date/Time 6.1.2 Forward completed procedure to IST Coordinator NOTE: To be completed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> of test completion by IST coordinator or his representative.

6.2 IST Coordinator 6.2.1 Comparisons with allowable ranges of test values and analysis N of deviations complete.

6.2.2 Any requirements for corrective action? (If yes, give details in the IST Remarks section.)

(Circle one) YES NO 6.2.3 IF Acceptance Criteria needs updating, THEN initiate a procedure revision. (Otherwise N/A)

Data Analyzed By Date/Time IST Remarks:

Pace 34 of 54 CONTINUOUS USE

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7.0 REFERENCES

7.1 Technical Specifications:

7.1.1 Technical Specification 3.7.5 I 7.1.2 Technical Specification 5.5.7 7.1.3 SR 3.7.5.2 7.1.4 SR 3.7.5.5 I 7.2 Procedures 7.2.1 CL 13E Part 2, Auxiliary Feedwater Valve Lineup Motor-Driven 7.2.2 P&ID M-217, Auxiliary Feedwater System 7.2.3 STPT 14.11, Secondary Systems: Auxiliary Feedwater 7.2.4 OM 3.26, Use of Dedicated Operators I 7.3 Other 7.3.1 ASME OM Code, 95Edition with 96 Addenda, Code for Operation and Maintenance of Nuclear Power Plants 8.0 BASES B-1 CR 98-0690, Surveillance procedures do not contain TS surveillance requirement references B-3 Reference TS-RE-061, AOP-21 Pagge 35 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

REMARKS SECTION:

Page 36 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

Performed By:

i Performer (Print) Performer (Sign) Date Time Initials Performer (Print) Performer (Sign) Date Time Initials

/

Performer (Print) Performer (Sign) Date Time Initials

/ Time Iitial Performer (Print) Performer (Sign) Date Time Initials Date

/ TIt Time Initials Performer (Print) Performer (Sign)

Performer (Print) Performer (Sign) Date Time Initials

/

Performer (Print) Performer (Sign) Date Time Initials

/

Performer (Print) Performer (Sign) Date Time Initials

/ Time Iitial Performer (Print) Performer (Sign) Date Time Initials D Time Iniial Performer (Print) Performer (Sign) Date Time Initials Performer (Print) Performer (Sign) Date Time Initials Performer (Print) Performer (Sign) Date Time Initials Reviewed By:

Shift Supervision (Print) Shift Supervision (Sign) Date Time Initials Page 37 of 54 CONTINUOUS USE

" POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

ATTACHMENT A VALVE STROKE VERIFICATION NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

Full Stroke Open and Shut, Timing, and Position Indication Test of AF-4023, P-38A AFP Discharge to 1HX-I A Steam Generator Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.5.1 Time to OPEN Stopwatch sec. 15.55-21.03 5.5.1 Local Position Indication N/A N/A OPEN 5.5.2 Time to SHUT Stopwatch sec. 15.62-21.14 5.5.2 Local Position Indication N/A N/A SHUT Stroke Open, Timing and Position Indiction Test of AF-4012, P-38A AFP Discharge Control, and Open Exercise Test of AF-133, P-38A AFP AF-4012 N 2 Backup First-off Isol Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.6.3 Time to OPEN - Stopwatch sec. 4.8-14.4 5.6.3 Local Position Indication NIA N/A OPEN 5.6.4 Time to SHUT (info only) Stopwatch sec. N/A 5.6.4 Local Position Indication N/A NIA SHUT Page 38 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT I1A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

ATTACHMENT A - Continued VALVE STROKE VERIFICATION NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

Ir Stroke Open and Shut, Timing, and Position Indication, and Fail-Safe Test of AF-4007, P-38A AFP Mini-Recirc Control Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria I 5.8.3 Time to OPEN Stopwatch sec. 1.9-5.68 5.8.3 Local Position Indication N/A N/A OPEN 5.8.5 Time to SHUT Stopwatch sec. 8.94-14.9 5.8.5 Local Position Indication N/A N/A SHUT Acceptance Criteria Satisfied for all tested valves in Attachment A: (Circle one) SAT UNSAT Remarks:

I I Performer Date/Time SRO Date/Time Page 39 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

ATTACHMENT B P-3 8A, AFW PUMP PERFORMANCE DATA (RECIRCULATION FLOW)

Data that falls outside the listed Acceptance Criteria constitutes inoperability of the NOTE 1: related equipment.

NOTE 2: Vibration points which are shaded must be recorded by the Micro-logger but are NOT required to be transferred to the table. Only points marked A, B, C, D, and E must be transferred to the I table and are required for ASME OM Code. See Figure 1 for locations.

Step No. jParameter Measured Units JReading jAcceptance Criteria Initials 5.11.3 PI-4010A, P-38A AFP Suction Pressure psig N/A 5.14 PI-4010A, P-38A AFP Suction Pressure psig >7 I 5.16 Full Stroke Open Test of AF-1 15 FIT-4050A, Mini-Recirc Flow gpm _70 5.19 PI-4011 Pump Discharge Pressure psig N/A 5.19 PI-4010A, P-38A AFP Suction Pressure psig N/A 5.19 j Recirculation Flow Vibration Data INSTRUMENT UNITS READINGS P38A IV ips Micro-logger IPS pk P38A IH ips Micro-logger IPS pk P38A IH ae Micro-logger G env P38A 1H acc Micro-logger G pk P38A IA ips Micro-logger IPS pk P38A 2V ips Micro-logger IPS pk P38A 2H ips Micro-logger IPS pk ______________

P38A 2H ae Micro-logger G env P38A 2H acc Micro-logger G pk _

P38A 2A ips Micro-logger IPS pk _

P38A 3V ips Micro-logger IPS pk P38A 3H ips Micro-logger IPS pk P38A 3H ae Micro-logger G env P38A 3H acc Micro-logger G pk ARM P38A 4V ips Micro-logger IPS pk P38A 4H ips Micro-logger IPS pk P38A 4H ae Micro-logger G env P38A 4H acc Micro-logger G pk P38A 4A ips Micro-logger IPS pk Page 40 of 54 CONTINUOUS USE

POLN'T BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

ATTACHMENT C P-38A, AFW PUMP FULL FLOW TEST PERFORMANCE DATA and Full Stroke Open Exercise Test of Check Valves IAF-102, AF-109, and AF-l 12 NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

I Full Stroke Open Exercise Test of Check Valves 1AF-102, AF-109, and AF-1 12 Step Parameter Units Reading Acceptance Initials No. Measured Criteria 5.20.5 1PI-468, IHX-1A SG Pressure psig NIA/A 5.20.5 1FI-4036, Flow to IHX-1A SG gpm > 200 P-38A Full Flow IST Required Data (200 gpm)

Step Parameter Units Reading Acceptance Initials No. Measured - Criteria 5.20.5 PI-4010A, P-38A AFP Suction Press psig N/A 5.20.5 PI-4011, P-38A AFP Discharge Press psig N/A 5.20.5 P-38A Delta P Note 1 psig 1186- 1231 5.20.5 FIT-4050A, Mini-Recirc Flow gpm N/A 5.20.5 DPIS-4007, P-38A Flow gpm _>200 5.20.5 P38A 3V ips (C) vibration IPS pk <_0.256 5.20.5 P38A 3H ips (D) vibration IPS pk <_0.491 5.20.5 P38A 4A ips (E) vibratian IPS pk _< 0.378 5.20.5 P38A4V ips (A) vibration IPS pk < 0.195 5.20.5 P38A 4H ips (B) vibration IPS pk <0.597 5.20.5 1TR-2000B, Pump Bearing Inboard Temp. <160 Note 2 5.20.5 1TR-2000B, Pump Bearing Outboard temp. F <160 Note 2 5.20.10 Pump Coastdown Behavior:. Check (i4)if OK NIA N/A Page 41 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

ATTACHMENT C NOTE 1: Differential pressure = pump discharge pressure - pump suction pressure during test.

NOTE 2: Check recorded bearing temperatures are within the limits listed on Attachment I.

Acceptance Criteria Satisfied for all tested valves in Attachment C: (Circle one) SAT UNSAT Va ,Vr

/ /

Performer Date/Time SRO Date!/Time Page 42 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

ATTACHMENT D VALVE STROKE VERIFICATION NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

I Shut Exercise Test of AF-133, P-38A AFP AF-4012 N2 Backup First-off Iso Step Parameter. Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.21.6 PI-4051, Pressure PI-4051 psig. N/A 5.21.8 Time Stopwatch Min > 15 Min 5.21.8 PI-4051, Pressure PI-4051 psig. less than 3 psig drop after 15 Min.

Open Exercise Test of AF-145, P-38A AFP AF-4012 N2 Backup South Bottle Shut Exercise Test of AF-142, P-38A AFP AF-4012 N2 Backup North Bottle Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.22.9 Time to OPEN Stopwatch sec. less than 20 5.22.11 Time to SHUT (info only) Stopwatch sec. N/A Open Exercise Test of AF-142, P-38A AFP AF-4012 N2 Backup North Bottle Shut Exercise Test of AF-145, P-38A AFP AF-4012 N2 Backup South Bottle Step Parameter - Instrument Units Reading Acceptance Initials No. Measured' Used Criteria 5.23.9 Time to OPEN Stopwatch sec. less than 20 5.23.11 Time to SHUT (info only) Stopwatch sec. N/A Acceptance Criteria Satisfied for all tested valves in Attachment D: (Circle one) SAT UNSAT Remarks:

/ /

Performer Date/Time SRO Date/Time Pace 43 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A LNSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

ATTACHMENT E VALVE STROKE VERIFICATION NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

I Full Stroke Open and Shut, Timing, and Position Indication Test of AF-4021, P-38B AFP Discharge to 1HX-1B Steam Generator Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.38.1 Time to OPEN Stopwatch sec. 15.84-21.44 5.38.1 Local Position Indication N/A N/A OPEN 5.38.2 Time to SHUT Stopwatch sec. 16.01-21.65 5.38.2 Local Position Indication N/A N/A SHUT Stroke Open, Timing, and Position Indication Test of AF-4019, P-38B AFP Discharge Control, and Open Exercise Test of AF-153, P-38B AFP AF-4019 N2 Backup First-off Isol Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.39.3 Time to OPEN Stopwatch sec. 4.62-13.84 5.39.3 Local Position Indication N/A N/A OPEN 5.39.4 Time to SHUT (info only) Stopwatch sec. N/A 5.39.4 Local Position Indication N/A N/A SHUT Page 44 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

ATTACHMENT E VALVE STROKE VERIFICATION NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

Stroke Open and Shut, Timing, Position Indication, and Fail-Safe Test of AF-4014, P-38B AFP Mini-Recirc Control Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.41.3 Time to OPEN Stopwatch sec. 1.78-5.34 5.41.3 Local Position Indication NIA N/A OPEN 5.41.5 Time to SHUT Stopwatch sec. 3.63-10.89 5A1.5 Local Position Indication N/A N/A SHUT Acceptance Criteria Satisfied for all tested valves in Attachment E: (Circle one) SAT UNSAT Remarks:

/ /

Performer Date/Time SRO .Date/Time Page 45 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

ATTACHMENT F P-38B, AFW PUMP PERFORMANCE DATA (RECIRCULATION FLOW)

NOTE 1: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

NOTE 2: Vibration points which are shaded must be recorded by the Micro-logger but are NOT required to be transferred to the table. Only points marked A, B, C, D, and E must be transferred to the I table and are required for ASME OM Code. See Figure 1 for Locations.

Step No. Parameter Measured JUnits Reading Acceptance Criteria Initials 5.44.3 PI-4017A, P-38B AFP Suction Pressure psig N/A 5.47 PI-4017A, P-38B AFP Suction Pressure psig >7 I Full Stroke Open Test of AF-116 FIT-4050B, Mini-Recirc Flow pm >70 5.52 P1-4018 Pump Discharge Pressure psig N/A 5.52 PI-4017A, P-38B AFP Suction Pressure psig N/A 5.52 Recirculation Flow Vibration Data INSTRUMENT UNITS READINGS P38B IV ips Micro-logger IPS pk P38B 1H ips Micro-logger IPS pk P38B IH ae Micro-logger G env P38B 1H acc Micro-logger G pk P38B IA ips Micro-logger IPS pk P38B 2V ips Micro-logger IPS pk __

P38B 2H ips Micro-logger IPS pk __

P38B 2H ae Micro-logger G env P38B 2H acc Micro-logger G pk

• P38B 2A ips Micro-logger IPS pk __

P38B 3V ips Micro-logger IPS pk P38B 3H ips Micro-logger IPS pk P38B 3H ae Micro-logger G env P38B 3H acc Micro-logger G pk -

P38B 4V ips Micro-logger IPS pk

• P38B 4H ips Micro-logger IPS pk _ _ _._

P38B 4H ae Micro-logger G env P38B 4H acc Micro-logger G pk ,

P38B 4A ips Micro-logger IPS pk ,

Page 46 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

ATTACHMENT G P-38B, AFW PUMP FULL FLOW TEST PERFORMANCE DATA, and Full Stroke Open Exercise Test of Check Valves 1AF-104, AF-1 10, AF-1 13 NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

Full Stroke Open Exercise Test of Check Valves 1AF-104, AF-1 10, AF-1 13 Step No. Parameter Measured Units Reading Acceptance Criteria 5.53.5 1PI-478, SG B Pressure psig N/A 5.53.5 1FI-4037, SG B Total AF Flow gpm > 200 P-38B Full Flow IST Required Data (200gpm)

Step Parameter Measured Units Reading Acceptance Initials No. -Criteria 5.53.5 PI-40171A, P-38B AFP Suction Pressure psig N/A 5.53.5 PI-4018, P-38B AFP Discharge Pressure psig NIA 5.53.5 P-38B Delta P Note 1 psid 1182- 1251.3 5.53.5 F1T-4050B, Mini-Recirc Flow gpm N/A 5.53.5 DPIS-4014, P-38B Flow gpm >200 5.53.5 P38B 3V ips (C) Vibration IPS pk < 0.383 5.53.5 P38B 3H ips (D) Vibration IPS pk < 0.4938 5.53.5 P38B 4A ips (E) Vibration IPS pk <0.252 5.53.5 P38B 4V ips (A) Vibration IPS pk <0.635 5.53.5 P38B 4H ips (B) Vibration IPS pk <50.7 5.53.5 1TR-2000B, Pump Bearing Inboard temp. Note 2 TF <160 5.53.5 1TR-2000B, Pump Bearing Outboard temp. Note 2 OF <160 5.53.10 Pump Coastdown Behavior: Check (,) if OK N/A N/A Paige 47 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

ATTACHMENT G NOTE 1: Differential pressure = pump discharge pressure - pump suction pressure during test.

NOTE 2: Check recorded bearing temperatures are within the limits listed on Attachment I.

Acceptance Criteria Satisfied for all tested valves in Attachment G: (Circle one) SAT UNSAT Remarks:

/ I Performer Date/Time SRO Date/Time Pagre 48 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

ATTACHMENT H VALVE STROKE VERIFICATION NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

I Shut Exercise Test of AF-153, P-38B AFP AF-4019 N 2 Backup First-off Isol Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.55.6 PI-4056, Pressure PI-4056 psig. N/A 5.55.8 Time Stopwatch Min >15 min 5.55.8 PI-4056, Pressure PI-4056 psig. less than 3 psig drop after 15 Min.

Open Exercise Test of AF-165, P-38B AFP AF-4019 N 2 Backup North Bottle Shut Exercise Test of AF-162, P-38B AFP AF-4019 N 2 Backup South Bottle Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.56.9 Time to OPEN Stopwatch sec. less than 20 5.56.11 Time to SHUT (info only) Stopwatch sec. N/A Open Exercise Test of AF-162, P-38B AFP AF-4019 N2 Backup South Bottle Shut Exercise Test of AF-165, P-38B AFP AF-4019 N 2 Backup North Bottle Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.57.9 Time to OPEN Stopwatch sec. less than 20 5.57.11 Time to SHUT (info only) Stopwatch sec. N/A Acceptance Criteria Satisfied for all tested valves in Attachment H: (Circle one) SAT UNSAT Remarks:

I /

Performer Date/Time SRO Date/Time Page 49 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT I0A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

ATTACHMENT I EVALUATION OF MOTOR DRIVEN AFP BEARING 1.0 Compare the bearing temperatures, as recorded on the Attachments C and G to the criteria below:

ACCEPTABLE RANGE Pump inboard bearing temperature less than or equal to 120°F Pump outboard bearing temperature less than or equal to 120'F ALERT RANGE Pump inboard bearing temperature > 120°F less than 160'F Pump outboard bearing temperature > 120'F less than 160'F ACTION REQUIRED (PUMP OOS) RANGE Pump inboard bearing temperature greater than or equal to 160*F.

Pump outboard bearing temperature greater than or equal to 160°F 2.0 If a bearing temperature falls into the Alert range, then:

2.1 The pump is still operable.

2.2 An Work Order shall be written to perform an engineering evaluation of the pump.

3.0 If a bearing temperature falls into the Required Action range, then:

3.1 The pump is considered inoperable.

3.2 The Technical Specification Action Condition remains in effect.

3.3 Notify the DCS and STA.

Page 50 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

AT[ACHMENT J P-38A TRAIN RECOVERY FOR AF INITIATION NOTE: Steps NO.TT required are marked as N/A and Independent verification steps may be performed after restoration is complete.

INITIALS 1.0 Set PC-4012, P-38A AFP Discharge Pressure Controller, setpoint at 1200 psig.

2.0 Open AF-135, P-38A AFP AF-4012 Nitrogen Backup Second Off Isolation.

3.0 Place PC-4012, P-38A AFP Discharge Pressure Controller in AUTO.

4.0 Open AF-123A, P-38A AFP Mini Recirc AF-4007-S Outlet Isolation.

IV 5.0 Shut AF-123B, P-38A AFP Mini Recirc AF-4007-S Bypass Isolation.

IV 6.0 IF the AF-4012 Backup Nitrogen Supply Valves were in the process of being tested, THEN perform the following:

6.1 Shut IA-355, Instrument Air Vent.

6.2 Shut AF-132, Intermediate Vent.

6.3 Open IA-354, I/P-4012 AFP Discharge Control Air Inlet.

6.4 Open AF-130, AF-4012 AFP Discharge Control Pneumatic Valve.

IV 6.5 Open AF-143 or AF-146, AF-4012 Backup N2 Bottle Isolation Valves.

4 7.0 Place P-38A control switch in AUTO.

IV Page 51 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 1 STEAM GENERATORS (QUARTERLY)

ATTACHMENT K P-38B TRAIN RECOVERY FOR AF INITIATION NOTE: Steps NOT required are marked as N/A and Independent verification steps may be performed after restoration is complete.

INITIALS 1.0 Set PC-4019, P-38B AFP Discharge Pressure Controller, setpoint at 1200 psig.

2.0 Open AF-155, P-38B AFP AF-4019 Nitrogen backup Second Off Isolation.

3.0 Place PC-4019, P-38B AFP Discharge Pressure Controller in AUTO.

4.0 Open AF-124A, P-38B AFP Mini Recirc AF-4014-S Outlet Isolation.

IV 5.0 Shut AF-124B, P-38B AFP Mini Recirc AF-4014-S Bypass Isolation.

IV 6.0 IF the AF-4019 Backup Nitrogen Supply Valves were in the process of being tested, THEN perform the following:

6.1 Shut IA-357, Instrument Air Vent.

6.2 Shut AF-152, Intermediate Vent.

6.3 Open IA-356, Instrument Air Isolation Valve.

6.4 Open AF-150, AF-4019 AFP Discharge Control Pneumatic Valve.

IV 6.5 Open AF-163 or AF-166, AF-4019 Backup N2 Bottle Isolation Valves.

7.0 Place P-38B control switch in AUTO.

IV Page 52 of 54 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

ATTACHMENT L 1.0 This attachment shall be completed to document multiple step performance. A separate copy of this attachment shall be prepared for each step series requiring multiple performance. All copies of this attachment shall be attached to this procedure when the procedure is complete.

2.0 Refer to procedure steps- when performing this attachment.

3.0 List procedure steps by number, including adequate spaces to record initials, as appropriate. For components requiring independent verification or concurrent checks, provide for such checks on the attachment.

4.0 Complete the attachment by performing the procedure steps and recording the required data.

Procedure Section Performed: Date:

Step Initials cc if not required)Dt Data

________ __________(N/A Pagre 53 of 54 CONTINUOUS USE

-4 POINT BEACH NUCLEAR PLANT IT I1A INSERVICE TESTS SAFETY RELATED Revision 13 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT I STEAM GENERATORS (QUARTERLY)

FIGURE 1 Electric Motor Driven Auxiliary Feed Pump 4A 1A 4H 1H 2H 3H General Layout Drawing - Refer to markings on machine for actual locations.

V = Vertical H = Horizontal A = Axial 1,2,3,4 = Standard bearing numbering (driver to driven)

Page 54 of 54 CONTINUOUS USE