ML030800159

Temporary Change Review and Approval, IT Lob, Test of Electric-Driven Auxiliary Feed Pumps and Valves with Flow to Unit 2 Steam Generators (Quarterly)

ML030800159
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
2002-0849, FOIA/PA-2003-0094, IT 10B, Rev 12 PBF-0026c, Rev 13
Download: ML030800159 (65)

Text

-Nuclear Power Business Unit '. ý TEMPORARY CHANGE REVIEW AND APPROVAL Note: Refer to NP 1.2.3, Temporary ProcedureChanges,for requirements. Page I of I - INITIATION Doc Number IT 1OB Current Rev 12 Unit PB2 Temp Change No. 2002-0849 Document Title Test of Electric-Driven Auxiliary Feed Pumps and Valves with flow to Unit 2 Steam Generators (quarterly)

Existing Effective Temporary Changes Brief Description 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) 0D 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 0- YES (PRmdc doc-nicutatioa cordingto N S.1.l)

Screening completed according to NP 5.1.8? El NA 0 YES (Anh cmy)

Safety Evaluation Reouired? R NO [] YES (ivya amvision my In memd wfinad meews nd spmovat; "b oshlbe W=ýinboefmti,,

Determine if the change constitutes a Change Of Intent to the procedure by evaluating the following questions.

(Ifany am'wns are YES, a revision nay 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)? El 0

2. Cause an increase in magnitude, significance or impact such that it should be processed as a revision? 0] 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 13

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

5. Change Tech Spec or other regulatory acceptance criteria other than for re-baselining 0] 0 purposes?

6. Require a change to the procedure Purpose or change the procedure classification? E] 0 Initiated By (print/sign) Ross Groehier I A A43j ~T'AJd-- ate 11/0112002 11 - INITIAL APPROVAL This change is correct and complete, can be performed as written, oes not adversely affect personnel or nuclear safety, or Plant operating cofdcohs. .,...

Group Supervisor (print/sign) K ('C ) lc- I / n>-i J -) Date tI/i//

(Cannot be the Initiator)

This change does not adve oet Pl t operatig c ditions. Safety lated procedures only) ii Senior Reactor Operator (print/sign) < r . ,74_,, Date (Cannot be the Initiator or Group Supervisor)

III - PROCEDURE OWNER REVIEW 0 Permanent El One-time Use E] Expiration Date, Event or Condition:

El Hold change until procedure completed (4pk-view and approval stt uired'1i El QR/MSS Review NOT Required (Adm'I/ o'/ 0 QR Review Re dD Procedure Owner (print/sign) _ i`A4',), -... ) IM/ '

This Chanee and sunnortine reouirements correctly comaleted and orocessed ust be comnleted within 14 davs of in aniqyv vtokik .) IThe Initiator. OR and ADD"n'PIj Authorii Indicates 50.59/72.48 applicability assessed, any necessary screenings/evaluations performed, dew cross-disciplinary review required, and if required, performed. I

'MSSMeeting No. _ _/ ._/

',3roval Authority (vrint/sien) _ ___________ _________

V - REVISION INFORMATION FOR PERMANENT CHANGES

"\n Review (print/sign)

"Nestemporary change(s) incorporated exactly as approved and no other changes made to document.

to Revision Number EffectiveSDate I

References:

NP 1.23

,f6102

Point Beach Nuclear Plant DOCUMENT REVIEW AND APPROVAL CONTINUATION Page __ of Doc Number IT 10B Revision 12 Unit PB2 Title Test Of Electrically-Driven Auxiliary Feed Pumps and Valves with flow to Unit 2 Steam Generators (Quarterly)

Temporary Change Number 2002-0849 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 recirc flow is established / 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 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 5-53.7 also CAP029908 and CAP029952.

Other Comments

• Note- Recording of Step Numberts) is not required for multiple occurrences of identical information or when not beneficial to reviewers PBF-0026c Revision 6 04/18/01

References:

NP 1.1.3. NP 1.2.3

Point Beach Nuclear Plant TEMPORARY CHANGE AFFECTED MANUAL LOCATION Page of Procedure Number IT 1OB Revision 12 Unit PB2 Test Of Electrically-Driven Auxiliary Feed Pumps and Valves with flow to Unit 2 Steam Generators Title (Quarterly)

Temporary Change Number 2002-0849 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 El Copy included in work package for field implementation. (WO No. )

I*] Copy filed in Control Room temp change binder (Operations only). / / -(- o Z.

[ Original change package provided to ]r*a.5 to obtain Procedure Owner Review (e.&, Ownareview may be coordinated by Tn-Group OA IL Procedure Writer, Procedur Supervisor, etc.). / - CŽ El El El El El Performed By (print and sign) *__5v .*,e*.eJ / _ _---Date /(-/...

If - PROCEDURE OWNER REVIEW ON PBF-0026e (may be performed by OA IIL Procedure Writer, etc.)

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

[]l 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 changes.)

El Copy filed in Group one-time use file.

[] Original Temp Change provided to -- '" to obtain Final Approvals / ( -o0 Z-(e.g, final approval may be coordinated by In-Group OA IL Procedure Writer, Procedur Supervisor, etc.)

D Perormed By (print and sign) .C-.. .- ,x C-. . l _. / ". Dt /["- --

PBF-0026h

Reference:

NP 1.23 Revision 5 06/13/01

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Venfy scR number on all pages 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-1 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 / John P. Schroeder '* 6J ' LL e: /o/3. 2 Name (Print) Sraue Reviewed by: I__ (_ I A Date:

Namie-(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 NEI 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 in NP 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-38 A/B must be greater than 50 gpm and 1/2 P-29 discharge flow must be greater than 75 gpm. 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) Venrfy 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 Shutdown 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 : 0] Yes 0 No required.

If a Technical Specification change is required, explain what the change should be and why it is cask 1.4 Does the proposed activity involve a change to the terms, conditions or specifications incorporated in any VSC-24 (CoC)? Changes to a VSC-24 cask Certificate of Compliance require a CoC amendment request.

Certificate of Compliance 0 Yes G] No it is required.

If a storage cask Certificate of Compliance change is required, explain what the change should be and why 10 CFR 50.59 SCREENING Manual 5.3.2)

PART H (50.59) - DETERMINE IF THE CHANGE INVOLVES A DESIGN FUNCTION (Resource Compare the proposed activity to the relevant CLB descriptions, and answer the following questions:

YES NO QUESTION in the 0] I] Does the proposed activity involve Safety Analyses or structures, systems and components (SSCs) credited Safety Analyses?

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

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

that are 0] El Does the proposed activity involve CLB-descn'bed SSCs or procedural controls that perform functions with, regulations, license conditions, orders or technical required by, or otherwise necessary to comply 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) 1] 0] Does the activity exceed or potentially affect a design basis bmitfor afission product barrier(DBLFPB)?

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

"-theanswers to ALL of these questions are NO, mark Part III as not applicable, document the 10 CFR 50.59 screening in the Questions.

inclusion section (Part IV), then proceed directly to Part V - 10 CFR 72.48 Pre-screening method of evaluation(s) or DBLFPB(s)

If any of the above questions are marked YES, identify below the specific design function(s),

involved.

PBF-1515c

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Venrfy SCR number on all pages Page 3 MR-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 5.3.3)

If ALL the questions in Part II are answered NO then Part III is El 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.

mI.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 design function 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 E] 0l Does the activity use a revised or different method of evaluation for performing safety analyses than that described in the CLB?

El 0l 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 descrbe 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 11I.3.b are Z NOT APPLICABLE.

a. Answer these two questions first:

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

El E] Are the SSCs affected by the proposed test or experiment isolated from the facility?

PBF-1515c

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Venfy SCR number on all pages 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 III.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] 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 CLB?

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

El El 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 m.3.b is YES, a 10 CFR 50.59 Evaluation is required. If the answers in m.3.b are ALL NO describe 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 0 required or [0 NOT required.

A Point Beach FSAR change is E] 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.

Specification Bases is A Technical Specification Bases change is E] required or [D NOT required. If a change to the Technical required, then initiate a Technical Specification Bases change per NP 5.2.15.

A Technical Requirements Manual change is [E 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 for guidance to determine the NOTE: NET 96-07, Appendir B. Guidelines for 10 CFR 72.48 Implementation should be used proper responses for 72.48 screenings.

PART V (72.48) - 10 CFR 72.48 INITIAL SCREENING QUESTIONS and VII) for the proposed activity.

Part V determines if a full 10 CFR 72.48 screening is required to be completed (Parts VI

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

--- IZ.I

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 5 El ED 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 System1?.

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?

as El 0 Does the proposed activity involve a change to Point Beach CLB design criteria for external events such 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 N 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

• Tf ALL the questions in Part V are NO then Part VI is [] NOT APPLICABLE.)

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

YES NO QUESTION El Z Does the proposed activity involve cask/ISFSI 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 E Does the proposed activity involve plant, cask or ISFSI SSCs whose 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?

El [] 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 afissionproduct 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 O, mark Parts VII as not applicable, and document the 10 CFR 72.48 screening in the conclusion section (Part VIII).

or DBLFPB(s)

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

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

(If ALL the questions in Part V or Part VI are answered N.O, then Part VII is Z NOT APPLICABLE.)

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.I Changes to the Facility or Procedures YES NO QUESTION 0l I] Does the activity adversely affect the design function of a plant, cask, or ISFSI SSC credited in safety analyses?

I] 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, descr'be 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 M El Does the activity use a revised or different method of evaluation for performing safety analyses than that described in a cask SAR?

El 0- 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?

basis for the conclusion If any answer is YES, a 10 CFR 72.48 Evaluation is required. If both answers are NO, describe the (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 E] NOT APPLICABLE.)

a. Answer these two questions first:

YES NO QUESTION E] E] 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 NO continue to VII.3.b. If the answer to EITHER question is YES, then briefly describe the basis.

the criteria given in VII.3.a above.

b. Answer these additional questions ONLY for tests or experiments which do not meet If the answer to either question in VII.3.a is YES, then these three questions are E] NOT APPLICABLE:

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) vcnfy 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?

El 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 VU.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 [] required or ED 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 0 NOT required. If a VSC-24 cask SAR change is required, then contact the Point Beach Dry Fuel Storage group supervisor.

A Regulatory Commitment (CLB Commitment Database) change is [] 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 El required or 0D NOT required. If a VSC-24 10 CFR 72.212 Site Evaluation Report change is required, then contact the Point Beach Dry Fuel Storage group supervisor.

IT 10B TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 12 EFFECTIVE DATE: September 9, 2002 REVIEWER: Qualified Reviewer APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Operations Verified Current Copy: Date Time Signature List pages used for Partial Performance Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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-4021, AF-4023, 1AF-102, and 1AF-104 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 EdJ96A. 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 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-4020, P-38B AFP Discharge to 2HX-1B Steam Generator AF-4022, P-38A AFP Discharge to 2HX-1A Steam Generator 1.1.3 Quarterly stroke open, timing, and position indication test of the following 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 as required by the ASME OM Code:

AF-4007, P-38A AFP Mini-Recirc Control AF-4014, P-38B AFP Mini-Recirc Control 1.1.5 Quarterly full stroke open exercise tests for the following check valves, as required by the ASME OM Code.

2AF-103, P-38A AFP Discharge to 2HX-1A SG Check 2AF-105, P-38B AFP Discharge to 2HX-IB 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 Page 2 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY) 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 test for the following nitrogen backup I 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-3 8B AFP AF-4019 N2 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:

Rule, I 2.2 IF it is desired to consider the equipment Available per the Maintenance T"HEN two Level 4 Dedicated Operators will be required, one for the Control Room and of the second locally per OM 3.26, Use of Dedicated Operators, during the performance this procedure.

Pag~e 3 of 55 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, ThENN 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 extinguished.

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 train or component of the train, the opposite trains normal 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.

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 / or r4 I recirc flow greater than 50 GPM OR Stop respective AFW pump.

Page 4 of 54 CONTINUOUS USE

IT 10B POINT BEACH NUCLEAR PLANT SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 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 frequency requirements, Shift Management may N/A those portions of the procedure that are NOT applicable for the for performance of the PMT. The use of N/A is NOT acceptable Initial Conditions, Precautions and Limitations, or procedure it steps that pertain to the equipment requiring PMT, nor is unless the acceptable for restoration of equipment/components 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 tested is/are in buses lA05, 1A06, 2A05, 2A06, or the component(s) to be the same train that is out of service.

4.4 Chemistry notified about auxiliary feed injection.

level directed by 4.5 Reactor power reduced a minimum of 2% OR to a power DSS. (Mark step N/A if in Mode 3, 4, 5, 6, or defueled)

MDAFW 4.6 The IST Coordinator is available for PMT data review if the motor (motor pumps have been replaced, disassembled, realigned to the This replacement included) or the coupling has been disassembled.

prior to review will establish new reference values and is performed other minor declaring the pump operable. (Mark N/A for oil changes and maintenance which does NOT affect pump vibration or hydraulic performance).

Page 5 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS 4.7 The IST Coordinator is available for power operated 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.

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:

(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 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INS ERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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, 1P-29, and 2P-29 are operable

b. For single-unit operation:

P-38B and 1P-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 3.7.5.

Specification TIME DATE of 5.4 IF an Auxiliary Feedwater Initiation is required during the performance this test, THEN immediately perform Attachment J to recover Train A. (N/A this step if not required.)

Page 7 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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 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.)

5.5 Perform Quarterly Full Stroke Open and Shut, Timing, and Position Indication Test of AF-4022. P-38A AFP Discharee to 2HX-1A Steam Generator as follows:

5.5.1 Open AND time AF-4022, P-38A AFP Discharge to 2HX-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-4022, P-38A AFP Discharge to 2HX-1A Steam Generator:

a. Record time to shut on Attachment A.

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

Page 8 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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-1 33, 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 Isolation.

5.6.6 IF NOT continuing with the balance of this procedure, THEN continue 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.

in PULLOUT.

5.7 Place P-38A Motor Driven Aux Feed Pump control switch Page 9 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLAINT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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 55 CONTINUOUS USE

IT 10B RELATED POINT BEACH NUCLEAR PLANT SAFETY INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY) 1P41 TTTT I 1riL.2 A T C' finq L Irlij-3 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 1HX-1A Steam Generator.

the glass.

5.10 Check P-38A pump bearing oil level between the red lines on Inboard Outboard in service:

5.11 Place PI-4010A, P-38A AFP Suction Pressure Indicator 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.

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

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

than the 5.14 Ensure P-38A suction pressure as read on PI-4010A is greater Attachment B.

7.0 psig low suction pressure alarm setpoint. Record on Page 11 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

LNI FIALS 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 Minimum Flow Check Valve 5.16 Check mini-recirculation is equal to or greater than 70, (expected range is I 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.

1 5.19 WHEN P-38A has run for two-minutes, THEN record the following on Attachment B.

1, Pump Discharge Prssr

• ~PI-4010A, Pump Suction Pressure* .

S~CAUTION To prevent damage to P-38A monitor and maintain AFW discharge and I or recirc flow greater than 50 GPM OR STOP P-38A.

I.

j r

-I.

7 A

Paae 12 of 55 CON'TINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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 2AF-103, AF-109. AF-1 12 and Full Flow Test of P-38A as follows:

5.20.1 Open AF-4022, P-38A AFP Discharge to 2HX-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 greater than or equal to 200 gpm, THEN record data 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.

55.20.8 Shut AF-4022, P-38A AFP Discharge to 2HX-1A Steam a-. ~~~~Generator.____________

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

ýJ Pny- 1,  !:?- CO \'\. TINUUS USE

POINT BEACH NUCLEAR PLANT IT JOB SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 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.

Page 14 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS 5.21 Perform Ouarterlv Shut Exercise Test of AF-133. P-38A AFP AF-4012 N, Backutn First-off Isol. as follows:

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

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:

0 AF-132, Intermediate Vent

. IA-355, Instrument Air Vent 5.21.6 Record PI-4051, AF-4012 AFP Disch Cd 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 P1-4054.

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 WHEN 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.

Page 15 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS 5.21.9 Shut AND cap the following:

9 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 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 N2 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 N 2 Bottle Stop Isolation Valve.

5.22.3 Ensure the north N2 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.

Page 16 of 55 CONTLNUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS 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 MANUAL 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.

Page 17 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

.INITIALS 5.22.13 Shut AF-143, P-38A AFP AF-4012 N2 Backup North Bottle Outlet Isolation Valve.

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

5.23.2 Open the north N2 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 N,!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 PC-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)

Page IS of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS 5.23.11 Record time to shut on Attachment D.

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

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

5.23.15 Shut the north N2 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-143 or AF 146.

IV 5.26 Ensure the associated north/south N2 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 the SOMs log stating that P-38A is available per IT 10B.

Paae 19 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 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-IA 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 coritrol switch AUTO

• The pump discharge valve control switch for an operating unit must be in AUTO 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 20 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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 IFperforming 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 IP-29 are operable for Unit 1 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, T'HEN enter the appropriate TS Action Condition for P-38B per Teclhnical 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 21 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

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-4020, P-38B AFP Discharge to 2HX-1B Steam Generator as follows:

5.38.1 Open AND time AF-4020, P-38B AEP Discharge to 2HX-lB.

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-4020, P-38B AFP Discharge to 2HX-IB 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 22 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9,2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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 NIA)

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

PULLOUT.

5.40 Place P-38B Motor Driven Aux Feed Pump control switch in Page 23 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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 on 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 Attachment 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 24 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INS ERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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-IB 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.

5.46 Start P-38B. Time Start 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.

Page 25 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 1OB SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 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, (expected 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:

Pump Discharge Pressure PI-4017A, Pump Suction Pressure Recirculation Flow Vibration Data CAUTION To prevent damage to P-38B monitor and maintain AFW discharge and / or N recirc flow greater than 50 GPM OR STOP P-38B.

Po 2)6 r)f 55 CONTI-NUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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) 5.53 Perform Full Stroke Open Exercise Test of Check Valves 2AF-105, AF-1 10, AF-1 13 and Full Flow Test of P-38B as follows:

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

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

5.53.2 Adjust PC-4019, P-38B AFP Discharge Control, to establish approximately 115 gpm as read locally on DPIS-4014.

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

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

5.53.4 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 greater than or equal to 200 gpm, THEN record data on Attachment G and the IST required vibration points listed'on Attachment G.

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

15.53.7 Check AF-4014, P-38B AFP Mini-Retire Control, open.

5.53.8 Shut AF-4020, P-38B AFT) Discharge to 2H-X-1B Steam Generator.

00 01 CAUTION(

N0 To prevent damagye to P-38B monitor and maintain AFW discharge and /or recirc flow greater than 50 GPM OR STOP P-38B.

7of55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS 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.

NOTE: C01A 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 2 Reactor Power was reduced to perform this test, "THENpower increase may be commenced as directed by the DSS. (Mark as N/A if desired)

Pa~ge 28 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

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

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

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

5.55.3 Shut AF-185, P-38B AFP AF-4064 Upstream Isolation.

5.55.4 Shut IA-356, Instrument Air Isolation valve.

5.55.5 Uncap AND open the following:

• AF-152, Intermediate Vent 0 IA-357, Instrument Air Vent 5.55.6 Record PI-4056, downstream pressure indicator, pressure on Attachment H.

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.

Page 29 of 55 CONTTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS 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 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 Ouarterly Open Exercise Test of AF-l165, P-38B AFP AF-4019 N2 Backup North Bottle, Check Valve, and Shut Exercise Test of AF-1 62, P-38B AFP-AF-4019 N, Backup South Bottle, Check Valve as follows:

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

5.56.2 Open the north N2 Bottle Stop Isolation Valve.

5.56.3 Ensure the south N2 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.

Page 30:ý of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS 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 N 2 Backup South Bottle Outlet Vent AND install downstream vent cap.

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

5.56.14 Shut AF-166, P-38B AFP AF-4019 Backup North 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-1 65, 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 Open the south N2 Bottle Stop Isolation Valve.

5.57.3 Ensure the north N2 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.

Page 3 1 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

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

5.57.7 Ensure PC-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.

5.57.12 Shut AF-167, P-38B AFP AF-4019 N 2 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 APP Discharge Pressure Controller, controller setpoint, at 1200 psig.

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

Page 32 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS NOTE: C01A 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 1OB.

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-1B Steam SHUT*

Generator AF-4021 P-38B AFP Discharge to 2HX-lA 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 5.66 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.

5.67 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, 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.

(NIA if continuing with Train A)

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IT 10B POINT BEACH NUCLEAR PLANT SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS 5.68.2 IF Train A has already been tested OR is NOT planned on being tested, THEN proceed to Step 5.69, Recovery.

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.

Page 34 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

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

I 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 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)

Date/Time Data Analyzed By 1ST Remarks:

Page 35 of 55 CONTINUOUS USE

IT 10B PONIT BEACH NUCLEAR PLANT SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

7.0 REFERENCES

7.1 Technical Specifications:

7.1.1 Technical Specification 3.7.5 7.1.2 Technical Specification 5.5.7 I

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

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-001, AOP-21 Pagze 36 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

REMARKS SECTION:

Page '37 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002.

PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

Performed By:

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

/

Performer (Print) Performer (Sign) Date Time Initials

/

Date Time Initials Performer (Print) Performer (Sign)

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

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

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

Date Time Initials Performer (Print) Performer (Sign)

/

Date Time Initials Performer (Print) Performer (Sign)

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

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

Date Time Initials Shift Supervision (Print) Shift Supervision (Sign)

Paae38:) of 55 CONTINUOUS USE

IT 10B POINT BEACH NUCLEAR PLANT SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM r.M*rP ATCI* * (CNT ARTFRLY)

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-4022, P-38A AFF Discharge to 2HX-1A Steam Generator Step Parameter Instrument Units Reading Acceptace Initials No. Measured Used Stopwatch sec. 15.27-20.67 5.5.1 Time to OPEN N/A N/A OPEN 5.5.1 Local Position Indication Stopwatch sec. 15.76-21.32 5.5.2 Time to SHUT N/A N/A SHUT 5.5.2 Local Position Indication Stroke Open, Timing and Position Indication Test of AF-4012, P-38A AFP Discharge Control, ana Open Exercise Test of AF-1 33, P-38A AFP AF-4012 N: B*ckup First-off Isol I

Instrument Acceptance Step Parameter Criteria Initials No. Measured Used Stopwatch 4.8-14.4 5.6.3 Time to OPEN N/A OPEN 5.6.3 Local Position Indication Stopwatch N/A 5.6.4 Time to SHUT (info only)

N/A SHUT 5.6.4 Local Position Indication Pasze 39 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM t(_=TTD AI'Ct ( " TAPTRT Yr)

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

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 criteria Initials Measured Used Cricepta No.

Time to OPEN Stopwatch sec. 1.9-5.68 I 5.8.3 Local Position Indication N/A NIA OPEN 5.8.3 Time to SHUT Stopwatch sec. 8.94-14.9 5.8.5 Local Position Indication N/A N/A SHUT 5.8.5 Acceptance Criteria Satisfied for all tested valves in Attachment A: (Circle one) SAT UNSAT Remarks:

I I Date!ilme Performer Date/lime SRO Date/Time Page 40 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT lOB INSERVICE TESTS SAFETY RELATED Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

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

Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related I NOTE 1: 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 table and are I required for ASME OM Code. See Figure I for locations.

I Page 41 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

ATTACHMENT C "P-38A,AFW PUMP FULL FLOW TEST PERFORMANCE DATA, and Full Stroke Open Exercise Test of Check Valves 2AF-103, AF-109, AF-l112 NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipmenL" Full Stroke Open Exercise Test of Check Valves 2AF-103, AF-109, AF-1 12 I

Step Parameter Units Reading Acceptance Initials No. Measured Criteria 5.20.5 2PI-468, 2HX-1A SG Pressure psig N/A 5.20.5 2FI-4036, Flow to 2HX-1A SG gpm > 200 P-38A Full Flow IST Required Data (200 gpm)

Step Parameter Units Reading Acceptance Initials Measured Readin Criteria No.

PI-4010A, P-38A AFP Suction Press psig N/A 5.20.5 PI-401 1, 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 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) vibrati6n IPS pk <_0.378 5.20.5 P38A 4V ips (A) vibration IPS pk <_0.195 5.20.5 P38A 4H ips (B) vibration IPS pk < 0.597 5.20.5 ITR-2000B, Pump Bearing Inboard Temp.

Note 2 OF 1 <160

<_6 ITR-2000B, Pump Bearing Outboard temp. OF < 160 Note 2 NIA N/A 5.20.10 Pump Coastdown Behavior. Check (4) if OK Pa-_e -42of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INS ERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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 Remarks:

I I Performer Date/Time SRO Date/Time Page 4'3: of 55 CONTLNUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

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

Shut Exercise Test of AF-133, P-38A AFP AF-4012 N2 Backup First-off Isol Step Parameter Instrument Units Reading Acceptance Initials No. Measured Used Criteria 5.21.6 PI-405 1, Pressure PI-4051 psig. N/A 5.21.8 Time Stopwatch Min >_15 Min less than 3 5.21.8 PI-4051, Pressure PI-4051 psig. 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 Acceptance Initials No. Measured Used Criteria 5.23.9 Time to OPEN Stopwatch se-. 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:

/ I Performer Date/Time SRO Date/Time Page 4-4 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (OUARTERLY)

ATTACHMENT E 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-4020, P-38B AFP Discharge to 2HX-1B Steam Generator Step Parameter Instrument Units Reading Acceptance No. Measured Used Criteria Initials 5.38.1 Time to OPEN Stopwatch sec. 15.67-21.21 5.38.1 Local Position Indication N/A N/A OPEN 5.38.2 Time to SHUT Stopwatch sec. 16.15-21.85 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 Readin1 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 NIA OPEN 5.39.4 Time to SHUT (info only) Stopwatch sec. N/A 5.39.4 Local Position Indication - N/A NIA SHUT Page 45 of 55 CONTNUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM (PNER AT RS ( UJARTERLY)

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 I

Step Parameter Instrument Units Readin cceptance No. Measured Used Criteria 5.41.3 Time to OPEN Stopwatch sec. 1.78-5.34 5.41.3 Local Position Indication N/A N/A OPEN 5.41.5 Time to SHUT Stopwatch sec. 3.63-10.89 5.41.5 Local Position Indication N/A NIA SHUT Acceptance Criteria Satisfied for all tested valves in Attachment E: (Circle one) SAT UNSAT Remarks:

I I Date/Time SRO Date/Time Performer Paae 46 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

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

Data that falls outside the listed Acceptance Criteria constitutes inoperability of the I 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 table and are required for ASME OM Code. See Figure 1 for Locations.

Parameter Measured Units Reading Crit Initials Step No.

PI-4017A, P-38B AFP Suction Pressure psig N/A 5.44.3 PI-4017A, P-38B AFP Suction Pressure psig >7 5.47 Full Stroke Open Test of AF-1 16 FIT-4050B, Mini-Recirc Flow g >70 PI-4018 Pump Discharge Pressure psig N/A 5.52 PI-4017A, P-38B AFP Suction Pressure psig NIA 5.52 5.52 J Reeirculation Flow Vibration Data INSTRUMENT UNITS. READINGS P38B IV ips Micro-logger IPS pk

• P39B 1H ips Micro-logger IPS pk P38B IH ae Micro-logger G env P38B 1H ace 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 ace Micro-logger G pk .

P38B 2A ips Micro-logger IPS pk ,

P38B 3V ips Micro-logger IPS pk .

P3SB 3H ips Micro-logger IPS pk P38B 3H ae Micro-logger G env ._____..________

Micro-logger G pk k,:

P39B 3H acc P38B 4V ips Micro-logger IPS pk . .

Micro-logger IPS pk P38B 4H ips Micro-logger G env ;C .

P38B 4H ae Micro-logger G pk .

P38B 4H acc Micro-logger IPS pk . -- .. -

P39B 4A ips PaL,ze 47 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM CTPNPR ATC)RS (OUARTERLY'3 ATTACHMENT G P-38B, AFW PUMP FULL FLOW TEST PERFORMANCE DATA, and Full Stroke Open Exercise Test of Check Valves 2AF-105, AF-110, and AF-113 NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

Full Stroke Open Exercise Test of Check Valves 2AF-105, AF-1 10, AF-1 13 and Full Flow Test of P-38B Parameter Units Readin Acceptance Initials Step No. Measured Criteria 5.53.5 IPI-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 (200 gpm) Acceptance I

Step Parameter Units Reading A Initials No. Measured Criteria 5.53.5 PI-4017A, P-38B AFP Suction Pressure psig N/A 5.53.5 PI-4018, P-38B AFP Discharge Pressure psig N/A 1182 Note 1 psid 1251.3 5.53.5 P-38B Delta P 5.53.5 F1T-4050B, Mini-Recirc Flow gpm N/A DPIS-4014, P-38B Flow gpm 200 5.53.5 5.53.5 P38B 3V ips (C) Vibration IPS pk 50.383 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 P38B 4H ips (B) Vibration IPS pk

• 0.7 5.53.5 OF <160 5.53.5 ITR-2000B, Pump Bearing Inboard temp. Note 2 OF <160 5.53.5 ITR-2000B, Pump Bearing Outboard temp. Note 2 Pump Coastdown Behavior: Check (SI) if OK N/A N/A 5.53.10 Pa~ze 48 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

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

I 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 Re~mark':

Remarks:

/ I Performer Date/Time SRO Date/Time Pa-.e 49 of 55 COPNTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED AND VALVES PUMPS ATO3R WITH FLOW TO UNIT 2 STEAM CFJPr* (O1JARTERLY'*

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

Shut Exercise Test of AF-153, P-38B AFP AF-4019 N2 Backup First-off Isol I

uAcceptance No. Measured Used Criteria 5.55.6 PI-4056, Pressure PI-4056 psig NIA 5.55.8 Time Stopwatch Min > 15 min less than 3 5.55.8 PI-4056, Pressure PI-4056 psig psig drop after 15 Min.

Open Exercise Test of AF-165, P-38B AFP AF-4019 N2 Backup North Bottle Shut Exercise Test of AF-1 62, P-38B AFP AF-4019 N2 Backup South Bottle Step No.

Parameter Measured Instrument Used ]

1cUnits _ Readi_i______ c te eReadingInitials 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 N2 Backup North Bottle Step Parameter Instrument Reading Ai pUnits teria Initials Used Units I ___ ___ __ Criteria No. M easured 5.57.9 Time to OPEN Stopwatch sec. Lless than 20 5.57.11 Time to SHUT (info only) Stopwatch sec. NIA Acceptance Criteria Satisfied for all tested valves in Attachment H: (Circle one) SAT UNSAT Remarks:

I I SRO Date/Time Performer Date/Time Date/Time Pae~e 50 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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 > 120F *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 A 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 Action Condition remains in effect.

3.3 Notify the DCS and STA.

Pa_.ze 51 of 55 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 10B SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS ATTACHMENT J P-38A 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.

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.

7.0 Place P-38A control switch in AUTO.

IV Page 52 of 55 CONTINUOUS USE

IT 10B POINT BEACH NUCLEAR PLANT SAFETY RELATED INSERVICE TESTS Revision 12 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

INITIALS ATTACHMENT K P-38B TRAIN RECOVERY FOR AF INITIATION NOTE: Steps NO.T required are marked as N/A and Independent verification steps may be performed after restoration is complete.

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 53 of 55 CONTINUOUS USE

IT 10B POINT BEACH NUCLEAR PLANT SAFETY RELATED INSERVICE TESTS RevisionI 2 September 9, 2002 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES WITH FLOW TO UNIT 2 STEAM GENERATORS (QUARTERLY)

ATTACHMENT L A separate copy of 1.0 This attachment shall be completed to document multiple step performance.

All copies this attachment shall be prepared for each step series requiring multiple performance.

is complete.

of this attachment shall be attached to this procedure when the procedure 2.0 Refer to procedure steps when performing this attachment.

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

the required data.

4.0 Complete the attachment by performing the procedure steps and recording Procedure Section Performed: Date:

cc Data Step Initials (N/A ifnot required)

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POINT BEACH NUCLEAR PLANT IT 10B INSERVICE TESTS SAFETY RELATED Revision 12 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED September 9, 2002 PUMPS AND VALVES WITH FLOW TO UNIT 2 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 55 of 55 CONTINUOUS USE