Text

Temporary Change Review and Approval, IT 09A, Cold Start of Turbine Driven Auxiliary Feed Pump and Valve Test (Quarterly) Unit 2
	ML030800044
Person / Time
Site:	Point Beach
Issue date:	11/01/2002
From:	Groehler R, Harper R, Sokol K; Nuclear Management Co
To:	; Office of Nuclear Reactor Regulation
References
	FOIA/PA-2003-0094, IT 09A, Rev 29 PBF-0026c, Rev 13
	Download: ML030800044 (57)
	v • d • e

"

Nuclear Power Business Unit 1 / -(L, A

V *c ,. j TEMPORARY CHANGE REVIEW AND APPROVAL Note: Refer to NP 1.2.3. Temporary ProcedureChanges,for requirements. Page I of I- INITIATION Doc Number IT 09A Current Rev 29 Unit PB2 Temp Change No. 2002-0848 Document Title Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly) Unit 2 Existing Effective Temporary Changes n/a 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) 0Z 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 [5 YES (prid d*c.metion .codtng to Np s.l.s)

Screening completed according to NP 5.1.8? E] NA ED YES (Atach copy)

Safety Evaluation Required? [0NO E-'YES (If Yes. arnision maybcpcessored or iewsaNdpovsts shall be oainedberorc.e-a"ing) mli Determine if the change constitutes a Change Of Intent to the procedure by evaluating the following questions.

(If any answers are YES, a revision may be processed or final reviews and approvals shall be obtained before implementing)

Will the proposed change: YES NO

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

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

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?

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

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

purposes?

6. Require a change to the procedure Purpose or change the procedure classification? El 0 Initiated By (printisign) Ross Groehler / 2

( . , L--- at 10131/2002 II - INITIAL APPROVAL This change is correct and complete be performed as wit d does not adversely affect personnel or nuclear safety, or Plant operating cbnjtns.

Group Supervsor (print/algn) <Z J1 le Date A1/(6= ..

(Cannot be the Initiator)

This change does not adve ly a ffiee~lant Qmurating~odiion s.aft R44ited procedures only)[

Senior Reactor Operator (prthsign) onditions. Sa-_ tyR p d only (Cannot be the Initiator or Group Supervisor)

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

E5 Hold change until procedure completed (final review and approval still rpek d within 14 days of initial approval)

Procedure Owner (print/sign) /

IV - FINAL REVIEW AND APE*3A'

,*,Vust be comoleted within 14 days of fait'a 1 00 V-11 p-r .. . .... I.1-l, I h 1Intiator. OR and Aooiu

. l Atho 1/

llbe indeoendent from~kh ter)

Date/ //

htl t

o MSS (print/sign)

Indicates 5059n72.48 applicability assessed, any necessary screenings/evaluations perfoftied, determination made as to whethf add ional cross-disciplinary review required, and If required, performed.

MSS Meeting No. _... / ""_

Approval Authority (Print/sin)

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

Incorporated into Revision Number _ _____Effective Date PBF-0026c Revision 13 01/16/02

References:

NP 1.2.3

Point Beach Nuclear Plant DOCUMENT REVIEW AND APPROVAL CONTINUATION Page _ of Doc Number IT 09A Revision 29 Unit PB2 Title Cold Start Of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly) Unit 2 Temporary Change Number 2002-0848 Description of Changes:

Step

Change/Reason Add new P&L associated with maintaining AFW minimum flow requirements] See SCR 2002-0458, and 3.8 also CAP029908 and CAP029952.

Add new caution associated with maintainingainimimumAFW 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 5.24 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 5.49 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 5.57 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 5.67 also CAP029908 and CAP029952.

i-i-

i i

i Other Comments

Note: Recording of Step Number(s) is not required for multiple occurrences of identical information or when not beneficial to reviewers.

PBF-0026c Rclsion6 04118/01

References:

NPI 113, NP 1.2.3

1.

Point Beach Nuclear Plant TEMPORARY CHANGE AFFECTED MANUAL LOCATION Page of Procedure Number IT 09A Revision 29 Unit PE 2 1.

Title Cold Start Of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly) Unit 2 Temporary Change Number 2002-0848 I - IMMEDIATELY AFTER INITIAL APPROVAL ON PBF-0026e (Non-Intent changes)

(after Final Approval if change of intent involved)

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

[21 Copy filed in Control Room temp change binder (Operations only). /' (-- z.

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

E/7 Performed By (print and sign) ("'fo z C< -ý , -6 , I Date /1-i -

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

This procedure change has been processed as follows: (ManualiLocation) Date Performed

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

(Not required for one-time me change)

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

El Copy filed in Group one-time use file.

0* Original Temp Change provided to _ _ __ __ _to obtain Final Approvals [ -i- _

(e.g., final approval may be coordinated by In-Group OA U,Procedure Writer, Procedure Supervisor, etc.)

El El El C6 1'- FCO El El Performed By (print and sign) (,,' . - , (/** Date , .

PBF-0026h Revision 5 06/13/01

Reference:

NP 1.2.3

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 en( J 6 4 Lt a e: /a.2 2

Name (Print)

Reviewed by: _ _6_, _A _ VI_ 2 Date: /.

9 ...

Name'('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 maybe 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 k 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) Venfy 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: 0l Yes 0 No If a Technical Specification change is required, explain what the change should be and why it is required.

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

[:]Yes E No If a storage cask Certificate of Compliance change is required, explain what the change should be and why it is required.

10 CFR 50.59 SCREENING PART 11 (50.59) - DETERMINE IF THE CHANGE INVOLVES A DESIGN FUNCTION (Resource Manual 5.3.2)

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

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

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

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

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

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

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

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

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

Tf the answers to ALL of these questions are NO. mark Part III as not applicable, document the 10 CFR 50.59 screening in the

,nclusion section (Part IV), then proceed directly to Part V - 10 CFR 72.48 Pre-screening Questions.

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

PBF-1515c

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

Page 3 tR-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 III (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 1113.

III.1 CHANGES TO THE FACILITY OR PROCEDURES YES NO QUESTION E3 Z Does the activity adversely affect the designfunction of an SSC credited in safety analyses?

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

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

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

111.2 CHANGES TO A METHOD OF EVALUATION (If the activity does not involve a method of evaluation, these questions are 0 NOT APPLICABLE.)

YES NO QUESTION

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

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

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

111.3 TESTS OR EXPERIMENTS If the activity is not a test or experiment, the questions in III.3.a and III.3.b are 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 El Are the SSCs affected by the proposed test or experiment isolated from the facility?

"I) r -

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 [E NOT APPLICABLE.

YES NO QUESTION El DI 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?

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

El F1 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 IUI.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 E] required or 0D 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 F] required or 0 NOT required. If a Regulatory Commitment Change is required, initiate a commitment change per NP 5.1.7.

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

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

... - 10 CFR 72.48 SCREENING --

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

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

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

PBF-1515c

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

1l 3 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 (SEP High Range Monitor), RE-221 (Drumming Area Vent Gas Monitor), RE-325 (Drumming Area Exhaust Low-Range Gas Monitor), PAB Crane, SFP Platform Bndge, Truck Access Area, or Decon Area?

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

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

0] 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 questons m Part VI and Part VII are to be provided. If ALL the questions in Part V are answered NO, then check Parts VI and VII as not applicable. Complete Part VIII to document the conclusion that no 10 CFR 72.48 evaluation is required.

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

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

YES NO QUESTION El 0] Does the proposed activity involve 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?

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

El 0D 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 N0O, mark Parts VII as not applicable, and document the 10 CFR 72.48 screening in the conclusion section (Part VIII).

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

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

(If ALI the questions in Part V or Part VI are answered NO, then Part VII is [0 NOT APPLICABLE.)

"I II. z.

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 6 Answer the following questions to determine if the activity has an adverse effect on a design function. Any YES answer means that a 10 CFR 72.48 Evaluation is required; EXCEPT where noted in Part VII.3.

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

El El Does the activity adversely affect the method of performing or controlling the design function 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 El El Does the activity use a revised or different method of evaluation for performing safety analyses than that descn'bed in a cask SARP?

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

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

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

a. Answer these two questions first:

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

E3 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.

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

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

PBF- ;!I, c

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

El El Does the activity utilize or control a plant, cask or ISFSI facility SSC in a manner that is inconsistent with the analyses or descnptions 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 VII.3.b is YES, a 10 CFR 72.48 Evaluation is required. If the answers are all NO, describe the basis for the conclusion (attach additional discussion as necessary):

PART VIII -DOCUMENT THE CONCLUSION OF THE 10 CFR 72A8 SCREENING Check all that apply:

A 10 CFR 72.48 Evaluation is El required or [D 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 El required or Z 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 E] required or Z NOT required. If a Regulatory Commitment Change is required, initiate a commitment change per NP 5.1.7.

A change to the VSC-24 10 CFR 72.212 Site Evaluation Report is E] required or [D 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 09A COLD START OF TURBINE-DRIVEN AUXILIARY FEED PUMP AND VALVE TEST (QUARTERLY) UNIT 2 DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 29 EFFECTIVE DATE: August 23, 2002 REVIEWER: Qualified Reviewer APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Operations Verified Current Copy:

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

IT 09A COLD START OF TURBINE-DRIVEN AUXILIARY FEED PUMP AND VALVE TEST (QUARTERLY) UNIT 2 DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 29 EFFECTIVE DATE: August 23, 2002 REVIEWER: Qualified Reviewer APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Operations Verified Current Copy:

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

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 1.0 PURPOSE 1.1 The purpose of this test is to perform a cold fast start of the Turbine-Driven Auxiliary Feedwater Pump. This procedure satisfies the Biennial comprehensive pump test requirements of the ASME OM Code.

1.2 The performance of this procedure partially satisfies Technical Specification 5.5.7 by conducting the following PBNP Inservice Testing Program tests in accordance with the ASME OM Code 95 Ed.96A. Successful performance of this procedure will also satisfy Technical Specifications and environmental qualification requirements. (B.3) 1.2.1 Quarterly Comprehensive functional test of 2P-29, Aux Feedwater Turbine-Driven Pump, to verify the developed head of each required AFW pump at the flow test point is greater than or equal to the required developed head as required by SR 3.7.5.2 and the ASMIE OM Code.

1.2.2 Quarterly full stroke exercise, stroke time shut, and position indication test of the following as required by the ASME OM Code:

2AF-4000, 2P-29 AFP Disch SG B Inlet MOV 0 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV 1.2.3 Quarterly full stroke exercise, stroke time open and shut, position indication, and check valve open test of the following as required by the ASME OM Code and for environmental qualification requirements:

2MS-2019, B SG STM Supply to 2P-29 AFP

2MS-2020, A SG STM Supply to 2P-29 AFP 1.2.4 A Shut test of 2MS-2082, Overspeed Trip Valve. This is a skid mounted device as allowed by the Code, whereas satisfactory testing of 1P-29 also satisfies the required testing for this valve.

1.2.5 Quarterly full stroke exercise, stroke time open, fail-safe open and position indication tests of 2MS-2090, 2P-29 AFP Bearing Cooling Inlet, as required by the ASME OM Code.

1.2.6 Quarterly partial open exercise stroke of SW-1 12A, 2P-29 AFP Inlet Check, valve as required by the ASME OM Code.

Page 2 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 1.2.7 Quarterly full stroke exercise, stroke time open and shut and position indication tests of 2AF-4002, 2P-29 AFP Mini-Recirc Control Valve, as required by the ASME OM Code.

1.2.8 Quarterly full stroke open exercise test for the following check valves, as required by the ASME OM Code:

"* 2AF-100, 2HX-lA SG Auxiliary Feedwater First Off Check Valve.

"* 2AF-o01, 2HX-1B SG Auxiliary Feedwater First Off Check Valve.

"* 2AF-106, 2P-29 AFP Discharge to 2HX-IA SG Check Valve.

"* 2AF-107, 2P-29 AFP Discharge to 2HX-IB SG Check Valve.

"* 2AF-108, 2P-29 AFP Discharge Check Valve.

0 2AF-1 14, 2P-29 Minimum Flow Check Valve 1.2.9 This procedure performs a bi-directional exercise and gross leakage check of the TDAFP Mini-Recirc Valve (2AF-4002) Instrument Air Accumulator, 2T-212 Seismic Boundary 2 dCheck valve as required by the ASME OM Code.

[ 2AF-173, 2P-29 AFP Mini-Recirc IA 2nd off check. (nearest accumulator) 1.3 To perform a quarterly flush of the turbine bearing coolers. Reference response to NRC Generic Letter 89-013, SE 2001-0059, and commitment change evaluation (CCE) 2001-010.

1.4 This procedure, when performed in conjunction with 2-PT-AF-2, Turbine Driven Auxiliary Feedwater System Main Steam Pressure Test - Outside Containment, Unit 2 fulfils the 40-month functional and/or the 10-year N-498-1 hydrostatic pressure test requirements for Class 2 Auxiliary Feedwater Pump steam supply piping and Class 3 Turbine-Driven Auxiliary Feedwater Pump 2P-29 piping and components.

1.5 SR 3.7.5.4, Successful performance of this test will ensure that 2P-29 Steam Driven AFW Pump, will start when given an actuation signal.

Page 3 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED COLD START OF TURBINE-DRIVEN AUXILIARY FEED Revision 29 August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 2.0 PREREQUISITES 2.1 Assemble the following portable test instruments and log their ID numbers for the applicable portions of this procedure.

2.1.1 Two stopwatches Control Room 1ID No.

Cal due date:

Local ID No.

Cal due date:

2.1.2 Vibration monitor ID No.

Cal due date:

2.1.3 RPM indicator ID No.

Cal due date:

2.2 IF it is desired to consider the equipment available per the maintenance rule, THEN two level 4 dedicated operators will be required, one for the control room and the second locally per OM 3.26, Use Of Dedicated Operators, during the performance of this procedure.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 If there is any problem in performing this test, immediately notify the Duty Shift Superintendent. Operability 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 feed flow. RTO is unreliable.

Use of DTP and Nuclear Instruments recommended. (Reftnc 0-TS-RE-O01 and AOP.21) 3.3 Do NOT perform more than one portion of this test at a time.

3.4 For the purposes 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 the control board indication for 2MS-2019, B SG STM Supply to 2P-29 AFP, and 2MS-2020, A SG STM Supply to 2P-29 AFP, and local indicating lights and control for 2MS-2090, 2P-29 AFP Bearing Cooling Inlet. The stopwatch should be started at the moment the control switch or trip lever is actuated. (B.2)

Page 4 of 46 CONTINUJOI S TISE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 3.5 Low suction pressure condition causes a common suction pressure alarm (COl A 4-9, Aux Feed Pump Suction Pressure Low), and a low suction pressure trip of 2MS-2082, 2P-29 AFP Overspeed Trip Valve, with an attendant alarm (2C03 2D 3-4, 2P-29 AFP Low Suction Pressure Trip).

3.6 If at any time pump suction pressure is less than the NPSH required, (6.5 psig) this test must be discontinued until problem is corrected.

3.7 If the as-found position of 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV or 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV do NOT agree with the wall plaque position (plus or minus 1%) the test may continue; however, a action request shall be submitted. It is acceptable for the valves to be found in positions specified by other approved procedures performed in the same LCO window.

3.8 To prevent dam age to 2P-29 m onitor and maintain AFW discharge and / or recirc flow fgreater than 75 GPM OR STOP 2P-29.

i Page 5 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS NOTE: This procedure can be used in its entirety or sections/steps may be marked as NOT applicable (N/A) by the DSS[DOS.

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 NO.T applicable for the performance of the PMT. The use of N/A is NOT acceptable for Initial Conditions, Precautions and Limitations, or procedure steps that pertain to the equipment requiring PMT, nor is it acceptable for restoration of equipment/components unless the component has been declared inoperable. (B-1)

Post maintenance operability test Equipment IDI WO No(s).

Task Sheet No.(s)

Special test - no numbers.

Explain:

NOTE: RTO calculation is unreliable for power readings during the test because it does NOT account for Auxiliary Feed Flow. Use DTP and Nuclear Instrumentation.

NOTE: Operating 2P-29 at 400 GPM feed rate to the S/G's will increase reactor power by approximately 0.8 %.

4.2 IF load reduction greater than or equal to 2% is required, THEN ensure load reduction is planned with WEPOG.

4.3 Reactor Power reduced 2% below limiting reactor power as directed by DSS.

4.4 Auxiliary feed system is lined up for critical operation per CL 13E, Part 1, Auxiliary Feedwater Valve Lineup Turbine-Driven Unit 2.

4.5 Chemistry notified about auxiliary feed water injection.

Page 6 of 46 CONTINUOUS USE

POhNT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 4.6 Steam generator pressures are greater than or equal to 780 psig.

4.7 Steam generators are available to receive water.

4.8 Reactor power is being monitored using PPCS point DTP, if available, and Nuclear Instrumentation. (Ref o-T.-RE--oo) 4.9 2P-29, Aux Feedwater Turbine-Driven Pump, has NOT been operated within the previous 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to be considered a valid Cold Start Test (e.g.

2MS-2019/2020 have not had steam flow through them within the previous four hours).

4.10 P-38A, Aux Feedwater Motor-Driven Pump with its associated flow path is operable.

4.11 P-38B, Aux Feedwater Motor-Driven Pump with its associated flow path is operable.

4.12 PBF-3070, Contaminated Steam Release, is available for recording data.

(Step 5.22) 4.13 The IST Coordinator is available for PMT data review if 2P-29 has been replaced, disassembled, realigned or the coupling has been disassembled.

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

4.14 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 the test is not being performed for power-operated valve PMT.

4.15 Permission to Perform Test The conditions required by this test are consistent with required plant conditions including equipment operability.

DSS TIME DATE Paqe "7 of -46 CONTINTOUS USE

POL--T BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.0 PROCEDURE 5.1 Adjust 2LC-2125, SC-1B Condenser Hotwell Level Controller, to maintain hotwell level at the lower end of the normal operating band.

5.2 Ensure pump bearing oil level between red lines on glass.

Inboard Outboard 5.3 Ensure Turbine bearing oil level is observable in Opto-matic oilers.

Inboard Outboard 5.4 Ensure that the oil level is visible in the sight glass of the governor right angle drive gear box.

Drive Gear Box.

5.5 Ensure that the oil level for the Turbine-governor is between the line and the top of the sightglass.

5.6 Record the as-found position of 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV AND 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV.

5.6.1 2AF-4000 2AF-4001 2C-03 Local Wall Plaque 5.6.2 Compare the local AND wall plaque positions to be within +/- 1%.

2AF-4000 Check if OK 2AF-40 01 Check if OK "

5.6.3 IF positions are NOT the same (+/- 1%),

THEN notify the DSS. (Ref P&L 3.7.)

Page 8 of 46 CONTINUOUS USE

POEfiT BEACH NUCLEAR PLANT IT 09A INS ERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.7 Perform one of the following (N/A the step not used) 5.7.1 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 G, IF required.

5.7.2 IF sufficient qualified operators are not available on shift to assign as dedicated operator, THEN consider the equipment unavailable per maintenance rule AND assign available qualified operators to perform the restoration steps of Attachment G, if required.

5.8 2P-29, Aux Feedwater Turbine-Driven Pump, will be inoperable during portions of this test. Enter LCO Action Condition 3.7.5.B for 2P-29, Aux Feedwater Turbine-Driven Pump.

TIME DATE 5.9 Defeat the blowdown isolation interlock for unit 2 by placing 2 P-29 AFP SGBD isolation defeat to on, if required.

Pace 9 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS NOTE: Timing for 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV, should be performed by a local operator receiving a countdown from the Control Room. The stopwatch should be started at the Count of "Zero" and stopped when the valve motor stops.

5.10 Perform Quarterly Full Stroke Exercise, Stroke Time Shut, and Position Indication Test of 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV as follows.

5.10.1 Shut 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV.

5.10.2 Open AND time 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV THEN record time to OPEN on Attachment A. (B-4)

(For Information only) 5.10.3 Record the 2C03 position of 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV on Attachment A.

5.10.4 Record Local position of 2AF-4000, 2P-29 Aux Feed Pump Discharge 2HX-1B SG Inlet Isolation Motor Operator Valve, on Attachment A.

5.10.5 Shut AND Time 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV THEN record time to SHUT on Attachment A.

5.10.6 Record the 2C03 position of 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV on Attachment A.

5.10.7 Record Local position of 2AF-4000, 2P-29 Aux Feed Pump Discharge 2HX-1B SG Inlet Isolation Motor Operator Valve, on Attachment A.

Page 10 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS NOTE: Timing for 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV, should be performed by a local operator receiving a countdown from the Control Room. The stopwatch should be started at the Count of "Zero" and stopped when the valve motor stops.

5.11 Perform the Ouarterly Full Stroke Exercise, Stroke Time Shut, and Position Indication Test of 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV as follows.

5.11.1 Shut 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV.

5.11.2 Open AND time 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV THEN record time to OPEN on Attachment A.

(For Information only) 5.11.3 Record the 2C03 position of 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV on Attachment A.

5.11.4 Record Local position of 2AF-4001, 2P-29 Aux Feed Pump Discharge 2HX-1A SG inlet Isolation Motor Operator Valve on Attachment A.

5.11.5 Shut AND time 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV THEN record time to SHUT on Attachment A.

5.11.6 Record the 2C03 position of 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV on Attachment A.

5.11.7 Record Local position of 2AF-4001, 2P-29 Aux Feed Pump Discharge 2HX-1A SG inlet Isolation Motor Operator Valve, on Attachment A.

Pagye 11 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A lINSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.12 Perform the Ouarterly Full Stroke Exercise, Stroke Time Open. Fail-Safe Open, and Position Indication Test of 2MS-2090. 2P-29 AFP Bearing CoolinE, Inlet. as follows:

5.12.1 On panel 2C-144, 2MS-2090 AFP Brg Cooling Inlet Control Panel, check the AMBER test switch power available light is LIT.

5.12.2 Observe the local panel indicating lights AND time OPEN 2MS-2090, 2P-29 AFP Bearing Cooling Inlet, by placing the test switch in the TEST position. (B-2) 5.12.3 Record time to OPEN on Attachment A.

5.12.4 Locally verify OPEN lamp indication AND record on Attachment A.

5.12.5 Observe the local panel indicating lights AND time SHUT 2MS-2090, 2P-29 AFP Bearing Cooling Inlet, by placing the test switch in the NORMAL position. (For Information only) aB.2) 5.12.6 Record time to SHUT on Attachment A.

5.12.7 Locally verify SHUT lamp indication AND record on Attachment A.

5.12.8 Red lock 2MS-2090, 2P-29 AFP Bearing Cooling Inlet, test switch in the NORMAL position.

Page 12 of 46 CONTLNUOUS USE

POLNT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INIT'IALS 5.13 Shut 2MS-2082. 2P-29 Overspeed Trip Valve.

NOTE: Notify the DSS if 2MS-2082, Overspeed Trip Valve, does NOT trip.

5.13.1 Make an entry into the SOMs log stating that 2P-29 is unavailable due to 2MS-2082, 2P-29 AFP Overspeed Trip cycling.

NOTE: C01A 2-10, Auxiliary Feed Water System Disabled, will alarm during the performance of the next step.

5.13.2 Trip shut 2MS-2082, Overspeed Trip Valve, by depressing the trip button on turbine shaft housing. Note status on Attachment A.

5.13.3 Check that the amber trip light illuminates on 2C-03 AND note status on Attachment A.

Page 13 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.14 Closure exercise of TDAFP Mini-Recirc Valve Instrument Air Accumulator 2T-212 Seismic Boundary Check Valve 2AF-173 5.14.1 Close IA-350, 2AF-4002 AFP Mini-Recirc Control Valve Operating Air Inlet.

5.14.2 Uncap AND slowly Open 2AF-176, 2P-29 IA AFP Mini Recirc 2AF-173 Test Connection.

I 5.14.3 After initial depressurization, Check closure of 2AF-173 by checking for the absence of air leakage approximately 6 inches above the outlet of 2AF-176 by hand.

5.14.4 Record 2AF-173 closure test results on Attachment A.

5.14.5 Shut and Cap 2AF-176, 2P-29 AFP Mini Recirc 2AF-173 Test Connection.

5.14.6 Open IA-350, 2AF-4002 Mini-Recirc Control Valve Operating Air Inlet.

Page 14 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLA.-NT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS NOTE: The ability for 2AF-4002 to exercise to the open position with accumulator 2T-212 isolated satisfies the.stroke open test of check valve 2AF-173.

NOTE: Use local indication for timing 2AF-4002, 2P-29 AFP Mini-Recirc CV.

5.15 Perform The Quarterly Full Stroke Exercise, Stroke Time Open and Shut, and Position Indication Test Of 2AF-4002, 2P-29 AFP Mini-Recirc Control Valve, as follows:

5.15.1 Unlock AND shut 2AF-125, 2P-29 AFP Mini Recirc 2AF-4002-S Outlet Isolation.

5.15.2 Shut 2AF-175, 2P-29 AFP Mini Recirc IA 2T-212 Isolation.

5.15.3 Open AND time 2AF-4002, 2P-29 AFP Mini-Recirc CV, by unlocking AND opening 2AF-126, 2P-29 AFP Mini Recirc 2AF-4002-S Bypass Isolation.

5.15.4 Record time to OPEN on Attachment A.

5.15.5 Check the local position indicator for OPEN indication AND record on Attachment A.

5.15.6 Shut 2AF-126, 2P-29 AFP Mini Recirc 2AF-4002-S Bypass Isolation.

5.15.7 Shut AND time 2AF-4002, 2P-29 AFP Mini-Recirc CV, by opening 2AF-125, 2P-29 AFP Mini Recirc 2AF-4002-S Outlet Isolation.

5.15.8 Record time to SHUT on Attachment A.

5.15.9 Check the local position indicator for SHUT indication AND record on Attachment A.

5.15.10 Open 2AF-175, 2P-29 AFP Mini Recirc IA 2T-212 Isolation.

Page 15 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.16 Perform the Followine to Reset and Open 2MS-2082.2P-29 AFP Overspeed Trip Valve.

5.16.1 Align the flat side of the washer under the trip button with the trip arm. (Local) 5.16.2 Move the plug/stem latching mechanism into line by moving the trip rod to the extreme SOUTH position. (Local) 5.16.3 Verify the overspeed trip mechanism is LATCHED. (Local) 5.16.4 Close 2MS-2082, 2P-29 AFP Overspeed Trip valve Reset Operator.

a. Verify 2MS-2082, 2P-29 AFP Overspeed Trip Valve Reset Operator, green light ON.

b. Verify 2MS-2082, 2P-29 AFP Overspeed Trip Valve Reset Operator, red light OFF.

5.16.5 Open 2MS-2082, 2P-29 AFP Overspeed Trip Valve Reset Operator.

a. Verify 2MS-2082, 2P-29 AFP Overspeed Trip Valve Reset Operator, red light ON.

b. Verify 2MS-2082, 2P-29 AFP Overspeed Trip Valve Reset Operator, green light OFF.

c. Verify 2MS-2082, 2P-29 AFP Overspeed Trip Valve Trip Valve Position, amber light OFF.

d. Verify 2MS-2082, 2P-29 AFP Overspeed Trip Valve Position, red light ON.

5.16.6 Verify the following annunciators are CLEAR:

"* 2C03 2D 3-4, 2P-29 AFP Low Suction Pressure Trip.

"* C01A 2-10, Unit 2 Auxiliary Feed Water System Disabled.

Page 16 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A iNSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.16.7 Make an entry into the SOMs log stating that 2P-29 is now available because cycling of 2MS-2082, 2P-29 AFP Overspeed Trip valve is completed.

5.17 Align 2PI-4013A, 2P-29 AFP Suction Pressure Indicator, gauge as follows:

5.17.1 Shut pressure gauge vent.

5.17.2 Valve in pump suction pressure gauge, 2PI-4013A, 2P-29 AFP Suction Pressure Indicator.

5.17.3 Record suction pressure on Attachment B.

5.18 Record 2PI-4458, 2P-29 AFP Cooling Water Supply Pressure Indicator, on Attachment B. (If pressure is a vacuum then multiply vacuum reading by 0.491 and change sign to negative, (i.e. 3" HG x 0.491 = -1.473 psig).

5.19 Record steam generator pressure as indicated by 2PI-468, SG A Pressure AND 2PI-478, SG B Pressure on Attachment B.

5.20 Open 2AF-4002, 2P-29 AFP Mini-Recirc CV, as follows:

5.20.1 Shut 2AF-125, 2P-29 AFP Mini Recirc AF-4002-S Outlet Isolation.

5.20.2 Open 2AF-I26, 2P-29 AFP Mini Recirc AF-4002-S Bypass Isolation.

CAUTION If at any time equipment operation appears abnormal stop pump by shutting steam supply valve.

5.21 Ensure 2P-29, Aux Feedwater Turbine-Driven Pump, has NOT been operated within the previous four hours to be considered a valid Cold Start Test.

PaL~e 17 of 46 CONTET uTOT T. USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.22 Concurrently Record appropriate data on PBF-3070 during the run time of 2P-29, Aux Feedwater Turbine-Driven Pump, as required.

NOTE: RCS Temperature should be monitored during this test (1.5) 5.23 Start 2P-29, Aux Feedwater Turbine-Driven Pump, by performing the following:

5.23.1 Open AND time 2MS-2019, B SG STM Supply to 2P-29 AFP.

5.23.2 Record time to OPEN on Attachment C.

5.23.3 Check the rising stem indicator for OPEN indication AND record on Attachment C.

5.23.4 Open AND time 2MS-2020, 2HX-1A SG Header 2P-29 AFP Steam Supply MOV. Record Clock Time 5.23.5 Record time to OPEN on Attachment C.

5.23.6 Check the rising stem indicator for OPEN indication AND record on Attachment C.

NOTE: Due to steam quality during cold start, governor oscillations could take as long as 1 to 2 minutes to stabilize.

5.24 Observe pump comes up to speed AND governor takes control.

NOTE: 2P-29, Aux Feedwater Turbine-Driven Pump, suction pressure trip is set at 6.5 psig with a 20 second time delay.

5.25 Check 2P-29, Aux Feedwater Turbine-Driven Pump, suction pressure is greater than 6.5 psig on 2PI-4013A, 2P-29 AFP Suction Pressure Indicator.

NOTE: 2AF-4002, 2P-29 AFP Mini-Recirc CV, should remain open when the instrument air valve is returned to normal.

5.26 Open 2AF-125, 2P-29 AFP Mini Recirc AF-4002-S Outlet Isolation.

5.27 Shut 2AF-126, 2P-29 AFP Mini Recirc AF-4002-S Bypass Isolation.

Pagre 18 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.28 Verify 2AF-4002, 2P-29 AFP Mini-Recirc CV, OPEN.

NOTE: The following step satisfies full stroke exercising of 2AF-114, 2P-29 Minimum Flow Check Valve.

5.29 Check mini-recirculation flow greater than 100 gpm (expected range 120-130) on 2FIT-4049, 2P-29 Aux Feedwater Pump Mini Recirc Flow Indicator Transmitter AND record on Attachment B.

5.30 Red lock 2AF-125, 2P-29 AFP Mini Recirc AF-4002-S Outlet Isolation, in the normally OPEN position.

5.31 Red lock 2AF-126, 2P-29 AFP Mini Recirc AF-4002-S Bypass Isolation, in the normally SHUT position.

5.32 Record 2PI-2076, 2P-29 AFP Steam Pressure Indicator, on Attachment B.

5.33 Check the packing glands for excessive leakage AND record on Attachment B.

5.34 Check the pump AND turbine for unusual noise, odors, overheating, or leaks and verify service water flow to bearings AND record on Attachment B.

5.35 Verify the stroke of SW-I 12A, 2P-29 AFP Inlet Check and 2MS-2090, 2P-29 AFP Bearing Cooling Inlet.

5.35.1 Shut FP-298, 2P-29 AFP Emer Bearing Cooling Header Isolation.

5.35.2 Record 2PI-4458, 2P-29 AFP Cooling Water Supply Pressure Indicator, on Attachment B.

5.35.3 Open AND lock FP-298, 2P-29 AFP Emer Bearing Cooling Header Isolation.

5.36 Record bearing cooling supply AP on Attachment B to verify the partial stroke test of SW-I 12A, 2P-29 AFP Inlet Check.

Step 5.35.2 Step 5.18 Pagze 19 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.37 Using the Micro-logger and Figure 1, obtain vibration data as shown on Attachment B. (readings are NOT required to be transferred to the attachment)

CAUTION Injection of Auxiliary feed to steam generators at power will cause an increase in Reactor Power. RTO calculation does NOT account for Auxiliary feed flow.

RTO is unreliable. Use of DTP and Nuclear Instruments recommended.

(Reference 0-TS-RE-001 and AOP-21) 5.38 Adjust flow with 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV, to approximately 150 gpm or as required to close 2AF-4002, 2P-29 AFP Mini-Recirc CV.

5.39 Check 2AF-4002, 2P-29 AFP Mini-Recirc CV, SHUT.

5.39.1 Local position indication (%)

5.39.2 Control board indication 2C-03.

5.40 IF the 40-month functional and/or 10-year N-498-1 Hydrostatic Pressure Test is being performed concurrently with this procedure, THEN notify NDE that inspection may commence shortly. (cue to report to AFP room)

Pa*_e 20 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT'2 INITIA5LS NOTE: Steam Generator level deviation alarms are possible when adjusting Auxiliary Feedwater Flow.

NOTE: The following provides a full stroke of 2AF-101, 2HX-1B SG Auxiliary Feedwater First Off Check, 2AF-107, 2P-29 AFP Discharge to 2HX-1B SG Check, 2AF-108, 2P-29 AFP Discharge Check, and 2AF-111, 2P-29 AFP Suction Check.

5.41 Adjust 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV, for a total auxiliary feed flow rate of 400 gpm as indicated on 2DPIS-4002 AND record the following:

Time 400 gpm is achieved CLOCK hrs Turbine steam pressure 2PI-2076 psig 2AF-4000 position 2C-03 2AF-4000 position Local 2B steam generator pressure 2PI-478 psig Auxiliary feed flow rate to 2B SG 2FI-4037 gpm Auxiliary feed flow rate to 2A SG 2FI-4036 gpm 2P-29 auxiliary feed flow rate 2DPIS-4002 gpmr 2P-29 recirculation flow rate 2FIT-4049 gpm 2P-29 disch pressure 2PI-4004 psig I 5.42 After a two minute run time, record the data on Attachment B AND the IST required vibration points listed on Attachment B.

5.43 IF the 40-month functional and/or 10-year N-498-1 hydrostatic pressure test is being performed concurrently with this procedure, THEN after feeding Unit 2 B S/G for greater than 10 minutes with pump discharge pressure than 1173 psig, instruct NDE to perform VT-2 on the piping and components downstream of AF-4000 and record in 2-PT-AF-2.

5.44 Compare recorded bearing temperatures in Attachment B to limits listed on Attachment E.

NOTE: Annunciator C01A 2-10, Unit 2 Aux Feed System Disabled will alarm and clear during the performance of steps 5.45 through 5.48 unless already in alarm.

5.45 Shut AND time 2MS-2019, B SG STM Supply to 2P-29 AFP.

5.45.1 Record time to SHUT on Attachment C.

5.45.2 Check the rising stem indicator for SHUT indication AND record on Attachment C.

Page 21 of 46 CONTINUOUS USE

PODNT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.46 Open 2MS-2019, B SG STM Supply to 2P-29 AFP.

5.47 Shut AND time 2MS-2020, 2HX-IA SG Header 2P-29 AFP Steam Supply MOV.

5.47.1 Record time to SHUT on Attachment C.

5.47.2 Check the rising stem indicator for SHUT indication AND record on Attachment C.

5.48 Open 2MS-2020, 2HX-1A SG Header 2P-29 AFP Steam Supply MOV.

NOTE: Steam Generator level deviation alarms are possible when securing Auxiliary Feedwater Flow.

5.49 Shut 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV AND observe 2AF-4002, 2P-29 AFP Mini-Recirc Control Valve, begins to OPEN as flow decreases to approximately 110 gpm.

5.50 Check 2AF-4002, 2P-29 AFP Mini-Recirc CV, OPEN AND controlling flow. Use either local or control board indication.

5.51 Adjust flow with 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV, to approximately 150 gpm OR as required to close 2AF-4002, 2P-29 AFP Mini-Recirc CV.

5.5a2 Check 2AF-o4002, 2P-29 AFP Mini-Recir M SHUT. Use either local or CV, Pa~ye 22 nf Ar, PONTTN-TTOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS NOTE: Steam Generator level deviation alarms are possible when adjusting Auxiliary Feedwater Flow.

NOTE: The following provides a full stroke of 2AF-100, 2HX-1A SG Auxiliary Feedwater First Off Check, 2AF-106, 2P-29 AFP Discharge to 2HX-1A SG Check, 2AF-108, 2P-29 AFP Discharge Check, and 2AF-111, 2P-29 AFP Suction Check.

5.53 Adjust 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV, for a total auxiliary feed flow rate of 400 gpm as indicated on 2DPIS-4002 AND record the following:

Time 400 GPM is achieved Clock hrs Turbine steam pressure 2PI-2076 psig 2AF-4001 position 2C-03 2AF-4001 position Local 2A steam generator pressure 2PI-468 psig Auxiliary feed flow rate to 2A SG 2FI-4036 gpm Auxiliary feed flow rate to 2B SG 2FI-4037 gpm 2P-29 Auxiliary feed flow rate 2DPIS-4002 gpm 2P-29 Recirculation flow rate 2FIT-4049 gpm 2P-29 Disch pressure 2PI-4004 psig 5.54 IF the 40 - month functional and/or 10-year N-498-1 hydrostatic pressure test is being performed concurrently with this procedure, THEN after feeding Unit 2 A S/G for greater than 10 minutes with pump discharge pressure than 1173 psig, instruct NDE to perform VT-2 on the piping and components downstream of AF-4001 and record in 2-PT-AF-2.

5.55 IF the 40-month functional and/or the 10-year N-498-1 hydrostatic pressure test is being performed concurrently with this procedure THEN perform steps 5.56, 5.57 and 5.58 (otherwise mark as N/A).

5.56 Shut the following valves.

2AF-4000, 2P-29 AFP Disch SG B Inlet MOV, AND 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV.

5.57 Ensure 2AF-4002, 2P-29 AFP Mini-recirc is OPEN.

Page 23 of 46 CONTLNUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A SAFETY RELATED INSERVICE TESTS Revision 29 August 23, 2002 COLD START OF TURBINE-DRIVEN AUXILIARY FEED PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS INITIALS 5.58 After 2P-29 has been in service for a total of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND with pump discharge pressure greater than 1173 psig, instruct NDE to complete VT-2 examination of the remaining balance of AF System piping and components AND record data in 2-PT-AF-2.

CAUTION Do NOT exceed a total flow greater than 450 gpm during the performance of steps 5.59, 5.60 and 5.61.

5.59 Using Attachment F, adjust 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV, to the indicated flow for the existing A SfG pressure.

5.60 Using Attachment F, adjust 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV, to the indicated flow for the existing B SIG pressure.

.5.61 Adjust 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV AND 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV, as necessary, to balance steam generator flows. (Total flow based on Attachment F.)

5.62 Record the following:

Aux Feed flow to 2A SG 2FI-4036 Aux Feed flow to 2B SG 2FI-4037 Aux Feed flow 2DPIS-4002 2A SG Pressure 2PI-468 2B SG Pressure 2PI-478 Page 24 of 46 CONTINUOUS USE

It POINT BEACH NUCLEAR PLAINT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.63 Record the as-left position of 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV AND 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV.

5.63.1 2AF-4000 2AF-4001 2C-03 % __ U/

Local __% %

5.63.2 Update the wall plaque with the date the test was run and the as-left positions for 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV and 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV. (B-6)

Wall Plaque 2AF-4000 position .%

Date as-left Wall Plaque 2AF-4001 position .%

Date as-left 5.64 Isolate AND vent pump suction pressure gauge 2PI-4013A, 2P-29 AFP Suction Pressure Indicator.

5.65 Unlock AND shut 2AF-56, P-29 AFP Discharge to Hx-IA Steam Generator.

NOTE: The following two steps are performed concurrently.

5.66 Unlock AND shut 2AF-57, P-29 AFP Discharge to Hx-lB Steam Generator.

5.67 Check that as flow decreases the mini-retire valve, 2AF-4002, 2P-29 AFP Mini-Recirc CV, begins to OPEN at approximately 110 gpm. (B-7)

CAUTION To prevent damage to P-29 Monitor and maintain AFW discharge' and or recirc flow greater than 75 GPM OR Stop the pump.

Paee 25 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS NOTE: Annunciator C01A 2-10, Unit 2 Aux Feed System Disabled will alarm and clear during the performance of step 5.68 unless already in alarm.

5.68 Restore 2P-29, Aux Feedwater Turbine-Driven Pump, steam supply valves to AUTOMATIC.

5.68.1 Position an Operator to observe the coastdown behavior of 2P-29, Aux Feedwater Turbine-Driven Pump, for unusual noises, vibrations, or any other abnormal conditions.

5.68.2 Shut 2MS-2019, B SG STM Supply to 2P-29 AFP, AND return control switch-to AUTO.

5.68.3 Shut 2MS-2020, 2HX-1A SG Header 2P-29 AFP Steam Supply MOV AND return control switch to AUTO.

5.68.4 Record Time 5.68.5 Note all abnormal conditions in Remarks Section.

5.69 Open AND lock 2AF-56, P-29 AFP Discharge to Hx-1A Steam Generator.

5.70 Open AND lock 2AF-57, P-29 AFP Discharge to Hx-IB Steam Generator.

5.71 IF reactor power was reduced to perform this test, THEN commence a power increase using RTO calculation, if available, as directed by the DSS while continuing with the procedure.

5.72 Ensure 2MS-126, 2P-29 AFP Steam Supply Inlet, LOCKED in the OPEN position.

5.73 Enable the blowdown isolation interlock for Unit 2 by placing 2P-29 AFP SGBD Isolation Defeat to OFF, if required.

5.74 Check valve operability on Attachment A, IST Valve Data Sheet.

5.75 Check pump AND valve operability by comparing the data with the limits on Attachment B. Full flow data is required (400 gpm) for operability determination.

Page 26 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 IN4ITIALS 5.76 Check valve operability on Attachment C, IST Valve Data Sheet.

5.77 Check 2P-29, Aux Feedwater Turbine-Driven Pump, pump and turbine bearing temperatures by comparing the test data recorded on Attachment B with the limits in Attachment E, if required.

5.78 Second independent operator perform the following valve lineup verification.

NOTE: Equipment Danger Tagged may be marked as N/A.

Position 2MS-2019 B SG STM Supply to 2P-29 AFP S-A 2MS-2020 A SG STM Supply to 2P-29 AFP S-A 2AF-4000 2P-29 AFP Disch SG B Inlet MOV T (Per Local Wall Plaque) 2AF-4001 2P-29 AFP Disch SG A Inlet MOV T (Per Local Wall Plaque) 2MS-126 2P-29 AFP Steam Supply Inlet LO 2MS-2082 2P-29 Overspeed Trip Valve Reset - 0 2AF-4002 2P-29 AFP Mini-Recirc CV UG/LH I FP-298 2P-29 bearing supply header isolation LO 2AF-125 2AF-4002-S, 2P-29 AFP Mini Recirc Solenoid Outlet Isol LO 2AF-126 2AF-4002-S, 2P-29 AFP Mini Recirc Solenoid Bypass Isolation LS IA-350 2AF-4002 AFP Mini-Recirc Control Valve 0 Operating Air Inlet 2P-29 AFP Mini-Recirc IA 2AF-173 Test Connection S&C 2AF-175 2P-29 AFP Mini-Recirc IA 2T-212 Isolation 0 Red Locked 2MS-2090 2P-29 AFP Bearing Cooling Inlet, test switch NORMAL 2P-29 AFP Discharge to 2HX-lA Steam 2AF-56 LO Generator 2P-29 AFP Discharge to 2HX-1A Steam 2AF-57 LO Generator N/A 2P-29 AFP SGBD Isolation Defeat switch OFF Page 27 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 5.79 Reset 2LC-2125, Condenser Hotwell Level Controller, to maintain desired hotwell level.

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

5.81 Complete Section 6.1.1 of the Analysis section.

5.82 IF level 4 dedicated operators were assigned for this procedure, THEN they may be released from their duties.

5.83 IF test was satisfactory, THEN exit LCO 3.7.5.B, Action Condition for 2P-29, Aux Feedwater Turbine-Driven Pump.

Time Date Page 28 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS 6.0 ANALYSIS 6.1 Operations 6.1.1 Comparisons with allowable ranges of Acceptance Criteria test values complete.

SRO Date/Time 6.1.2 Forward completed procedure to IST Coordinator/Cognizant Engineer via Operations Specialist.

NOTE: To be completed within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 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.

Data Analyzed By Date/Time IST Remarks:

Page 29 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2

7.0 REFERENCES

7.1 Technical Specifications 7.1.1 3.7.5, AFW System 7.1.2 5.5.7, Inservice Testing Program 7.1.3 SR 3.7.5.2 7.1.4 SR 3.7.5.4 7.2 Procedures 7.2.1 CL 13E.Part 1, Auxiliary Feedwater Valve Lineup Turbine-Driven, Unit 2 7.2.2 0-TS-RE-001, Power Level Determination 7.2.3 AOP-21, PPCS Malfunction 7.2.4 2-PT-AF-2, Turbine Driven Auxiliary Feedwater System Main Steam Pressure Test - Outside Containment, Unit 2 7.2.5 OM 3.26, Use of Dedicated Operators 7.3 Miscellaneous 7.3.1 NRC Generic Letter 89-013 7.3.2 ASME'OM Code, 95Edition with 96 Addenda, Code for Operation and Maintenance of Nuclear Power Plants 7.3.3 PBF-3070, Potentially contaminated steam releases for Unit 7.3.4 PBF-2114, Return to Service Testing Review P Cag.e "0 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 August 23, 2002 COLD START OF TURBINE-DRIVEN AUXILIARY FEED PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 8.0 BASES B-i IR 96-006, NRC Inspection Report; NRC Commitment for Operations procedures PMT/QC reviews.

B-2 CR 98-1064, SW to TDAFWP CLG WTR ISOL VLV incomplete position indication requirements.

B-3 CR 98-0690, which states that the procedure does NOT provide any guidance for pump operability verification as required by Technical Specification 15.4.8.2.

B-4 CR 98-0122, Move inservice testing acceptance criteria into the respective procedures.

B-5 CR 99-0654, Reactor was NOT tripped when Admin low TAvE value was exceeded.

B-6 CR 99-0801, Improper positioning of Turbine driven Aux Feed pump discharge valves.

B-7 CR 99-1205, Relief valve lifts during 1P-29, Aux Feedwater Turbine-Driven Pump, Shutdown.

Page 3 1 of 46 CONTINUOUS USE

I POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 REMARKS SECTION:

Performed By:

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

Performer (Print) Performer (Sign) Date Time Initials

/

Performer (Print) Performer (Sign) Date Time Initials

/

Performer (Print) Performer (Sign) Date Time Initials

/

Performer (Print) Performer (Sign) Date Time Initials Reviewed By:

Shift Supervision (Print) Shift Supervision (Sign) Date Time Initials Pase 32 of 46 CONTINUOUS USE

POLNT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 ATTACHMENT A VALVE STROKE VERIFICATION Page 1 of 3 NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

Quarterly Full Stroke Exercise, Stroke Time Shut, and Position Indication Test of 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV Step Parameter Instrument i i Acceptance I No. Measured Used Criteria 5.10.2 Time to OPEN (info only) Stopwatch sec. N/A 5.10.3 2C03 Position Indication Board Meter % ;->85 5.10.4 Local Position Indication Local Valve :85 Indicator 5.10.5 Time to SHUT Stopwatch sec. 16.35 - 22.13 5.10.6 2C03 Position Indication Board Meter %-15 5.10.7 Local Position Indication Local Valve 515 Indicator %

Quarterly Full Stroke Exercise, Stroke Time Shut, and Position Indication Test of 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV Step No. Measured Parameter Instrument Used Reading Acceptance Criteria Initials 5.11.2 Time to OPEN (info only) Stopwatch sec. N/A 5.11.3 2C03 Position Indication Board Meter % Ž_85 Local Valve>8 5.11.4 Local Position Indication Indicator % :85 5.11.5 Time to SHUT Stopwatch sec. 16.64 -22.52 5.11.6 2C03 Position Indication Board Meter % -<15 Local Valve 5.11.7 Local Position Indication Local Indicator % -*15 Pnc-- -"' nf'Arý rrWN"TTTT TrNT Tc T I Q

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBLNE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

"UNIT2 ATTACHMENT A VALVE STROKE VERIFICATION Page 2 of 3 NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

Quarterly Full Stroke Exercise, Stroke Time Open, Fail-Safe Open, and Position Indication Test of 2MS-2090, 2P-29 AFP Bearing Cooling Inlet Step No. Parameter Instrument Units Reading Acceptance Initials Measured Used Criteria 5.12.3 Time to OPEN Stopwatch sec. 0-2 5.12.4 Local Position Indication Panel 2C-144 N/A OPEN Open Light 5.12.6 Time to SHUT (info only) Stopwatch sec. N/A 5.12.7 Local Position Indication Panel 2C-144 N/A SHUT Shut Light ____________________

Quarterly Stroke Shut test of 2MS-2082, 2P-29 Overspeed Trip Valve Step No. Parameter Measured Instrument Usd Used U

Units ICriteria Reading Acceptance JI Initials 5.13.2 SHUT 2MS-2082, Overspeed trip button on N/A. N/A Trip Valve turbine shaft 5.13.3 2C-03 trip light illuminates on Amber Lamp N/A _____ N/A ____

Quarterly Closure Exercise of 2AF-173, 2P-29 AFP Mini-Recirc IA 2 d Off Check Instrument Units Acceptance Parameter Step No. Measured Used (Note 1) Reading Criteria Initials (Note 1)

Excessive No excessive flow 5.14.4 Flow from 2AF-176 N/A flow after initial present d (Yes/No) depressurization NOTE: If excessive flow is present after one minute then the test is UNSAT. Excessive flow is defined as audible flow or flow that can be felt by hand at a distance of six inches from the valve.

Palge 34 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 ATTACHMENT A VALVE STROKE VERIFICATION Page 3 of 3 Quarterly Full Stroke Exercise, Stroke Time Open and Shut, and Position Indication Test of 2AF-4002, and Open Test of 2AF-173 e N Parameter Instrument Acceptance Step No. MaueUsd Units Reading CrtraInitials MesrdUsed Criteria I 5.15.4 Time to OPEN Stopwatch N/A sec.

1.87_- 5.6 OPEN 5.15.5 Local Position Indicator 5.15.8 Time to SHUT Stopwatch sec. 4.17 - 12.50 5.15.9 Local Position Indicator N/A % SHUT Acceptance Criteria Satisfied for all tested valves in Attachment A: (Circle one) SAT UNSAT Remarks:

/ I Performer Date/Time SRO Date/Time Paze 35 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UN1T 2 ATTACHMENT B 2P-29 Steam Turbine-Driven Auxiliary Feedwater Pump Recire Flow Data Paee I of 3 Step Parameter 5.17.3 Pump Suction Pressure Before Test 5.18 Bearing Cooling Supply Pressure 5.19 Steam Generator Pressure 1A 5.19 Steam Generator Pressure 1B 5.29 Mini-Recirculation Flow (Full Stroke Open Test of 2AF-114) 5.32 Turbine Steam Piessure 5.33 Packing glands for excessive leakage Pump and turbine for unusual noise, odors, 5.34 overheating, or leaks and verify service water flow to bearings 5.352 Bearing Cooling Supply Pressure 5.36 Bearing Cooling Supply AP 5.35.2 -5.18 K" VIBRATION POINT ID 5.37 21:29 GOV H ips Note 4 5.37 2P29 GOV H ips Note 4 Micro-logger G pk 5.37 2P29 GOV H ips" Note 4 Micro-logger G env 5.37 2P29 IV ips Note 4 Micro-logger IPS pk II 5.37 2P29 IH ips Note 4 Micro-logger IPS pk 5.37 2P29 1H ae Note 4 Micro-logger G env 5.37 2P29 1H ace Note 4 Micro-logger G pk 5.37 2P29 IA ips Note 4 Micro-logger IPS pk 5.37 2P29 2V ips Note 4 Micro-logger ITS pk 5.37 2P29 2H ips Note 4 Micro-logger IFS pk 5.37 2P29 3V ips (C) Note 3 Micro-logger IPS pk 5.37 2P29 3H ips (D) Note 3 Micro-logger IPS pk 5.37 2P29 3H ae Note 4 Micro-logger G env 5.37 2P29 3H ace Note 4 Micro-logger G pk 5.37 2P29 4V ips (A) Note 3 Micro-logger IPS pk 5.37 2P29 4H ips (B) Note 3 Micro-logger IPS pk 5.37 2P29 4H ae Note 4 Micro-logger G env 5.37 2P29 4H ace Note 4 Micro-logger G pk 5.37 2P29 4A ips (E) Note 3 5.37 __________

Pasze 36 of 46 CONTINUOUS USE

POU'T B-EACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 ATTACHMENT B 2P-29, Aux Feedwater Turbine-Driven Pump, 400 GPM flow data 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV Page 2 of 3 Step Parameter Instrument Units Acceptance Criteria Reading I 5.42 2P-29 Auxiliary Feed Flow Rate 2DPIS-4002 gpm 400 Note 6 542 2P-29 Recirculation Flow Rate 2FIT-4049 gpm NIA 5.42 Pump Discharge Pressure 2PI-4004 psig NIA 5.42 Pump Suction Pressure During Test 2PI-4013A psig N/A 5.42 Pump Differential Pressure Note 2 psid 1167 - 1303 5.42 Condensate Storage Tank Temperature (Note I) TI-4045/4046 OF NIA 5.42 Turbine rpm Portable 3564 - 3636

___VIBRATION POINT ID ________A ______

5.42 2P29 IV ips Note 4 Micro-logger IPS pk _

5.42 2P29 1H ips Note 4 Micro-logger IPS pk.

5.42 2P29 1A ips Note 4 Micro-logger IPS pk -' -

5.2 2P29 2V ips Note 4 Micro-logger IPS pk 5.42 2P29 2H ips Note 4 Micro-logger IPS pk ___ M___

5.42 2P29 3V ips (C) Note 3 Micro-logger IPS pk _ 0.332 542 2P29 3H ips (D) Note 3 Micro-logger IPS pk < 0.7 5.42 2P29 4A ips (E) Note 3 Micro-logger IPS pk < 0.503 5.42 2P29 4V ips (A) Note 3 Micro-logger IPS pk < 0.216 5.42 2P29 4H ips (B) Note 3 Micro-logger IPS pk < 0.666 5.42 Pump Inboard 2TR-2000 B Pt 17 OF <5160 5.42 Bearing Outboard 2TR-2000 B Pt 18 OF <5160 Temperature 5.42 Note 5 Turbine Outboard 2TR-2000 B Pt 19 OF _<250 5.42 Inboard 2TR-2000 B Pt 20 OF < 250 Page 37 of 46 CONTINUOUS USE

POLhNT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 ATTACHMENT B Page 3 of 3 NOTE 1: On the data sheet, circle the appropriate temperature indicator. If tanks are cross-connected, used the average of both tanks. TI-4045, A Tank / T1-4046, B Tank NOTE 2: Differential pressure = pump discharge pressure - pump suction pressure during test.

I NOTE 3: Points marked A, B, C, D, and E on Figure I-are required for ASME OM Code. Other points shown are for analysis and trending only.

NOTE 4: 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.

NOTE 5: Bearing temperatures are compared to limits listed on Attachment E.

NOTE 6: A flow rate of 400 GPM is the reference point.

Acceptance Criteria Satisfied for all parameters in Attachment B: (Circle one) SAT UNSAT Remarks:

I /

Performer Date/Time SRO Date/Time Pae~e 389 of,-46 3of46CONTTMTTTJq IJSE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 ATTACHMENT C VALVE STROKE VERIFICATION NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment.

I Quarterly Stroke Time Open and Position Indication Test of 2MS-2019, B SG STM Supply to 2P-29 AFP Parameter Instrument Units Acceptance Measured Used Criteria 5.23.2 Time to OPEN Stopwatch sec. 20.32- 27.50 5.23.3 Local Position Indication N/A N/A OPEN I Quarterly Stroke Time Open and Position Indication Test of 2MS-2020, A SG STM Supply to 2P-29 AFP I

5.23.5 Time to OPEN Stopwatch sec. 18.71-25.31 5.23.6 Local Position Indication N/A N/A OPEN I

I I

Quarterly Stroke Time Shut and Position Indication Test of 2MS-2019, B SG STM Supply to 2P-29 AFP 5.45.1 Time to SHUT Stopwatch sec. 20.05-27.13 5.45.2 Local Position Indication N/A N/A SHUT i

I Quarterly Stroke Time Shut and Position Indication Test of 2MS-2020, A SG STM Supply to 2P-29 AFP 5.47.1 Time to SHUT Stopwatch Sec. 19.01 -25.71 5.472 Local Position Indication NIA NIA SHUT Acceptance Criteria Satisfied for all tested valves in Attachment C: (Circle one) SAT UNSAT Remarks:

I I Performer Date/Time SRO Date/Time Pa.-e 39 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 ATTACHMENT D 1.0 This attachment shall be completed to document performance of multiple valve strokes. A separate copy of this attachment shall be prepared for each valve requiring multiple valve strokes. All copies of this attachment shall be attached to this procedure when the procedure is complete.

2.0 Refer to procedure steps required to perform stroking.

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

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

Valve Number: Date:

Step Initials Initials Initials Initials Initials Initials Initials Safety Related Requirement: Open / Shut (circle as required)

Data Data Data Data Data Data Data Data Time to shut (sec.)

Timne to open (sec.)

Page 40 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT2 ATTACHMENT E EVALUATION OF TURBINE DRIVEN AFP BEARING COOLING 1.0 Compare the bearing temperatures as recorded on the appropriate Attachment B to the criteria below.

ACCEPTABLE RANGE Pump inboard bearing temperature <120°F Pump outboard bearing temperature <120°F Turbine inboard bearing temperature _<2251F Turbine outboard bearing temperature 9225"F ALERT RANGE Pump inboard bearing temperature >1200 F <160°F Pump outboard bearing temperature >120°F <160°F Turbine inboard bearing temperature >225°F <2501F Turbine outboard bearing temperature >225°F <250'F ACTION REQUIRED (PUMP OOS) RANGE Pump inboard bearing temperature >160°F Pump outboard bearing temperature >160°F Turbine inboard bearing temperature ;.250°F Turbine outboard bearing temperature Ž.2500 F 2.0 If a bearing temperature falls into the Alert range, then:

2.1 The pump is still operable.

2.2 A MWR 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 LCO Action Condition remains in effect.

3.3 Notify the DCS and STA.

Page 41 of 46 CONTINUOUS USE

POLNT BEACH NUCLEAR PLANT IT 09A LNSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 ATTACHMENT F STEAM GENERATOR PRESSURE vs. AUX FEEDWATER FLOW NOTE: If Steam Generator pressures are NOT equal, flows should be set based on the highest indicated pressure.

S/G Press Total Aux Flow to S/G Press Total Aux Flow to each SIG Press Total Aux Flow to SIG Press Total Aux Flow 1o FW Flow each SIG FW Flow S/G FW Flow each S/G FW Fow each S/G 1090 261 131 1006 290 145 922 319 160 838 348 174 1087 262 131 1003 291 146 919 320 160 835 349 175 1084 263 132 1000 292 146 916 321 161 832 350 175 1081 264 132 997 293 147 913 322 161 829 351 176 1078 265 133 994 294 147 910 323 162 826 352 176 1075 266 133 991 295 148 907 324 162 823 353 177 1072 267 134 988 296 148 904 325 163 820 354 177 1069 268 134 985 297 149 901 326 163 817 355 178 1066 269 135 982 298 149 898 327 164 814 358 178 1063 270 135 979 299 150 895 328 164 811 357 179 1060 271 136 976 300 150 892 329 165 808 358 179 1057 272 136 973 301 151 889 330 165 805 359 180 1054 274 137 970 302 151 886 331 166 802 360 180 1051 275 137 967 304 152 883 333 166 799 362 181 1048 276 138 964 305 152 880 334 167 796 363 181 1045 277 138 961 306 153 877 335 167 793 364 182 1042 278 139 958 307 153 874 336 168 790 365 182 1039 279 139 955 308 164 871 337 168 787 366 183 1036 280 140 952 309 164 868 338 169 784 367 183 1033 281 140 949 310 155 865 339 169 , 781 368 184 1030 282 141 .946 311 155 862 340 170 778 369 184 1027 283 141 943 312 156 859 341 170 1024 284 142 940 313 156 856 342 171 1021 285 142 937 314 157 853 343 171 1018 286 143 934 315 167 850 344 172 1015 287 144 931 316 158 847 345 173 1012 288 144 928 317 159 844 346 173 1009 289 145 925 318 159 841 347 174 1006 290 145 922 319 160 838 348 174 PaeaCA2 0ofJ.6 P(ant2TTlITN lOT IS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS ATTACHMENT G 2P-29, Train Recovery for AF Initiation Page 1 of 3 NOTE: Steps that do NOT apply are marked N/A.

1.0 Enable the blowdown isolation interlock for Unit 2 by placing 2P-29 AFP SGBD Isolation Defeat switch to OFF, if required.

2.0 Open 2AF-125, AFP Mini Recirc AF-4002-S Outlet Isolation.

3.0 Shut 2AF-126, 2P-29 AFP Mini Recirc AF-4002-S Bypass Isolation.

4.0 Open 2AF-56, P-29 AFP Discharge to Hx-IA Steam Generator.

5.0 Open 2AF-57, P-29 AFP Discharge to Hx-1B Steam Generator.

6.0 Adjust 2AF-4000, 2P-29 AFP Disch SG B Inlet MOV, to the required position.

7.0 Adjust 2AF-4001, 2P-29 AFP Disch SG A Inlet MOV, to the required position.

I 8.0 Shut and Cap 2AF-176, 2P-29 AFP Mini-Recirc IA 2AF-173 Test Connection.

[ 9.0 Open 2AF-175, 2P-29 AFP Mini-Recirc IA 2T-212 Isolation.

10.0 Open IA-350, 2AF-4002 AFP Mini-Recirc Control Valve Operating Air Inlet.

I 11.0 Open FP-298, 2P-29 Bearing Supply Header Isolation.

12.0 Place 2MS-2090, 2P-29 AFP Bearing Cooling Inlet, test switch in the NORMAL position.

13.0 IF 2MS-2082, 2P-29 AFP Overspeed Trip Valve, is SHUT, THEN reset AND open 2MS-2082, Overspeed Trip Valve as follows.

13.1 Align the flat side of the washer under the trip button with the trip arm.

13.2 Move the plug/stem latching mechanism into line by moving the trip rod to the extreme SOUTH position. (Local) 13.3 Verify the overspeed trip mechanism is LATCHED. (Local)

Page 43 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS ATTACHMENT G 1P-29 Train Recovery for AF Initiation Page 2 of 3 13.4 Close 2MS-2082, 2P-29 AFP Overspeed Trip, valve Reset Operator AND verify the following: (C03) 13.4.1 Green light ON.

13.4.2 Red light OFF.

13.5 Open 2MS-2082, 2P-29 AFW Overspeed Trip Valve Reset Operator AND verify the following: (C03) 13.5.1 Red light ON.

13.5.2 Green light OFF.

13.5.3 Verify 2MS-2082, 2P-29 AFW Overspeed Trip, valve position, amber light OFF.

13.5.4 Verify 2MS-2082, 2P-29 AFW Overspeed Trip Valve Position, red light ON.

13.6 Verify the following annunciators are CLEAR:

2C203 2D 3-4, 2P-29 AFP Low Suction Pressure Trip.

C01A 2-10, Auxiliary Feed Water System Disabled.

14.0 Ensure the following after restoration when time is available:

14.1 2P-29 AFP SGBD Isolation Defeat switch for Unit 2 is in the OFF position, if required.

IV 14.2 2AF-125, AFP Mini Recirc AF-4002-S Outlet Isolation, OPEN AND LOCKED IV 14.3 2AF-126, 1P-29 AFP Mini Recirc AF-4002-S Bypass Isolation, SHUT AND LOCKED IV Page 44 of 46 CONTINUOUS .USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 INITIALS ATTACHMENT G IP-29 Train Recovery for AF Initiation Page 3 of 3 14.4 2AF-56, P-29 AFP Discharge to Hx-1A Steam Generator, OPEN AND LOCKED IV 14.5 2AF-57, P-29 AFP Discharge to Hx-IB Steam Generator, OPEN AND LOCKED IV 14.6 2AF-176, 2P-29 AFP Mini-Recirc IA 2AF-173 Test Connection. S&C IV 14.7 IA-350, 2AF-4002 AFP Mini-Recirc Control Valve Operating Air Inlet.

OPEN IV 14.8 2AF-175, 2P-29 AFP Mini Recirc IA 2T-212 Isolation.

OPEN IV 14.9 FP-298, 2P-29 Bearing Supply Header Isolation.

OPEN AND LOCKED IV 14.10 2MS-2090, 2P-29 AFP Bearing Cooling Inlet, test switch.

NORMAL AND LOCKED IV Page 45 of 46 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT IT 09A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)

UNIT 2 FIGURE 1 TURBINE-DRIVEN AUXILIARY FEED PUMP 3V 4V 1V 2V 4A (E) 4H (B)

GOV 2H (D)

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)

GOV = Governor Page 46 of 46 CONTINUOUS USE

ML030800044

Contents

Text

References:

References:

Reference:

7.0 REFERENCES

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