ML030790060

Temporary Change Review and Approval, OI 62B, Turbine-Driven Auxiliary Feedwater System (P-29)

ML030790060
Person / Time
Site:	Point Beach
Issue date:	10/30/2002
From:	Nuclear Management Co
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2003-0094 OI62B, Rev 9
Download: ML030790060 (34)

Text

Nuclear Power Business Unit TEMPORARY CHANGE REVIEW AND APPROVAL Note: Refer to NP 1.2.3. Temporary ProcedureChanges.for requirements.

Page I of Page 1 of I - INITIATION Dec Number 01 62B Current Rev 9 Unit PBO Temp Change No. 2002-0765 Document Title Turbine-Driven Auxilliary Feedwater System (P-29)

Existing Effective Temporary Changes N/A Brief Description Add P&L to address AFW Minimum Flow requirements (Identify specific changes on Form PBF-0026c. Document Review and Approval Continuation, and include with the package) 0 Initiate PBF-0026h and include with the change.

Other documents required to be effective concurrently with the temporary change: _t.A Changes pre-screened according to NP 5.1.8? 0 NO Dl YES (Provide domnentation according to Nps.I.)

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

Safety Evaluation Required? 0 NO El YES (tfy. a rcWon may be processed or fina, review; andapprovals hall be obainead before ibnp-*,,,n)

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)? El 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 0] El Ell 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 purposes? El ED

6. Requir0 a change to the procedure Purpose or change the procedure classifiction?

Initiated By (print/sign) Ross Groehler ate 10t29/2002 II - INITIAL APPROVAL This change is correct and complet,-ca be performed as written i es not adversely affect personnel or nuclear safety, or Plant operating cldons. I. ]

Group Supervisor (print/sign) 1(R_? Ii )

(Cannot be the Initiator)

I Date /o0?ln I I

/0,4- _j This change does not adversely ffect JIJant Ollerating conditions. (5aety ReJafed prcres only)

Senior Reactor Operator (print/sign) s, /AK- iZ. *-,I 7.'A *.. . Date ea

' (Candot be the Initiator or Gr'OufSupervisor) flI - PROCEDURE OWNER REVIEW SPermanent El One-time Use [E Expiration Date, Event or Condition:

[E Hold change until procedure completed (final revi and approval stipz.¶ired within 14 days of initial approval)

El QRIMSS Review NOT Required (Admin/NNS"!y)') QR Review Reqhifed Required (Retece H116.5))

Procedure Owner (print/sign) C A Date 1, 4 This Change and sucoortine reouirements correctlv comoleted and trocessed.

IV - FINAL REVIEW AND APPROVAL,-,

be comoleted within 14 days of initial aoorovanl (The Initiator. OR Annrova "lv shall Kdeoendent from ach er*

ISS (print/sign) ~, ~C'-E, !W1F oz. Ra f t fDcaiderl Indicates 50.5972.48 applicability assessed, any necessary screening~evaluations performed, determination made as to whoheradditional cross-disciplinary review required, and if required, performed.

MSS Meeting No. AQ'W__

Approval Authority pitsm f UT"A -1 '25, 99-7`

V - REVISION INFORMATION FOR PERMANENT CHANGES Post Typing Review (print/sign) /

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

Incorporated into Revision Number E I

PBF-0026e Revision 13 01/16/02 COY

References:

NP 1.2-3

Point Beach Nuclear Plant TEMPORARY CHANGE AFFECTED MANUAL LOCATION Page of Procedure Number 01 62B Revision 9 Unit PBO Title Turbine Driven Auxiliary Feedwater System (P-29)

Temporary Change Number 2002-0765 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: (ManualfLocation) Date Performed E] Copy included in work package for field implementation. (WO No. )

[* Copy filed in Control Room temp change binder (Operations only). / o ', -' z 0 Original change package provided to _ K G to obtainProcedure Owner Review (et, O*r r-eview may be coordinated by M-roup OA ILProcedue Writer, Procd*,me Supervisor, -t 0

5q 5

E5

[]

Perfornmed By (print and sign) . i-

/-/e 6. Date /ao-,.z-II-PROCEDURE OWNER REVIEW ON PBF-0026e (may be performed by OA I. Procedure Writer. etc.)

This prýcedure change has been processed as follows: (ManualfLocation) Date Performed I*] Copy sent to Document Control Distribution Lead for Master File.

(Not required for one-tirne use change) r-5 Copy filed in Group satellite file. (Not mqired for one.-time use changes.)

I] Copy filed in Group one-time use file.

0 Original Temp Change provided to cl) 1 c> to obtain Final Approvals /o *

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

P Ca._om y ntd ) c,,{,Sc -at -, .. , ( -. -,C -

Performed By (print and sign) C., (%SCk&-(Lo I. 6' L_ŽJ Date/c. -2 PBF-Re006h 6 Revision 5 0 113iV efrn0:1P1.

Reference.- NP 12.3

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Very SCR number o 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 , /  : /0i/. 2 Nam (Print)

Reviewed by - _ _ u _e_ Dae Date:

PART I (5059/72.48) - DESCRIBE THE PROPOSED ACTIVITY AND SEARCH THE PLANT AND ISFSI LICENSING BASIS (Resource Manual 5.3.1)

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

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

This screening supports procedural uprgrades to address the Auxiliary Feedwater (AFW) System issue as identified in CAP 29908 and CAP 29952. Procedural guidance for operation of AFW System will be changed such that the operator must ensure that discharge flow for P-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.

L2 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 "TSBases B 3.7.5 Auxiliary Feedwater (AFW) System FSAR 7.3.3A 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 6.6A 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.

Bfll a F%

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

TS 3.7.5 Auxiliary Feedwater (AFW) System "TSBases 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 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 ONo 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 1I (50.59) - DETERMINE IF THE CHANGE INVOLVES A DESIGNFUNCTION (Resource Manual 5.3.2)

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

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

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

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

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

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

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

copy vnrj*. ,

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 3 1R-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 11 are answered NO then Part III is [: 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 M11.3.

II.1 CHANGES TO THE FACILITY OR PROCEDURES YES NO QUESTION E] [0 Does the activity adversely affect the design function of an SSC credited in safety analyses?

El [] 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 [0 NOT APPLICABLE.)

YES NO QUESTION El 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. Ifboth 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 IH.3.b are 0 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?

Nit.

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Vedry SCRnunbef on all pages Page 4 If the answer to BOTH questions in V.3.a is NO continue to m.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 I1.3.a is YES, then these three questions are E] NOT APPLICABLE.

YES NO QUESTION 0 El Does the activity utilize or control an SSC in a manner that is outside the reference bounds ;f the design bases as described in the CLB?

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

[1 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 lL3.b is YES, a 10 CFR 50.59 Evaluation is required. If the answers in I113.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 Dl required or 0 NOT required.

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

A Regulatory Commitment (CLB Commitment Database) change is [3 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 10 NOT required. If a change to the Technical Specification Bases is required, then initiate a Technical Specification Bases change per NP 5.2.15.

"ATechnical Requirements Manual change is [l 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 (72A8) - 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.

YES NO QUESTION El 09 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? < ,.

Doc I Ci1C

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Vrify SCRnumbe on all p2geS Page 5 El [] Does the proposed activity involve IN ANY MANNER SSC(s) installed in the plant specifically added to support cask loading/unloading activities, as follows: Cask Dewatering System (CDW), Cask Reflood System (CRF), or Hydrogen Monitoring System?

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

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

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

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

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

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

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

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

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

El 0 Does the proposed activity involve plant, cask or ISFSI SSCs 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 casklISFSI 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 ofevaluation described in the ISFSI licensing basis?

E] 0 Is the activity a test or experiment? (i.e., a non-passive activity which gathers data) 0] 0] Does the activity exceed or potentially affect a cask design basislimitfor afissionproductbarrier(DBLFPB)?

(NOTE: If TH!S questions is answered YES, a 10 CFR 72.48 Evaluation is required.)

If the answers to ALL of these questions are NO mark Parts VII as not applicable, and document the 10 CFR 72.48 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 ALL the questions in Part V or Part VI are answered NO, then Part VII is 0 NOT APPLICABLE.)

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

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

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

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

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

YES NO QUESTION E] 11 Does the activity use a revised or different method of evaluation for performing safety analyses than that described in a cask SAP.?

El [I 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):

VH.3 - Tests or Experiments (If the activity is not a test or experiment, the questions in VII.3.a and VII3.b are El NOT APPLICABLE.)

a. Answer these two questions first:

YES NO QUESTION D] 1 Is the proposed test or experiment bounded by other tests or experiments that are described in the cask ISFSI licensing basis?

[E [E 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:

Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on ill pages Page 7 YES NO QUESTION 0 11 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?

I] 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?

0] 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 72A8 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 0 required or 0 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 [I required or ED 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 El required or 0 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 [: required or 0 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.

(, rý I T~nIra 1 19

01 62B TURBINE-DRIVEN AUXILIARY FEEDWATER SYSTEM (P-29)

DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 9 EFFECTIVE DATE: August 16,2001 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 CO'PY

• -POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16,2001 t* SYSTEM (P-29) 1.0 PURPOSE To provide instruction for proper operation of the turbine-driven auxiliary feedwater system (P-29) during the following evolutions:

1.1 Section 5.1, Maintaining Steam Generator Levels using P Non-Emergency Starts.

1.2 Section 5.2, Securing P-29.

1.3 Section 5.3, Resetting MS-2082 due to an Overspeed Trip.

1.4 Section 5.4, Locally Stopping a Turbine Driven Pump Following MS-2019 and/or 2020 Failure.

1.5 Section 5.5, Resetting or Overriding MS-2082 due to a Low Suction Pressure Trip.

1.6 Section 5.6 Perform an approximate Five Minute PMT Run of P-29 following Maintenance.

2.0 PREREQUISITES None 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Turbine bearing oil coolers must have normal (service water) or alternate (fire water) cooling supplied to run the turbine-driven pump. Upon a loss of power, alternate cooling should be verified.

3.2 If a pump or turbine bearing high temperature alarm is received then:

3.2.1 Check service water flow to bearing oil coolers.

3.2.2 Check for proper oil levels.

Governor oil level gauge glass - VISIBLE Governor right angle gear box sight glass - VISIBLE Pump bearing oil level between the red lines on the glass

- Turbine bearing oil available in Opto-matic oilers 3.2.3 Continue monitoring temperatures.

Page 2 of 25 CONTINUOUS USE

. "POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29) 3.2.4 Secure the pump if any of the following limits are reached (Action Required Range):

a. Pump inboard bearing temperature greater than or equal io 160 0F.

b. Pump outboard bearing temperature greater than or equal to 1600 F.

c. Turbine inboard bearing temperature greater than or equal to 250 0F.

. d. Turbine outboard bearing temperature greater than or equal to 250°F.

Q TO 3.3 The condensate storage tanks shall contain 13,000 gallons, of usable water per operating unit and lined up to the auxiliary feed pumps.TS: 3 .7 .6 (Ref.Tank Level Book) 34 Starting the turbine-driven pump will isolate blowdown for it's unit. Blowdown isolation can be prevented by using 1(2)P-29 AFP SGBD Isolation Defeat Switch.

3.5 Packing on the pumps is NOT normally adjusted by Operations personnel. Some stuffing box leakage is required for packing lubrication and cooling. Leakage should be considered excessive when water is being sprayed outside the catch basin.

3.6 When RCS Temperature is greater than 200'F, then steam generator narrow range level should be maintained above the "J" nozzles (48% - Unit 1, 60% - Unit 2) and near the program level 64%. (Acceptable range is 60 - 75%)

3.7 When RCS Temperature is greater than 200°F and Steam Generator narrow range level is less than 48% on Unit 1 (60% on Unit 2), then auxiliary feedwater addition is limited to 100 gpm and should NOT be interrupted for more than 15 minutes until water level recovers the feed ring J-nozzles, to minimize Feed Line water hammer.

3.8 UNIT I ONLY When RCS Temperature greater than 200'F and Steam Generator narrow range level is greater than 48%, then auxiliary feedwater addition is limited 400 gpm for feed ring "J Tube" water hammer concerns.

3.9 UNIT 2 ONLY When RCS Temperature is greater than 2000 F, then maintain Unit 2 steam generator narrow range levels greater than 47%, to ensure appropriate steam generator downcomer feedwater preheating.

Page 3 of 25 CONTINUOUS USE

• POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16,2001 SYSTEM (P-29) 3.10 To avoid lifting the suction relief valve when the pump is secured, reduce discharge flow to less than or equal to 110 gpm and check that the mini-recirc valve has opened before securing the pump.

3.11 The motor-driven auxiliary feedwater pumps are the preferred pumps for feeding the steam generators during normal startup, hot standby and shutdown evolutions when the main feed system is NOT available. The use of the turbine-driven auxiliary feedwater pump should be limited, if possible, to testing and abnormal or emergency situations.

3.12 Feedwater additions during hot standby should be performed in such a manner as to minimize the thermal stress cycles for the feedwater nozzle, i.e. continuous feed at a lower flow rate is less severe than batch feeding at a high flow rate.

3.13 For emergency situations, the existing criteria established in EOPs for assurance of effective auxiliary feedwater flow will continue to be followed. However, for those instances when the unaffected units turbine-driven pump is incapable of automatically delivering flow, a motor-driven pump will be returned to service as soon as possible.

3.14 It is possible that valves MS-2019 and/or MS-2020 could fail to operate following a design basis earthquake because these valves are only qualified for 10 minutes in harsh environments. Manual action may be needed to stop a turbine driven auxiliary feedwater pump.

TIS 3.15 The minimum pump flow requirement is ,fgpm, but it is desirable to maintain 120 gpm to increase pump life.

• 3.16 IF at any time, P-29 AFW Pump Flow is adjusted to less than gpm, THEN the associated AFW Pump must be secured OR a level 3 dedicated operator must be Rstationed to continuously monitor recirc flow per ATTACHMENT B Page 4 of 25 CONTINUOUS USE

-POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

INITIALS NOTE: The Initial Conditions do NOT apply to manually tripping Turbine Driven Auxiliary Feed Pump, resetting Overspeed Trip or Low Suction Pressure Trip or overriding the Low Suction Pressure Trip.

4.0 INITIAL CONDITIONS 4.1 A minimum of 13,000 gallons of usable water are available in the CSTs per operating unit TS: 3.7.6 4.2 The auxiliary feedwater system is lined up for critical operation per CL 13E, Part 1, Auxiliary Feedwater Valve Lineup Turbine Driven.

NOTE: The Feedwater Addition Form should be maintained whenever auxiliary feedwater is added on shutdowns from turbine off-line until RCS temperature is less than 200'F. It should also be maintained on unit startup when RCS temperature is greater than or equal to 2001F until the unit is synchronized on-line. The feedwater flow rate is the average rate for each addition.

4.3 Feedwater Addition Form, PBF-2027, is available if required.

4.4 The CST water temperature is greater than or equal to 32'F and less than or equal to 110°F.

Pagre 5 of 25 CONTINUOUS USE

""POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16,2001 SYSTEM (P-29)

INITIALS NOTE: It is NOT necessary to complete all sections of this procedure. Only the applicable section(s) as noted below need to be completed.

• Section 5.1, Maintaining Steam Generator Levels using P-29 -Non-emergency Starts.

• Section 5.2, Securing P-29.

• Section 5.3, Resetting MS-2082 due to an Overspeed Trip.

• Section 5.4, Locally Stopping a Turbine Driven Pump Following MS-2019 and/or 2020 Failure.

• Section 5.5, Resetting or Overriding MS-2082 due to a Low Suction Pressure Trip.

NOTE: This procedure is written for both units. Steps which are NOT applicable to the evolution in progress should be marked N/A.

CAUTION When RCS Temperature is greater than 200'F and Steam Generator narrow range level is less than 48 % on Unit 1 (60 % on Unit 2), then auxiliary feedwater addition is limited to 100 gpm and should NOT be interrupted for more than 15 minutes until water level recovers the feed ring J-nozzles, to minimize Feed Line water hammer.

CAUTION UNIT 1 ONLY When RCS Temperature is greater than 200°F and Steam Generator narrow range level is greater than 48%, then auxiliary feedwater addition is limited 400 gpm for feed ring "J Tube" water hammer concerns.

CAUTION UNIT 2 ONLY When RCS Temperature is greater than 200'F, then maintain Unit 2 steam generator narrow range levels greater than 47%, to ensure appropriate steam generator downcomer feedwater preheating.

Page 6 of 25 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16,2001 SYSTEM (P-29)

INITIALS 5.0 PROCEDURE 5.1 Maintaining the Steam Generator Levels Using P Non-Emergency Starts 5.1.1 IF the RCS is greater than or equal to 200°F, THEN document feedwater addition on PBF-2027, Feedwater Addition Form.

5.1.2 Defeat blowdown isolation interlock for the applicable unit using the switch on C03. (Mark the one NOT used N/A)

• 1P-29 AFP SGBD Interlock Defeat

• 2P-29 AFP SGBD Interlock Defeat J 5.1.3 IF the RCS is in Modes 1, 2, OR 3, or Mode4 whenSG is relied upon for heat removal THEN perform the following:

a. EnterTS: 3.7.5, Action Condition 7 b. Declare P-29 INOPERABLE due to tripping the low suction/overspeed trip valve MS-2082.

5.1.4 Shut the pump discharge valves. (C03)

"* AF-4000, P-29 AFP Disch SG B Inlet MOV

"* AF-4001, P-29 AFP Disch SG A Inlet MOV 5.1.5 Trip the turbine locally via the low suction/overspeed trip valve MS-2082 by manually actuating the turbine overspeed manual trip lever.

5.1.6 Check for proper oil levels.

0 Governor oil level gauge glass - VISIBLE

• Governor right angle gear box sight glass - VISIBLE

• Pump bearing oil level between the red lines on the glass

• Turbine bearing oil available in Opto-matic oilers Page 7 of 25 CONTINUOUS USE

'POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16,2001 SYSTEM (P-29)

INITIALS

( 5.1.7 Document steam release on PBF-3070, Potentially Contaminated Steam Releases.

5.1.8 IF at any time, P-29 AFW Pump Flow is adjusted to less than 1715 *,Xgpm, THEN the associated AFW Pump must be secured OR a level 3 dedicated operator must be stationed to continuously monitor recirc flow per ATTACHMENT B 5.1.9 Open either steam supply valve. (C03) (Mark valve NOT used N/A.)

"* MS-2019, B SG Stm Supply to P-29 AFP

"* MS-2020, A SG Stm Supply to P-29 AFP 5.1.10 Ensure AF-4002, P-29 Aux Feedwater Pump Mini Recirc Control Valve, OPENS. (C03) 5.1.11 Check PI-4458, P-29 Aux feedwater Pump Cooling Water Supply Pressure Indicator, greater than or equal to 25 psi.

5.1.12 Allow moisture to be blown out of steam supply.

5.1.13 Shut MS-126, P-29 Aux Feed Pump Steam Supply Inlet.

5.1.14 Reset the low suction/overspeed trip valve, MS-2082 per Step 5.3, Resetting MS-2082 due to an Overspeed Trip.

5.1.15 Raise the pump up to speed over a period of approximately 2 minutes by throttling open MS-126, P-29 Aux Feed Pump Steam Supply Inlet.

5.1.16 Notify Control to record the start time in the control room logbook.

5.1.17 WHEN the governor takes over, THEN open AND red lock MS-126, P-29 Aux Feed Pump Steam Supply Inlet.

IV Page 8 of 25 CONTINUOUS USE

, POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

INITIALS CAUTION UNIT 1 ONLY:

Do NOT exceed 400 gpm to a single steam generator.

5.1.18 Adjust the discharge valve for the desired flow rate. (C03)

"* AF-4000, P-29 AFP Disch SG B Inlet MOV

"* AF-4001, P-29 AFP Disch SG A Inlet MOV 5.1.19 IF P-29 was declared INOPERABLE in Step 5.1.3, THEN perform the following:

a. Declare P-29 OPERABLE due to resetting the low suction/overspeed trip valve MS-2082 AND demonstrating ability of P-29 to obtain required speed.

b. Exit TS: 3.7.5 Action Condition 5.1.20 Monitor the pump/turbine for proper operation.

FI-4002, P-29 AFP Discharge Flow (C03).

PI-4005, P-29 AFP Discharge Press (C03).

TR 2000 B-17 Point, Inboard Pump Bearing.

TR 2000 B-18 Point, Outboard Pump Bearing.

TR 2000 B-19 Point, Outboard Turbine Bearing.

TR 2000 B-20 Point, Inboard Turbine Bearing.

5.1.21 WHEN P-29 is no longer required, THEN continue with step 5.2.

Page 9 of 25 CONTINUOUS USE

• POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16,2001 SYSTEM (P-29)

INITIALS 5.2 Securing P-29 5.2.1 WHEN no longer required, THEN perform the following: (C03)

a. Reduce flow to less than or equal to 110 gpm.

b. Check AF-4002, P-29 Aux Feedwater Pump Mini Recirc Control Valve, is OPEN.

c. IF C03 El 3-2, Loss Of FW Turbine Trip, first out annunciator is lit, THEN depress Loss Of Turbine Trip Reset pushbutton.

(C03) (Mark N/A if NOT required.)

NOTE: The following step will cause C01A 2-8 (2-10),

Unit 1(2) Auxiliary Feedwater System Disabled annunciator to alarm.

d. Shut the steam supply valves to STOP the pump. (Mark any valve NOT used N/A.)

I

"* MS-2019, B SG Stm Supply to P-29 AFP IV

"* MS-2020, A SG Stm Supply to P-29 AFP IV

e. Return the steam supply valves control switches to AUTO.

0 MS-2019, B SG Stm Supply to P-29 AFP IV 0 MS-2020, A SG Stm Supply to P-29 AFP IV 5.2.2 Secure the level 3 dedicated operator stationed in step 5.1.8.

Notify Control to record the stop time in the control room logbook.

Page 10 of 25 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

INITIALS 5.2.4 Adjust the discharge valves, to their design positions per the local plaques. (C03)

"* AF-4000, P-29 AFP Disch SG B Inlet MOV IV

"* AF-4001, P-29 AFP Disch SG A Inlet MOV IV 5.2.5 IF blowdown isolation interlock switch is ON, THEN enable blowdown isolation by placing the switch to OFF. (N/A the one NOT used)

"* IP-29 AFP SGBD Isolation Defeat IV

"* 2P-29 AFP SGBD Isolation Defeat IV Page I11 of 25 CONTINUOUS USE

'POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

INITIALS 5.3 Resetting MS-2082 due to an Overspeed Trip NOTE: The turbine low suction/overspeed trip valve (MS-2082) is an emergency valve and will NOT be used for throttling.

When tripping, the valve stem and plug assembly operate independently of the operator of the valve. Therefore, it is necessary, when resetting the valve, to place the operator in the same position as the "tripped" plug and stem. The following steps will accomplish this.

5.3.1 Reset the overspeed trip mechanism. (Local)

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

b. Move the plug/stem latching mechanism into line by moving the trip rod to the extreme south position.

c. Verify the overspeed trip mechanism is latched.

5.3.2 Place the control switch for MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, momentarily to the SHUT position. (C03)

a. Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, green light ON. (C03)

b. Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, red light OFF. (C03)

Page 12 of 25 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

INITIALS 5.3.3 Place the control switch for MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, momentarily to the OPEN position, (C03)

a. Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, red light ON.

b. Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve IV Reset Operator, green light OFF.

IV

c. Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve Position, amber light OFF.

IV

d. Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve Position, red light ON.

5.3.4 IV Verify CO0A 2-8 (2-10), Unit 1(2) Auxiliary Feedwater System Disabled, alarm is CLEAR.

IV 5.3.5 Return to procedure and/or step in affect.

Page 13 of 25 CONTINUOUS USE

-POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16,2001 SYSTEM (P-29)

INITIALS 5.4 Locally Stopping a Turbine Driven Pump Following MS-2019 and/or 2020 Failure.

5.4.1 IF the RCS is in Modes 1, 2, OR 3, or Mode 4 when SG is relied

-d upon for heat removal THEN perform the following:

a. Enter TS: 3.7.5 Action Condition

b. Declare P-29 INOPERABLE due to MS-2019 and/or MS-2020 Failure.

5.4.2 Trip the turbine using one or more of the following three methods. (Mark the methods NOT used N/A.)

"* Trip MS-2082, P-29 Low Suction/Overspeed Trip Valve, by depressing the trip button on turbine shaft housing.

"* Shut MS-126, P-29 Aux Feed Pump Steam Supply Inlet.

CAUTION Shutting MS-235 and/or MS-237 may isolate Radwaste Steam.

Shut the manual isolation valve associated with the failed MOV. (If both are failed, shut both. If one is failed, mark the other N/A.)

(a) IF MS-2020 is failed, THEN shut MS-235, AFP/Radwaste steam header isolation.

(b) IF MS-2019 is failed, THEN shut MS-237, AFP/Radwaste steam header isolation.

5.4.3 Notify Control to record the stop time in the control room logbook Page 14 of 25 CONTINUOUS USE

-POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

INITIALS 5.5 Resetting or Overriding MS-2082 due to a Low Suction Press Trip NOTE: There are two ways to restart a pump that has tripped on low suction press. One method resets the low suction press trip and one overrides it. If it becomes necessary to override the trip, the operator shall monitor the pump response to ensure it has sufficient net positive suction head, and take manual action, if required.

5.5.1 IF a low suction pressure condition exists, THEN ve-ify the following actions.

a. MS-2082, P-29 Low Suction/Overspeed Trip Valve, is SHUT.

• Amber TRIP position light ON.

• Red TRIP position light OFF.

b. The following annunciators are in alarm condition:

"* C01A 4-9, Aux Feed Pump Suction Pressure Low

"* C03 ID (2D) 3-8 (3-4), P-29 AFP Low Suction Pressure Trip 5.5.2 IF the low suction pressure condition clears, THEN verify COlA 4-9, Aux Feed Pump Suction Pressure Low, alarm clear.

Page 15 of 25 CONTINUOUS USE

-POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

INITIALS INITIALS 5.5.3 Determine appropriate response to low pressure trip. (Mark the step NOT used N/A.)

a. IF normal conditions exist (COIA 4-9, Aux Feed Pump Suction Pressure Low, clears),

THEN perform the following:

"* Mark Steps 5.5.4 and 5.5.5 N/A.

"* Reset the low suction pressure trip per Step 5.5.6.

b. IF it is necessary to override the Low Suction Pressure Trip due to failure (i.e. - instrument failure) AND it is necessary to run the pump, THEN override the Low Suction Pressure Trip per Step 5.5.4.

CAUTION After the performance of step 5.5.4, the pump will not trip if a low suction pressure condition exists.

5.5.4 Perform the following to override the low suction pressure, NOTE: The following step will establish the override circuit and de-energize the trip/hold coil.

a. Momentarily place the control switch for MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, in the OPEN position. (C03)

b. Verify C03 ID (2D) 4-8 (4-4), P-29 AFP Suction Pressure Trip Disabled, in alarm.

Page 16 of 25 CONTINUOUS USE

"POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

INITIALS

c. Place the control switch for MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, to the CLOSE position. (C03)

"* Verify motor operator green light ON.

"* Verify amber trip light ON.

d. Place the control switch for MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, in the OPEN position. (C03) '

"* Verify reset operator red light is ON.

"* Verify reset operator green light is OFF.

"* Verify trip position red light is ON.

"* Verify trip position amber light is OFF.

e. WHEN P-29 is no longer required to operate OR the condition causing the low suction pressure trip has been corrected, THEN Perform Step 5.5.5.

NOTE: If the low suction condition has cleared, step 5.5.5.b will NOT occur and may be marked N/A.

5.5.5 Perform the following to clear C03 ID (2D) 4-8 (4-4),

P-29 AFP Suction Pressure Trip Disabled, alarm.

a. Momentarily depress the P-29 Low Suction Pressure Trip Override Reset push button.

b. Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve, trips CLOSED.

c. Verify C03 ID (2D) 4-8 (4-4), P-29 AFP Suction Pressure Trip Disabled, alarm is CLEAR.

Page 17 of 25 CONTINUOUS USE

"POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

INITIALS NOTE: Normal operation of the pump will be restored.

5.5.6 Perform the following to reset the low suction pressure trip:

a. Place the control switch for MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, momentarily to the SHUT position. (C03)

• Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, green light ON. (C03)

I Verify C03 ID (2D) 3-8 (3-4), P-29 AFP Low Suction Pressure Trip, is CLEAR: (C03)

b. Place the control switch for MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, momentarily to the OPEN position, (C03)

Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, red light ON.

IV Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve Reset Operator, green light OFF.

IV

"* Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve Position, amber light OFF.

IV

"* Verify MS-2082, P-29 Low Suction/Overspeed Trip Valve Position, red light ON.

IV 5.5.7 Return to procedure and/or step in effect.

Page 18 of 25 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16,2001 SYSTEM (P-29) 5.6 Perform an approximate Five Minute PMT Run of an inoperable P-29 following Maintenance

..6.1 IF the RCS is greater than or equal to 200'F, THEN document feedwater addition on PBF-2027, Feedwater Addition Form.

5.6.2 Defeat blowdown isolation interlock for the applicable unit using the switch on C03. (Mark the one NOT used N/A)

"* IP-29 AFP SGBD Interlock Defeat

"* 2P-29 AFP SGBD Interlock Defeat 5.6.3 IF NOT tripped, THEN trip the turbine locally via the low suction/overspeed trip valve MS-2082 by manually actuating the turbine overspeed manual trip lever.

5.6.4 IF NOT shut, THEN shut the pump discharge valves. (C03) e AF-4000, P-29 AFP Disch SG B Inlet MOV.

• AF-4001, P-29 AFP Disch SG A Inlet MOV.

5.6.5 Check for proper oil levels.

"* Governor oil level gauge glass - VISIBLE.

"* Governor right angle gear box sight glass - VISIBLE.

"* Pump bearing oil level between the red lines on the glass.

"* Turbine bearing oil available in Opto-matic oilers.

5.6.6 Document steam release on PBF-3070, Potentially Contaminated Steam Releases.

S5.6.7 IF at any time, P-29 AFW Pump Flow is adjusted to less than "75"0T4gpm,THEN the associated AFW Pump must be secured SJOR a level 3 dedicated operator must be stationed to SJcontinuously monitor recirc flow per ATTACHMENT B Page 19 of 25 CONTINUOUS USE

• POINTBEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 I

SYSTEM (P-29) 5.6.8 Open either steam supply valve. (C03) (Mark valve NO._.T.

used N/A.)

"* MS-2019, B SG Stm Supply to P-29 AFP.

"* MS-2020, A SG Stm Supply to P-29 AFP.

5.6.9 Ensure AF-4002, P-29 Aux Feedwater Pump Mini Recire Control Valve, OPENS. (C03) 5.6.10 Check PI-4458, P-29 Aux feedwater Pump Cooling Water Supply Pressure Indicator, greater than or equal to 25 psi.

5.6.11 Allow moisture to be blown out of steam supply.

5.6.12 Shut MS-126, P-29 Aux Feed Pump Steam Supply Inlet.

5.6.13 IF NOT reset, THEN reset the low suction/overspeed trip valve, MS-2082 per Step 5.3, Resetting MS-2082 due to an Overspeed Trip.

5.6.14 Raise the pump up to speed over a period of approximately 2 minutes by throttling MS-126, P-29 Aux Feed Pump Steam Supply Inlet OPEN.

5.6.15 Notify Control to record the start time in the control room logbook.

5.6.16 WHEN the governor takes over, THEN open AND red lock MS-126, P-29 Aux Feed Pump Steam Supply Inlet.

IV Page 20 of 25 CONTINUOUS USE

- - 'POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

I 1 5.6.17 Monitor the pump/turbine for proper operation.

"* FI-4002, P-29 AFP Discharge Flow (C03).

"* PI-4005, P-29 AFP Discharge Press (C03).

"* TR 2000 B-17 Point, Inboard Pump Bearing.

"* TR 2000 B-18 Point, Outboard Pump Bearing.

"* TR 2000 B-19 Point, Outboard Turbine Bearing.

I

"* TR 2000 B-20 Point, Inboard Turbine Bearing.

5.6.18 AFTER approximately five minutes, THEN secure P-29 as follows:

a. IF C03 El 3-2, Loss Of FW Turbine Trip, first out annunciator is lit, THEN depress Loss Of Turbine Trip Reset pushbutton.

(C03) (Mark N/A if NOT required.)

NOTE: The following step will cause CO0A 2-8 (2-10),

Unit 1(2) Auxiliary Feedwater System Disabled annunciator to alarm.

b. Shut tti6 steam supply valves to STOP the pump. (Mark any valve NOT used N/A.)

"* MS-2019, B SG Stm Supply to P-29 AFP.

IV

"* MS-2020, A SG Stm Supply to P-29 AFP.

IV

c. Return the steam supply valves control switches to AUTO.

"* MS-2019, B SG Stm Supply to P-29 AFP.

IV

"* MS-2020, A SG Stm Supply to P-29 AFP.

IV Page 21 of 25 CONTINUOUS USE

1. POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

d. Record the stop time in the control room logbook.

e. Ensure the discharge valves, are in the required positions per the local plaques. (C03)

"* AF-4000, P-29 AFP Disch SG B Inlet MOV.

IV

"* AF-4001, P-29 AFP Disch SG A Inlet MOV.

IV I 5.6.19 Secure the level 3 dedicated operator stationed in step 5.6.7 5.6.20 IF desired, THEN perform the following:

I.

a. Declare P-29 OPERABLE due to resetting the low I.) suction/overspeed trip valve MS-2082 AND demonstrating ability of P-29 to obtain required speed.

b. Exit TS: 3.7.5 Action Condition.

I."

5.6.21 IF blowdown isolation interlock switch is ON, THEN Enable blowdown isolation by placing the switch to OFF. (N/A the one NOT used)

IIP-29 AFP SGBD Isolation Defeat.

IV

• 2P-29 AFP SGBD Isolation Defeat.

IV Page 22 of 25 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16,2001 SYSTEM (P-29)

I

6.0 REFERENCES

6.1 Tank Level Book

( 6.2 Technical Specifications

! 6.2.1 TS: 3.7.5, Auxiliary Feedwater (AFW) System i

6.2.2 TS: 3.7.6, Condensate Storage Tank (CST) 6.3 CL 13E Part 1, Auxiliary Feedwater Valve Lineup Turbine Driven 6.4 P&IDs 6.4.1 M-217, Auxiliary Feedwater System, Sheets 1 & 2 6.4.2 M-207, Service Water System, Sheets 1, 1A, 2,4 6.4.3 M-201, Main & Reheat Steam Unit 1, Sheet 1 6.4.4 M-2201, Main & Reheat Steam Unit 2, Sheet 1 6.5 Westinghouse Technical Manuals 6.5.1 00104, Unit 1 Steam Generator 6.5.2 00109, Unit 2 Steam Generator 6.6 DBD 01, Auxiliary Feedwater Design Basis Document 6.7 Procedures 6.7.1 PBF-2027, Feedwater Addition Form.

6.7.2 CL 13E, Part 1, Auxiliary Feedwater Valves Lineup Turi Driven Pine 6.7.3 PBF-3070, Potentially Contaminated Steam Release.

7.0 BASES None Page 23 of 25 CONTINUOUS USE

- 'POINT BEACH NUCLEAR PLANT 01 62B OPERATING INSTRUCTIONS SAFETY RELATED Revision 9 TURBINE-DRIVEN AUXILIARY FEEDWATER August 16, 2001 SYSTEM (P-29)

Remarks:

Performed By:

i Performer (Print and Sign) Date Time Initials

/

Performer (Print and Sign) Date Time Initials

/

Performer (Print and Sign) Date Time Initials

/

Performer (Print and Sign) Date Time Initials

/

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

/

Reviewer (Print and Sign) Date Time Initials Page 24of 25 CONTINUOUS USE

01 62B ATTACHMENT A Level 3 Dedicated Operator at P-29 recirc flow meter instructions C)

C6 1.0 Continiously monitor 1FIT-4049, 1P-29 AFP Mini Recirc Flow Indicator OR 2FIT-4049, 2P-29 AFP Mini Recirc Flow Indicator.

i 2.0 IF indicated flow is less than 75 GPM THEN immediately notify the Control Room.

"Q PAGE 25 of 25