ML030800095
| ML030800095 | |
| 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 | |
| 2002-0847, FOIA/PA-2003-0094, IT 08A, Rev 29 PBF-0026c, Rev 13 | |
| Download: ML030800095 (64) | |
Text
{{#Wiki_filter:Nuclear Power Business Unit 7 TEMPORARY CHANGE REVIEW AND APPROVAL Note: Refer to NP 1.2.3, TemporaryProcedureChanges,for requirements. Page I of I- INITIATION Doc Number IT 08A Current Rev 29 Unit PBI Temp Change No. 2002-0847 Document Title Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly) Unit 1 Existing Effective Temporary Changes 2002-0722 Brief Description Add P&L and Cautions associated with AFW minimum Flow (Identify specific changes on Form PBF-0026c, Document Review and Approval Contnuation, 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 [0 YES (Provide domntsion acordng toNP 1.8) Screening completed according to NP 5.1.8? E5 NA ED YES (,tatch copy) Safety Evaluation Required? 0 NO E5 YES (ir'e arevision atay be p ,v*ced or final rviews and approls shan be aWned -ore impvjn.6ng) Determine if the change constitutes a Change Of Intent to the procedure by evaluating the following questions. (Ifany answers am 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 purposes?
- 6. Require a change to the procedure Purpose or change the procedure classifica ion? 5 0 Initiated By (prilnt/sign) Ross Groehler / 9U - - Date 10/31f2002 II - INITIAL APPROVAL This change is correct and complete, can be performed as written, ayds not adversely affect personnel or nuclear safety, or Plant operatin*;,conditiis. ,"
Group Supervisor (print/sign) I.K 6K-4I'- I N Date (Cannot be the Initiator) This change does not adversely ect Plao r n diti' afRa edures only Senior Reactor Operator (print/sign) _-Date,' \ 7..-.-, (Cannot be the Initiator or Group Supervisor) III - PROCEDURE OWNER REVIEW 0 Permanent 5l One-time Use E5 Expiration Date, Event or Condition: 5l Hold change until procedure completed (final review and approval still ^qtied within 14 days of initial approval) QR9 nc . Procedure Review Owner NOT Required (print/sign)paSS (Admng)evua I'- ,// QR Review Requirfomd OI - 1d 7/ reiew Date /1,//;po Required tVas weh ,o6a t nis Chance and stmvortine renuirernents correctly comoleted an oced-" // TV_- FINAL REVIEW AND APPROVAL (Mu.st be comoleted within 14 days fflnutial~n~ ,rlhe Initiator. OR and Aomgd* Auth 11lbe indeoendenf from eh dher)
*_* SS (print/sign) *Itc* C561 Jzdn , ).* ]/ Date 1/I / -"
Indicates 50.59t72.48 appnicabolty asss ed, eatany asaroscraeningtevaluations prformed, determination made as to whdthereditntonal cross-dpscplinary review requiredr and ifrequfd, performed. MSS Meeting No. _. Avoroval Authority (print/sian) / ' 7a7;*-
- V - REVISION INFORMATION FOR PERMANENT CHANGES l 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'
.1 PBF-0026e
References:
NP 1.2. Revision 13 01/16102
Point Beach Nuclear Plant DOCUMENT REVIEW AND APPROVAL CONTINUATION Page _ of Doc Number IT 08A Revision 29 Unit PBI Title Cold Start Of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly) Unit 1 Temporary Change Number 2002-0847 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 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 5.24 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 SCR2002-0458, 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 V Other Comments
- Note: Recording or Step Number(s) is not required for multiple occurrences of identical information or whcn not beneficial to reviewers.
PBF-0026c Revision6 0418/01
References:
NP 1.1.3,NP 1.2.3
Point Beach Nuclear Plant TEMPORARY CHANGE AFFECTED MANUAL LOCATION Page of Procedure Number IT 08A Revision 29 Unit PBI Title Cold Start Of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly) Unit I Temporary Change Number 2002-0847 I - IMMEDIATELY AFTER INITIAL APPROVAL ON PBF-0026e (Non-Intent changes) (after Final Approval if change of intent involved) Date This procedure change has been processed as follows: (Manual/Location) Performed E- Copy included in work package for field implementation. (WO No. ) MIR Copy filed in Control Room temp change binder (Operations only). [ Original change package provided to - k .& to obtain Procedure Owner Review (e.g., Owner review may be coordinated by In-Group OA II, Procedure Writer, Procedure Suprvisor, etc.). I/ / - " El El__ _ El El Performed By (print and sign) ~A ~ v,,-A ! v (/Dt (- . II - PROCEDURE OWNER REVIEW ON PBF-0026e (may be performed by OA II, Procedure Writer, etc.) Date This procedure change has been processed as follows: (Manual/Location) Performed [9 Copy sent to Document Control Distribution Lead for Master File. /I (Not required for one-time use change) [E Copy filed in Group satellite file. (Not required for one-time use changes.) El Copy filed in Group one-time use file. 0 Original Temp Change provided to 3M K- to obtain Final Approvals / (- / (e g., final approval may be coordinated by In-Group OA II, Procedure Writer, Procedure Supervisor, etc.) El 1:1 I-I 1E1 Performed By (print and sign) (j -J*-/*,-Z- 6,16 1' J '*-J Date (-{a-- PBF-0026h Revision 5 06/13/01
Reference:
NP 1.1.3
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) vcliry sCR number on all pages Page 1 Title of Proposed Activity: AFW rnimmum flow requirement change to AOP, EOP, CSP, ECA, SEP, 01-62 A/B procedures Associated Reference(s) #: Removal of internals from AF-117 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 Name ( Print) Reviewed by: ,6,_ VI Date: .C Nar--Print) Signature PART I (50.59172A8) - 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 72A8 screenings. Describe the proposed activity and the scope of the activity being covered by this screening. (The 10 CFR 50.59 / 72.48 review of other portions of the proposed activity may be documented via the applicability and pre-screening process requirements in NP 5.1.8.) Appropriate descriptive material may be attached. This screening supports procedural uprgrades to address the Auxiliary Feedwater (AFW) System issue as identified in CAP 29908 and CAP 29952. Procedural guidance for operation of AFW System will be changed such that the operator must ensure that discharge flow for P-38 A/B must be greater than 50 gpm and 1/2 P-29 discharge flow must be greater than 75 gpm. If pump flow cannot be maintained within these requirements, the pump must be secured. 1.2 Search the PBNP Current Licensing Basis (CLB) as follows: Final Safety Analysis Report (FSAR), FSAR Change Requests (FCRs) with assigned numbers, the Fire Protection Evaluation Report (FPER), the CLB (Regulatory) Commitment Database, the Technical Specifications, the Technical Specifications Bases, and the Technical Requirements Manual. Search the ISFSI licensing basis as follows: VSC-24 Safety Analysis Report, the VSC-24 Certificate of Compliance, the CLB (Regulatory) Commitment Database, and the VSC-24 10 CFR 72.212 Site Evaluation Report. Describe the pertinent design function(s), performance requirements, and methods of evaluation for both the plant and for the cask/ISFSI as appropriate. Identify where the pertinent information is described in the above documents (by document section number and title). (Resource Manual 5.3.1 and NEI 96-07, App. B, B.2) FSAR 10.2 Auxiliary Feedwater System (AF) - The AFW system shall automatically start and deliver adequate AFW flow to maintain adequate steam generator levels during accidents which may result in main steam safety valve opening, such as: Loss of normal feedwater (LONF) and Loss of all AC power to the station auxiliaries (LOAC). AFW system shall also deliver sufficient flow to the steam generators supporting rapid cooldown during such accidents as: steam generator tube rupture (SGTR) and main steam line break (MSLB). Each pump has an AOV controlled recirculation line back to the condensate storage tanks to ensure minimum flow to prevent hydraulic instabilities and dissipate pump heat. TS 3.7.5 Auxiliary Feedwater (AFW) System TS Bases B 3.7.5 Auxiliary Feedwater (AFW) System FSAR7.3.3A 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 6.6.4 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.
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pag 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. El Yes ID 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 El (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 0 E] 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? 0D E] 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? ED 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 ED Does the activity involve a method of evaluation described in the FSAR? El 0 Is the activity a test or experiment? (i.e., a non-passive activity which gathers data) El 0] Does the activity exceed or potentially affect a design basis limitfor afissionproduct barrier(DBLFPB)? (NOTE: If THIS questions is answered YES, a 10 CFR 50.59 Evaluation is required.)
"the answers to ALL of these questions are NO. mark Part III as not applicable, document the 10 CFR 50.59 screening in the .inclusion section (Part IV), then proceed directly to Part V - 10 CER 72.48 Pre-screening Questions.
If any of the above questions are marked YES identify below the specific design function(s), method of evaluation(s) or DBLFPB(s) involved.
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 3 MR-02-029 upgraded the open function of the AFW pumps mini-recirc AOV to safety-related. The safety-related boundary includes the recirc orifice and all associated upstream components and piping. It is postulated that a failure of the piping downstream of the recirc orifice .will not have any adverse affects on the AFW system. The availability of the recirculation flowpath provides an additional flowpath to support minimum flow requirements. This procedure change will improve the reliability of the AFW pumps by not relying upon the recirc flow path for operability as it has been concluded that the restrictions in the recirc orifice may not be adequate for use. Whereas current guidance mandates that the operator verify the position of the recirc AOV and the status of the Instrument Air system, these procedural changes will only require the operator to monitor pump discharge flow. PART 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 1HI is C 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 11.3. III.1 CHANGES TO THE FACILITY OR PROCEDURES YES NO QUESTION C] 0] Does the activity adversely affect the designfunction of an SSC credited in safety analyses? C] 0] Does the activity adversely affect the method of performing or controlling the design function of an SSC credited in the safety analyses? If any answer is YES a 10 CFR. 50.59 Evaluation is required. If both answers are NO, describe the basis for the conclusion (attach additional discussion as necessary): Minimum flow requirements will be maintained within recommendations from the vendor by monitoring pump discharge flow and securing the pump as required. Starting and stopping of the AFW pumps has been previously evaluated in 50.59 Evaluation 2002-005, which addressed procedural changes to reduce the potential of pump damage as a result of the loss of the recirculation flow path. 111.2 CHANGES TO A METHOD OF EVALUATION (If the activity does not involve a method of evaluation, these questions are Z NOT APPLICABLE.) YES NO QUESTION C C] Does the activity use a revised or different method of evaluation for performing safety analyses than that described in the CLB? C C] 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 desc'be 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 11.3.a and Il.3.b are Z NOT APPLICABLE.
- a. Answer these two questions first:
YES NO QUESTION S C] Is the proposed test or experiment bounded by other tests or experiments that are described in the CLB? C E Are the SSCs affected by the proposed test or experiment isolated from the facility?
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) venry SCR number on all pages Page 4 If the answer to BOTH questions in V.3.a is NO, continue to III.3.b. If the answer to EITHER question is YES, then describe the basis.
- b. Answer these additional questions ONLY for tests or experiments which do NOT meet the criteria given in III.3.a above.
If the answer to either question in III.3.a is YES, then these three questions are [] NOT APPLICABLE. YES NO QUESTION [I El Does the activity utilize or control an SSC in a manner that is outside the reference bounds 6f the design bases as described in the CLB? l [E1 Does the activity utilize or control an SSC in a manner that is inconsistent with the analyses or descriptions in the CLB? El El Does the activity place the facility in a condition not previously evaluated or that could affect the capability of an SSC to perform its intended functions? If any answer in III.3.b is Y, a 10 CFR 50.59 Evaluation is required. If the answers in 11L3.b are ALL NO describe the basis for the conclusion (attach additional discussion as necessary): 'art IV - 10 CFR 50.59 SCREENING CONCLUSION (Resource Manual 5.3.4). Check all that apply:
"A10 CFR 50.59 Evaluation is El required or 0 NOT required.
"APoint Beach FSAR change is [E required or 0D 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 [] required or 0 NOT required. If a Regulatory Commitment Change is required, initiate a commitment change per NP 5.1.7. A Technical Specification Bases change is El required or 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 0 NOT required. If a change to the Technical Requirements Manual is required, then initiate a Technical Requirements Manual change per NP 5.2.15. 10 CFR 72.48 SCREENING for guidance to determine the NOTE: NET 96-07. Appendix B. Guidelines for 10 CFR 72.48 Implementation should be used proper responses for 72.48 screenings. PART V (72.48) - 10 CFR 72.48 INITIAL SCREENING QUESTIONS for the proposed activity. Part V determines if a full 10 CFR 72.48 screening is required to be completed (Parts VI and VII) ES NO QUESTION the cask transfer/transport El 01 Does the proposed activity involve IN ANY MANNER the dry fuel storage cask(s), ISFSI facility SSC(s), or any ISFSI facility monitoring as follows: Multi-Assembly Sealed Basket equipment, any (MSB), MSB Transfer Cask (MTC), MTC Lifting Yoke, Ventilated Concrete Cask (VCC), Ventilated Storage Links, Cask (VSC), VSC Transporter (VCST), ISFSI Storage Pad Facility, ISFSI Storage Pad Data/Communication or PPCS/ISFSI Continuous Temperature Monitoring System?
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 5 0l 0 Does the proposed activity involve IN ANY MANNER SSC(s) installed in the plant specifically added to support cask loading/unloading activities, as follows: Cask Dewatering System (CDW), Cask Reflood System (CRF), or Hydrogen Monitoring System? El 0] Does the proposed activity involve IN ANY MANNER SSC(s) needed for plant operation which are also used to support cask loading/unloading activities, as follows: Spent Fuel Pool (SFP), SFP Cooling and Filtration (SF), Primary Auxiliary Building Ventilation System (VNPAB), Drumming Area Ventilation System (VNDRM), RE-105 (SFP Low Range Monitor), RE-135 (SFP High Range Monitor), RE-221 (Drumming Area Vent Gas Monitor), RE-325 (Drumming Area Exhaust Low-Range Gas Monitor), PAB Crane, SFP Platform Bridge, Truck Access Area, or Decon Area? such as El 0 Does the proposed activity involve a change to Point Beach CLB design criteria for external events earthquakes, tornadoes, high winds, flooding, etc.? used to support cask El 0 Does the activity involve plant heavy load requirements or procedures for areas of the plant loading/unloading activities? El 0] Does the activity involve any potential for fire or explosion where casks are loaded, unloaded, transported or stored? to the questions in If ANY of the Part V questions are answered YES, then a full 10 CFR 72A8 screening is required and answers the questions in Part V are answered NO then check Parts VI and VII as not Part VI and Part VII are to be provided. If ALL document the conclusion that no 10 CFR 72.48 evaluation is required. applicable. Complete Part VIII to PART VI (72.48) - DETERMINE IF THE CHANGE INVOLVES A ISFSI LICENSING BASIS DESIGN FUNCTION "TfALL the questions in Part V are NO then Part VI is [] NOT APPLICABLE.) following questions: Compare the proposed activity to the relevant portions of the ISFSI licensing basis and answer the YES NO QUESTION and El 0 Does the proposed activity involve cask/ISFSI Safety Analyses or plant/cask/ISFSI structures, systems 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? of a El 0 Does the proposed activity involve plant, cask or ISFSI SSCs whose function is relied upon for prevention radioactive release, OR whose failure could impact SSC(s) credited in the Safety Analyses? are El 0] Does the proposed activity involve cask/ISFSI described SSCs or procedural controls that perform functions that with, regulations, license conditions, CoC conditions, or orders? required by, or otherwise necessary to comply El 0 Does the activity involve a method of evaluation described in the ISFSI licensing basis? El 09 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 basislimitfor afissionproduct barrier(DBLFPB)? (NOTE: If THIS questions is answered YES, a 10 CFR 72.48 Evaluation is required.) screening in the If the answers to ALL of these questions are ., mark Parts VII as not applicable, and document the 10 CFR 72.48 conclusion section (Part VIII). method of evaluation(s) or DBLFPB(s) If any of the above questions are marked YES, identify below the specific design function(s), involved. ADVERSE EFFECTS (NEI 96-07, PART VII (72.48) - DETERMINE WHETHER THE ACTIVITY INVOLVES Appendix B, Section B.4.2.1) NOT APPLICABLE.) (If ALL the questions in Part V or Part VI are answered NO, then Part VII is Z
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Very 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 V113. VII.1 Changes to the Facility or Procedures YES NO QUESTION El El Does the activity adversely affect the design function of a plant, cask, or ISFSI SSC credited in safety analyses? I] El Does the activity adversely affect the method of performing or controlling the designfunction of a plant, cask, or ISFSI SSC credited in the safety analyses? If any answer is YES a 10 CFR 72A8 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 [I 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 a cask SAR? El 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 72A8 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 E] NOT APPLICABLE.)
- a. Answer these two questions frst:
YES NO QUESTION El El Is the proposed test or experiment bounded by other tests or experiments that are described in the cask ISFSI licensing basis? El I] Are the SSCs affected by the proposed test or experiment isolated from the cask(s) or ISFSI facility? describe If the answer to both questions is __,O continue to VII.3.b. If the answer to EITHER question is YES, then briefly the basis. criteria given in VII.3.a above.
- b. Answer these additional questions ONLY for tests or experiments which do not meet the Ifthe answer to either question in VII.3.a is YES, then these three questions are [E NOT APPLICABLE:
Point Beach Nuclear Plant SCR 2002-0458 10 CFR 50.59/72.48 SCREENING (NEW RULE) Vernfy SCR number on all pages Page 7 YES NO QUESTION E] E] Does the activity utilize or control an SSC in a manner that is outside the reference bounds of the design bases as described in the ISFSI licensing basis? El El Does the activity utilize or control a plant, cask or ISFSI facility SSC in a manner that is inconsistent with the analyses or descriptions in the ISFSI licensing basis? El El Does the activity place the cask or ISFSI facility in a condition not previously evaluated or that could affect the capability of a plant, cask, or ISFSI SSC to perform its intended functions? If any answer in VII.3.b is YES, a 10 CFR 72.48 Evaluation is required. If the answers are all NO. describe the basis for the conclusion (attach additional discussion' as necessary): PART VIII - DOCUMENT THE CONCLUSION OF THE 10 CFR 72.48 SCREENING Check all that apply: A 10 CFR 72.48 Evaluation is E3 required or Z NOT required. Obtain a screening number and provide the original to Records Management regardless of the conclusion of the 50.59 or 72.48 screening. A VSC-24 cask Safety Analysis Report change is [] required or 10 NOT required. If a VSC-24 cask SAR change is required, then contact the Point Beach Dry Fuel Storage group supervisor. A Regulatory Commitment (CLB Commitment Database) change is [] required or [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 El required or 0D NOT required. If a VSC-24 10 CFR 72.212 Site Evaluation Report change is required, then contact the Point Beach Dry Fuel Storage group supervisor.
Nuclear Power Business Unit TEMPORARY CHANGE REVIEW AND APPROVAL Note: Refer to NP 1.2.3, Temporary ProcidureChanges,for requirements. Page 1 of I - INITIATION Doc Number IT 8A Current Rev 29 Unit PB1 Temp Change No. 2002-0722 Document Title Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly) Unit 1 Existing Effective Temporary Changes none Brief Description changed Acceptance criteria for 1AF-4002 to 3.3-9.7 sec. SCR 2002-0447 (Identify specific changes on Form PBF-0026c, Document Review and Approval Coaunuation. and include with the package) ED Initiate PBF-0026h and include with the change. Other documents required to be effective concurrently with the temporary change: none Changes pre-screened according to NP 5.1.8? 0 NO 0l YES (Prome doction acdig to N s.ax Screening completed according to NP 5.1.8? [1 NA Z YES (Atach copy) Safety Evaluation Required? Z NO E] YES U(lY-.= a.i.o y b.pro.,d or &W ,kw and waa " b. "Ibeobained bo.r Determine if the change constitutes a Change Of Intent to the procedure by evaluating the following questions. (If any answers are M, a revision may be processed or final revie 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 0]
description in the Current or ISFSI Licensing Basis (as defined in NP 5.1.8 and NP 5.1.7)?
- 2. Cause an increase in magnitude, significance or impact such that it should be processed as a 0]
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? 0]
- 4. Delete QC hold points, Independent Verification or Concurrent Check steps without the El 0]
related step(s) that require the performance also being deleted?
- 5. Change Tech Spec or other regulatory acceptance criteria other than for re-baselining El 0]
purposes?
- 6. Require a change to the procedure Purpose or change the procedure c1*tlyion? ae 0]
Initiated By pntsign) K Sokol I RM b Z ) ) Date 1( or2/-2L'0 II - INITIAL APPROVAL This change is correct and complete, can be performed as written, and does not ersely affect nnel or nuclear safety, or Plant operating conditions. 1/ Group Supervisor (print/sign) -. DateZ (Cannot be thafnlttator) L This change does not adveI~ly affect Plant operatingc only) Senior Reactor Operator (print/sign)y rn ý = Date_ (Cannot be the Initiator or Group Supervisor) -J m - PROCEDURE OWNER REVIEW 0 Permanent El One-time Use [E Expiration Date, Event or Condition: El Hold change until procedure completed (final review and approvalstil required within 14 days of initial approval) El QR/MSS Review NOT Required (AdmidINSRs [ QR Review ) Review Required aec=e Ny i&Sý Procedure Owner (print/sign) (-,*:akI / Date This Qianve and saunordne reauirernents correctlv eomoleted and "rocessed. WV- FINAL REVIEW AND APPROVAl. I ust be cornoleted within 14 days of Initial avorovaf . The Initiator. OR and. 6 R/SS (printlsisp) /7--1 -'r-A-"4; < / .
"Indicates50.59/2.48 applicability assessed, any necessary screenings/evaliatic cross-dsciplinary review required, and if required, performed.
I MSS Meeting No. .;_IZff Approval Authority (printisimii al,41109 V( 4 Post Typing Review (print/sign) Indicates temporary change(s) incorporated exactly as approved and no other changes made to document. Incorporated into Revision Number Effective Date PBF-0026 2
References:
NP 1.2.3 Revision 13 01116102
Point Beach Nuclear Plant TEMPORARY CHANGE AFFECTED MANUAL LOCATION Page of Procedure Number IT 8A Revision 29 Unit PBI Title Cold Start of Turbine-Drived Auxiliary Feed Pump and Valve Test (Quarterly) Unit 1 Temporary Change Number 2002-0722 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: (Manutalocation) Date Performed "E"l Copy included in work package for field implementation. (WO No. ) [j Copy filed in Control Room temp change binder (Operations only). 0 - Zz [ Original change package provided to.
- kc G5S to obtain Procedure Owner Review (eg., Ownr,rview may be corcinated by In-Group OA L Procedure Wrter. Proced-re Suprsor i d 42.). " 2.
0 E] El El Performed By (print and sign) C-(b-V. t.- S c-c-v / CL- ..'--v Date /I -ZZ -t. H - PROCEDURE OWNER REVIEW ON PBF-0026e (may be performed by OA IL Procedure Writer. etc.) This procedure change has been processed as follows: (Manual/Location) Date Performed [J Copy sent to Document Control Distribution Lead for Master File. (Not required for one-time use change) E "Copy filed in Group satellite file. (Not required for one-tirm use changes.) El *Copy filed in Group one-time use file. [] Original Temp Change provided to -1) L) to obtain Final Approvals /.- . a (c.g. final approva may be coordinated by In-Group OA IL Prouedure Writer, Prcedare Suprdsor. etc.) I~ Ct~A-týV-*JS rC: V 1r____ El El_ _ El_ i--i( (Jttc _ _ [PerformedfBy (print and sign) Ca,(~Ic e-e *:~tL.~ ~Date bZ .6 j PBF-0026h Revisio5 06113/01
Reference:
NP 1.2.3
Point Beach Nuclear Plant SCR _2cc,- O,.q4. 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page I
,itle of Proposed Activity: IAF-4002 Rebaseline Associated Reference(s) #: SCR #2002-032 1, WO #0203508 Prepared by. David Dobson Date:
., - .7. r.
Name (Print) Signature Reviewed by- Date: Io-t7 ~ 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. 1.1 Descnrbe the proposed activity and the scope of the activity being covered by this screening. (The 10 CFR 50.59 / 72.48 review of other portions of the proposed activity may be documented via the applicability and pre-screening process requirements in NP 5.1.8.) Appropriate descriptive material may be attached. The IT-8ý open stroke time acceptance criteria for IAF-4002 is being revised due to maintenance. WO #0203508 disassem~led the valve and replaced internals (stemplug,cage). The actuator was also bench set and adjusted, the adustments and internal parts replacement justify the establishment of a new opening reference value. Actuator adjustments included limit switch adjustment, and an increase in the pressure required to stroke the valve (RMP 9141). 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 (-PER), 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) IAF.4002 is stroke timed to satisfy IST Program surveillance requirements (TS 5.5.7). TS 5.5.7 compliance requires the testing of components to the ASME OM Code 95 EdJ96A. The ASME OM Code, Subsection ISTC 3.4 allows for the establishment of new reference values after componeint maintenance. 1.3 Does the proposed activity involve a change to any Technical Specification? Changes to Technical Specifications require a License Amendment Request (Resource Manual Section 5.3.1.2). Technical Specification Change : El Yes Z No If a Technical Specification change is required, explain what the change should be and why it is required. 1.4 Does the proposed activity involve a change to the terms, conditions or specifications incorporated in any VSC-24 cask Certificate of Compliance (CoC)? Changes to a VSC-24 cask Certificate of Compliance require a CoC amendment request. DYes 0]No PBF-!SISc Rcvsin I 04MA11O <.--..%DIQ
Point Beach Nuclear Plant SCR .2ocZ - 0,4A47 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verfy SCR number on all pages Page 2 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 H (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 [] I] Does the proposed activity involve Safety Analyses or structures, systems and components (SSCs) credited in the Safety Analyses? 0 [] Does the proposed activity involve SSCs that support SSC(s) credited in the Safety Analyses? 0 C0 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? El 0 Does the proposed activity involve CLB-described SSCs or procedural controls that perform functions that arn required by, or otherwise necessary to comply with, regulations, license conditions, orders or technical specifications? :* C3 0 Does the activity involve a method of evaluation described in the FSAR? 0 C3 Is the activity a test or experiment? (i.e., a non-passive activity which gathers data)
".] 0] *oes the activity exceed or potentially affect a design basis limitfor afission product barrier(DBLFPB)?
(NOTE: If THIS questions is answered YES, a 10 CFR 50.59 Evaluation is required.) 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. The establishment of an open safety function for IAF-4002 was evaluated under SCR 2002-0321. This Screening established the initial open stroke time acceptance criteria for IAF-4002. An open safety function was attributed to this valve as the result of an NRC Red finding. This Red finding resulted in the classification of the TDAFWP minimum flow path as safety related. 1AF-4002 will open to provide a minimum flow path for the pump if inadequate flow (for pump protection) is detected. As noted in SCR 2002-0321 there is no DBA limiting stroke time requirement for IAF-04002 to open. The acceptance criteria for this valve to open is calculated in accordance with the ASME OM Code, Subsection ISTC 4.2.8. "Basedon a new opening reference value of 6.47 seconds, ISTCeSubsection 4.2.8 of the OM Code allows a plus or minus 50% variation in stroke time. Therefore, the new allowable opening band is 3.3 to 9.7 seconds. The previous reference value of 3.3 seconds is no longer applicable, the increase in the opening reference value can be attributed into the increase in stroke pressure to move from 36 to 43 psig. PART III (50.59) - DETERrIYNE 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 [] NOT APPLICABLE. wer the following questions to determine if the activity has an adverse effect on a design function. Any YE.S answer means that a
,:FR 50.59 Evaluation is required; EXCEPT where noted in Part 111.3.
111.1 CHANGES TO THE FACILITY OR PROCEDURES YES NO QUESTION PBF-1515c
- r. .- a l Point Beach Nuclear Plant SCR 2*o oZ .- q 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify sc w,ý=b on l] pageS Page 3 El 0] Does the activity adversely affect the designfunction of an SSC credited in safety analyses?
El 0] Does the activity adversely affect the method of performing or controlling the design function of an SSC credited in the safety analyses? If any answer is YES, a 10 CFR 50.59 Evaluation is required. Ifboth answers are NO, describe the basis for the conclusion (attach additional discussion as necessary): IAF-4002 provides a minimum flow path for TDAFWP protection, as noted in SCR 2002-0321 there is no DBA limit associated with valve opening. The new limits are calculated in accordance with the ASME OM Code and utilized to trend actuator/valve degradation. 111.2 CHANGES TO A METHOD OF EVALUATION (If the activity does not involve a method of evaluation, these questions are Z NOT APPLICABLE.) YES NO QUESTION El 0l Does the activity use a revised or different method of evaluation for performing safety analyses than that described in the CLB? El] E Does the activity us..-.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 11L.3.b are [] NOT APPLICABLE.
- a. Answer these two questions first:
YES NO QUESTION 0 El Is the proposed test or experiment bounded by other tests or experiments that are described in the CLB? D [0 Are the SSCs affected by the proposed test or experiment isolated from the facility? 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. The stroke time testing and rebaselining of 1AF-4002 are required for TS 5.5.7 "Inservice Testing Program" compliance. As allowed by the ASME OM Code, it is acceptable to rebaseline components after performance altering maintenance. WO
#0203508 replaced valve internals, adjusted limit switches and altered valve bench settings.
- b. Answer these additional questions ONLY for tests or experiments which do NOT meet the criteria given in I11.3.a above.
If the answer to either question in 111.3.a is YES then these three questions are [] NOT APPLICABLE. YES NO QUESTION El E] Does the activity utilize or control an SSC in a manner that is outside the reference bounds of the design bases as described in the CLB? El El Does the activity utilize or control an SSC in a manner that is inconsistent with the analyses or descriptions in the CLB?
Point Beach Nuclear Plant SCR 2o0Z.- oqqt7 10 CFR 50.59/72.48 SCREENING (NEW RULE) Veify SCR numer o all pages Page 4 l [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 11.3.b is YES a 10 CFR 50.59 Evaluation is required. If the answers in II.3.b are ALL NO, descnibe 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 C] required or 0 NOT required. A Point Beach FSAR change is E] required or [E 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 [] 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 0R NOT required. If a change to the Technical Specification Bases is required, then initiate a Technical Specifi&alýn Bases change per NP 5.2.15. A Technical Requirements Manual change is [] required or 0 NOT required. If a change to the Technical Requirements Manual is required, then initiate a Technical Requirements Manual change per NP 5.2.15. S10 CFR 72.48 SCREENING NOTE: NET 96-07. Appendir 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. YES NO QUESTION O3 0z Does the proposed activity involve IN ANY MANNER the dry fuel storage cask(s), the cask tmafer/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? [] 0] Does the proposed activity involve IN ANY MANNER SSC(s) installed in the plant specifically added to support cask loading/unloading activities, as follows: Cask Dewatering System (CDW), Cask Reflood System (CRF), or Hydrogen Monitoring System? El 0] Does the proposed activity involve IN ANY MANNER SSC(s) needed for plant operation which are also used to support cask loading/unloading activities, as follows: Spent Fuel Pool (SFP), SFP Cooling and Filtration (SF), Primary Auxiliary Building Ventilation System (VNPAB), Drumming Area Ventilation System (VNDRM), RE-105 (SFP Low Range Monitor), RE-135 (SFP High Range Monitor), RE-221 (Drumming Area Vent Gas Monitor), RE-325 (Drumming Area Exhaust Low-Range Gas Monitor), PAB Crane, SFP Platform Bridge, Truck Access Area, or Decon Area? El 0] Does the proposed activity involve a change to Point Beach CLE 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? PBF-1515c
Point Beach Nuclear Plant SCR 2eoZ - oqq -' 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR numiber on all pages Page 5
. 0] " Does the activity involve any potential for fire or explosion where casks are loaded, unloaded, transported or stored?
If AN. " of the Part V questions are answered YES, then a full 10 CFR 72.48 screening is required and answers to the questions in part VI and Part VII are to be provided. If ALL the questions in Part V are answered NO, then check Parts VI and VII as not applicable. Complete Part VIII to document the conclusion that no 10 CFR 72.48 evaluation is required. PART VI (72.48) - DETERMINE IF THE CHANGE INVOLVES A ISFSI LICENSING BASIS DESIGN FUNCTION (If ALL the questions in Part V are NO then Part VI is 0 NOT APPLICABLE.) Compare the proposed activity to the relevant portions of the ISFSI licensing basis and answer the following questions: YES NO QUESTION 5 [] Does the proposed activity involve cask/ISFSI Safety Analyses or plant/cask/ISFSI structures, systems and components (SSCs) credited in the Safety Analyses? 0 C0 Does the proposed activity involve plant, cask or ISFSI SSCs that support SSC(s) credited in the Safety Analyses? O3 01 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? F1 ] Does the proposed activity involve cask/ISFSI described SSCs or procedural controls that perform functions that are required by, or otherwise nec.esary to comply with, regulations, license conditions, CoC conditions, or orders? [3 El Does the activity involve a method of evaluation described in the ISFSI licensing basis? [I E3 Is the activity a test or experiment? (i.e., a non-passive activity which gathers data)
"J [] Does the activity exceed or potentially affect a cask design basis limitfor a fission product barrier(DBLFPB)?
N4OTE: If THIS questions is answered YES, a 10 CFR 72.48 Evaluation is required.) If the answers to ALL of these questions are NO mark Parts VII as not applicable, and document the 10 CFR 72.48 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 Z NOT APPLICABLE.) -Answer the following questions to determine if the activity haslan adverse effect on a design function. Any YES answer means that a 10 CFR 72.48 Evaluation is required, EXCEPT where noted in Part VII3. VII.1 Changes to the Facility or Procedures YES NO QUESTION EJ [] Does the activity adversely affect the design function of a plant, cask, or ISFSI SSC credited in safety analyses? Ei [] 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): PBF-1515c
iW 20-29f irPBV-Temp Chanze No. 2002-0722. - .. . Point Beach Nuclear Plant SCR 2coz. 10 CFR 50.59/72.48 SCREENING (NEW RULE) Vrify SCR numbe ao all pages Page 6 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 described in a cask SAR?. El Dl 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 jIf the activity is not a test or experimn.enthe questions in VI.3.a and VIL3.b are El NOT APPLICABLE.)
- a. Answer these two questions first:
YES NO QUESTION El 4*] Is the proposed test or experiment bounded by other tests or experiments that are described in the cask ISFSI licensing basis? [I [] 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 E] NOT APPLICABLE: YES NO QUESTION "C3 El Does the activity utilize or control aA SSC in a manner that is outside the reference bounds of the design bases as described in the ISFSI licensing basis? El El Does the activity utilize or control a plant, cask or ISFSI facility SSC in a manner that is inconsistent with the analyses or descriptions in the ISFSI licensing basis? 0l 0l 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):
Point Beach Nuclear Plant SCR i-z-_" 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 7
.RT VII- DOCUMENT THE CONCLUSION OF THE 10 CFR 72.48 SCREENING Check all that apply:
A 10 CFR 72.48 Evaluation is [] required or Z NOT required. Obtain a screening number and provide the original to Records Management regardless of the conclusion of the 50.59 or 72.48 screening. A VSC-24 cask Safety Analysis Report change is 0] required or 0 NOT required. If a VSC-24 cask SAP, change is required, then contact the Point Beach Dry Fuel Storage group supervisor. A Regulatory Commitment (CLB Commitment Database) change is [] required or Z NOT required. Ifa 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 Z 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. 41 -- 4 PBF-1515c 0 ....... *fl*
IT 08A COLD START OF TURBINE-DRIVEN AUXILIARY FEED PUMP AND VALVE TEST (QUARTERLY) UNIT 1 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 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 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 EdJ96A. Successful performance of this procedure will also satisfy Technical Specifications and environmental qualification requirements. (B-3) 1.2.1 Quarterly Comprehensive functional test of [P-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 developed head as required by SR 3.7.5.2 and the ASME 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:
- 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV
- 1AF-4001, 1P-29 AFP Disch SGA 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:
- 1MS-2019, B SG STM Supply to IP-29 AFP
- IMS-2020, A SG STM Supply to 1P-29 AFFP 1.2.4 A Shut test of 1MS-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 test of 1MS-2090, 1P-29 AFP Bearing Cooling Inlet, as required by the ASME OM Code. 1.2.6 Quarterly partial open exercise stroke of SW-135A, IP-29 AFP Inlet Check, valve as required by the ASME OM Code. 1.2.7 Quarterly full stroke exercise, stroke time open and shut, and position indication test of 1AF-4002, 1P-29 AFP Mini-Recirc Control Valve, as required by the ASME OM Code. Page 2 of 45 CONTTNT MTOI Tq TTPT7
"POINTBEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 1.2.8 Quarterly full stroke open exercise test for the following check valves, as required by the ASME OM Code:
- lAF-100, 1HX-1A SG Auxiliary Feedwater First Off Check Valve..
- 1AF-101, IHX-IB SG Auxiliary Feedwater First Off Check Valve.
- 1AF-106, IP-29 AFP Discharge to IHX-IA SG Check Valve.
- 1AF-107, 1P-29 AFP Discharge to lHX-lB SG Check Valve.
a 1AF-108, 1P-29 AFP Discharge Check Valve.
- 1AF-1 14, 1P-29 Minimum Flow Check Valve 1.2.9 A bi-directional exercise and gross leakage check of the TDAFP Mini-Recirc Valve (1AF-4002) instrument air accumulator, IT-212 Seismic Boundary 2 "d Check Valve as required by the ASME OM Code.
0 1AF-173, IP-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 I-PT-AF-2, Turbine Driven Auxiliary Feedwater System Main Steam Pressure Test - Outside Containment, Unit I 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 1P-29 piping and components. 1.5 SR-3.7.5A, Successful performance of this test will ensure that 1P-29, Steam Driven AFW Pump, will start when given an actuation signal. Paae 3 of 45 of4 Pa~e CtWvTTT\TT TCNTT(' Ye'
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNITI 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 ID 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 is desired to consider the equipment available per 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. 0cemcc 0-ws-001 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 1MS-2019, B SG STM Supply to IP-29 AFP, and 1MS-2020, A SG STM Supply to IP-29 AFP, and local indicating lights and control for 1MS-2090, IP-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 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 3.5 Low suction pressure condition causes a common suction pressure alarm (CO1 A 4-9, Aux Feed Pump Suction Pressure Low), and a low suction pressure trip of IMS-2082, IP-29 AFP Overspeed Trip Valve, with an attendant alarm (1C03 ID 3-8, IP-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 1AF-4000, IP-29 AFP Disch SG B Inlet MOV or 1AF-4001, 1P-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. t I 3.8 To prevent P-29 AFW Pump Damage, Monitor and Maintain AFW discharge SI AND / OR recirc flow greater than 75 GPM OR STOP 1P-29. .- N* Page 5 of 45 Page5of5OTTTTTT TT T7
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 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 NOT applicable for the performance of the PMT. The use of N/A is NOT acceptable for Initial Conditions, Precautions and Limitations, or procedure steps that pertain to the equipment requiring PMT, nor is it acceptable for restoration of equipment/components unless the component has been declared inoperable. ta-i) __Post maintenance operability test Equipment ID 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 1P-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 to 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 1. 4.5 Chemistry notified about auxiliary feed water injection. Page 6 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I 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 Instrumnntation. OcfW-TS- -O_00_1) 4.9 IP-29, Aux Feedwater Turbine-Driven Pump, has NOT been operated within the previous four hours to be considered a valid Cold Start Test (e.g. MS-2019/2020 have not had steam flow through them within the previous four hours). 4.10 P-3 8A, Aux Feedwater Motor-Driven Pump with its associated flow path is operable. 4.11 P-3 8B, 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 1P-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 N/A 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
'ln 7 1 .fal TýC-
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS 5.0 PROCEDURE 5.1 Adjust ILC-2125, SC-1A Condenser Hotwell Level Controller, to maintain hotwell level at the lower end of the normal operating band. 5.2 Ensure .pump beating 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 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV, AND 1AF-4001, IP-29 AFP Disch SG A Inlet MOV. 5.6.1 IAF-4000 IAF-4001 IC-03 Local Wall Plaque 5.6.2 Compare the local AND wall plaque positions to be within =-1%. 1AF-4000 Check if OK 1AF-4001 Check if OK 5.6.3 IF positions are NOT the same (d-1%), THEN notify the DSS. (Ref P&L 3.7.)
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 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 operators, 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 lP-29, Aux Feedwater Turbine-Driven Pump, will be inoperable during portions of this test. Enter LCO Action Condition 3.7.5.B for IP-29, Aux Feedwater Turbine-Driven Pump. TIME DATE 5.9 Defeat the blowdown isolation interlock for Unit I by placing IP-29 AFP SGBD isolation defeat to on, if required. r% - - ^ e POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS NOTE: Timing for 1AF-4000, 1P-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 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV as follows. 5.10.1 Shut 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV. 5.10.2 Open AND time 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV THEN record time to OPEN on Attachment A. (B4) (For Information only) 5.10.3 Record the 1C03 position of 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV on Attachment A. 5.10.4 Record Local position of IAF-4000, 1P-29 Aux Feed Pump Discharge IHX-IB SG Inlet Isolation Motor Operator Valve, on Attachment A. 5.10.5 Shut AND time 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV THEN record time to SHUT on Attachment A. 5.10.6 Record the 1C03 position of 1AF-4000, IP-29 AFP Disch SG B Inlet MOV on Attachment A. 5.10.7 Record Local position of 1AF-4000, 1P-29 Aux Feed Pump Discharge IHX-1B SG Inlet Isolation Motor Operator Valve, on Attachment A. Pagoe 10 of 45 10of45rm TnUTCTT Page CYT T Mur
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I INITIALS NOTE: Timing for 1AF-4001, 1P-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 Quarterly Full Stroke Exercise, Stroke Time Shut, and Position Indication Test of IAF-4001 1P-29 AFP Disch SG A Inlet MOV as follows. 5.11.1 Shut 1AF-4001, 1P-29 AFP Disch SG A Inlet MOV. 5.11.2 Open AND time 1AF-4001, 1P-29 AFP Disch SG A Inlet MOV THEN record time to OPEN on Attachment A. (For Information only) 5.11.3 Record the 1C03 position of 1AF-4001, 1P-29 AFP Disch SG A Inlet MOV on Attachment A. 5.11.4 Record Local position of 1AF-4001, 1P-29 Aux Feed Pump Discharge 1HX-1A SG Inlet Isolation Motor Operator Valve, on Attachment A. 5.11.5 Shut AND time 1AF-4001, 1P-29 AFP Disch SG A Inlet MOV THEN record time to SHUT on Attachment A. 5.11.6 Record the IC03 position of 1AF-4001, 1P-29 AFP Disch SG A Inlet MOV on Attachment A. 5.11.7 Record Local position of 1AF-4001, 1P-29 Aux Feed Pump Discharge 1HX-lA SG Inlet Isolation Motor Operator Valve, on Attachment A. Page I11 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS 5.12 Perform the Quarterly Full Stroke Exercise, Stroke Time Open, Fail-Safe Open, and Position Indication Test of IMS-2090, 1P-29 AFP Bearing Cooling Inlet, as follows: 5.12.1 On panel 1C-144, 1MS-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 1MS-2090, 1P-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 1MS-2090, IP-29 AFP Bearing Cooling Inlet, by placing the test switch in the NORMAL position. (For Information only) 0E-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 lMS-2090, 1P-29 AFP Bearing Cooling Inlet, test switch in the NORMAL position. Page 12 of 45 CONTINUOUS USE
"POINTBEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS 5.13 Shut 1MS-2082, 1P-29 AFP Overspeed Trip, Valve. NOTE: Notify the DSS if IMS-2082, 1P-29 AFP Overspeed Trip, does NOT trip. 5.13.1 Make an entry into the SOMs log stating that 1P-29 is unavailable due to cycling 1MS-2082, 1P-29 AFP Overspeed Trip valve. NOTE: C01A 2-8, Auxiliary Feed Water System Disabled, will alarm during the performance of the next step. 5.13.2 Trip shut 1MS-2082, 1P-29 AFP Overspeed Trip, 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 1C-03 AND note status on Attachment A. 5.14 Closure Exercise of TDAFP Mini-Recirc Valve Instrument Air Accumulator IT-212 Seismic Boundary Check Valve 1AF-173 5.14.1 Close IA-352, 1AF-4002 AFP Mini-Recirc Control Valve Operating Air Inlet. 5.14.2 Uncap AND slowly'Open 1AF-176, 1P-29 AFP Mini Recirc 1AF-173 Test Connection. 5.14.3 After initial depressurization, check closure of 1AF-173 by checking for the absence of air leakage approximately 6 inches above the outlet of 1AF-176 by hand. 5.14.4 Record 1AF-173 closure test results on Attachment A. 5.14.5 Shut and Cap 1AF-176, 1P-29 AFP Mini Recirc 1AF-173 Test Connection. 5.14.6 Open IA-352, IAF-4002 Mini-Recirc Control Valve Operating Air Inlet. Page 13 of 45 CONTINUOUSI lISP
"POINTBEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS NOTE: The ability for IAF-4002 to exercise to the open position with accumulator 1T-212 isolated satisfies the stroke open test of check valve 1AF-173. NOTE: Use local indication for timing 1AF-4002, 1P-29 AFP Mini-Recirc CV. 5.15 Perform the Quarterly Full Stroke Exercise. Stroke Time Open and Shut, and Position Indication Test of 1AF-4002, 1P-29 AFP Mini-Recirc Control Valve, as follows: 5.15.1 Unlock AND shut 1AF-125, IP-29 AFP Mini Recirc 1AF-4002-S Outlet Isolation. 5.15.2 Shut 1AF-175, 1P-29 AFP Mini Recire IA IT-212 Isolation. 5.15.3 Open AND time 1AF-4002, 1P-29 AFP Mini-Recirc CV, by unlocking AND opening 1AF-126, IP-29 AFP Mini Recirc 1AF-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 1AF-126, IP-29 AFP Mini Recirc 1AF-4002-S Bypass Isolation. 5.15.7 Shut AND time 1AF-4002, IP-29 AFP Mini-Recirc CV, by opening 1AF-125, 1P-29 AFP Mini Recirc 1AF-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 1AF-175, IP-29 AFP Mini Recirc IA IT-212 Isolation. Page 14 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I INITIALS 5.16 Perform the Following to Reset and Open 1MS-2082, IP-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 IMS-2082, 1P-29 AFP Overspeed Trip, valve Reset Operator. (C03)
- a. Verify 1MS-2082, IP-29 AFP Overspeed Trip Valve Reset Operator, green light ON.
- b. Verify IMS-2082, 1P-29 AFP Overspeed Trip Valve Reset Operator, red light OFF.
5.16.5 Open 1MS-2082, IP-29 AFP Overspeed Trip Valve Reset Operator. (C03)
- a. Verify 1MS-2082, 1P-29 AFP Overspeed Trip Valve Reset Operator, red light ON.
- b. Verify 1MS-2082, 1P-29 AFP Overspeed Trip Valve Reset Operator, green light OFF.
- c. Verify 1MS-2082, 1P-29 AFP Overspeed Trip Valve Position, amber light OFF.
- d. Verify 1MS-2082, 1P-29 AFP Overspeed Trip Valve Position, red light ON.
5.16.6 Verify the following annunciators are CLEAR:
"* 1C03 ID 3-8, 1P-29 AFP Low Suction Pressure Trip.
"* CO1A 2-8, Unit 1 Auxiliary Feed Water System Disabled.
Page 15 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS 5.16.7 Make an entry into the SOMs log stating that 1P-29 is now available because cycling of 1MS-2082, 1P-29 AFP Overspeed Trip valve is completed. 5.17 Align 1PI-4013A, 1P-29 AFP Suction Pressure Indicator, gauge as follows: 5.17.1 Shut pressure gauge vent. 5.17.2 Valve in pump suction pressure gauge, 1PI-4013A, IP-29 AFP Suction Pressure Indicator. 5.17.3 Record suction pressure on Attachment B. 5.18 Record 1PI-4458, 1P-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 1PI-468, SG A Pressure AND 1PI-478, SG B Pressure on Attachment B. 5.20 Open 1AF-4002, 1P-29 AFP Mini-Recire CV, as follows: 5.20.1 Shut 1AF-125, 1P-29 AFP Mini Recirc AF-4002-S Outlet Isolation. 5.20.2 Open 1AF-126, IP-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 IP-29, Aux Feedwater Turbine-Driven Pump, has NOT been operated within the previous four hours to be considered a valid Cold Start Test. 5.22 Concurrently Record appropriate data on PBF-3070 during the run time of 1P-29, Aux Feedwater Turbine-Driven Pump, as required. Page 16 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I INITIALS NOTE: RCS Temperature should be monitored during this test. (B-5) 5.23 Start 1P-29, Aux Feedwater Turbine-Driven Pump, by performing the following: 5.23.1 Open AND time 1MS-2019, B SG STM Supply to 1P-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 1MS-2020, 1HX-1A SG Header 1P-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 I to 2 minutes to stabilize. 5.24 Observe pump comes up to speed AND governor takes control. NOTE: 1P-29, Aux Feedwater Turbine-Driven Pump, suction pressure trip is set at 6.5 psig with a 20 second time delay. 5.25 Check 1P-29, Aux Feedwater Turbine-Driven Pump, suction pressure is greater than 6.5 psig on 1PI-4013A, 1P-29 AFP Suction Pressure Indicator. NOTE: 1AF-4002, 1P-29 AFP Mini-Recirc CV, should remain open when the instrument air valve is returned to normal. 5.26 Open 1AF-125, 1P-29 AFP Mini Recirc AF-4002-S Outlet Isolation. 5.27 Shut IAF-126, 1P-29 AFP Mini Recirc AF-4002-S Bypass Isolation. 5.28 Verify 1AF-4002, 1P-29 AFP Mini-Recirc CV, OPEN. Page 17 of 45 CONTINUOUS USE
"POINTBEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS NOTE: The following step satisfies full stroke exercising of 1AF-114, 1P-29 Minimum Flow Check Valve. 5.29 Check mini-recirculation flow greater than 100 gpm (expected range 120-130) on IFIT-4049, 1P-29 Aux Feedwater Pump Mini Recirc Flow Indicator Transmitter AND record on Attachment B. 5.30 Red lock 1AF-125, 1P-29 AFP Mini Recirc AF-4002-S Outlet Isolation, in the normally OPEN position. 5.31 Red lock 1AF-126, 1P-29 AFP Mini Recirc AF-4002-S Bypass Isolation, in the normally SHUT position. 5.32 Record 1PI-2076, 1P-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-135A, 1P-29 AFP Inlet Check, and IMS-2090, 1P-29 AFP Bearing Cooling Inlet 5.35.1 Shut FP-306, 1P-29 AFP Emer Bearing Cooling Header Isolation. 5.35.2 Record 1PI-4458, 1P-29 AFP Cooling Water Supply Pressure Indicator, on Attachment B. 5.35.3 Open AND lock FP-306, IP-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-135A, 1P-29 AFP Inlet Check, check valve. (- ) _--__ __ Step 5.35.2 Step 5.18 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) Page 18 of 45 CONTINUOUS USE
"-POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS 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. eRf e 0-TS-RE401 and AOP-21) 5.38 Adjust flow with IAF-4000, IP-29 AFP Disch SG B Inlet MOV, to approximately 150 gpm or as required to close IAF-4002, 1P-29 AFP Mini-Recirc CV. 5.39 Check 1AF-4002, IP-29 AFP Mini-Recirc CV, SHUT. 5.39.1 Local position indication (%) 5.39.2 Control board indication 1C-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) Page 19 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I INITIALS NOTE: Steam Generator level deviation alarms are possible when adjusting Auxiliary Feedwater Flow. NOTE: The following provides a full stroke of 1AF-101, 1HX-IB SG Auxiliary Feedwater First Off Check, 1AF-107, IP-29 AFP Discharge to 1HX-1B SG Check, 1AF-108, 1P-29 AF? Discharge Check, and 1AF-111, 1P-29 AFP Suction Check. 5.41 Adjust IAF-4000, IP-29 AFP Disch SG B Inlet MOV, for a total auxiliary feed flow rate of 400 gpm as indicated on lDPIS-4002 AND record the following: Time 400 gpm is achieved CLOCK hrs Turbine steam pressure 1PI-2076 psig 1AF-4000 position IC-03 1AF-4000 position Local 1B steam generator pressure 1PI-478 psig Auxiliary feed flow rate to lB SG IFI-4037 gpm Auxiliary feed flow rate to IA SG 1FI-4036 gpm IP-29 auxiliary feed flow rate 1DPIS-4002 gpm IP-29 recirculation flow rate IFIT-4049 gpm IP-29 disch. pressure 1PI-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 I B S/G for greater than 10 minutes with pump discharge pressure greater than 1173 psig, instruct NDE to perform VT-2 on the piping and components downstream of AF-4000 and record in I-PT-AF-2. 5.44 Compare recorded bearing temperatures in Attachment B to limits listed on Attachment E. Pare 20 nf45 iT 0eC%\VT-'T~T fT C-. T-r-
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS NOTE: Annunciator CO1A 2-8, Unit I 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 1MS-2019, B SG STM Supply to IP-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. r 5.46 Open 1MS-2019, B SG STM Supply to 1P-29 AMP. 5.47 Shut AND time 1MS-2020, 1HX-1A SG Header 1P-29 AFP Steam SupplyMov. 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. to 5.48 Open 1MS-2020, 1HX-1A SG Header 1P-29 AFP Steam Supply MOV. 0 NOTE: Steam Generator level deviation alarms are possible when
~
- securing Auxiliary Feedwater Flow.
5.49 Shut 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV AND observe 1AF-4002, 1P-29 AFP Mini-Recirc Control Valve, begins to OPEN as flow decreases to approximately 110 gpm. 5.50 Check 1AF-4002, 1P-29 AFP Mini-Recirc CV, OPEN AND controlling flow. Use either local or control board indication. 5.51 Adjust flow with 1AF-4001, IP-29 AFP Disch SG A Inlet MOV, to -7*4-zW'/.- approximately 150 gpm OR as required to close 1AF-4002, 1P-29 AFP Mini-Recirc CV. 5.52 Check IAF-4002, IP-29 AFP Mini-Recirc CV, SHUT. Use either local or control board indication. Page 21 of 45 CONTINUOIUS T SF
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS NOTE: Steam Generator level deviation alarms are possible when adjusting Auxiliary Feedwater Flow. NOTE: The following provides a full stroke of 1AF-100, IHX-1A SG Auxiliary Feedwater First Off Check, 1AF-106, 1P-29 AFP Discharge to 1HX-1A SG Check, 1AF-108, 1P-29 AFP Discharge Check, and 1AF-111, 1P-29 AFP Suction Check. 5.53 Adjust 1AF-4001, IP-29 AFP Disch SG A Inlet MOV, for a total auxiliary feed flow rate of 400 gpm as indicated on IDPIS-4002 AND record the following: Time 400 GPM is achieved Clock hrs. Turbine steam pressure IPI-2076 psig 1AF-4001 position IC-03 IAF-4001 position Local IA steam generator pressure 1PI-468 psig Auxiliary feed flow rate to IA SG 1FI-4036 gpm Auxiliary feed flow rate to lB SG 1FI-4037 gpm IP-29 Auxiliary feed flow rate IDPIS-4002 gpm IP-29 disch pressure IPI-4004 psig IF the 40-month functional and/or 10-yearN-498-1 hydrostatic pressure test is being performed concurrently with this procedure THEN after feeding Unit I A S/G for greater than 10 minutes with pump discharge pressure greater than 1173 psig, instruct NDE to perform VT-2 on the piping and components downstream ofAF-4001 and record in 1-PT-AF-2. 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). Shut the following valves. 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV, AND IAF-4001, IP-29 AFP Disch SG A Inlet MOV. Ensure 1AF-4002, IP-29 AFP mini-recirc is open. TC+J 2IWt- M1 Page 22 of 45 CONTINUOUS USE
"POINTBEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS 5.58 After IP-29 has been in service for a total of 4 hours 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 1-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 1AF-4001, 1P-29 AFP Disch SG A Inlet MOV, to the indicated flow for the existing A S/G pressure. 5.60 Using Attachment F, adjust 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV, to the indicated flow for the existing B S/G pressure. 5.61 Adjust 1AF-4000, IP-29 APP Disch SG B Inlet MOV AND 1AF-4001, 1P-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 1A SG IFI-4036 Aux Feed flow to lB SG IFI-4037 Aux Feed flow IDPIS-4002 1A SG Pressure IPI-468 1B SG Pressure 1PI-478 t Page 23) of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I INITIALS 5.63 Record the as-left position of lAF-4000, IP-29 AFP Disch SG B Inlet MOV AND 1AF-4001, 1P-29 AFP Disch SG A Inlet MOV. 5.63.1 IAF-4000 1AF-4001 IC-03 % _% Local % % 5.63.2 Update the wall plaque with the date the test was run and the as-left positions for 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV AND 1AF-4001, 1P-29 AFP Disch SG A Inlet MOV. (B-6) Wall Plaque 1AF-4000 position % Date as-left Wall Plaque 1AF-4001 position _ % Date as-left 5.64 Isolate AND.. vent pump suction pressure gauge 1PI-4013A, 1P-29 AFP Suction Pressure Indicator. 5.65 Unlock AND shut IAF-18, P-29 AFP Discharge to Hx-IA Steam Generator. NOTE: The following two steps are performed concurrently. 5.66 Unlock AND shut 1AF-19, P-29 AFP Discharge to Hx-IB Steam Generator valve. 5.67 Check that as flow decreases the mini-recirc valve, 1AF-4002, 1P-29 AFP Mini-Recirc CV, begins to OPEN at approximately 110 gpm. (B-7) r1 0 To prevent damage to P-29 Monitor and maintain AFW discharge and or recirc flow greater than 75 GPM ORl Stop the pump. Page 24 of 45 CONTINUOUS USE
"POINTBEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS NOTE: Annunciator C01A 2-8, Unit 1 Aux Feed System Disabled will alarm and clear during the performance of Step 5.68 unless already in alarm. 5.68 Restore 1P-29, Aux Feedwater Turbine-Driven Pump, steam supply valves to AUTOMATIC. 5.68.1 Position an Operator to observe the coastdown behavior of 1P-29, Aux Feedwater Turbine-Driven Pump, for unusual noises, vibrations, or any other abnormal conditions. 5.68.2 Shut 1MS-2019, B SG STM Supply to 1P-29 AFP AND return control switch to AUTO. 5.68.3 Shut 1MS-2020, IHX-1A SG Header 1P-29 AFP Steam Supply MOV AND return control switch to AUTO. 5.68A Record Time 5.68.5 Note all abnormal conditions in Remarks Section. 5.69 Open AND lock 1AF-18, 1P-29 AFP Discharge to Hx-lA Steam Generator. 5.70 Open AND lock 1AF-19, 1P-29 AFP Discharge to Hx-1B 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 IMS-126, IP-29 AFP Steam Supply Inlet, LOCKED in the OPEN position. 5.73 Enable the blowdown isolation interlock for Unit 1 by placing IP-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 25 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I INITIALS 5.76 Check valve operability on Attachment C, IST Valve Data Sheet. 5.77 Check 1P-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 1MS-2019 B SG STM Supply to 1P-29 AFP S-A 1MS-2020 A SG STM Supply to IP-29 AFP S-A 1AF-4000 1P-29 AFP Disch SG B Inlet MOV T (Per Local Wall Plaque) 1AF-4001 1P-29 AF? Disch SG A Inlet MOV T (Per Local Wall Plaque) 1MS-126 1P-29 AFP Steam Supply Inlet LO 1MS-2082 1P-29 AFP Overspeed Trip Reset - 0 IAF-4002 1P-29 AFP Mini-Recirc CV UG/LH FP-306 1P-29 Bearing Supply Header Isolation LO 1AF-4002-S, 1P-29 AFP Mini Recirc IAF-125 LO Solenoid Outlet Isol 1AF-4002-S, 1P-29 AFP Mini Recirc IAF-126 LS Solenoid Bypass Isolation 2AF-4002 AFP Mini-Recirc Control IA-352 0 Valve Operating Air Inlet 1P-29 AFP Mini-Recirc IA 1AF-173 Test 1AF-176 S&C Connection IP-29 AFP Mini-Recirc IA 1I-212 IAF-175 0 Isolation 1P-29 AFP Bearing Cooling Inlet Test Red Locked 1MS-2090 Switch NORMAL IP-29 AFP Discharge to Hx-lA Steam IAF-18 LO Generator IP-29 AFP Discharge to Hx-IB Steam IAF-19 LO Generator IP-29 AFP SGBD Isolation Defeat N/A OFF switch Page Z"726 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 INITIALS 5.79 Reset 1LC-2125, Condenser Hotwell Level Controller, to maintain desired hotwell level. 5.80 IF this 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/valves 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, THIEN exit LCO 3.7.5.B, Action Condition for 1P-29, Aux Feedwater Turbine-Driven Pump. Time Date Page 27 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 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 hours 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 28 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1
7.0 REFERENCES
7.1 Technical Specifications 7.1.1 3.7.5, AFW System I 7.1.2 5.5.7,.Inservice Testing Program I 7.1.3 SR 3.7.5.2 I 7.1A SR 3.7.5.4 7.2 Procedures 7.2.1 CL 13E Part 1, Auxiliary Feedwa ter Valve Lineup Turbine-Driven, Unit 1 7.2.2 0-TS-RE-001, Power Level Deter irination 7.2.3 AOP-21, PPCS Malfunction 7.2.4 1-PT-AF-2, Turbine Driven Auxil]liary Feedwater System Main Steam Pressure Test - Outside Co:ntainment, Unit 1 I 7.2.5 OM 3.26, Use of Dedicated Operators 7.3 Miscellaneous 7.3.1 NRC Generic Letter 89-013 I 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 I 7.3.4 PBF-2114, Return to Service Testing Review Page 29 of 45 CONTINUOUS USE
"POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED COLD START OF TURBINE-DRIVEN AUXILIARY FEED Revision 29 PUMP AND VALVE TEST (QUARTERLY) August 23, 2002 UNIT 1 8.0 BASES B-1 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 99-08001, Improper positioning of Turbine driven Aux Feed pump disch valves B-7 CR 99-1205, Relief valve lifts during 1P-29, Aux Feedwater Turbine-Driven Pump, shutdown Page 30 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I REMARKS SECTION: Performed By:
/ Time Iniial Performer (Print) Performer (Sign) Date Time Initials
/ Tim _Iital 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 i
Performer (Print) Performer (Sign) Date Time Initials Reviewed By: Shift Supervision (Print) Shift Supervision (Sign) Date Time Initials Page 31 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) I TMT 1 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 1AF-4000, 1P-29 AFP Disch SG B Inlet MOV step Parameter In~strumnent Uis Rang Acceptance Iiil NO. Measured Used Criteria 5.102 Time to OPEN (info only) Stopwatch sec. N/A 5.103 IC03 Position Indication Board Meter % >85 Local Valve 5 5.10.4 Local Position Indication Indicator 5.10.5 Time to SHUT Stopwatch sec. 17.34 -23.46 5.10.6 1C03 Position Indication Board Meter % 515 5.10.7 Local Position Indication Local Valve 15 1 1 Indicator Quarterly Full Stroke Exercise, Stroke Time Shut, and Position Indication Test of 1AF-4001, 1P-29 AFP Disch SG A Inlet MOV Parameter Instrument i i Acceptance Step No. Measured Used Criteria 5.112 Time to OPEN (info only) Stopwatch sec. N/A 5.113 1C03 Position Indication Board Meter % >85 5.11.4 Local Position Indication Local Valve Indicator Val %>5 5.11.5 Time to SHUT Stopwatch sec. 17.68 -23.92 5.11.6 1C03 Position Indication Board Meter % *15 5.11.7 Local Position Indication Local Valver15 1 ~Indicator I Page 32 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 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 1MS-2090, IP-29 AFP Bearing Cooling Inlet Step No. Parameter Measured Instrument Used Un Units 1Reading R Acceptance Criteria Initials 5.12.3 Time to OPEN Stopwatch sec. 0-2 5.12.4 Local Position Indication Panel Ight N/A OPEN _____________________ Open Light __________ 5.12.6 Time to SHUT (info only) Stopwatch sec. N/A 5.12.7 Local Position Indication Panel LIC-1 N/A SHUT Shut Light I Quarterly Closure Exercise of 1AF-173, 1P-29 AFP Mini-Recirc IA 2 nd Off Check Parameter Instrument Units Acceptance Step No. M U Reading Criteria Initials Measured Used (Note1)1 I _Note Excessive No excessive flow 5.14.4 Flow from IAF-176 N/A f after initial (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. Page 33 of 45 CONTINUOTSlTISF
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 ATITACHMENT A VALVE STROKE VERIFICATION Page 3 of 3 Quarterly Full Stroke Exercise, Stroke Tune Open and Shut, and Position Indication Test of 1AF-4002, 'V IP-29 AFP Mini-Recirc Control Valve and Stroke Oven Test of 1AF-173 Parameter Measured Instrument I Used C II 5.15.4 Time to OPEN Stopwatch 5.15.5 Local Position Indicator N/A 5.15.8 Time to SHUT Stopwatch 5.15.9 Local Position Indicator N/A Acceptance Criteria Satisfied for all tested valves in Attachment A: (Circle one) SAT UNSAT Remarks:
/
Performer Date/Time SRO Date/Time Page 34 of 45 CONTINUOUS TJ5Zp
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNITI ATTACHMEINT B 1P-29, Aux Feedwater Turbine-Driven Pump, Recirc Flow Data Page 1 of 3
- Step Parameter Instrument I_ Units ICritt~erniac Acceptance Reading Radn 5.17.3 Pump Suction Pressure Before Test I1PI4013A psgN/A 5.19g Bearing Cooling Supply Pressure IPI-4458 psig NIA 5.19 Steam Generator Pressure IA IPI-468 psig NIA 5.19 Steam Generator Pressure lB 1PI-478 psig N/A Mini-Recirculation Flow (Full Stroke Open Test of IAF-114) IFJT-4049 gpm >100 5.32 Turbine Steam Pressure 1PI-2076 psig NIA 5.33 Packing glands for excessive leakage NIA NIA Check (4) if
___ ___ok. unusual noise, odors, Pump and turbine for 5.34 overheating, or leaks and verify service water NIA NIA Check (4) if flow to bearings ok. 5.35.2 Bearing Cooling Supply Pressure 1PI-4458 psig N/A 5.36 Bearing Cooling Supply AP 5.35.2 - 5.18 IPI-4458 psid >10 VIBRATION POINT ID "5.37 IP29 GOV H ips Note 4 Micro-logger Ipk 5.37 1P29 GOV Hips Note 4 Micro-logger G pk 5.37 1P29 GOV Hips Note 4 Micro-logger G env 5.37 1P29 lV ips Note 4 Micro-logger IPS pk 5.37 1P29 1Hips Note4 Micro-logger IPS pk 5.37 IP29 lHae Note 4 Micro-logger G env 5.37 1P29 11 acc Note 4 Micro-logger G pk 5.37 IP29 lA ips Note 4 Micro-logger IPS pk 5.37 1P29 2V ips Note 4 Micro-logger IPS pk 5.37 1P29 2H ips Note 4 Micro-logger IPS pk 5.37 IP29 3V ips (C) Note 3 Micro-logger IPS pk O E 5.37 IP29 3Hips (D) Note 3 Micro-logger IPSpk _____ _______ 5.37 1P29 3H ae Note 4 Micro-logger G env " -_,_-_-__ 5.37 1P29 3H acc Note 4 Micro-logger G pk _ 5.37 1P29 4V ips (A) Note 3 Micro-logger IPS pk _ __ 5.37 IP29 4H ips (B) Note 3 Micro-logger IPS pk *
- 5.37 1P29 4H ae Note 4 Micro-logger G env 5.37 1P29 4H acc Note 4 Micro-logger G pk._____ H, 5.37 1P29 4A ips (E) Note 3 Micro-logger IPS pk ,
Pa f4 1e3 ONIU U S Page 35 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 ATfACHMENT B IP-29, Aux Feedwater Turbine-Driven Pump, 400 GPM Flow Data 1AF-4000, IP-29 AFP Disch SG B Inlet MOV Page 2 of 3 Step Parameter Instrument Units Acceptance Reading Criteria Redn I 5.42 IP-29 Auxiliary Feed Flow Rate IDPIS-4002 gpm 400 Note 6 5.42 IP-29 Recirculation Flow Rate IFIT-4049 gpm N/A 5.42 Pump Discharge Pressure IPI-4004 psig N/A 5.42 Pump Suction Pressure During Test IPI-4013A psig N/A 5.42 Pump Differential Pressure Note 2 psid '1167 - 1303.8 5.42 Condensate Storage Tank Temperature (Note 1) TI-4045/4046 OF NIA 5.42 Turbine rpm Portable 3564-3636 VIBRATION POINT ID 5.42 IP29 IV ips Note 4 Micro-logger IPS pk _ 5.42 1P29 1H ips Note 4 Micro-logger IPS pk 5.42 1P29 IA ips Note 4 Micro-logger IPS pk _ 5.42 1P29 2V ips Note 4 Micro-logger IPS pk _ 5.42 1P29 2H ips Note 4 Micro-logger IPS pk' <0.36 5.42 1P29 3V ips (C) Note 3 Micro-logger IPS pk <50.36 5.42 1P29 3H ips (D) Note 3 Micro-logger IPS pk _<0.54 5.42 1P29 4A ips (E) Note 3 Micro-logger IPS pk <0.15 5.42 IP29 4V ips (A) Note 3 Micro-logger IPS pk < 0.312 5.42 IP29 4H ips (B) Nate 3 ______ Micro-logger IPS pk -<0.504 5A2 Bearing Pump Inboard 1TR-2000 B Pt 17 OF < 160 5.42 Temperature Outboard ITR-2000 B Pt 18 OF < 160 5.42 Note 5 Turbine Outboard 1TR-2000 B Pt 19 °F < 250 5.42 Inboard ITR-2000 B Pt 20 1 F < 250 Page 36 of 45 CONTINUOUS USE
"POINTBEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY)
UNIT 1 ATfACHMENT 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/ TI-4046, B Tank NOTE 2: Differential pressure = pump discharge pressure - pump suction pressure during test. [ 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: Performer / Date!Time / SRO Date/Time Page 37 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT1 ATTACHMENT C VALVE STROKE VERIFICATION NOTE: Data that falls outside the listed Acceptance Criteria constitutes inoperability of the related equipment. Quarterly Stroke Time Open and Position Indication Test of IMS-2019, B SG STM Supply to IP-29 AFP Step No. Parameter Instrument Units Reading AcceptanceI Measured Used Criteria 5.232. ime to OPEN Stopwatch sec. 18_28 -_24.70 5.23.3 Local Position Indication N/A N/A OPN Quarterly Stroke Time Open and Position Indication Test of 1MS-2020, A SG STM Supply to 1P-29 AFP 5.23.5 Time to OPEN Stopwatch sec. 19.06-25.78 5.23.6 Local Position Indication N/A N/A OPEN I Quarterly Stroke Time Shut and Position Indication Test of IMS-2019, B SG STM Supply to IP-29 AFP 5.45.1 Time to SHUT Stopwatch sec. 18.43 -24.93 5.45.2 Local Position Indication N/A N/A SHUT I I g Quarterly Stroke Time Shut and Position Indication Test of 1MS-2020, A SG STM Supply to 1P-29 AFP 5.47.1 Time to SHUT Stopwatch sec. 19.51-26.39 5.47.2 Local Position Indication N/A N/A SHTJ Acceptance Criteria Satisfied for all tested valves in Attachment C: (Circle one) SAT UNSAT Remarks:
/ I Performer Date/Time SRO Date/Time Page '38of 45 CONTINUOUS TJSE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 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 Req uirement: 0en / Shut (circle as required) Data Data Data Data Data Data Data Data Time to shut (sec.) Time to open (sec.) Page 39 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNITI 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 *225-F Turbine outboard bearing temperature <"1250 F ALERT RANGE Pump inboard bearing temperature >1200 F <160°F Pump outboard bearing temperature >120°F <1600 F Turbine inboard bearing temperature >2250 F <250°F Turbine outboard bearing temperature >2250 F <2500 F ACTION REQUIRED (PUMP OOS) RANGE Pump inboard bearing temperature >160 0 F Pump outboard bearing temperature >160°F Turbine inboard bearing temperature _.250 0F Turbine outboard bearing temperature >_250 0 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 40 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I 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 Total Aux Flow to S/G Total Aux Flow to SIG Total Aux Flow to SIG Total Aux Flow to Press FW Flow each S/G Press FW Flow each S/G Press FW Flow each S/G Press FW Flow each SIG 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 269 135 982 298 149 898 327 164 814 356 178 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 279 139 955 308 154 871 337 168 787 366 183 1036 280 140 952 309 154 868 338 169 784 367 183 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 286 143 934 315 157 850 344 172 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 Page 41 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I ATTACHMENT G 1P-29 Train Recovery for AF Initiation Page 1 of3 INITALS NOTE: Steps that do NOT apply are marked N/A. 1.0 Enable the blowdown isolation interlock for Unit 1 by placing 1P-29 AFP SGBD Isolation Defeat to OFF, if required. 2.0 Open 1AF-125, AFP Mini Recirc AF-4002-S Outlet Isolation. 3.0 Shut 1AF-126, 1P-29 AFP Mini Recirc AF-4002-S Bypass Isolation. 4.0 Open 1AF-18, P-29 AFP Discharge to HX-1A Steam generator. 5.0 Open 1AF-19, P-29 AFP Discharge to HX-1B Steam generator. /6.0 Adjust 1AF-4000, IP-29 AFP Dish SG B Inlet MOV, to the required position. 7.0 Adjust 1AF-4001, 1P-29 AFP Disch SG A Inlet MOV, to the required position. I 8.0 Shut and Cap 1AF-176, 1P-29 AFP Mini-Recirc IA IAF-173 Test Connection. 9.0 Open 1AF-175, 1P-29 AFP Mini-Recirc IA 1T-212 Isolation. 10.0 Open IA-352, IAF-4002 AFP Mini-Recire Control Valve Operating Air Inlet. 111.0 Open FP-3 06, 1P-29 Bearing Supply Header Isolation. 12.0 Place 1MS-2090, 1P-29 AFP Bearing Cooling Inlet, test switch in the NORMAL position. 13.0 IF IMS-2082, 1P-29 AFP Overspeed Trip, valve is SHUT, ThEN reset AND open 1MS-2082, 1P-29 AFP Overspeed Trip, valve as folloivs. 13.1 Align the flat side of the washer under the trip button with the trip arm. (Local) 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 42 of 45 CONTINUOUS USE
POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNITI ATTACHMENT G I P-29 Train Recovery for AF Initiation Page 2 of 3 INITIALS 13.4 Close IMS-2082, 1P-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 1MS-2082, 1P-29 AFP 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 1MS-2082, 1P-29 AFP Overspeed Trip, valve Position, amber light OFF. 13.5.4 Verify IMS-2082, 1P-29 AFP Overspeed Trip, valve Position, red light ON. 13.6 Verify the following annunciators are CLEAR:
- IC03 ID 3-8, IP-29 AFP Low Suction Pressure Trip.
- CO 1A 2-8, Auxiliary Feed Water System Disabled.
14.0 Ensure the following after restoration when time is available: 14.1 IP-29 AFP SGBD Isolation Defeat switch for Unit 1 is in the OFF position, if required. IV 14.2 IAF-125, AFP Mini Recirc AF-4002-S Outlet Isolation, OPEN AND LOCKED IV 14.3 1AF-126, 1P-29 AFP Mini Recirc AF-4002-S Bypass Isolation, SHUT AND LOCKED IV Page 43 of 45 CONTINUOUS USE
It POINT BEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 I" COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT I ATTACHMENT G 1P-29 Train Recovery for AF Initiation Page 3 of 3 INITIALS 14.4 1AF-18, P-29 AFP Discharge to HX-1A Steam generator, OPEN AND LOCKED IV 14.5 1AF-19, P-29 AFP Discharge to HX-1B Steam generator, OPEN AND LOCKED. IV I 14.6 1AF-176, 1P-29 AFP Mini-Recirc IA 1AF-173 Test Connection. S&C IV 14.7 IA-352, 1AF--4002 AFP Mini-Recirc Control Valve Operating Air Inlet. OPEN ( IV 14.8 1AF-175, 1P-29 AFP Mini Recirc IA 1I-212 Isolation. OPEN IV 14.9 FP-306, 1P-29 Bearing Supply Header Isolation. OPEN AND LOCKED IV 14.10 1MS-2090, 1P-29 AFP Bearing Cooling Inlet, test switch. NORMAL A LOCKED IV Page 44 of 45 CONTINUOUS USE
"POINTBEACH NUCLEAR PLANT IT 08A INSERVICE TESTS SAFETY RELATED Revision 29 COLD START OF TURBINE-DRIVEN AUXILIARY FEED August 23, 2002 PUMP AND VALVE TEST (QUARTERLY) UNIT 1 FIGURE 1 TURBINE-DRIVEN AUXILIARY FEED PUMP IV 2V 3V 4V 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 45 of 45 CONTINUOUS USE}}