ML030730731

Temporary Change Review and Approval, IT 10, Rev 43, Temp Change No. 2002-0048

ML030730731
Person / Time
Site:	Point Beach
Issue date:	02/06/2002
From:	Herman B, Sokol K Nuclear Management Co
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2003-0094, IT 10, TCN 2002-0048 PBF-0026c, Rev 13
Download: ML030730731 (27)

Text

S* -. Nuclear Power Business Unit TEMIPORARY CHANG E REVI ENV AND APPROVAL Page I of

.. No:c, Refer to NP 1.2.3. Temporary ProcedureChanges.forrequirements.

I - INITIATION Doc Number IT 10 Current Rev 43 Unit PBO Temp Change No. 2002-0043

ýocument Tite TEST OF ELECTRICALLY-DRIVEN AUXILARY FEED PUM'PS AND VALVES (QRTLY)

Existing Effective Temporary Changes Brief Description Include valves related to MR 01-144 (mini recirc control valve mod)

(!dtrtify specific changes on Form PBF-0026c. Document Review and Approval Continuaton, and include with we package)

Z 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? NO 0 YES (Prodc docurnentaaon accordng to HP 5.l.S)

Screening completed according to NP 5.1.8? C] NA [] YES (Attch copy)

Safety- Evaluation Required? m RNO [] YES (irY, a,r,,,onmaybe processed or fu, r-,ic-s andapprovals s*li beobtained before irnpc.e.n..s)

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

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

Will the proposed change: YES NO

1. Require a change to, affect or invalidate a requirement, commitment, evaluation or description in the Current or ISFSI Licensing Basis (as defined in NP 5.1.9 and NP 5.1.7)?

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

3. Delete or.nodify 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-baseliningc 0 purposes?

6. Require a change to the procedure Purpose or change the pu 0] 0 lnr;iti ated Brv erint/signn Bill Herman IZ Date 02/06/2002

.----J--

II - INITIAL APPROVAL This change is correct and complete, can be performed as written, and does not adv affect personnel or nuclear safety, or Plant operating conditions.

Group Supervisor (ptnt/sign)e (Ca nnot be thelnitiator)

This change does not adversely affect Plp,,perating conditior tafezy Ri procedures only)

Senior Reactor Operator (print/sign) . .oD lejI I Date (Cannot be the Initiator or Group Supervisor)

MI - PROCEDURE OWNER REVIEW J0 Permanent Q One-time Use E] Expiration Date, Event or Condition:

o] Hold chang; until procedure completed (final review and approMal still required within 14 days of initial approval) oProcedure Owner (print/sign)

QR/MSS ReviewNOT Required (Admin NS only) [3 QR Rcview Rf I

j*M$SS*evicw Required (itzrcrNc.NP ,5)

Date~ 2-t aDreL 2

This Change and supporting requirements correctly completed and processed.

TV.

• WAT. rVTVW ANT) APPJtVAL M4,ust be completed within day .Jtial approval) (The Initiator, QR in , thoritiall be Independent firoyd A other) 4- 3 )ASS (print/sign) 'C F'zrZ:d.f /_ 14Dae Indicates 50.59fl2.49 applicability assessed, any necessary screenings/*e'duations performcdfideternmanaton made as to whether additional eross-disciplinary o.. review required, and if required. performed.

MSS Meeting No./_ (7 ) /Dt" Approval Authority (print/sign) /Date-V - REVISION INFORMATION FOR PERMANENT CHANGES

/ Date PostTyping Review (print/sign)

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

Incorporated into Revision Number Effective Date rnces N?1.2.3 Re PBF-Rev*io 0106/ J3

5 f1 Point Beach Nuclear Plant DOCUMENT REVIEW AND APPROVAL CONTINUATION Paze of Doc Number IT 10 Revision 43 Unit PBO Title TEST OF ELECTRICALLY DRIVEN AUXILIARY FEED PUMPS AND VALVES (QUARTERLY)

Temporary Change Number 2002-0043 Description of Changes:

Step Change/Reason 5.23.2.a jAdd step to shut AF- 184 / isolates potential nitrogen leakage path during leak test of P38A valves.

5.23.10 Add step to open AF-1S4 / returns P38A system to normal alignment.

5.60.2.a Add step to shut AF-185 / isolates potential nitrogen leakage path during leak test of P38B valves.

5.60.10 -Add step to open AF-185 / returns P38B system to normal alignment.

Other Comments 0 Note: Recording of Step Number(s) is not required for multiple occurrences of identical information or when not beneficial to reviewers.

PBF-0026c Revision 6 04l VO/I

References:

NP 1.13. NP 1.23

r I.'

Point Beach Nuclear Plant

.TEMNIPORARY CHANGE AFFECTED MANUAL LOCATION y.

Page of Procedure Number IT 10 Revision 43 Unit PBO Title TEST OF ELECTRICALLY DRIVEN AUXILARY FEED PUMPS AND VALVES (QUARTERLY)

Temporary Change Number 2002-0048 I - IIMMEDIATELY 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 r

[--5 Copy included in work package for field implementation. (WO No. )

S Copy filed in Control Room temp change binder (Operations only). 2- 6-o

[] Original change package provided to *

• to obtain Procedure Owner Review (eg, Owner review may be coordinated by In-Group OA II.Procedure Writer. Procedure Supervisor, etc)

E_

C1 El__ _

El El _____

Performed By (print and sign) C..[ .. _- / 6.-*z *.L_./ Date .2. 0 -x 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 f[J Copy sent to Documentchange) use Control Distribution Lead for Master File.

(Not required for one-time E] Copy filed in Group satellite file. (Not required for on'e-time use changes.)

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

] Original Temp Change provided to k 65 to obtain Final Approvals - C .2 (e.g.. firal approval may be coordinated by In-Group OA IL,Procedure Wnter. Procedure Supervisor, etc.)

( Performed By (print and sign) $c..-(' cc - / D ate .2.,-- A PBF-0026h

Reference:

NP 1.2.3 Revision 5 06/13/01

r T Point Beach Nuclear Plant 10 CFR 50.59/72.48 PRE-SCREENING REVIEW Page of Brief Activity Title or IT 10, TEST OF ELECTRICALLY DRIVEN AUXILIARY FEED PUMPS AND

Description:

VALVES (QUARTERLY) rev 43 This form is required to be completed and attached to the applicable activity change forms (i e., PBF-0026a/c, etc.) to document use of Pre-screening Criterion 3 through 6 for 10 CFR 50.59 / 72.48 review of proposed changes (see NP 5.1.8, 10 CFR 50.59172.48 Applicability, Screening and Evaluation (New Rule) Section 4.6 and Attachment A.)

Pre-screening Criterion 3 - Activity Covered by Existing 10 CFR 50.59172.48 Screening or Evaluation Criterion 3 is [] Not Applicable to the proposed activity.

Identify the screening or evaluation number(s) (SE for old 50.5972.48 rule evaluations, EVAL for new rule evaluations):

SCR / SE / EVAL 4(s): SCR 2002-0010 If applicable, briefly summarize the parts of the proposed activity that are covered by Pre-screening Criterion 3.

Include valves which as a result of (AFW MOTOR DRIVEN PUMP MINI RECIRC CONTROL VALVE MOD 01-144) now impact performance of nitrogen leakage portion of IT-10 Pre-screening Criterion 4 - Activity Covered by Existing Approved and Valid Plant Procedure Criterion 4 is [D Not Applicable to the proposed activity.

Identify the applicable plant procedure.

Procedure number, revision and title:

If applicable, briefly summarize the parts of the proposed activity that are covered by Pre-screening Criterion 4.

Pre-screening Criterion 5 - NRC has Reviewed and Approved the Activity.

Criterion 5 is [D Not Applicable to the proposed activity.

Identify the NRC Safety Evaluation Report Number and/or Date.

NRC SER(s) . or Date(s):

If applicable, briefly summarize the parts of the proposed activity that are covered by Pre-screening Criterion 5.

Pre-screening Criterion 6 - Maintenance Activity (NOTE: Dry cask or ISFSI facility maintenance CANNOT use this criterion. A screening is required for dry cask or ISFSI facility maintenance.)

Criteriorn6 is [0 Not Applicable to the proposed activity.

I(.applicable, briefly summarize the parts of the proposed activity that are covered by Pre-screening Criterion 6.

VERIFY THAT NONE OF THE FOLLOWfNG CHANGES ARE PRE-SCREENED TO CRITERION 6: Verified No changes to structure, system or component design, performance, acceptance criteria, types of materials, 0 torque values outside of vendor recommended values, etc.

No temporary alterations to support maintenance or modification installation will be in place longer than 90 f]

days. (If there is any doubt whether the temporary alteration will be removed in 90 days, perform a screening.)

r No changes in acceptance criteria in technical specification surveillance or post-maintenance test procedures.

PBF-i Sb Revision 0 10,2410l Reference NP 5.1.g

• I.-

Point Beach Nuclear Plant 10 CFR 50.59/72.48 PRE-SCREENING REVIEW Page of_

i 10 CFR 50.59/72.48 PRE-SCREENING REVIEW CONCLUSION Preparer and Reviewer signatures below signify that the portions of the proposed activity as described above are within the scope of Prescreening Criteria 3, 4, 5, or 6 of NP 5.1.8.

EITHER preparer OR reviewer shall be 50.59fl2.48 screening or evaluation qualified.

Performed By Bill Herman / Date 216/02 Name (Print) Sigpaýure Reviewed Baye D Pr A Sigu Date Name (Print) Signature A4 PBF-1515b Revision 0 10;24/01

Reference:

NP 5 1 8

,'v%

Point Beach Nuclear Plant SCR 2002-0010 I0 CFR5o.59s72.48 SCREENING (NEW RULE) Verify SC*umberoal pag Page I "itle of Proposed Activity: Backup Air Systems for Auxiliary Feedwater Pumo Minimum Flow Recirculation Valves Associated Reference(s) #r. MR 02-001. MR 01-144, CR 01-2278, CR 01-3595, Calculation 2001-0056, Calculation 2002-0002, Calculation 2002-0001, Calculation M-09334-266-IA.1 Rev 0 - Nitrogen Backup System to AFW Pump Discharge Valve, Calculation S-09334-266-IA.2 Rev 2 - 3D Restraint with Girard Tube Clamp, Calculation 14410.1 1-NP(B)-001-XE Rev 0 - Qualification of 6 Foot Spans for 318 inch Tubing at PBNP, ASME Section VIH - Pressure Vessels, ASMI B31.1 - Power Piping, IT 10, IT 10A. IT IOB, EOP 0, EOP 0.1, ECA 0.0, AOP 5B, MR 97-038. NPM 2002-0030. Calculation WE 0005-06 Prepared by: Rob Chapman Date: /--..St- b" Name (Print) & tu'c Reviewed by: Dave Black ( iZgfaT11 Date: 1 ZnX 2 Name ( Print) Signature PART I (50.59/72.48) - DESCRIBE THE PROPOSED ACTIVI1Y 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 "10CFR 72.48 screenings.

Li Describe the proposed activity and the scope of the activity being covered by this screening. (The 10 CFR 50.59 172.48 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.

CR 01-2278, CR 01-3595 and LER 266/2001-005-00 identified an issue that could cause a common mode failure of all auxiliary feedwater pumps. If an accident or event has occurred that has led to the loss of instrument air, then the auxiliary feedwater pump minimum recirculation control valves 1/2AF-4002 for 1/2P-29, AF-4007 for P 38Ak and AF-4014 for P-38B will all fail closed. During this event, it will become necessay. for operations to throttle back auxiliary feedwater flow to control steam generator level, especially if all four auxiliary feedwater pumps auto start as designed. If care is not taken to ensure that the minimum recirculation valves are open, and the pump discharge valves are shut with no minimum flow path, then the pumps will dead head and fail in a very short time due to overheating. Currently, there is guidance in EOP 0. EOP 0.1, ECA 0.0, and AOP 5B to direct "operations to verify adequate pump flow if insutument air has been lost before reducing flow to the steam generators, or to stop the pump.

To provide additional assurance that the auxiliary feedwater pumps will not be damaged on a loss of instrument air. backup air sources will be supplied to all minimum flow recirculation valves. These modifications are an enhancement that will reduce the core damage probability from a loss of instrument air and increase the time for an cperator to tk-e manual action to override the valves open. Instrument air accumulator tanks will be installed by MR 02-001 for the 1/2P-29 valves (1/2AF-4002), and the existing nitrogen backup system for the MDAFP discharge valves will be tied in by MR 01-144 for the P-38A/B valves (AF-4007, AF-4014).

Currently, the auxiliary feed&ater minimum flow recirculation valves do not have a safety function in the open position, however this function is a design function described in FSAR Section 10.2 and Tlchnical Specification Bases B3.7.5. The basis for the recirculhtion valves not having a spfety fnction in the open position is that 211 of the auxiliary feedwater pumps will have open discharge valves upon auto-start (even with a loss of instrument air), and thus the nunimum flow recirculation line is not nezded early in the accident or event. These minimum recirculation valves currently have an augmented quality function to open (by manual cve.:ri6e) to ensure adequaie flow though tht associzt.d auxiliary feedwater pump during an Appendix R. fire within 45 minutes (per i-'.ior.O tO/2i RItfc% N? 5.1.8

Point Beach Nuclear Plant SCR 2002-0010 10 CFR 50.59f72.48 S CREENING (NEW RULE) Vcwdf SCR number on all pages r Page 2 Calculation WE-0005-06), and the backup systems installed by these modifications may be credited to support this function.

These modifications will provide a sufficient secondary source of air or nitrogen such that these valves are able to operate for at least two hours stroking 10 times per hour if the regular instrument air system is disabled due to a the seismic event, tornado, fire, or loss of offsite power. No changes will be made to the control circuitry of valves, and they will still open automatically when the auxiliary feedwater pump flow drops below the setpoint, when the pumps are started, and when the pumps are secured.

MR 02-001 - 1/2AF-4002 - TDAFP Mini Recirc Valves For 1I2AF-4002, a stainless steel accumulator tank will be installed in each of the instrument air lines to the mini recirc valves. Upstream of these tanks will be two check valves in series that will isolate the tank from the rest of the instrument air system. These check valves will be spring loaded and will shut on a very small differential pressure to ensure that the tank pressure will remain as high as possible when the instrument air pressure drops. The volume of the tanks will be approximately 150 gallons, which is greater than the required minimum volume determined by Calculation 2001-0056 to be needed to stroke each valve 10 times per hour for two hours. In order to reduce the amount of air required to stroke the valve and thus the tank size, the pressure regulator for the AF-4002 valves which is currently set at 85 psig, and will be re-set to 65 psig. The valve will still stroke full open at this pressure. Calculation 2001-0056 has also verified that these valves will pass full flow even when less than 20% open, since the flow restricting orifices 1/2RO-4003 govern the flow rate in the recirculation line and have the lowest flow coefficient.

The accumulator tanks will be ASME code vessels, designed to Section VIII, and will be rated to 200 psig.

These tanks will be installed in the north and south sections of the auxiliary feedwater pump room (not in the "pump cubicles). The tank locations were chosen based on the best possible tubing run, and to limit obstructions to plant equipment. Isolation valves will be installed to permit replacement of the check valves should leakage or failure occur. The tubing will be configured such that system pressure can be used to test "eachthe check valves, if necessary.

The new tubing will be routed through the wall that separates the IP-29 cubicle from the south section of the auxiliary feedwater pump room (Fire Zone 304S). This is a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated fire wall that is considered a partition within a fire zone. The penetration will be filled and the wall will maintain its 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rating.

MR 01-1444- AF-4007 and AF.-4014 - MDAFP Mini Recirc Valves The existing nitrogen supply systems for the AF-4012 and AF-4019 MDAFP Discharge Control Valves (one independent system for each valve) will be used to supply the AF-4007 and AF-4014 MDAFP Minimum.

-- Recirculation Control Valves. The existing instrument air isolation check valves AF-131/133 (for AF-4012)

"andAF-151/153 (AF-4019) and nitrogen tubing and tanks mill be used for the AF-4007 and AF-4014 valves.

New tubing will be installed to connect the nitrogen supply tubing near the AF-4012/4019 valves downstream "ofthe check valves to the AF-4007/4014 minimum recirculation valves. Also, a bypass line will be installed around the AF-1331153 check valves to allow the AF-1311151 check valves to be tested using system "pressure,if necessary. The existing instrument air connections to the AF-4007/4014 valves will be capped.

The nitrogen system pressure regulators (PCV-4053/4058) are currently set to 60 psig, and will be re-set to 65 psig. This will increase the margin for stroking the recirculation valves open. although this is still less than the normal valve rTerulator setring of 100 psivg Calculation 2002-0002 has verified that these valves are full open at this pressure, and that they will pass full flow even when less than 20% open, since the flow restricting orifices ROQ-008/4015 govern the flow rate and have the lowest flow coefficient in the recirculation line. This in:rease in pressureregulator setting will not affect the discharge valve positioners, since they normally operate with 100 psig instrument air, but only require 45 psig.

The existing nitrogen supply system installed by MR 97-038 consists of two nitrogen boutles, with one valved in and the other bottle mzintained full in standby mode. When the aligned bottle pressure drops to the changeout point, the standby bottle is aligned, and the drain bottle is replaced with a full bottle. Calculation PBF-1515c Refertnce N'P 5 1.9 Revision 0 O1/2-401

"Point Beach Nuclear Plant SCR 2002-0010 10 CFRs5.972.48 SCREENING (NrEW RULE) vc-ifySCR nmb* on anpages

• Page 3 "2002-0002 determined the changeout pressure for the bottle that will supply 90 minutes of nitrogen to the discharge and minimum recirculation valves. Therefore, there is always greater than three hours of capacity available in the system at any given time, although operator action is required to align the standby bottle.

Although the AF-4007/4014 valves do not have a safety function to open, all components in the air supply line to the valve will be installed as safety related, since it will be part of the pressure boundary for the existing discharge valve backup system, which was installed safety-related by MR 97-038. Several existing instrument air components upstream of the solenoid valve that are not safety related will be reclassified as safety related. This can be done on the basis that these components have demonstrated adequate functionality over time, and these components will also be leak tested by MR 01-144. This is equivalent to qualification testing, and therefore these components may be dedicated. Furthermore, the dimensions of these components have been verified to be appropriate for the installation. Finally, the material acceptability will be evaluated based on a detailed walkdown.

Common Issues All new tubing and valves installed for both modifications will be stainless steel and have design ratings that are the same as or greater than the existing components. All new components will be installed using ASME B31.1.

All new tubing, valves, and accumulators will be analyzed as seismic Class 1. Standard wall mounted tube supports will be used and supported with Hilti bolts into the walls of the auxiliary feedwater pump room.

Calculation 14410.11-NP(B)-001-XE Rev 0 (including Addendum A) provides a seismic basis for the use of tubing supports and a required spacing, and the limitations of this calculation shall apply to all tubing installation.

Supports for the pressure gauges for MR 02-001 will be designed in accordance with Calculation S-09334-266 IA.2 Rev 2. The floor supports for the accumulator tanks were seismically analyzed by Calculation 2001-0001.

Portions of the system not covered by any calculation will receive a SQUG walkdown to ensure seismic adequacy.

Currently the nitrogen system AF-133/153 check valves are safety-related and in the IST program. They are leak tested quarterly by IT 10, and are also tested by IT IOA and IT lOB. The upstream check valves AF-1311151 will not be tested periodically, but a bypass line is being installed to facilitate testing, should it be necessary in the future. The check valves for the instrument air accumulator will not be part of the IST program, nor will they be periodically tested. They will be tested as PMT for the modification. Since the accumulators are not supporting a safety function of the AF-4002 recirculation valves, then there is no need to periodically test these check valvei.

The specified two hour time duration on the backup systems is not a licensing basis requirement. There is a one hour required coping duration for the Station Blackout event (FSAR Appendix A.1), and a 45 minute requirement for Appendix R (Calculation WE-O005-06), but no other time requirements are specifed. Two hours was chosen conservatively to be enough time to allow an operator to be dispatched to the auxiliary feedwater pump room to take manual action if necessary, and to bound current and future requirements. The sizing of these systems with a two hour capability does not imply a new licensing basis requirement to supply these valve for two hours.

The minimum recirculation valves were assumed in each of the calculations to stroke 10 times per hour. This is a

.,... conservative estimate that was also used in the original calculation for the MDAFP discharge v,ve nitrogen "backup system (Calculation M-09334-266-IA.I). Simulator runs have confirmed that this is very conservative since operations personnel will typically attempt to maintain the steam generator levels steady by balancing "auxiliaryfeedwater flow with steam flow. See Calculations 2001-0056 and 2002-0002 for more details on this assumption.

Modifications MR 01-144 and MR 02-001 and the issue documented in LER 2001-005-00 will necessitate a revision to FSAR Sections 9.7 (Instrument Air) and 10.2 (Auxiliary Feedwater) and to Technical Specification Bases 3.7.5 to clearly reflect the design function of the minimum recirculation valves to open and to describe the backup air supplies installed by these modifications.

Necess.*y updates to Appendix R documents 1o teke credit for the backup systems will be evaluated by a separate 50.59. However, this 50.59 can provide the basis for the backup systems to perform this function.

P3F.1515c Ftevision(0 la!23l10

Reference:

N? 5.1.8

t -'

Point Beach Nuclear Plant SCR 2002-0010 I

10 CFR 5o.$9r72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 4

'- 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 (both Custom and Improved), 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 Section 7.4.1 - AMSAC FSAR Section 9.7 - Instrument Air/Service Air FSAR Section 10.2 -Auxiliary Feedwater FSAR Figure 10.2-1 Sheet I - Bech M-217 Sh. I -Auxiliary Feedwater System FSAR Figure 10.2-1 Sheet 2- Bech M-217 Sh. 2 - Auxiliary Feedwater System FSAR Section 14.1.10 - Loss of Normal Feedwater FSAR Section 14.1.11 -Loss of All AC Power to the Station Auxiliaries FSAR Section 14.2.4 - Steam Generator Tube Rupture FeSAR Section 14.2.5 - Rupture of a Steam Pipe FSAR Appendix A.1 - Station Blackout FPER 5.2.2 - Safe Shutdown Systems and Equipment FPER 5.2.5.2.3 - Auxiliary Feedwater Pump Room SSAR 2.3.1.4 - Reactor Heat Removal Function SSAR 2.3.2.4 - Auxiliary Feedwater System Tech Spec 3.7 Auxiliary Feed water Tech Spec Bases B 3.7.5 - Auxiliary Feedwater LER 266/2001-005-00 See Part II for the description of the design functions and performance requirements.

4 I-PBF-ISIc Rr"son 0 10t244VI Refhezncc: SP 5 1.8

"PointBeach Nuclear Plant SCR 2002-0010 10 CFR 50.59/72.48 SCREENING (NEW RULE) Verity SCR numnbe on alt pages Page 5

,- 1.3-, Does the proposed activity involve a change to any Custom or Improved Technical Specification (ITS)? Changes to Technical Specifications require a License Amendment Request (Resource Manual Section 5.3.1.2).

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

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

[']Yes Z No Ifa storage cask Certificate of Compliance change is required, explain what the change should be and why it is required.

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

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

YES NO QUESTION

, " 0] [J Does the proposed activity involve Safety Analyses or structures, systems and components (SSCs) credited in the Safety Analyses?

0 1] Does the proposed activity involve SSCs that support SSC(s) credited in the Safety Analyses?

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

0] 5 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?

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

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

] [] -. Does the activity exceed or potentially affect a design basis limitforafission product barrier(DBLFPB)?

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

[f'ý"ezanswers to ALL of these questions are NO, mark Part III as not applicable, document the 10 CER 50-59 screening in the conclusion section (Part IV), then proceed directly to Part V - 10 CFR 72.48 Pre-screening Questions.

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

These modifications affect the operation of the minimum recirculation valves for the auxiliary feed%ater pumps (l/2AF 4002, AF-4007, AF-40i4). These v'lves have the following design functions:

A.1. To isolate the minimum recircul'aion line to ensure that the auxiliary feedwater pumps deliver the required flow to Sthe steam generators as needed to support the following accidents or events: LON-F, LOAC, MSLB, SGTR.,

ATWS, Appendix R, and SB0.

A.2. To open to provide flow thro,.gh the auxiliary feedwater pumps to prevent hydraulic instabilities and to dissipate pump heat.

A.3. To maintain the pressure bo-.d_-"y integ*rity of the auxiliary feedwater system.

PBF-1IS1c R.'*i'*.'. 19"2-'/9'RefL'e.:* e NP S !

We: cc N'p 5 8

Point Beach Nuclear Plant SCR 2002-0010 Verify SCR number on all pages 4

10 CFR 50.59/72.48 SCREENING (NEW RULE) Page 6

• "" These modifications affect the auxiliary feedwater system, which has the following design functions:

B.l. To automatically start and ensure that adequate feedwater is supplied to the steam generators for heat removal during accidents which may result in a main steam safety valve opening (LONF - including ATWS, and LOAC).

B.2. To automatically start and provide flow to maintain steam generator levels during accidents which require or result in rapid reactor coolant system cooldown (SGTR. MSLB).

B.3. To allow the isolation of all lines to the ruptured steam generator in the SGTR event B.4. To provide sufficient feedwater to remove decay heat for one hour during a station blackout event (TDAFP only).

B.5. To provide sufficient flow to the steam generators to remove decay heat to achieve cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following a plant fire (Appendix R).

B.6. To withstand a seismic event (designed as seismic Class 1) and to ensure that steam generator levels are maintained during a seismic event.

B.7. To provide flow to the steam generators during plant startup and shutdown, and during hot shutdown or hot standby conditions for chemical additions and when operation of the main feedwater and condensate systems is not warranted.

These modifications also affect the insurument air system, which has the following design functions:

C.A. To provide dry, oil-free air to pneumatic controllers and control valves required for the normal operation of both units.

C.2. To isolate instrument air lines inside containment on a containment isolation signal to maintain containment integrity.

C.3. To ensure that the purge supply and exhaust valve boot seals are inflated to maintain containment integrity.

CA. To supply nitrogen to the motor driven auxiliary feedwater pump discharge control valves.

.4. .'

C.5. To supply nitrogen to the power operated relief valves (PORVs) when LTOP is functional.

C.6. To ensure that the instrument air headers inside containment can be depressurized to preclude the chance of a circuit fault causing a PORV or CVCS seal return valve to open.

These modifications are being installed in the Auxiliary Feedwater Pump Room, which has the following design functions:

D.1. The walls act as 3-hour rated fire barriers D.2. The walls are designed to withstand a seismic event without failing.

A I

FE.- If 15c Re'i-PnO 10/./-OI e.cftrnc* N7, 5 !.9

• Point Beach Nuclear Plant SCR 2002-0010 10 CFR 50.59n72.48 SCREENING (NEW RULE) Venfy SCR number on al pages

£ Page 7 "PARTI11 (50.59) - DETERMINE WHETHER THE ACTIVITY INVOLVES ADVERSE EFFECTS (Resource Manual 5.3.3)

"IfALL the questions in Part 11 are answered NO, then Part III is [] NOT APPLICABLE.

Answer the following questions to determine if the activity has an adverse effect on a design function. Any YES answer means that a 10 CFR 50.59 Evaluation is required; EXCEPT where noted in Part M1-3.

MA1.1 CHANGES TO THE FACILITY OR PROCEDURES YES NO QUESTION 0 0 Does the activity adversely affect the designfunction of an SSC credited in safety analyses?

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

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

The modifications will improve the ability for the minimum flow recirculation valves to perform their non safety related design function in the open position (A.2). Currently, this design function is completely provided by either the instrument air system or by manual operator action. These modifications will install backup systems to perform this design function after instrument air is lost before operator action is taken. These backup systems (nitrogen bottles and air accumulators) will always be available if the instrument air system fails, and will be isolated from the instrument air system with two check valves in series. The backup systems for the recirculation valves will be installed using safety-related components, even though they are not supporting a safety function for the minimum recirculation valves. The components for the MDAFP recirculation valves will be classified as safety-related since they are part of the nitrogen system pressure boundary required for the AF-4012/4019 valves. The components for the TDAFP recirculation valves will be installed as augmented quality, seismic Class 1. There will not be an adverse effect on the existing non safety-related instrument air system that currently supports this design function. The recirculation valves will need to operate at a lower air pressure of 65 psig. but the valves will still fully open at this pressure, and Calculations 2001-0056 and 2002-0002 has shown that the valves will pass adequate flow to perform this design function when they are only approximately 20% open. The net effect of these modifications is an improvement that results in a lower core damage probability (see NPM 2002-0030). and will ensure that the minimum flow recirculation valves have the capability to open and that the auxiliary feedwater pumps will not be damaged by operating at low flows. Therefore, design function A.2 is not adversely affected, and is actually enhanced.. This will provide the operators with additional time to diagnose the loss of instrument air and take action to properly control auxiliary feedwater flow and secure pumps if required.

Under most conditions when the auxiliary feedwater system is needed, the recirculation valves must be closed (design

"-function A.1). The addition of these backup systems will not create a new failure mode that will fail the valve in the open position when it is needed to be shut. The source of the air is independent of the circuitry that would open and close the valve. The solenoid valves and associated circuitry that supply the air to the actuator are being not being affected, and are currently qualified as safety-related. The minimum recirculation valves will still fail closed on loss of air, although this failure is less likely to occur with the installation of these backup systems. Therefore, these modifications will not have an adverse effect on design function A.I, and the likelihood that the valves will fail open has not been affected.

These modifications will not affect the auxiliary feedwater pressure boundary in any way, and thus design function A.3 is not adversely affected. The modifications will only involve the instrument air and nitrogen systems that actuate the minimum recirculation valves and the MDAFP discharge valves.

The air accumulators for the TDA.FP recirc valves installed in the instrument air lines will not adversely affect any of the design functions of the instrument air system (C.1 through C.6). Once the accumulators have been pressurized.

there is no additional long-term loading on the system required by installing accumulator tanks. The tank will not "affectthe operation of the other safety related accumulators or nitrogen bottles anywhere in the instrument air syste.m.

The accumulator tanks rnd a-.l new tubing will be insvalled and anchored as seismic Class 1, which will preclude interactions with other plant equipment.

PB F-IS I5c RcviSCno 10.12410? Rfir-nc:: NP 5.1.9

Point Beach Nuclear Plant SCR 2002-0010 10* CFR 50.59/72.48 SCREENING (NEW RULE) Verify SCR numbcron all pagcs8 Page The nitrogen tie in for the MDAFP recirc valves will utilize the existing nitrogen backup system for the MDAFP "dischargecontrol valves. Calculation 2002-0002 was performed to show that the existing nitrogen bottles are adequate to supply nitrogen to stroke the minimum recirculation valves and the discharge valves, with no additional bottles necessary, for two hours. Nitrogen bottle changeout at a pressure that ensures 90 minutes from one bottle with a second full bottle available will not change from current practice, other than the changeout pressure will be reduced, which is an improvement. There will be a negligible effect on the discharge valves stroke time to close by opening the recirculation valve with the same system. Furthermore, there are currently no stroke time acceptance criteria for the discharge valves opening and the recirculation valves closing. Since the calculation has shown that the existing system can handle the additional demand, there is no adverse affect on the discharge valves, and there is therefore no adverse effect on design function C.4. The backup nitrogen systems for the MDAFP discharge valves will still be fully capable of supporting the design functions of the MDAFPs and the auxiliary feedwater system (functions B.1 through B.7).

All new components, including the new tubing, valves, and accumulator tanks will be designed as seismic Class 1.

Therefore, the components installed by MR 01-144 and MR 02-001 will not adversely affect the seismic design functions of any components or systems in the auxiliary feedwater pump room (design function D.2) and the auxiliary feedwater system (design function B.6).

The new components will not affect the ability of the auxiliary feedwater pump room walls to act as 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated fire barriers (design function D.1). No additional combustible loading is being added to the auxiliary feedwater pump room (Fire Zones 304N,304M, 304S).

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

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

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

M.3 TMSTS OR EXPERflMENTS If tht activity is not a test or experiment, the questions in III.3.a and I11.3.b are ED NOT APPLICABLE.

az..Aswer these two questions first:

" YES NO QUESTION

[] [] Is the proposed test or experiment bounded by other tests or experiments that are described in the CLB?

0] D] ke the SSCs affected by the proposed test or experiment isolated from the facility?

If the answ:e to BOTH questions in V.B.a is NO, continue to 1fl.3.b. If the answer to EITHER question is ..ES, then describe the basis.

b. Answer these additional questions ONLY._ for tests or experiments which do NOT meet the criteria given in 1l1.3.a above.

If the zr.swer to either question in 111.3.a is YES, then these three questions are [] NOT APPLICABLE.

ioi:4o RRefernnce. NP 5 I1 Rev's'on o0

Point Beach Nuclear Plant SCR 2002-0010

" 10 CFR 50.59172.48 SCREENING (NEW RULE) VeifySCRnucranalpagts Page 9 YES NO QUESTION

[] fl 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?

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

0 D 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 1I13.b is YES. a 10 CE 50.59 Evaluation is required. If the answers in II1.3.b are N0, describe the

-ALL basis for the conclusion (attach additional discussion as necessary):

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

Check all that apply:.

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

A Point Beach FSAR change is 0 required or E] NOT required. If an FSAR change is required, then initiate an FSAR Change Request (FCR) per NP 52.6.

A Regulatory Commitment (CLB Commitment Database) change is j] required or 10 NOT required. If a Regulatory "CommitmentChange is required, initiate a commitment change per NP 5.1.7.

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

10 CFR 72.48 SCREENING NOTE: NEI 96-07. Appendix B. Guidelines for 10 CFR 72.49 Impleinentatior should be used for guidance to determine the proper responses for 72.48 screenings.

PART V (72.48) - 10 CFR 72AS INITALL 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 0D ED Does the proposed activity involve IN ANY MANNER the dry fuel storage cask(s), the cask transfer/transport equipment, any ISFSI facility SSC(s), or any ISFSI facility monitoring as follows: Multi-Assembly Sealed Basket (MSB). hMSB 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/Cormnunication Links, or PPCS/ISFSI Continuous Temperature Monitoring System?

0 [] Does the proposed activity involve IN AhN' MAINNER SSC(s) installed in the plant specifically added to support cask loading/unloading a:tivities, as follows: CasI: Dewaterng System (CDW), Cask Reflood System (CRF), or Hydrogen Monitoring System?

O [] Does the proposed -cti'ity involve IN ANY IMAINER SSC(s) needed for plant operation which are also used to support cask loading/unloading Zciivities, as follows: Spern Fuel Pool (SFT), SF? Cooling and Filtration (SF),

Primary Auxiliary Buiidine Ventilation Sy-erm (*OrPAB). Drumming Area Ventilation System (VNDP,M),

PBF-15ISc Reoisront0 10,,O2I Rcfe,-nct: NP 5.1.1

"PointBeach Nuclear Plant SCR 2007-0010 10 CFR 50.59n72.48 SCREENING (NEW RULE) Verify SCR number on all pages Page 10 "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 [ Does the proposed activity involve a change to Point Beach CLB design criteria for external events such as earthquakes, tornadoes, high winds, flooding, etc.?

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

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

If ANY of the Part V questions are answered YES, then a full 10 CFR 72.48 screening is required and answers to the 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 O] [I Does the proposed activity involve cask/ISFSI Safety Analyses or plantfcask/ISFSI structures, systems and components (SSCs) credited in the Safety Analyses?

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

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

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

ED El Does the activity involve a method of evaluation described in the ISFSI licensing basis?

E3 0 Is the activity a test or experiment? (i.e., a non-passive activity which gathers data)

E] El Does the activity exceed or potentially affect a cask design basis limit for afissionproduct barrier(DBLFPB)?

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

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

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

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

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

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

VII.1 Changes to the Facility or Procedures YES NO QUESTION PBF-135sc F.evwsionO W0124101 Rec'ence: SP 5.1 9

Point Beach Nuclear Plant SCR 2002-0010 10 CFR 50.59172.48 SCREENING (NEW RULE) verif scR nbronalpages Page 11 F-

""-" [ Does the activity adversely affect the designfuncrion of a plant, cask, or ISFSI SSC credited in safety analyses?

[] [] Does the activity adversely affect the method of performing or controlling the desrignfunction of a plant.

cask, or ISFSI SSC credited in the safety analyses?

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

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

YES NO QUESTION E 0 Does the activity use a revised or different method of evaluation for performing described in a cask SA.R? k'" safety analyses than that 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 72.48 Evaluation is required. If both answers are NO. describe the basis for the conclusion (attach additional discussion, as necessary):

• I.3 Tests or Experiments (If the activity is not a test or experiment, the questions in VIL3.a and VII.3.b are [ NOT APPLICABLE.)

a. Answer these two questions first:

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

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

If the answer to both questions is NO. continue to Vfl.3.b. If the answer to EITHER question is YES, then briefly describe the basis.

44

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 V1I.3.a is YES, then these three questions are [E NOT APPLICABLE:

YES NO QUESTION El El Does the acti%ity utilize or control an SSC in a mznner that is outside the reference bounds of the design bases as described in the ISFSI lice-nsing basis?

El El Does the activity utilize or control a plant, cask or ISFS1 facility SSC in a manner that is inconsistent with "thean2lyses o; descriptions in the ISFSI licensing basis?

ED El Does the activity ?lace the cask or ISFSI facility in a condition not previously evaluated or that could affect 6-e capability of 2 plant. cask, or ISFSI SSC to perform its intended functions?

PrC-1Of24I. NP 5 11

M Point Beach Nuclear Plant SCR 2002-0010 10 CFR 50.59/72.48 SCREENING (NEW RULE) Veify SCR nurnmb on all pages Pagve 12 If any answer in VI.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 VYI - DOCUMENT THE CONCLUSION OF THE 10 CFR 72.48 SCREENING Check all that apply:

A 10 CFR 72.48 Evaluation is 0] required or & 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 EQ required or [D NOT required. If a VSC-24 cask SAR change is required. then contact the Point Beach Dry Fuel Storage group supervisor.

A Regulatory Commitment (CLB Commitment Database) change is El required or (D 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 EO required or ED 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.

AU PBP-1.55c pxv~is:-.* o 1=4,12Z01 P

Reference:

NIP 5 1 28 evisc 0 l0.2.OI

Reference:

is'? S I

Point Beach Nuclear Plant PROCEDURE RECORD AND FIELD COPY TRACKING

,I I

Field Copy Number Record/Field Copy Identification N- -1 .4 r-= M RED - Record Copy; BLACK - Field Copy Revision Number I Procedure Number -.4T- /0 Unit / e Revision Date "-7 t"l Procedure.Tinle aJnCuZ~- T rne,- f4ir T Chan ges:

Tr~acking C~hecked for Temporary ProcRe iionnC~hecked and Curr~ent; Date _______.

yBy Record Copy Holder/Location eýo II A,

FIELD COPY DISTRIBUTION I

Copy No.

Aeý Holder/Location Alt It2--L.lo2 Issue Date Return Date 3

4 5

6 7

9, I10 RECORD COPY NOTE 1: ANY TEMPORARY CHANGES MADE TO THIS PROCEDURE SHALL BE MADE TO THE AND ALL OTHER FIELD COPIES THAT HAVE BEEN ISSUED.

NOTE 2: RETURN ALL FIELD COPIES TO THE HOLDER OF THE RECORD COPY UPON PROCEDURLE CONPLETION.

PBF-0026i Reference. NP 1.1.4 Revision 2 2r/1I101

r

• IT 10 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES (QUARTERLY)

DOCUMENT TYPE: Technical CLASSIFICATION: Safety Related REVISION: 43 EFFECTIVE DATE: July 5, 2001 REVIEWER: Qualified Reviewer APPROVAL AUTHORITY: Department Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Operations Verified Current Copy:2 ,,.& .

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

• . ."POINT BEACH NUCLEAR PLANT IT 10

'INSERVICE TESTS SAFETY RELATED Revision 43 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED July 5,2001 PUMPS AND VALVES (QUARTERLY) INITIALS p

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.

NOTE: If this test is being performed to satisfy pump PMT requirements any vibration levels above 0.325 ips measured at any ASME Section XI Code required location shall be evaluated by engineering prior to declaring the pump operable.

Post maintenance operability test Equipment M _ _

WO No(s).

Task Sheet No.(s)

___Special test - no numbers

,a-5 ,rl av J-W?16T9 Explain:A . /ýa ~o~z 7 v~/~~~~

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

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

4.4 Chemistry notified about auxiliary feed injection.

4.5 Reactor power on both Units is reduced a minimum of 2% OR to a power level directed by DSS. (Mark step N/A if in CTS: Hot or Cold Shutdown

{1TS: Modes 3, 4, 5, 6, & defueled))

Page 5 of 53 CONTINUOUS USE

I POINT B EACH NUCLEAR PLANT IT 10

'INSERVICE TESTS SAFETY RELATED A -Revision 43 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED July 5, 2001 PUMPS AND VALVES (QUARTERLY)

INITIALS 4.6 Permission to Perform Test The conditions required by this test are consistent with required plant conditions, equipment operability. Permission is granted to perform this test.

Cz L - TIME z DATE -L/ 4"'/ -

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

5.0 PROCEDURE 5.1 IF in CTS: cold shutdown {ITS: Modes 5, 6, or defueled),

THEN verify the following:

(Otherwise mark this step as N/A) a The Steam Generators are drained to a level sufficient to accept FW flows.

• The RCS is NOT solid.

NOTE: When operability testing of Train A is NOT required, then N/A Steps 5.2 through 5.38.

5.2 TRAIN A TEST 5.2.1 LF performing Section 5.2, THEN the following auxiliary feedwater pumps with their associated flow paths, are operable as applicable.

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

a. For two-unit operation:

P-38B, 1P-29, and 2P-29 are operable.

b. For single-unit operation:

P-38B and 1P-29 are operable for Unit 1.

OR P-38B and 2P-29 are operable for Unit 2. 411,4,/

Page 6 of 53 CONTINUOUS USE

- . ". POINT BEACH NUCLEAR PLANT IT 10 "IINSERVICE TESTS SAFETY RELATED Revision 43 July 5, 2001 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES (QUARTERLY)

INITIALS

• 1 5.2.2 IF sufficient qualified operators are NOT available on shift to support Step 5.2.3, TFHEN consider the equipment unavailable per Maintenance Rule AND N/A Step 5.2.3.

5.2.3 Assign a Level 4 Dedicated Operator in the Control Room

-Lg*

AND a Level 4 Dedicated Operator in the field per OM 3.26, Use of Dedicated Operators, to perform the restoration steps of Attachment J, if required. (Otherwise mark this step as N/A)

I 5.3 Enter a CTS: LCO {ITS: Action Condition }for P-38A.

I (N/A this step if NOT required for current plant conditions per CTS: Technical Specification 15.3.4. {ITS: 3.7.5})

TIME ;2-5§y DATE 2A10o2 I

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

(N/A this step if NO. required.)

i!

Page 7 of 53 CONTINUOUS USE

• ,  ; .-POINT BEACH NUCLEAR PLANT IT 10 SAFETY RELATED

" 'INSERVICE TESTS Revision 43 July 5, 2001 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES (QUARTERLY)

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

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

5.16 Check AF-4007, P-38A AFP Mini-Recirc Control, mini-recirculation ,9-1 ,

valve open.

5.17 Check mini-recirculation flow equal to or greater than 70 gpm on FIT-4050A.

5.18 Check the packing glands for excessive leakage or overheating. 4P la'-

5.19 Check pump and motor for unusual noise or overheating.

5.20 WREN P-38A has run for five-minutes, THEN record the following on Attachment B.

PI-4011, Pump Discharge Pressure.

PI-4010A, Pump Suction Pressure.

S FIT-4050A, Mini-Recirculation Flow.

0 Recirculation Flow Vibration Data. a -Y.,

.e Page 12 of 53 CONTINUOUS USE

--YOINT BEACH NUCLEAR PLANT IT 10 "INSERVICE TESTS SAFETY RELATED Revision 43 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED July 5, 2001 PUMPS AND VALVES (QUARTERLY)

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

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

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

5.54 Check mini-recirculation flow equal to or greater than 70 gpm on F1T-4050B. 71/

5.55 Check packing glands for excessive leakage or overheating.

5.56 Check the pump and motor for unusual noise or overheating. 41_Mýý'Fpv 5.57 .WHEN P-38B has run for five-minutes, THEN record the following data on Attachment F.

• j 0 PI-4018, Pump Discharge Pressure 0 PI-4017A, Pump Suction Pressure 0 FIT-4050B, Mini-Recirculation Flow 0 Recirculation Flow Vibration Data Page 25 of 53 CONTINUOUS USE

S:-.POINT BEACH NUCLEAR PLANT IT 10 SAFETY RELATED IN SERVICE TESTS Revision 43 July 5, 2001 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED PUMPS AND VALVES (QUARTERLY)

INITIALS 6.0 ANALYSIS 6.1 Operations 6.1. Comparisons with allowable ranges of Acceptance Criteria test values complete. All performers have signed onto the ed by" page.

Ze SRO Date/Time 6.1.* 2 Forward completed procedure to IST Coordinator NOTE: To be completed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> of test completion by IST coordinator or his representative.

6.2 IST Coordinator Comparisons with allowable ranges of test values and analysis 6.2.1 of deviations complete. A' 6.2.2 Any requirements for corrective action? (If yes, give details in the IST Remarks section.)

A' (Circle one) YES 6.2.3 IF Acceptance Criteria needs updating, THEN initiate a procedure revision. (Otherwise N/A)

,.g~l.Ib Z /2-0 - ./A!

Data Analyzed By Date/Time IST Remarks: .. L .. Li. l-., ., . - .- ,

.4 AJe 3 "a-" I-W owi6

,A O,-3T8I ,Aa-,. 7&) mAA.4dT..&k1AJ-f.C

/14,coA*O_66at .

I C/

I 1215 ýf TV Page 34 of 53 CONTINUOUS USE

-~ .-. POINT BEACH NUCLEAR PLANT IT10 INSERVICE TESTS SAFETY RELATED Revision 43 TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED July 5,2001 PUMPS AND VALVES (QUARTERLY)

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

NOTE 1: The data recorded on Attachment B is for information only.

NOTE 2: Vibration points which are shaded must be recorded by the Micro-logger but are NO.T required to be transferred to the table. Only points marked A, B, C, D, and E must be transferred to the table and are required for ASME Section XI. See Figure 1 for locations.

Step No. 1 I....

Parameter Measured I____

Reading tUnitsc Accptan I Criteria Initials 5.12.3 PI-4010A. P-38A AFP Suction Pressure psig 15. 1 N/A 5.15 PI-4010A. P-38A AFT Suction Pressure psig " >7 f.',,4 ft 5.20 PI-4011 Pump Discharge Pressure psig )*/C) N/A 9 psig [5"

• N/A Sx "

5.20 PI-4010A, P-38A AFP Suction Pressure 5.20 FIT-4050A, Mini-Recirc Flow gpm 1 N/A 5.20 Recirculation Flow Vibration Data INSTRUMENT UNITS READINGS P38A IV ips Note 2 Micro-logger IPS pk P38A IH ips Note 2 Micro-logger IPS pk P38A 1H ae Note 2 Micro-logger G env I P38A lH acc Note 2 Micro-logger G pk P38A IA ips Note 2 Micro-logger IPS pk P38A 2V ips Note 2 Micro-logger IPS pk P38A 2H ips Note 2 Micro-logger IPS pk P38A 2H ae Note 2 Micro-logger G env P38A 2H acc Note 2 Micro-logger G pk P38A 2A ips Note 2 Micro-logger IPS pk P38A 3V ips Note 2 Micro-logger IPS pk P38A 3H ips Note 2 Micro-logger IPS pk P3'BA 3H se Note 2 Micro-logger G env P38A 3H ace Note 2 Micro-logger G pk ____,_

P38A 4V ips Note 2 Micro-logger IPS pk

.4 P38A 4H ips Note 2 Micro-logger IPS pk

• P38A 4H ae Note 2 Micro-logger G cnv

• P38A 4H acc Note 2 Micro-logger G pk P38A 4A ips Note 2 Micro-logger IPS pk I

Page 39 of 53 CONTINUOUS USE

-4 -" POINT BEACH NUCLEAR PLANT IT 10 SAFETY RELATED

• INSERVICE TESTS Revision 43 July 5, 2001 S~~PT TEST OF ELECTRICALLY-DRIVEN AUXILIARY FEED TkPC* Al"J') VAL.VES (OUARTERLLY')

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

NOTE 1: The data recorded on Attachment F is for information only.

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

Units Reading ACceiae Initials 5.49.3 PI-4017A, P-38B AFP Suction Pressure psig 1(0, N/A ASaa 552 PI-4017A, P-38B AFP Suction Pressure psig 15,1 >7 . q 5.57 PI-4018 Pump Discharge Pressure psig /313 ) NIA _K 5.57 PI-4017A, P-38B AFP Suction Pressure psig /A N/A gpm -8 NIA f 4- I 5-57 F1T-4050B. Mini-Recirc Flow 73 557 Recirculation Flow Vibration Data INSTRUMENT UNITS READINGS P38B IV ips Note 2 Micro-logger IPS pk_

P38B IH ips Note 2 Micro-logger IPS pk

'I P38B 1H ae Note 2 Micro-logger G env 4 1 j P38B IH acc Note 2 Micro-logger G pk _I P38B IA ips Note 2 Micro-logger IPS pk P38B 2V ips Note 2 Micro-logger IPS pk __

P38B 2Hips Note 2 Micro-logger IPS pk P38B 2H ae Note 2 Micro-logger G env P38B 2H ace Note 2 Micro-logger G pk . _ _ _

P38B 2A ips Note 2. Micro-logger IPS pk -.

P38B 3V ips Note 2 Micro-logger IPS pk P38B 3H ips Note 2 Micro-logger IPS pk P38B 3H ae Note 2 Micro-logger G env P38B 3H ace Note 2 Micro-logger G pk P38B 4V ips Note 2 Micro-logger IPS pk_

14 P38B 4H ips Note 2 Micro-logger IPS pk ,.

P38B 4H ae Note 2 Micro-logger G env P38B 4H acc Note 2 Micro-logger G pk P38B 4A ips Note 2 Micro-logger IPS pk

• Page 45 of 53 CONTINUOUS USE